ML110190424

Initial Exam 2010-301 Final Es 401-2 and Final Es 401-9s

ML110190424
Person / Time
Site:	Watts Bar
Issue date:	01/19/2010
From:	NRC/RGN-II
To:
References
50-390/10-301
Download: ML110190424 (67)

Text

-lw_ 4 ES-401, Rev. 9E PWR Examination Outline Form ES-401-2 Facility: Watts Bar 2010-301 August 2010 RD K/A Category Points SRO-Dnly Points Tier Group KKK KKKAAAAG 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 Categories J 1 2 3 4 10 1 2 3 4 7 1 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 RD 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 RD exam must total 75 points and the SRD-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 (IR) of 2.5 or higher shall be selected. Use the RD and SRD ratings for the RD and SRD-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. Dn 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 RD and SRD-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 SRD selections to K/As that are linked to 10 CFR 55.43.

ES-401, Rev. 9 2 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 CR0 I SRO)

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

007EK3.01 Knowledge of the reasons for the 000007 (BW/E02&E1 0; CE/E02) Reactor Trip X following as the apply to a reactor trip: Actions 40/46

- Stabilization - Recovery I 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 2 8/3.3 following as they apply to a small break LOCA:

RCP operating parameters and limits 011 EK2.02 Knowledge of the interrelations 000011 Large Break LOCA / 3 X 2.6/2.7 between the and the following Large Break LOCA: Pumps: CVCS letdown and charging 000015/17 RCP Malfunctions /4 000022 Loss of Rx Coolant Makeup / 2 022AA1 .01 Ability to operate and I or monitor the 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 9/3.8 following as they apply to the Loss of Reactor Coolant Makeup:

025AG2.1.7 Loss of RHR system; Ability to 000025 Loss of RHR System /4 X 4.4/4.7 evaluate plant performance and make 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 3.6/3.8 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 3.5/3.6 Malfunction / 3 (SRO) following as they apply to the Pressurizer 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 3.9/4.2 implications of the following concepts as they apply to the SGTR: Natural circulation O4OAK1 .05 Knowledge of the operational 000040 (BW/E05; CE/E05; W/E1 2) Steam X 4.1/44 implications of the following concepts as Line Rupture - Excessive Heat Transfer /

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 4.3/4.6 following responses as the apply to the Station 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 action level thresholds and classifications.

2.9 /4 .6 057AG2.4.1 Knowledge of EOP entry conditions 000057 Loss of Vital AC Inst. Bus / 6 x and immediate action steps. 4.6 .8 058AA2.02 Ability to determine and interpret the 000058 Loss of DC Power /6 X 3/3 6 following as they apply to the Loss of DC Power: 125V dc bus voltage, low/critical low, alarm 062AA2.03 Ability to determine and interpret the 000062 Loss of Nuclear Svc Water! 4 X following as they apply to the Loss of Nuclear 2.6/2.9 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 4.0/4.6 logic used to assess the status of safety 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 35/3.9 implications of the following concepts as they 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 / or monitor 3.7/4.0 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 36/3.9 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: 18 SRO K/A Category Totals: = = = 3 3[ Group Point Total: 6

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

E/APE # / 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 005AK1 .05 Knowledge of the operational X 3.3/4.1 implications of the following concepts as they apply to Inoperable I Stuck Control Rod: Calculation of minimum shutdown margin 000005 Inoperable/Stuck Control Rod / 1 (SRO) X 005AG2.1 .32 Ability to explain and apply system limits and precautions. 3.8/4.0 000024 Emergency Boration / 1 (SRO) x 024AA203 Ability to determine and 2.9/3.0 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 X 032AK2.01 Knowledge of the 000032 Loss of Source Range NI /7 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 / 7 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 036AG2446 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 monitor the following as they apply to 3.6/3.9 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 ReI. / 9 (SRO) X 060AG2.4.3 Ability to identify post- 3.7/3.9 accident instrumentation.

000061 ARM System Alarms /7 x 061AK2.01 Knowledge of the interrelations between the Area Radiation 2.5/2.6 Monitoring (ARM) System Alarms and the following: Detectors at each ARM system location 000061 ARM System Alarms / 7 (SRO) x 061AA2.01 Ability to determine and 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 076AA2.03 Ability 000076 High Reactor Coolant Activity / 9 x to determine and interpret the following as they apply to 2.5/3.0 the High Reactor Coolant Activity: RCS radioactivity level meter W/EO1 & E02 Rediagnosis & SI Termination / 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 I BW/A02&A03 Loss of NNI-X/Y / 7 BW/A04 Turbine Trip / 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; CE/Al 3; WIEO9&E10 Natural Circ. / 4 BW/E13&E14 EOP Rules and Enclosures

CE/All; W/E08 RCS Overcooling - PTS / 4 CE/A16 Excess RCS Leakage / 2 CE/E09 Functional Recovery K/A Category Point Totals: I 2 1 1 2 2 Group Point Total: 9 K/A Category Point Totals: (SRO) = = 2 2 Group Point Total:

[

ES-401, Rev. 9 4 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems Tier 2IGrour 1 (RO / SRO)

System # / 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 Reactor Coolant Pump (SRO) X 2.7/3.1 impacts of the following malfunctions or 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, including faulty motors and current, and winding and bearing temperature problems 004K6.36Knowledgeofthephysical 004 Chemical and Volume Control X 2.6/2.8 connections and/or cause-effect relationships between the CVCS and the following systems: CCWS 005K5.01 Knowledge of the operational 005 Residual Heat Removal X 2.6/2.9 implications of the following concepts as they apply the RHRS: Nil ductility transition temperature (brittle fracture) 005A2.01 Ability to (a) predict the 005 Residual Heat Removal (SRO) X 2.7/2.9 impacts of the following malfunctions or 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 3.6/3.9 supplies to the following: ECCS pumps 006K6.l3Knowledgeoftheeffectofa 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 2.9/3.1 changes in parameters (to prevent 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 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:

008A4.10 Ability to manually operate 008 Component Cooling Water X 3.1/3.1 andlor 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 3.0/3.2 operation of the PZR PCS, including: PRT temperature and pressure during PORV testing 01 2K1 .05 Knowledge of the physical 012 Reactor Protection X connections and!or cause effect 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 013G2.2.12 Knowledge of surveillance 013 Engineered Safety Features 3.7/4.1 procedures.

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 andlor cause- effect relationships between the ice condenser system and the following systems:

Containment ventilation 026A4.05 Ability to manually operate 026 Containment Spray X andlor monitor in the control room:

Containment spray reset switches

039K3.04 Knowledge of the effect that a 039 Main and Reheat Steam X 2.5/2.6 loss or malfunction of the MRSS will 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 3.6/3.7 have on the following: AFW system 059A2.03 Ability to (a) predict the 059 Main Feedwater X 2.7/3.1 impacts of the following malfunctions or 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 3.5/3.6 operation of the ac distribution system, including: Safety-related indicators and controls 062K2.01 Knowledge of bus power suppli 062 AC Electrical Distribution X to the following: Major system loads 063A1 .01 Ability to predict and/or 063 DC Electrical Distribution X 2.5/3.3 monitor changes in parameters associated with operating the DC electrical system controls including:

Battery capacity as it is affected by discharge rate 063A2.O1 Ability to (a) predict the 063 DC Electrical Distribution X 2.5/3.2 impacts of the following malfunctions or 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 064 Emergency Diesel Generator 064K1 .03 Knowledge of the physical X 3.6/4.0 connections and/or cause-effect relationships between the ED/G system and the following systems: Diesel fuel oil supply system 064 Emergency Diesel Generator 064K4.03 Knowledge of EDIG system 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) which provide for the following: Letdown isolation on high-RCS activity 076A2.01 Ability to (a) predict the 076 Service Water X 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 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.

103A3.01 Ability to monitor automatic 103 Containment X 3.9/4.2 operation of the containment system, including: Containment isolation K/A Category Point Totals: ]3 2 2 2[3[3 3 212[ Group Point Total:

K/A Category Point Totals: (SRO) j 3 = Group Point Total: 5

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

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

1 234561234 001 Control Rod Drive 002 K6.07 Knowledge of the effect or a 002 Reactor Coolant X 2.5/2.8 loss or malfunction on the following RCS components: Pumps 01 1 Pressurizer Level Control 014 Rod Position Indication 014A1.04 Ability to predict andlor X monitor changes in parameters (to 35/38 prevent exceeding design limits) associated with operating the RPIS controls, including: Axial and radial power distribution 015 Nuclear Instrumentation X 01 5A3.03 Ability to monitor automatic 3.9/3.9 operation of the NIS, including:

Verification of proper functioning/operability 016 Non-nuclear Instrumentation 016K3.06 Knowledge of the effect that a 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 2.1/2.7 (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.

041A2.03 Ability to (a) predict the 041 Steam Dump/Turbine Bypass X impacts of the following malfunctions or 2.8/3.1 Control (SRO) operations on the SDS; and (b) based on those predictions or mitigate the consequences of those malfunctions or operations: Loss of lAS 045 Main Turbine Generator 055 Condenser Air Removal

056 Condensate X 056G2.1 .32 Ability to explain and apply 3.8/4.0 system limits and precautions 068 Liquid Radwaste 071 Waste Gas Disposal 072K4.03 Knowledge of ARM system 072 Area Radiation Monitoring X 3.2/3.6 design feature(s) and/or interlock(s) which provide for the following: Plant ventilation systems 075 Circulating Water 079K1.01 Knowledge of the physical 079 Station Air X 3.0/3.1 connections and/or cause-effect relationships between the SAS and the following systems: lAS 079G2.1 .20 Ability to interpret and 079 Station Air (SRO) X 4.6/4.6 execute procedure steps.

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, in fire damage K/A Category Point Totals:

K/A Category Point Totals: (SRO) 1 1 1 1 0 1 1 1 1 0 21 Group Point Total:

1 io 1] Group Point Total: 3

Facility: Watts Bar Date of Exam: 8/23/2010 2010-301 RO SRO-Only Category K!A # Topic IR Q# JR 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 2.2.15 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 2.2.43 inoperable alarms.

Knowledge of the process for conducting special 227 3. 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

Knowdge 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 4 1 resultant operational effects. .

4.

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

Knowledge of emergency plan protective action 2.4.44 recommendations. 4.4 Subtotal 3 1 Tier 3 Point Total 10 7

Watts Bar 2010-301 August 2010 RO Exam NRC Exam I

ES-401 Record of Rejected KIAs Form ES-401-4 Tier / Randomly Reason for Rejection Group Selected K/A 1/2 076 AA2.03 Plant does not have an RCS radioactivity level meter for monitoring Reactor Coolant Activity. Chemistry sampling is the method used for monitoring.

K/A Replaced by the Chief Examiner on 05/04/10 with K/A#076AA2.02.

2/1 073 K4.02 Plant does not have a Design feature or interlock for the isolation of letdown on high-RCS activity.

K/A Replaced by the Chief Examiner on 05/04/10 with K/A# 073 K4.01.

Watts Bar 2010-301 August 2010 SRO Exam NRC Exam I

ES-401 Record of Rejected KIAs Form ES-401-4 Tier / Randomly Reason for Rejection Group Selected K/A 2/1 003A2.03 Unable to write an SRO only question.

K/A replaced by the Chief Examiner on 08/06/10 with K/A # 003A2.01.

ES-401, Rev. 9 Watts Bar 201 0-301 RO Written Examination Review Worksheet FINAL Form ES-401-9

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO U/E/ Explanation Focus Dist. Link units ward K/A Only S Instructions

[Refer to Section D of ES-401 and Appendix B for additional information regarding each of the following concepts.]

Enter the level of knowledge (LOK) of each question as either (F)undamental or (H)igher cognitive level.

Enter the level of difficulty (LOD) of each question using a 1 5 (easy difficult) rating scale (questions in the 2 4 range are acceptable).

Check the appropriate box if a psychometric flaw is identified:

• The stem lacks sufficient focus to elicit the correct answer (e.g., unclear intent, more information is needed, or too much needless information).

• The stem or distractors contain cues (i.e., clues, specific determiners, phrasing, length, etc).

• The answer choices are a collection of unrelated true/false statements.

• The distractors are not credible; single implausible distractors should be repaired, more than one is unacceptable.

• One or more distractors is (are) partially correct (e.g., if the applicant can make unstated assumptions that are not contradicted by stem).

4. Check the appropriate box if ajob content error is identified:

• The question is not linked to the job requirements (i.e., the question has a valid KJA but, as written, is not operational in content).

• The question requires the recall of knowledge that is too specific for the closed reference test mode (i.e., it is not required to be known from memory).

• The question contains data with an unrealistic level of accuracy or inconsistent units (e.g., panel meter in percent with question in gallons).

• The question requires reverse logic or application compared to the job requirements.

5. Check questions that are sampled for conformance with the approved KIA and those that are designated SRO-only (K/A and license level mismatches are unacceptable).

6. Based on the reviewers judgment, is the question as written (U)nsatisfactory (requiring repair or replacement), in need of (E)ditorial enhancement, or (S)atisfactory?

7. At a minimum, explain any U ratings (e.g., how the Appendix B psychometric attributes are not being met).

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q# LOK LOD (F/H) (1-5) Stem Cues TIE Cred. Partial Job- Minutia #1 Back- Q= SRO U/El Explanation Focus Dist. Link units ward K/A Only S H 2 X E 007EK3.01 Question appears to match K/A. After reading the W.B. back ground that you sent me, I arr not sure that there is a totally correct answer. The reason for the step is to ensure that RCS heat is being properly removed through the secondary side.

I agree that it must be adequate, but is also could be too much, in which the step has actions to take care of this also. The answer listed is not complete, and could be appealed.

BANK Changed wording from adequate to controlled.SAT 7/27/2010 2 H 2 S 008AK2.01 Question appears to match K/A.

BANK

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q# LOK LOD i (F/H) (1-5) Stem Cues Focus T/F Dist. Link I

Cred. Partial Job- Minutia #1 Back-unitsj ward 0=

KJA SRO Only U/E/

S Explanation x X E 009EA2.23 Question appears to match K/A. Stem 3 information can be trimmed down.

. Unit is @ 100% Power

. The following equipment is OOS:

SIP lB-B TBBP 1A

. A LOCA Occurs

-RCS Pressure stabilized at 1605...

-Containment Pressure has increased to 1.6 psig and is slowly rising.

-E-1 is in progress Distractor C is not plausible. If a SI pump fails to start, why would you want to secure an RCP?

MODIFIED Replaced distractor C. SAT 8/212010.

H 2 S 011 EK2.04 Question appears to match the K/A. 300 4 psig is still kind of high. Need to lower this some is we can. 250#? Otherwise appears to be SAT Changed to 250 psig as requested.

NEW H 2 X U 022AA1 .01 Question kind of matches K/A. Some 5 teaching in stem and picture. This could also be asked: Unit 1 is at 100% with the B letdown orifice in service. The running charging pump trips.

Which one of the following describes how letdown will be isolated? Why do you need the pictures?

2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- 0= SRO U/El Explanation Focus Dist. Link units ward K/A Only S With the picture/symbols can an applicant determine what valves are interlocked P-A Permissive Auto?

IF so, this would make the question a direct look-up.

The pictures also give the applicants more information than is required to answer the question.

You would have to ensure that this information will not help answer any other questions The form states the question is new; but question history states it is modified. Which one is it? I do not believe that this is a new question.

MODIFIED Removed Picture and made changes as requested. SAT 7/26/2010.

025AG2.1 .7 Question appears to match the K/A.

H 2 Question appears to be SAT 6

MODIFIED H 2 X E 029EA1 .08 Question appears to match the K/A.

7 The stem of the question puts the plant at 55%. The last bullet states that a turbine trip occurs, but the reactor fails to trip. At what power does the turbine trip/reactor trip become active? (This could be teaching in the stem). The applicants are not using this for any information. You could place the plant at 100% and this would be moot.

NEW Changed to 100% SAT 7/27/2010

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q# LOK LOD i I (F/H) (1-5)

Focus Dist. Link I

Stem ICues T/F Cred. Partial Job- Minutia #1 Back-junits ward Q=

K/A I SRO Only U/E/

S Explanation 8 H 2 S 038EK1 .03 Question kind of matches the K/A. SAT MODIFIED H 2 E O4OAK1 .05 Question appears to match the K/A.

9 Distractor C is not plausible. It power rose to the

, POAH, what would make it stop here? (this essentially the same as D except stopping sooner).

Replace Distractor C.

MODIFIED After discussion with licensee agreed to leave as is. SAT 7/27/2010 H 2 S 054AG2.1 .23 Question appears to match the K/A.

10 SAT BANK 2 F S 055EK3.02 Question appears to match the K/A. SAT 11 BANK H 2 S 057G2.4.1 Question Kind of matches K/A. SAT 12 NEW

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q= SRO U/E/ Explanation Focus Dist. Link units ward K/A Only S 13 F 1 X U 058AA2.02 Do not believe that this meets the K/A.

The K/A asks for the ability to determine and interpret the following as they apply to the loss o DC Power 125V DC bus voltage, low/critical low alarm.

The question as written already gives the operator the alarm, and tells him the low voltage (teaching in stem). You should be testing the low voltage setpoint or when the alarm comes in. There is not much discriminatory value in this question.

MODIFIED Will allow voltage that the battery becomes inoperable. Will write new question. Wrote New question based on operable battery voltage. SAT 7/27/2010

.03 Question appears to match the K/A. SAl MODIFIED U 065AK3.03 Question does not match the K/A. The K/A asks for the reason(s) for isplatinga certain piece of equipment and how that effects plant operation. This question does not ask for any reason why a piece of equipment is isolated. It just informs the applicant that the equipment has been isolated. .

BANK Continue to work Replaced Question 8/16/2010 SAT

2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q# LOK LOD (F/H) (1-5) Stem Cues TIE Cred. Partial Job- Minutia #1 Back- 0= SRO U/E/ Explanation Focus Dist. Link units ward K/A Only S 16 F 2 X X U WEO4/EK1 .3 Question kind of matches the K/A.

With the plant in Mode 3, distractors C and D are not plausible. Very few radiation monitors would alarm with the reactor in mode 3 and a SGTR in progress.

Distractor A may also be considered correct. The third step in ECA 1.2 has the operator check letdown valves closed (These are normally closed on an S.l.)

But are normally open at 100% power (prior to S.l.)

So both of these A and B could be considered correct.

NEW Replaced with a Bank question (SEQ 2007) SAT.

7/26/2010.

17 H 2 S WEO5/EA1 .2 Question appears to match the K/A.

SAT NEW

2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q# LOK LOD (F/H) (1-5) Stem Cues TIE Cred. Partial Job- Minutia #1 Back- Q= SRO U/E/ Explanation Focus Dist. Link units ward K/A Only S 18 H 2 E WE1 1/EK2.1 Question appears to match the K/A. Is resetting the containment spray signal required prior to being able to close the discharge valve? If so, and the team exited E-1 at step 20, the signal would not have been reset. Therefore Answer C could not be correct. Several Items were added (modified) from the SON question (RHR pump and Containment sump level). I assume to make distractor B more plausible. And it does. Does the containment spray signal get reset somewhere else, or does is go away after a certain period of time? If so, A and B are not plausible. Will discuss. Very similar to question 42.

MODIFIED Made changes as requested. SAT 8/212010 19 F 1 E 003K2.4.1 Question appears to match K/A. Are any of these immediate actions of AOl-2? As the question is asked now, there are not any immediate actions being tested. I realize that this is a situation that the crew will open the reactor trip breakers, but reading E-0 I did not see this entry condition listed, I believe this is based on step 4 of AOl-2. But is does not appear that it is an immediate step. Is E-0 applicable in Mode 3? Your procedure does not indicate the mode of applicability. If this is the case, not sure that distractors A and B are plausible. Will discuss. Not much discriminatory value here.

MODIFIED Gerry to get back to licensee on this.

Licensee changed all distractors and stem. SAT

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q= SRO U/E/ Explanation Focus Dist. Link units ward K/A Only S 81212010 20 H 2 E OO5AK1 .05 Question appears to match the K/A.

Why is the term NuPOP used? I did see it in section 6.2 of 1-Sl-0-10 Obtain the NuPOP for the applicable cycle... If this is required, then the applicant need only remember this, and pick the only distractor that contains this. Either the term needs tc be included in another distractor, or removed.

NEW Licensee stated they would delete NUPOP from distractor C. SAT 7/27/2010 21 H 2 S 032AK2.01 Question appears to match the K/A. SAl MODIFIED 22 H 2 S 033AA2.03 Question appears to match the K/A. SAl MODIFIED 23 H 2 X U 036G2.4.46 Question appears to match the K/A. A lot of information in the stem. I am not sure all of it i required. Distractors A and C are not plausible. If you had any kind of a leak, in containment or in the SFP, why would anyone leave the valve open? Both sections of your AOl closes the valve. Need to

2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= I SRO U/El S

Explanation Focus Dist. Link units ward K/A Only replace/fix A and C.

NEW Continue to work on Question 7/26/2010.Replaced A and C Distractors. SAT 8/5/2010.

24 H 2 X X U 037AA1 .04 I do not believe that this was the intent of the K/A. I believe the intent is how do you monitor (as it applies to a SGTL) condensate air ejector exhaust radiation (your first part) and how would you know if it failed and how would you monitor it then.

(In other words, how would you know if it was not working? I do not think that distractors B and D are plausible. Generator PCB opening may cause the Hi alarm to come in, is this a result of high back pressure, or an interruption of electrical power?

Need to rewrite this question.

Need original question.

MODIFIED Will Continue to work. Replaced with a NEW question SAT 7/27/2010 25 F 2 S 061AK2.01 Question appears to match K/A.

NEW

2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q# LOK LOD (F/H) (1-5) Stem Cues Focus T/F Cred. Partial Job- Minutia #1 Back-Dist. Link units ward Q

K/A I SRO Only U/El S

Explanation 26 H 2 X X U 076AA2.02 Question appears to match the K/A.

Distractors C and D do not really make sense, because one mixed bed is already in service. Flow will be raised to 120 gpm. Why dont you test flow and cation beds? Are cation beds required by AOl-28? No, but if it was placed in service, flow would be limited to 75 gpm. The technical specification portion is okay, but does not really meet the K/A.

MODIFIED Replaced Question. SAT Bank. 7/26/2010.

27 F 2 X E WEO2IEK3.1 Question appears to match the K/A.

Not really sure if I would call distractor C a true basis. The basis of the step is to ensure that the faulted S/G is the only event in progress and once it is completely depressurized all primary parameters can be controlled by the operating crew. If parameters cannot be controlled, then another event is in progress. Need to ensure that C is correct.

NEW Made changes to stem, and distractors. SAT 8/05/2010.

28 F 2 S 003K5.04 Question appears to match the K/A. SAT MODIFIED

2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q# LOK LOD (F/H) (1-5) Stem Cues Focus TIF I Cred.

Dist.

Partial Job- Minutia #1 Back-Link units ward Q=

K/A SRO Only U/E/

S Explanation j

29 H 2 X X E 003K6.14 Question appears to match the K/A. The procedure for starting an RCP states that RCS pressure must be between 330 and 350 psig. None of the responses are between 330-350. This question could be appealed as not have a correct answer. I realize that the SQl states the minimum should be 325 psig. I understand that the stem of the question states lAW the SQL Discuss changing 330 to 331 and 350 to 349 etc.

BANK Made changes as requested. SAT 8/05/2010.

30 H 2 X E 004K6.36 Question appears to match K/A. Teaching in stem. Qperators should know 1-PT-62-81 controls 1 PCV-62-81. Just state that the pressure transmitter 1-PT-62-81 fails high.

NEW Made changes as requested. SAT 8/05/201 0.

31 H 2 X X U 005K5.01 Question appears to match K/A. How can you verify the statement Making an existing vessel beitline crack more susceptible to a brittle fracture ii your documents. I did not see this. I am not sure the A RHR HX outlet temperature is plausible. Why not use Tcolds?

MODIFIED Made changes to Tcolds, need to ensure that the reason is correct. 7/26/2010.

Okay 8/05/2010

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q# LOK LOD (F/H) (1 -5) Stem Cues TIE Cred. Partial Job- Minutia #1 Back- 0= SRO U/El Explanation Focus Dist. Link units ward K/A Only S 32 H 2 X U 006K2.01 Question appears to match the K/A. Do not believe that distractors A and B are plausible. If these motors are 6.9 KV then why would I choose either of these distractors?

MODIFIED Modified question (went up one level to the CSSTs. SAT 7/26/2010.

33 H 2 X E 006K6.13 Question appears to match the K/A.

Distractor D is not plausible. If they were in cold leg recirc with an RHR pump supplying the suction for one of the HHSI pumps that might work.

NEW Made changes as requested SAT 8/05/201 0.

34 F 2 S 007A1 .01 Question appears to match the K/A. Lots of words in the stem. Could we reduce these?

Otherwise SAT.

BANK Changed wording (reduced) SAT 8/05/201 0.

35 H 2 5 008A2.05 Question appears to match the K/A. SAT NEW

2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q# LOK LOD (F/H) (1-5) Stem Cues TIF Cred. Partial Job- Minutia #1 Back- Q= SRO U/E/ Explanation Focus Dist. Link units ward K/A Only S 36 F 2 S 008A4.10 Question appears to match the K/A. This question is difficult to understand as written. How can we make is simpler? Otherwise SAT.

NEW Changed wording (reduced) SAT 8/05/2010.

37 F 2 S 010A3.01 Question appears to match the K/A. SAT NEW 38 H 1 X E/U 012K1.05 Question appears to match the K/A. A and B are not plausible Cycle the Reactor Breakers?

I think you mean reactor trip breakers. P-li does not appear to be an operational valid point to test resetting of the SI, it has nothing to do with an SI.

This question while matching the K/A has little discriminatory value. Please enhance. (use the parameters in the SI termination procedure).

MODIFIED Still to work on 7/26/2010.Replaced question SAT 8/05/2010.

39 H 2 S 013G2.4.6 Question appears to match the K/A. This question is testing a part of the SI/RPS interface tested in question 38. Double jeopardy. Need to replace one of these. There are many questions on procedure strategy.

MODIFIED Will Change # 38. Will allow 39 to stand as is. SAT 7/26/2010.

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q# LOK LOD (F/H) (1-5) Stem Cues Focus T/F Cred. Partial Job- Minutia #1 Back-Dist. Link units ward Q=

K/A I SRO Only U/El S

Explanation 40 F 1 U 022G2.2.36 Question kind of matches the K/A.

None of the distractors appears to be plausible.

There are only three items in the section 3.6.3 of the TRM, and the LCCs are one. All of the other items do not appear to safety related at all.

MODIFIED Replaced with new question. SAT 7/26/2010.

41 F 2 S 025K1 .01 Question appears to match the K/A. SAT BANK 42 H 2 E 026A4.05 Question appears to match the K/A. Very similar to question 18. In fact some of the same knowledge is required.

MODIFIED Made changes as requested 8/05/2010.

43 H 2 S 039K3.04 Question appears to match the K/A. SAT MODIFIED 44 H 2 S 059K3.02 Question appears to match the K/A. SAT BANK 45 H 2 E 061A1.04 Question appears to match the K/A. In the distractors you state that suction will automatically swap to ERCW due to low pressure. If this is suction pressure we need to say that.

MODIFIED SAT 8/05/201 0.

2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q# LOK LOD I

(F/H) (1-5) Stem Cues Focus T/E Cred. Partial Job- Minutia #1 Back-Dist. Link units ward Q=

KJA I SRO Only U/El S

Explanation 46 H 2 E 062A3.05 Question appears to match the K/A.

Distractor D should state loads already sequenced on will load shed or de-energize. Timers Otherwise Okay MODIFIED Made changes as requested 8/05/2010.

47 F 2 S 062K2.01 Question appears to match the K/A. SAT MODIFIED 48 F 2 X E 063A1 .01 Question appears to match the K/A.

Distractor D reason is not plausible. How about to allow for longer DC oil pump operation to protect equipment? Need to develop another reason.

Asked for a second opinion on distractors A and B. I know that the procedure directs the operators to load shed the 125VDC vital bus, but I am not sure if the DG buses are plausible.

NEW Made changes as requested 8/05/2010.

49 H 2 X U 063A2.01 Question appears to match the K/A.

Distractors C and D are not plausible. Try one of the other 125VDC Vital Battery boards (other train is Okay).

MODIFIED Replaced distractors C and D (1 25VDC IV).

SA17/26/201 0.

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q= SRO U/El Explanation Focus Dist. Link units ward K/A Only S 50 F 2 E 064K1 .03 Question appears to match the K/A. Does the priming pump only start if the DIG gets an emergency start, or will it start if the D/G gets a normal start? May need to clarify this.

MODIFIED SAT 8/05/2010.

51 H 2 S 064K403 Question kind of matches K/A. Why do you not use the terms: speed droop and Isochronous? Otherwise SAT BANK SAT 810512010.

2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q# LOK LOD I I (F/H) (1-5) Stem Cues Focus TIE Dist. Link 1 ward units I

Cred. Partial Job- Minutia #1 Back- Q=

K/A spo Only U/El S

Explanation 52 F 2 U 073K4.O1 Question appears to match the K/A.

Distractors C and D are not plausible as written. The first two distractors ask about what would occur, and the second two where an alarm would be received.

Need to reword distractors C and D.

A. O-RCV-77-43 Cooling tower blowdown will automatically close terminating the release.

B. O-FCV-27-100 and O-FCV-27-1O1 Cooling tower blowdown diffuser valves will automatically close directing the effluent to the holding pond.

C. O-RCV-77-43 Cooling tower blowdown must be manually closed to terminate the release.

D. O-FCV-27-100 and O-FCV-27-1O1 Cooling tower blowdown diffuser valves must be manually closed to direct the effluent to the holding pond.

This is just an example. I am still not really sure that C and D are plausible.

Do you have anything for a waste gas release, or SGBD release?

BANK Made changes as requested. SAT. 7/26/2010 53 H 2 S O76A201 Question appears to match the K/A. SAT NEW

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q= SRO U/E/ Explanation Focus Dist. Link units ward K/A Only S 54 F 2 S 078K2.02 Question appears to match the K/A. SAT BANK 55 F 2 X E 103A3.01 Question appears to match the K/A.

Remove the second bullet in the stem. Then state WOOTF indicates where an operator is able to determine if 1-FCV-81-12 is in its correct position.

Distractor B is very weak. Need to replace it.

NEW Made changes as requested 8/05/2010.

56 H 2 X X X E 002K6.07 Kind of a backwards way of addressing the K/A. (Not really a malfunction or Loss) I realize that they are being secured for maint. Where does Mode 2 begin? Some plants declare mode 2 as soon as the RT Breakers are closed. If two loops are required in mode 3 and two loops are in operation, then the question is okay.

NEW Made changes as requested 8/05/201 0.

57 H 2 E 014A1.04 Question appears to match the K/A.

Question is similar to question 82 on the SRO exam.

Could be double jeopardy question for SROs. Will Discuss. May be okay if question 82 is changed.

NEW Replaced question 8/05/2010.

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q= SRO UIFJ Explanation Focus Dist. Link unitsi ward K/A Only S 58 H 2 S 015A3.08 Question appears to match the K/A. SAT MODIFIED 59 H 2 X E 016K3.06 Question appears to match the K/A.

Distractors B and C are not plausible. If the signal failed low, why would I lower the output and vice versa for C. We need to change these distractors.

We are not talking about opening or closing being reversed, but controller output.

NEW Upon discussion left question as is. (several controllers operate opposite of each other. SAT 8/05/2010.

60 F 2 X E 028K2.01 Question appears to match the K/A. Not very discriminating. How many of these buses supply safety related loads?

BANK After discussion no changes SAT 8/05/201 0.

61 F 2 S 035G2.1 .20 Question appears to match the K/A.

SAT MODIFIED

2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- 0= SRO U/E/ Explanation Focus Dist. Link units ward K/A Only S 62 F 2 S 056 G2.1.32 Question appears to match the K/A WBN bank question SYSO14A.08 003 changed but not called a bank modified question.

BANK 63 H 2 S 072 K4.03 Question appears to match the K/A WBN bank question SYSO3O 002 MODIFIED 64 H 2 X X U 079 Ki .01 Question does not appear to match the K/A. This question does not test either the physical connections or a cause effect relationship between the Control Air subsystem and the Service Air subsystem. It instead focuses on the compressors which are the common supply to both subsystems.

The distractors all involve switch and control signal alignments. Only the correct answer involves a condition (depressurized) on the system.

NEW Continue to work on question 7/26/2010. Wrote a new question testing isolations setpoints. SAT 7/27/2010.

2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q SRO U/E/ Explanation Focus Dist. Link units ward K/A Only S 65 H 2 S 086 A2.04 Question appears to match K/A. Delete has from the first part of the stem. Otherwise SAT NEW Reworded question to reduce words, SAT 8/05/2010.

66 F 2 E G 2.1.15 Question appears to match K/A .The examples provided in the distractor analysis for the plausibility of 60 days and 7 days as credible distractors (i.e., surveillance frequency, LERs, LCO times) does not provide a lot of confidence that these times are plausible given the context of the question. Are there other examples or times that link back to temporary activities (e.g., temporary change notices or procedure changes, etc.) that would either support these times or be more credible as distractors? Maybe like 90 days?

BANK Changed two distractors to 90 days, Discussed plausibility of others SAT 8/05/2010.

67 F X X U G 2.1.18 The question doesnt test the K/A (i.e.,

ability to make accurate, clear, and concise log entries....). The first half of the question requires the applicant to know when log entries are required and the second half of the question requires the applicant to know the narrative log review requirements for watch standing. Nothing in the question tests the applicants knowledge of the information required to be entered in the log for reactivation. Would recommend revising the second half of the question to ask the information that must

2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q# LOK LOD (F/H) (1-5) Stem Cues Focus TIF Dist. Link I

Cred. Partial Job- Minutia #1 Back-units ward 1

Q=

K/A SRO Only U/E/

S Explanation be recorded in the log for reactivation (See step 3.34.4 of OPDP-1O for requirements). The first Part (1) does not make sense as written log entries are required to be made for: only at the beginning, or for at the beginning?

MODIFIED Added a new second part and changed the stem.

SAT 7/26/2010.

68 F 2 X S G 2.1.45 Question appears to match K/A. Distractors C and D are not plausible. I have never heard of too much bypass flow. (maybe spray flow?).

MODIFIED After discussion left question as originally written. SAT 7/26/2010.

69 F 2 X E G.2.2.15 Question appears to match K/A. Add identified the only... Use of the phrase could be controlling in the stem leads the reader to think in terms of physical control of the valve position rather than administrative control. Recommend replacing the above phrase with can be used for configuration control of.

MODIFIEDSAT Completely changed question.

8/05/2010.

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- 0= SRO U/El Explanation Focus Dist. Link units ward K/A Only S 70 F 2 X E G 2.2.18 Question appears to match the K/A. Based on the distractor analysis it appears choice D is also correct (i.e., keeping the OSSDM log open to track the equipment will provide protection.) Is this in accordance with a specific procedure?

NEW Fixed distractor analysis. SAT 8/05/2010.

71 F 2 S G 2.3.5 Question appears to match the K/A. SAT NEW (There may be a similar question to this one we need to check) Changed the other question. SAT 8/05/2010.

72 H 2 X E G 2.3.11 Question appears to match the K/A. Drop the lAW GO-5 from the stem. It adds nothing to the stem other than more words. Drop the words to minimize the radiation release. The applicant should recognize a radiation release is in progress given the plant conditions.

MODIFIED SAT 8/05/2010.

2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q# LOK LOD (F/H) (1-5) Stem Cues TIF Cred. Partial Job- Minutia #1 Back- Q= SRO U/El Explanation Focus Dist. Link units ward K/A Only S 73 F 2 X E G2.4.16 Question appears to match the K/A.

Wording on the second part of stem is confusing.

Couldnt it be simplified after the fill-in-the-blank to just read .concurrently with ES-O.1 without being directed by ES-O.1.?

You could also have the stem read something like:

Which one of the following describes when E-O Reactor Trip and / or Safety Injection is applicable, and when can an AOl be performed when in the Emergency procedures lAW Tl12.04? Then have four distractors (one being correct) for the applicant to choose from.

A. Modes 1-4...

B. Modes 1-3...

C. Modes 1-4 D. Modes 1-3...

NEW Made changes as requested. SAT 8/05/2010.

2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q# LOK LOD (F/H) (1-5) Stem Cues TIE Cred. Partial Job- Minutia #1 Back- Q= SRO U/E/ Explanation Focus Dist. Link units ward K/A Only S 74 F 2 X U G2.4.34 The question kind of matches the K/A. The second part of the question focuses on actions to be performed on task completion but not on identifying the operational effects of task performance. This should be tied closer to resultant operational effects.

The second part of the question stem also asks for operational status, but the choices list possible actions that may be taken rather than providing operational status of the cold leg accumulators. In addition, mixed terminology in the choices is confusing circuits/components are energized / de energized; breakers are open / closed.

With a LOCA and a loss of offsite power, it pretty much cues the examinee that not all of the CLA isolation valves are going to operate, making choices A and B implausible. Could improve plausibility by providing specific combinations of CLA isolation valves (i.e., Train A valves vs- Train B valves) that will be energized upon completion of the H attachment. Some of the information in the stem

. could also be reduced.

Bank (Vogtle 2009, Q# 6)

Changed stem and all distractors. Now a new question SAT 7/26/2010.

75 F 2 S G2.4.35 Question appears to match the K/A.

Modified

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- 0= SRO U/El Explanation Focus Dist. Link units ward K/A Only S 31 Sats, 18 Unsats, and 26 Enhancements

ES-401, Rev. 9 Watts Bar 2010-301 SROWritten Examination Review Worksheet FINAL Form ES-401 -9

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job Minutia #/ Back- Q= SRO U/E/ Explanation Focus Dist. - units ward K/A Only S Link Instructions

[Refer to Section D of ES-401 and Appendix B for additional information regarding each of the following concepts.]

Enter the level of knowledge (LOK) of each question as either (F)undamental or (H)igher cognitive level.

2. Enter the level of difficulty (LOD) of each question using a 1 5 (easy difficult) rating scale (questions in the 2 4 range are acceptable).

3. Check the appropriate box if a psychometric flaw is identified:

• The stem lacks sufficient focus to elicit the correct answer (e.g., unclear intent, more information is needed, or too much needless information).

• The stem or distractors contain cues (i.e., clues, specific determiners, phrasing, length, etc).

• The answer choices are a collection of unrelated true/false statements.

• The distractors are not credible; single implausible distractors should be repaired, more than one is unacceptable.

• One or more distractors is (are) partially correct (e.g., if the applicant can make unstated assumptions that are not contradicted by stem).

Check the appropriate box ifajob content error is identified:

• The question is not linked to the job requirements (i.e., the question has a valid KIA but, as written, is not operational in content).

• The question requires the recall of knowledge that is too specific for the closed reference test mode (i.e., it is not required to be known from memory).

• The question contains data with an unrealistic level of accuracy or inconsistent units (e.g., panel meter in percent with question in gallons).

• The question requires reverse logic or application compared to the job requirements.

5. Check questions that are sampled for conformance with the approved KIA and those that are designated SROonly (K/A and license level mismatches are unacceptable).

6. Based on the reviewers judgment, is the question as written (U)nsatisfactory (requiring repair or replacement), in need of (E)ditorial enhancement, or (S)atisfactory?

7. At a minimum, explain any U ratings (e.g., how the Appendix B psychometric attributes are not being met).

ES-401, Rev. 9 Watts Bar 201 0-301 SROWriften Examination Review Worksheet FINAL Form ES-401 -9

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job Minutia #1 Back- Q= SRO U/E/ Explanation Focus Dist. - units ward K/A Only S Link Instructions

[Refer to Section D of ES-401 and Appendix B for additional information regarding each of the following concepts.]

Enter the level of knowledge (LOK) of each question as either (F)undamental or (H)igher cognitive level.

2. Enter the level of difficulty (LOD) of each question using a 1 5 (easy difficult) rating scale (questions in the 2 4 range are acceptable).

3. Check the appropriate box if a psychometric flaw is identified:

• The stem lacks sufficient focus to elicit the correct answer (e.g., unclear intent, more information is needed, or too much needless information).

• The stem or distractors contain cues (i.e., clues, specific determiners, phrasing, length, etc).

• The answer choices are a collection of unrelated true/false statements.

• The distractors are not credible; single implausible distractors should be repaired, more than one is unacceptable.

• One or more distractors is (are) partially correct (e.g., if the applicant can make unstated assumptions that are not contradicted by stem).

4. Check the appropriate box if ajob content error is identified:

• The question is not linked to the job requirements (i.e., the question has a valid K/A but, as written, is not operational in content).

• The question requires the recall of knowledge that is too specific for the closed reference test mode (i.e., it is not required to be known from memory).

• The question contains data with an unrealistic level of accuracy or inconsistent units (e.g., panel meter in percent with question in gallons).

• The question requires reverse logic or application compared to the job requirements.

5. Check questions that are sampled for conformance with the approved K/A and those that are designated SRO-only (K/A and license level mismatches are unacceptable).

6. Based on the reviewers judgment, is the question as written (U)nsatisfactory (requiring repair or replacement), in need of(E)ditorial enhancement, or (S)atisfactory?

7. At a minimum, explain any U ratings (e.g., how the Appendix B psychometric attributes are not being met).

2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job Minutia #1 Back- Q SRO U/E/ Explanation Focus Dist. - units ward K/A Only S Link 1/76 H 2 X E 022AA2.04 Question appears to match the K/A.

Appears to be SRO Only. Some items in the stem are not required. If the unit is at 100%, is it not at NOP and NOT? Second part of question (2) needs to be reworded. As written this is very hard to understand what you are asking.

BANK Made changes to stem to clarify. SAT 7/26/2010 Replacement Question of 911312010: question appears to match the KIA. Distractors B and D are not plausible. During a loss of off-site power the reactor will be tripped. Maintaining the RCS and Pressurizer boron concentration is not a large issue when the reactor is shutdown, so why would this be in the basis? (Gerry) 911312010. Removed off-site power condition from question. SAT Gerry 2/77 H 2 X X X U 025AA2.03 Question appears to match the K/A.

Which procedure is the required procedure to enter?

Starting the distractors with IF is not a good idea and is not normally allowed. Need to rework the stem and distractors. As written I could argue B is correct.

Does not appear to be SRO only.

NEW Made changes to stem and all distractors. TS basis

2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q# LOK LCD (F/H) (1-5) Stem Cues TIF Cred. Partial Job Minutia #1 Back- Q= SRO U/El Explanation Focus Dist. - units ward K/A Only S Link SG level to determine operability of loops.

SAT 7/26/2010 H 2 X X X U 027AA2.09 Question appears to match the K/A. I do 3/78 not believe that it is SRO only. If the applicant understands that the PORV with excessive seat leakage is a one hour tech spec, he can rule out PORV 340A. (Using RO Knowledge) and using RO knowledge understand that the SSPS did not have a failure. The applicant could arrive at the correct answer without using SRO knowledge. Need to find a way to have the applicant make a choice using SRO knowledge.

The stem of the question states that Reactor Power is at 8%, and then reiterates that power is stabilized at 8%. Why is this mentioned twice? Could be viewed as cueing. (Nothing happened in the question that would have changed reactor power). I realize that you state it again to inform the applicant that a reactor trip did not occur. Change the stem to read:

Pressurizer pressure drops to approximately 1940 psig and begins to recover. Reactor power remains at 8 %.

NEW Wrote a new question will review and get a second opinion. 712612010.

No reference, question Okay waiting on Licensee. SAT 8!10l2010.

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q# LOK LCD (F/H) (1-5) Stem Cues TIE Cred. Partial Job Minutia #1 Back- Q= SRO U/E/ Explanation Focus Dist. - units ward K/A Only S Link H 2 X E 056AG2.4.41 Question appears to match the K/A.

4/79 Question appears to be SRO only. Second part of distractor needs to be changed to something like:

What is the maximum amount of time available until the TEMA would be called directly in accordance with theEPlP-2.

Modified.

Made changes as requested SAT 7/26/2010 Made additional changes on 813112010 based on validation comments.

Licensee submitted a replacement question on 911 3I2010. Question appears to match the KIA and is SRO only. Distractors A and C are not plausible. The agency to notify was also tested on the A.4 Admin JPM. The original question also had the applicant decide between and NOUE and an Alert, this question has them decide between a NOUE and an SAE. Why change this part of the question? UNSAT Gerry 911 3I201 0.

Changed question back to NOUE and Alert, SAT Gerry

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job Minutia #1 Back- Q SRO U/E/ Explanation Focus Dist. - units ward K/A Only S Link H 2 X U 065AG2.4.21 Question appears to match K/A. Does 5/80 not appear to be SRQ only knowledge. It is systems knowledge to know that a loss of air will affect RCS inventory and feed flow. (air controlled valves). There is not any procedure selection in this question, just the safety functions that would be affected. ROs are required to know the entry conditions for ESF safety functions. Stem needs to be clearer.

• A loss of all control and essential air has occurred on Unit 1.

• The reactor was tripped and a transition to ES-0.1 has been made.

Which one of the... .Need to make it SRO only.

NEW Wrote new question will look at it and get another examiner to review also. (Specifically for SRO knowledge). 712612010.

All yellow paths, gray area, will allow. No reference allowed. Question SAT 8I1 01201 0.

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q# LOK LCD (F/H) (1-5) Stem Cues T/F Cred. Partial Job Minutia #1 Back- Q= SRO U/E/ Explanation Focus Dist. - units ward K/A Only S Link H 2 E WEIIEG2.1.30 Question appears to match the K/A.

6/81 Question appears to be SRO only. Some stem modification is required. There is way too much information listed. Try: The crew is performing the actions of ECA 1.1 due to a ISLOCA outside of containment and is at the step to check Aux Air pressure. SI termination criteria has just been met Which one of the following describes O-FCV-32-82 and 85 will be controlled and When talking about controls, are there any controls on the MCB like indicating lights, or position indicators? If there are we may need to change the wording. This could be appealed.

NEW Made changes as requested. SAT 7/26/2010 Licensee submitted a replacement question on 911312010. Question appears to match the KIA, and is SRO only. The change adds a statement that includes ... valves 0-FCV-32-82, and 32-85 are closed if Aux Air Pressure is less than 75 psig. I realize that this is a value from the procedure, but is it a setpoint that could help answer other questions. (these valves are in the RNO column), and if they were to be verified could this be done on 1-M-15? If not then the original question is satisfactory. Used original question. GERRY

2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job Minutia #1 Back- Q= SRO U/E/ Explanation Focus Dist. - units ward K/A Only S Link H 1 X X U 005AG2.1.32 Question appears to match K/A. Does 7/82 not appear to be SRO only. While this is a bases in Technical Specifications, it is also tested on the GEE exam which both ROs and SROs take. Distractors C and D are not plausible. How would one stuck or mis-positioned control rod affect flux shape? In fact one control rod is typically full out on most safety analysis. The distractor that states; The banks most withdrawn rod must be within 12 steps of the leas withdrawn rod is not plausible either. How would you ever do a startup? It should state of the banks least withdrawn rod. Question needs to be re-written.

Modified.

Modified question, stem and distractors, will have another examiner check to ensure SRO only. (not GFES) 712612010.

Not SRO only reviewed by three examiners.

Replace question 811 0I201 0. Replaced question SAT 811 1I201 0.

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job Minutia #1 Back- Q= SRO U/E/ Explanation Focus Dist. - units ward K/A Only S Link H 2 X U 024AA2.03 Question appears to match the K/A.

8/83 Does not appear to be SRO only. The value used in the question is listed in the Indications section of the AOl. This is RO knowledge. Knowledge of what occurs on a Boric Acid deviation alarm is systems knowledge, also RO knowledge.

NEW Made changes to stem and distractors.

Connected the basis to a singular TR.(3.1.6) SAT 712612010.

2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q# LOK LOD [ }

(F/H) (1-5) Stem Cues T/F Cred. Partial Job Minutia #1 Back- Q= SRO U/E/ Explanation Focus Dist. - units ward K/A Only S Link F 2 X E 060AG2.4.3 Question appears to match the K/A.

9/84 Question does have an SRO aspect to it. Need to tighten question up. There are many radiation monitors that Could detect this leak. Some could be local area monitors; some could be monitors in other areas that would be affected by the release etc. Why would anyone pick a PAM monitor (no accident is in progress) and these are typically containment radiation monitors? This leak will not b seen by any containment radiation monitors. Try ODCM on Not ODCM required by tech specs or EPIP.

NEW More work to do. 7/26/2010 Replaced Question SAT 8/11/2010 Licensee requested changes on 9/13/2010 because question was Artificially Difficult. The Licensee is making an attempt to make the question easier. One bullet in the original stem gives the conditions of the plant that would require the ABGTS to be in ser,ice. The new version just states that ABGTS is in service, and normal aux building ventilation is shutdown.

Either way it is still SRO only, but the original question is SAT also. Used the version without the statement of ABGTS in the Stem. Sat Gerry

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q# LOK LCD (F/H) (1-5) Stem Cues TIF Cred. Partial Job Minutia #1 Back- Q= SRO U/E/ Explanation Focus Dist. - units ward K/A Only S Link H 2 X X X X U 061AA2.O1 Question appears to match the K/A.

Question does not appear to be SRO only. What is 10/85 the normal status of ABGTS when moving or shuffling fuel?

If the applicant knows 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> technical specifications (RO knowledge) distractors a and b can be eliminated. Knowing how many trains of a system are required to satisfy its safety related function (typically 1) the applicant would arrive at the correct answer with only RO knowledge. Also all distractors state an ABGTS train is required.. .this tends to lead the applicant to selection of one train.

May not have a correct answer. To move fuel I dont need to have any ABGTS is service for 7 days, is that correct? I believe you are asking if I no longer have auto start signal capability, then one train is required to be started lAW 3.3.8. This is very confusing and seems like backwards logic.

NEW Changed Stem and all Distractors. (still somewhat backwards logic) But SRO has to make operability call. SAT 712612010 Changes were requested on 813112010 and a replacement question was submitted. However no changes were made because there was not a technical basis to replace the question. On 911 3(2010 the Licensee submitted the replacement question again with several others.

The first half of the question is very similar to the

2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q# LOK LOD (F/H) (1-5) Stem Cues TIF Cred. Partial Job Minutia #1 Back- 0= SRO U/E/ Explanation Focus Dist. - units ward K/A Only S Link original, only the timesIcondition is reversed.

(This is RO knowledge). The second part of the question asks If conditions required by tech specs can be established at 1400 to allow continued fuel movement with the current status of the spent fuel pit area radiation monitors?

These conditions are already satisfied up in the stem. Allowing a reference would make this a direct lookup. Not really sure it is SRO only.

GERRY Allowed the question without a reference.

1 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q# LOK LCD (F/H) (1-5) Stem Cues T/F Cred. Partial Job Minutia #1 Back- Q SRO U/El Explanation Focus Dist. - units ward K/A Only S Link 2 F X U 003A2.03 Question kind of matches K/A. Does not appear to be SRO only. Typically lAW SRO 11/86 guidance, the SRO portion is procedure selection, or selecting a path within the procedure. This does not have either part. This is procedure entry requirements (RO knowledge) and RCP Immediate trip criteria RO knowledge. Furthermore with the unit in mode 4 and these indications, why would anyone wait for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to secure the RCP? In reading the procedure there are not any specific items that state parameters that allow pump operation or direct tripping the pump within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

MODIFIED Need to look at closer. Still needs to work.

712612010.

S Asked for another KIA. Replaced with 003A2.01 Wrote Question for New KIA. SAT 811112010. When KIA was replaced the U was removed and the replacement Question was SAT Based on validation, the licensee asked for the question to be changed. The change allowed the question to be answered using RO knowledge.

Chief Examiner did not replace question 8I31I2010 The Licensee submitted a replacemeni question on 9I1 312010 The replacement question lists in the stem Annunciator 97-C RCP 3 Standpipe level HIILO is DARK.

Appendix E of NUREG-1 021 states: When answering a question, do not make assumptions

2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job Minutia #1 Back- Q= SRO U/E/ Explanation Focus Dist. - units ward K/A Only S Link regarding conditions that are not specified in the question unless they occur as a consequence of other conditions that are stated in the question. For example, you should not assume that any alarm has activated unless the question so states or the alarm is expected to activate as a result of the conditions that are stated in the question. Therefore this must be removed from the question. Otherwise, the replacement question appears to be acceptable. Made changes as requested SAT GERRY 2 H S 005A2.O1 Question appears to match K/A, and appears to be SRO only. First part (1) should read 12/87 something like what action is directed by the procedure to mitigate the pumps symptoms lAW GO 10 and Otherwise SAT Modified

2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job Minutia #1 Back- Q SRO U/E/ Explanation Focus Dist. - units ward K/A Only S Link Made changes as requested Still SAT 7/26/2010 13/88 H 2  ? E 013G2.2.12 Question does not appear to match the K/A. May be SRO only. This question does discuss surveillance requirements, but for the Reactor Protection system, not the engineered Safety Features Actuation system. The second part of the question (2) is confusing, Why do you consider this anESF surveillance? I listed question as enhanced because we may be able to salvage it by changing the surveillance.

NEW Determined that ESF equipment is also Checked in the test. SAT 7/26/2010 H 2 X U 059A2.03 Question appears to match the K/A. Does 14/89 not appear to be SRO as written. RO must know the entry requirements for major and E-O is a major procedure. I realize that you are treating this as a transition but this is common knowledge. When E-O is complete (SI not present) transition is to ES-O.1.

This is RO knowledge.

NEW Rewrote question to include reporting requirements. SAT 712612010.

1 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job Minutia #1 Back- Q= SRO U/E/ Explanation Focus Dist. - units ward K/A Only S Link H 2 X E 078G2.4.4 Question appears to match the K/A.

15/90 Appears to be SRO only. I have read your background document, but I am not convinced that the TDAFW pump is still considered operable.

This is also from your technical specification basis document on B-3.7-27 The AFW System is considered OPERABLE when the components and flow paths required to provide redundant AFW flow to the steam generators are OPERABLE. This requires that the two motor driven AFW pumps be OPERABLE in two diverse paths, each supplying AFW to separate steam generators.

The turbine driven AFW pump is required to be OPERABLE with redundant steam supplies from each of two main steam lines upstream of the MSIVs, and shall be capable of supplying AFW to any of the steam generators. The piping, valves, instrumentation, and controls in the required flow paths also are required to be OPERABLE.

So my question is, is the TDAFW pump still OPERABLE?

If not, the correct answer would be B. Can this be argued in appeal space?

Licensee made a change to make B Correct (two trains mop). SAT 7/26/2010

2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job Minutia #1 Back- Q= SRO U/El Explanation Focus Dist. - units ward K/A Only S Link F 2 X U 034K5.03 Question appears to match the K/A.

16/91 Question is not SRO only. Note prior to the line states that the RHR pump may be secured... This is RO knowledge. The note also states that no operations are conducted that would cause reduction of the reactor coolant systems boron concentration.

NEW Replaced question with another new question SAT.

7I26I2010.

Based on validation removed Basis from stem.

81311201 0.Licensee did further validation, and submitted a new question on 911312010. New question submitted essentially tells the operator that fuel movement is allowed, and asks if valve testing is allowed without entry in TS 3.9.5. This should state with fuel movement still in progress.

Distractors B and 0 are not plausible. Used the initial replacement question. SAT GERRY

2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job Minutia #1 sack- Q SRO U/E/ Explanation Focus Dist. - units ward K/A Only S Link F 2 X U 041 A2.03 Question appears to match the K/A.

17/92 Question is not SRO only.

What directs the operators to go to SQl-I .02? Is there a step in the loss of Air AOl that directs them to go to the SOl? Is this just common knowledge?

Does the GO direct this procedure entry? Can atmospheric relief valves be used?

NEW Rewrote question using procedures for control of the wire lift. This appears to be SRO only.

New Question SAT 7/2612010. During validation discovered a procedure Issue. Went back to the original version of the question and included administrative procedures that were used to conduct the action to notify the operators of the wire lift. SAT 8116/2010. Made additional changes after more validation 8131I2010.

Licensee sent in a replacement question on 9I1 3I201 0, (actually just a modification) appears to be acceptable. SAT GERRY F 2 E 079G2.1.20 Question appears to match the K/A.

18/93 Question appears to be SRO only. Distractors A and B should both start out, Declare the valve inoperable or the valve is inoperable. The stem should state:

Which one of the following actions must be taken lAW STP... We could also better line up the question so that it is easier for the applicants to read.

Does the plant always perform a second test? There

Ii fl Q#

1 LOK 1 2.

LOD

3. Psychometric Flaws 4. Job Content Flaws 1 5. Other 6. 7.

(F/H) (1-5) Stem Cues T/F Cred. Partial Job Minutia T-1 fl #/ Back- Q= SRO U/E/ Explanation IL Focus Dist.

Link units K/A Only S is an option to just declare the valve inoperable. I think the question is asked at the fundamental level.

NEW Made changes as requested. SAT 7/26/2010 F 2 E 02.1.21 Question appears to kind of match the K/A.

19/94 How do I know that the ODMI in the Standing orders is the controlled copy? I have seen in the standing orders several that are different revisions? How do I know that an ODMI is in a standing order? ( I looked at several and did not see one listed) I did look at the standing order index page, but none of these listed an ODMI reference. I did not see anything labeled as trigger points. If we use this question the top of the question could be removed and the stem read: Which one of the following identifies how the SRO will determine the controlled copy of an ODMI in accordance with OPDP-11?

Appears to be SRO only.

NEW Need to look at this one to ensure question is correct. SAT 7/26/2010. Based on another Issue.

Need to have another examiner look at it.

Removed all items in the stem, reconstructed stem and all distractors. SAT 7/27/2010

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job Minutia #1 Back- Q= SRO U/E/ Explanation Focus Dist. - units ward K/A Only S Link F 2 S G2.1.8 Question appears to match the K/A. Appears 20/95 to be SRO only. Distractors C and D should start the same way. Either After being notified of the task...

or The OSC will be notified of the task... Otherwise SAT NEW F 2 E G2.2.43 Question appears to match the K/A.

2 1/96 Appears to be SRO only. This question was on the 2009 Seq. Retake as mentioned. We can modify this question by simply stating that it will be approximately 3.5 months before parts arrive to fix the annunciator or something similar. We do not have to test the exact same item. Please modify in some way, so that one of the other answers is correct.

BANK 2009-302 SEQ. Retake Modified question to make D the correct answer. SAT. 712712010.

F X U G2.2.7 Question appears to match the K/A.

22/97 Question appears to be SRO only. Distractors C and D are not plausible. The CIPTE may not even be a licensed individual so how could he be responsible?

The Shift Manager is always responsible.

Need to change the second part of the question.

Maybe we could ask: Who is the minimum approving authority for permission for the test/evolution to be conducted?

BANK

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q# LOK LCD (F/H) (1-5) Stem Cues T/F Cred. Partial Job Minutia #1 Back- Q= SRO U/E/ Explanation Focus Dist. - units ward K/A Only S Link Rewrote question SAT 712612010.

G2.3.15 Question appears to match the K/A.

Question appears to be SRO only. Need to see the bank question (not included) to ensure that it is modified. Otherwise SAT

2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job Minutia #1 Back- 0= SRO U/E/ Explanation Focus Dist. - units ward K/A Only S Link F 1 X X U G2.3.5 Question appears to match the K/A.

24/99 Question does have an SRO link to it, but the first part of the question is not really discriminating. You cannot challenge the containment (radiation wise) without a fuel clad failure. Question may also contain cueing in stem, (without a failed clad how would radiation levels go up unless the conditions in the stem caused them to go up? Need to work on this question. If the conditions in containment cause the monitors to indicate higher than actual Then this is what we should be asking. If you changed this to a LOCA, would this be the same.

NEW Changed stem and distractors to make question work. SAT 712612010.

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job Minutia #1 Back- Q SRO U/El Explanation Focus Dist. units ward K/A Only S Link F 2 X U G2.2.44 Question appears to match the K/A.

251100 Question appears to be SRO only. I do not believe distractors C and D are plausible. I do not know of anywhere in the U.S. that you can declare a General Emergency and not give PARs. It is always required.

At some plant the SAE classification allows PARS and I dont have a problem testing this. I know that it is not on the form, but if conditions warranted it I think that PARS would be given to the state or local EOC if requested.

NEW Wrote new question SAT 712612010.

4Sats, 12 Unsats, and 9 Enhancements