ML110350577

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Initial Exam 2010-302 Draft Administrative Documents
ML110350577
Person / Time
Site: Sequoyah  Tennessee Valley Authority icon.png
Issue date: 02/04/2011
From:
NRC/RGN-II
To:
Tennessee Valley Authority
References
50-327/10-302, 50-328/10-302
Download: ML110350577 (20)
v • d • e


Text

ES-401, Rev. 9 PWR Examination Outline Form ES-401-2 Facility: 4f- Date of Exam: Zc) l 3o +/-3(-\ ..v\

RO K/A Category Points SRO-Only Points Tier Group KKKKKKAAAAG A2 0* [Total 1 2 3 4 5 6 1 2 I

3 4 Total

1. 1 3 3 3 3 3 3 18 3 3 6 Emergency&

Abnormal Plant 2

  • 2 1 1 9 2 2 4 N/A N/A Evolutions Tier Totals 5 4 4 27 5 5 10 1 32333223232 28 3 2 5 2.

2 1 1 1 11 01 11 1 1 10 2 1 Plant 3 Systems Tier Totals 4 3 4 44 2 3 4 3 4 3 38 5 3 8

3. GenericKnowledgeandAbilitiesj 1 2 3 4 10 1 2 3 4 7 Categories 2 2 3 3 1 2 2 2
1. Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category In Tier 3 of the SRO-only outline, the uTler 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 +/- I 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 section 0.1 .b of ES-401 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.
5. Absent a plant-specific priority, only those K/As having an importance rating (IR) of 2.5 or higher shall be selected.

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

6. Select SRO topics for Tiers I 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. Refer to section 0.1 .b of ES-401 for the applicable KA5.
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 (Note # I does not apply). 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..

ES-401, REV 9 T1G1 PWR EXAMINATION OUTLINE FORM ES-40I-2 KA NAME I SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 008AK2.02 Pressurizer Vapor Space Accident / 3 2.7 2.7 Li Li Li Li Li Li Li Li IL] Li Sensors and detectors O11EK2.02 Large Break LOCAI3 2.6 2.7 Li ] Li Li Li Li LI Li El fl Li Pumps 022AA2.01 Loss of Rx Coolant Makeup? 2 3.2 3.8 LI LI Li Li Li Li Li : Li jL] Whether charging line leak exists 025AG2.1 .7 Loss of RHR System /4 4.4 4.7 Li Li Li F] Li Li Li Li Li Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior and instrument interpretation.

026AK3.01 Loss of Component Cooling Water / 8 3.2 3.5 Li Li 1 [1 Li Li LiLiLILiE The conditions that will initiate the automatic opening and closing of the SWS isolation valves to the CCWS coolers 027AA1 .05 Pressurizer Pressure Control System 3.3 3.2 Malfunction I 3 Li Li Li Li Li Li Li Li El LI Transfer of heaters to backup power supply 029EG2.4.31 ATWS I 1 4.2 4.1 F] Li LiLi Li Li LiLiLi F] Knowledge of annunciators alarms, indications or response procedures 038EA1.17 Steam Gen. Tube Rupture/3 3.2 3.2 LI Li Li Li Li Li Li Li Li Li S/G sample isolation valve indicators 054AA2.07 Loss of Main Feedwater / 4 3.4 3.9 Li Li Li Li Li Li Li ] Li Li Li Reactor trip first-out panel indicator 056AA2.56 Loss of Off-site Power/6 3.6 3.7 Li Li Li Li Li. Li Li ] LI LI Li RCST-ave 057AK3.0l Loss of Vital AC Inst. Bus /6 4.1 4.4 Li Li Li Li El Li Li LI Li Actions contained in EOP for loss of vital ac electrical instrument bus Page 1 of 2 01/07/2010 2:20 PM

ES-401, REV 9 TIGI PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 058AK1 .01 Loss of DC Power! 6 2.8 3.1 LI El LI LI LI fl LI Battery charger equipment and instrumentation 062AA1.7 Loss of Nudear Svc Water) 4 2.9 3 El [J Flow rates to the components and systems that are serviced by the SWS; interactions among the components 077AK1 .03 Generator Voltage and Electric Grid 3.3 Disturbances /6 i LI LI El fl fl fl Under-excitation WEO4EKI.1 LOCA Outside Containment/3 3.5 3*9 E] fl [E Components, capacity, and function of emergency systems.

WEO5EK3.2 Inadequate Heat Transfer Loss of 3.7 4.1 Secondary Heat Sink / 4 LI LI LI LI fl LI LI LI LI Normal, abnormal and emergency operating procedures associated with (Loss of Secondary Heat Sink).

WE11EK2.1 Loss of Emergency Coolant Recirc. /4 3.6 3.9 LI ELI H LI LI LI LI LI LI Components and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes and automatic and manual features.

we 12 EG2. 4.3 Steam Line Rupture - Excessive Heat 3.7 3.9 Transfer I 4 LI L 1 LI LI fl LI LI H F1 Ability to identify post-accident instrumentation.

Page 2 of 2 01/07/2010 2:20PM

ES-401, REV 9 TIG2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 028AK2.02 Pressurizer Level Malfunction / 2 2.6 2.7 LI l LI LI LI LI LI LI LI LI LI Sensors and detectors 032AK3.02 Loss of Source Range NI / 7 3.7 4.1 LI LI LI LI LI LI LI LI Li LI Guidance contained in EOP for loss of source-range nuclear instrumentation 033AG2.4.30 Loss of Intermediate Range NI /7 2.7 4.1 LI LI LI Li LI LI LI LI LI LI Knowledge of events related to system operations/status that must be reported to internal orginizations or outside agencies.

036AK1.0l Fuel Handling Accident/8 3.5 4.1 LI LI LI LI LI LI LI LI LI LI Radiation exposure hazards 068AA1 .06 Control Room Evac. / 8 4.1 4.2 fl LI LI LI LI LI LI LI LI Li Charging pump 074EA1.23 mad. Core Cooling /4 Li LI LI LI LI LI LI LI LI LI PORV block valve indicators, switches, controls (for both RCS and S/G).

076AK3.06 High Reactor Coolant Activity / 9 3.2 3.8 LI LI LI LI LI LI LI LI L 1 LI Actions contained in EOP for high reactor coolant activity WE14EA2.1 Loss of CTMT Integrity / 5 3.3 3.8 LI LI LI LI LI LI LI iI LI LI LI Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

WE15EK1.2 Containment Flooding /5 2.7 2.9 LI LI LI Li LI LI LI LI LI LI Normal, abnormal and emergency operating procedures associated with (Containment Flooding).

Page 1 of 1 01/07/2010 2:20PM

ES-401, REV9 T201 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 003A4.03 Reactor Coolant Pump 2.8 2.5 [] fl flj fl El RCP lube oil and lift pump motor controls 004K4.08 Chemical and Volume Control 2.8 3.2 El El El El El El fl El El H Hydrogen control in RCS 004K5.29 Chemical and Volume Control 2.6 3.3 El El El LI [1 LI El El El LI Reason for sampling for chloride, fluoride, sodium and solids in RCS 005G2.4.46 Residual Heat Removal 4.2 4.2 LI El LI LI fl fl El LI Ability to verify that the alarms are consistent with the plant conditions.

006K2.04 Emergency Core Cooling 3.6 3.8 El 1 LI El LI LI El El LI LI El ESFAS-operated valves 007K1.03 Pressurizer Relief/Quench Tank 3.0 3.2 El LI LI El LI El RCS 008A2.08 Component Cooling Water 2.5 2.7 El LI El LI E] LI El LI LI El Effects of shutting (automatically or otherwise) the isolation valves of the letdown cooler 008K1.04 Component Cooling Water 3.3 3.3 El LI LI El LI LI [1 H El El RCS, in order to determine source(s) of RCS leakage into the CCWS 010K4.02 Pressurizer Pressure Control 3.0 3.4 El El El LI El El LI El LI El Prevention of uncovering PZR heaters 012A1 .01 Reactor Protection 2.9 3.4 El LI LI LI El LI El LI LI LI Trip setpoint adjustment 013K5.02 Engineered Safety Features Actuation 2.9 3.3 LI LI El El LI El LI El LI LI Safety system logic and reliability Page 1 of 3 01/07/2010 2:21 PM

ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 013K6.0l Engineered Safety Features Actuation 2.7 3.1 ri n fl El fl fl [] Sensors and detectors 022K3.01 Containment Cooling 2.9 3.2 El D El El El El El fl Containment equipment subject to damage by high or low temperature, humidity and pressure 025K5 02 Ice Condenser 2.6 2.8 F *El El fl fl Heat transfer 026A3.01 Containment Spray 4.3 4.5 [] fl fl Pump starts and correct MOV positioning 026A4.01 Containment Spray 4.54.3 [1 El El El El El [] El CSS controls 039A3.02 Main and Reheat Steam 3.1 3.5 El El El El El El LI [1 I LI fl Isolation of the MRSS 059K3.02 Main Feedwater 3.6 3.7 DLI I LI Li LI LI LI LI LI LI AFW system 059K3.03 Main Feedwater 3.5 37. LI LI LI LI LI TI LI LI LI LI S/GS 061 K6.02 Auxiliary/Emergency Feedwater 2.6 2.7 fl El* LI fl [2 LI LI LI LI LI Pumps 062G2.4.35 AC Electrical Distribution 3.8 4.0 LI LI LI LI El LI LI LI LI LI Knowledge of local auxiliary operator tasks during emergency and the resultant operational effects 063A4.01 DC Electrical Distribution 2.8 3.1 LI El LI LI El El LI LI LI LI Major breakers and control powerfuses Page 2 of 3 01/07/2010 2:21 PM

ES-401, REV 9 T2GI PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 064A2.05 Emergency Diesel Generator 3.1 3.2 Li El El El El El El i.

El Li Li Loading the EDIG 073A1.01 Process Radiation Monitoring 3.2 3.5 El El El fl El Li fl El El El Radiation levels 073K1 01 Process Radation Monitonng 36 39 C] El C] El El El El Li El Those systems served by PRMs 076K2.04 Service Water 2.5 2.6 El El C] IC] H Li El C] El El Reactor building closed cooling water 078K4.02 Instrument Air 3.2 3.5 C] fl El El Li El C] El El Cross-over to other air systems lO3A04 Containment 3.5 3.6 flC]flEl LIElEl Containment evacuation (including recognition of the alarm)

Page 3of3 01/07/2010 2:21 PM

ES-401, REV9 T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR Ki K2 K3 K4 K5 1<6 Al A2 A3 A4 G TOPIC:

RO SRO 001K2.03 Control Rod Drive 2.7 3.1 Li Li fl Li [Z One-line diagram of power supplies to logic circuits 002A4.02 Reactor Coolant 4.3 4.5 fl fl [] Fl Indications necessary to verify natural circulation from appropriate level, flow and temperature indications and valve positions upon loss of forced circulation 017K3.01 In-core Temperature Monitor 3.5 3.7 Li Li fl Li Natural circulation indications 0271<5,01 Containment Iodine Removal 3.1 3.4 El Li [1 Fl [] [] Li Li Li Purpose of charcoal filters 028A1 .02 Hydrogen Recombiner and Purge 3A3.7 Control El Li Li Li Li Li Li LID Containment pressure 034K4.03 Fuel Handling Equipment 2.6 3.3 LI LI LI El LI El LI El LI Li Overload protection 035G2.2.40 Steam Generator 3.4 4.7 El fl fl fl lZ Ability to apply technical specifications for a system.

055K1.06 CondenserAirRemoval 2.6 2.6 LI LI LI El fl LI fl fl PRMsystem 071A3.02 Waste Gas Disposal 2.8 2.8 LI LI LI LI LI E LI LI Pressure-regulating system for waste gas vent header 075A2.03 Circulating Water 2.5 2.7 LI LI LI LI LI Li LI LI El El Safety features and relationship between condenser vacuum, turbine trip and steam dump Page 1 of 1 01/07/2010 2:21 PM

ES-401, REV 9 T3 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO G2.l.38 onductof operations 3.7 3.8 5 5 5 5 5 5 5 5 5 5 Knowledge of the stations requirements for verbal communication when implamenting procedures G2.l.7 Conduct of operations 4.4 4.7 5 5 5 5 5 5 5 5 5 5 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior and instrument interpretation.

G2.2.ll Equipment Control 2.3 3.3 5 5 5 5 5 5 5 5 5 Knowledge of the process for controlling temporary design changes.

G2.2.19 Equipment Control 2.3 3.4 5 5 5 5 5 5 5 5 5 5  ; Knowledge of maintenance work order requirements.

G2.3.13 Radiation Control 3,4 3.8 5 5 5 5 5 Knowledge of radiological safety procedures pertaining to licensed operator duties G2.3.15 Radiation Control 2.9 3.1 5, 55 5 5 5 5 fl 5 5 Knowledge of radiation monitoring systems G2.3.4 Radiation Control 3.2 3.7 5 5 5 5 5 5 5 5 5 5 Knowledge of radiation exposure limits under normal and emergency conditions G2.4.28 Emergency Procedures/Plans 3.2 4.1 5 5 5 5 5 5 5 5 5 5 Knowledge of procedures relating to emergency response to sabotage.

G2.4.31 Emergency Procedures/Plans 4.2 4.1 5 5 5 5 5 5 5 5 5 5 . Knowledge of annunciators alarms, indications or response procedures G2.4.6 Emergency ProcedureslPlans 3.7 4.7 5 5 5 5 5 5 5 5 5 5 Knowledge symptom based EOP mitigation strategies.

Page 1 of 1 01/07/2010 2:21 PM

ES-401, REV 9 SRO T1GI PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 029EA2.06 ATWS / 1 3.8 3.9

[] E] LI Main turbine trip switch position indication 038EG2.2.40 Steam Geri, Tube Rupture! 3 3.4 4.7 rjF[] [Z LI Li LI LI Li Ability to apply technical specifications for a system.

054AG2.4.30 Loss of Main Feed water /4 2.7 41 fl fl fl fl fl Knowledge of events related to system operations/status that must be reported to internal orginizations or outside agencies.

055EA2.03 Station Blackout? 6 3.9 4.7 fl fl Actions necessary to restore power 058AG2.4.18 LossofDCPower/6 3.3 4.0 fl Lj LI Li LI Li Li Knowledge of the specific bases for EOPs.

077AA2.08 Generator Voltage and Electric Grid 4.3 4.4 Disturbances /6 Li LI LI LI Li LI Li LI rz E Criteria to trip the turbine or reactor Page 1 of 1 01/07/2010 2:21 PM

ES-401, REV 9 SRO TIG2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO OO1AA2.02 Continuous Rod Withdrawal 1 1 4.2 4.2 fl El [1 fl [] Position of emergency boration valve 060AG2.4.1 Accidental Gaseous Radwaste Rel. /9 4.6 4.8 fl fl Knowledge of EOP entry conditions and immediate action steps.

061AA2.Ol ARM System Alarms /7 3.5 3.7 1 ri Z El El El El El El El ARM panel displays 069AG2.4.21 Loss of CTMT Integrity I 5 4.0 4.6 Li El Li El El Li LI El Li } Knowledge of the parameters and logic used to assess the status of safety functions Page 1 of 1 01/07/2010 2:21 PM

ES-401, REV 9 SRO T2GI PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 012A2.O1 ReactorProtecon 3.1 3.6 El El El El El El El E] Faultybistableoperation 039A2.03 Main and Reheat Steam 3.4 3.7 [ El El El El El Indications and alarms for main steam and area radiation monitors (during SGTR) 076G2.4.3 Service Water 3.7 3.9 El El El El El El El El H El J Ability to identify post-accident instrumentation.

078A2.Ol histrumentAir 2.4 2.9 El El El El El El El El Airdryerandfiltermalfunctions 103G2.4.3 Containment 3.7 3.9 El El El El El El El El El El Ability to identify post-accident instrumentation.

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ES-401, REV 9 SRO T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 028A2.01 Hydrogen Recombiner and Purge 3.4 3.6 Hydrogen recombiner power setting, determined by using Control plant data book 068A2.04 - Liquid Radwaste Failure of automatic isolation 071 G2.2.36 Waste Gas Disposal 3.1 4.2 flj Ability to analyze the effect of maintenance activities.

such as degraded power sources, on the status of limiting conditions of operations Page 1 of 1 01/07/2010 2:21 PM

ES-401, REV 9 SRO T3 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO G2.l.27 Conduct of operations 3.9 4 fl El El Knowledge of system purpose and or function.

G2.2.18 Equipment Control 2.6 3.8 fl Knowledge of the process for managing maintenance activities during shutdown operations.

G2.2.40 Equipment Control 3.4 4.7 J fl El Ability to apply technical specifications for a system.

(32.3.12 Radiation Control 3.2 3.7 LI LI El El LI Knowledge of radiological safety principles pertaining to licensed operator duties (32.3.14 Radiation Control 3.4 3.8 LIfl LI LI LI LI LI LI LI LI Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities G2.4.30 Emergency Procedures/Plans 2.7 4.1 LI 1 LI LI LI El LI fl fl Knowledge of events related to system operations/sta tus that must be reported to internal orginizations or outside agencies.

(32.4.46 Emergency Procedures/Plans 4.2 4.2 1 LI El LI LI LI LI LI LI LI Ability to verify that the alarms are consistent with the plant conditions.

Page 1 of 1 01/07)2010 2:21 PM

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Sequoyah Nuclear Station 1 & 2 Date of Examination: 09107/2010_

Examination Level: RO SRO X Operating Test Number: 2010302 Administrative Topic Type Describe activity to be performed (see Note) Code*

M, R, P 2.1.5 Ability to use procedures related to shift staffing, such as minimum crew compliment, overtime Conduct of Operations limitations, etc.

Evaluate Overtime Restrictions N, R 2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc.

Conduct of Operations Review of Estimated Critical Position Calculation M, R 2.2.43 Knowledge of the process used to track inoperable alarms.

Equipment Control Review and Approve a Disabled Alarm Checklist D, R 2.3.4 Knowledge of radiation exposure limits under normal and emergency conditions.

Radiation Control Evaluate Worker Exposure D, R 2.4.38 Ability to take actions called for in the facility emergency plan, including supporting or acting as Emergency Procedures/Plan emergency coordinator if required.

Classify the Event per the REP (SGTR with Failed S/G Safety)

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)

Admin l.a This JPM has the candidate review several different work schedules and determine if any of the required work-hour rules were violated. This is a Bank JPM that was on the 2009 NRC exam but has been Modified.

Admin 1 .b This JPM has the candidate review a completed ECP calculation and identify any and all errors that were committed during the development of the ECP. This is a New JPM.

Admin 2 This JPM has the candidate review a Disabled Annunciator request and identify any and all errors that may have committed during the development of the request. This is a Modified Bank JPM.

Admin 3 This JPM has the candidate review projected workers dose for performing a job in the RCA and determine if any Federal or Administrative dose limits may be exceeded by any of the workers and which notifications would need to be made if the actual doses were to reach the estimated values. This is a Bank JPM.

Admin 4 This JPM has the candidate review the data presented during a proposed accident and determine the Emergency Event Classification and report any Protective Action Recommendations (PARs) which would appropriate for the accident. This is a Bank JPM.

ES-301 Administrative Topics Outline Form ES-301-1 Facility: ..Sequoyah Nuclear Station 1 & 2 Date of Examination:

Examination Level: RO X SRO Operating Test Number: 2010302 Administrative Topic Type Describe activity to be performed (see Note) Code*

M, R, P 2.1.5 Ability to use procedures related to shift staffing, such as minimum crew compliment, overtime Conduct of Operations limitations, etc A.1 .a Evaluate Overtime Restrictions N, R 2.1.7 Ability to interpret reference materials, such as graphs, curves, tables, etc.

Conduct of Operations A.1 .b Perform RCS Deboration Calculation D, R 2.2.12 Knowledge of surveillance procedures Equipment Control Boric Acid Storage Tank Level Operability Determination M, R 2.3.4 Knowledge of radiation exposure limits under normal and emergency conditions.

Radiation Control Determine Maximum Stay Time Emergency Procedures/Plan NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes)

(N)ew or (M)odified from bank ( 1)

(P)revious 2 exams ( 1; randomly selected)

Admin l.a This JPM requires the candidate to evaluate different schedules and determine if any of the required work-hour rules were violated. This is a Bank JPM that was used on the 2009 NRC exam which has been Modified.

Admin 1 .b This JPM requires the candidate to calculate the amount time that a de-borating demineralizer needs to be placed in service to reduce the desired RCS boron concentration during normal EOL plant operation. This is a New JPM.

Admin 2 This JPM requires the candidate to evaluate the conditions of a Boric Acid Storage Tank to determine if it meets the Tech Spec requirements. This is a Bank JPM.

Admin 3 This JPM requires the candidate to determine the expected dose they would receive while conducting tagging operations in the RCA. This is a Modified Bank JPM from a previous Watts Bar exam.

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Nuclear Station 1 & 2 Date of Examination: 09I07/20l0 Exam Level: RD X SRO-l X SAC-U Operating Test No.:

Control Room Systems (8 for AD); (7 for SAC-I); (2 or 3 for SAD-U, including 1 ESF)

System / JPM Title Type Code* Safety Function

a. 001 Control Rod Drive System; A2.17 (3.3/3.8) M, A, S, L 1 038-AP3 Shutdown Bank Withdrawal
b. 006 Emergency Core Cooling System; Al .13 (3.5/3.7) D, A, S 2 097-2AP Refill #3 CLA to within Normal Range
c. 007 Pressurizer Relief Tank System A2.02 (2.6/3.2) D, S 5 036 Return PAT to Normal
d. 003 Reactor Coolant Pump System; A1.02 (2.9/2.9) N, S 4P Sim. D Respond to Loss of Flow to RCP Oil Cooler
e. 064 Emergency Diesel Generation; A4.06 (3.9/3.9) D, S 6 046-1 Shutdown the Diesel Generators Following Auto Start
f. 015 Nuclear Instrumentation System; A4.02 (3.9/3.9) D, A, S 7 022-AP2 Calibrate Power Range Nis
g. 036 Fuel Handling Incidents AA2.02 (3.4/4.1) M, A, S, L 8 104-AP Initiate Makeup to the Refueling Cavity
h. W/E14 High Containment Pressure; EA1.1 (3.7/3.7) D,A,S 3 057-APi Respond to HI CNMT Pressure, Place RHR Spray In Service In-Plant Systems (3 for AD); (3 for SAC-I); (3 or 2 for SAD-U)
i. 063 D.C. Electrical Distribution; A4.01 (2.7/3.0) D 6 071 Spare out a Vital Ball Charger
j. 061 Auxiliary/Emergency Feedwater System; A2.07 (3.4/3.5) D, A, R 4S 024AP Local control of MD AFW Pump Flow
k. 002 Reactor Coolant System; A3.0i (3.7/3.8) D, R 8 072-2 Local Alignment of 2-RM-90-i 12 to Lower CNMT

@ All RD and SRO-l control room (and in-plant) systems must be different and serve different safety functions; all 5 SAD-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 / SRD-U (A)lternate path 4-6 / 4-6 I 2-3 (C)ontrol room (D)irectfrombank 918/4 (E)mergency or abnormal in-plant 1 / 1 / 1 (EN)gineered safety feature - / - / 1 (control room system)

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

(R)CA (S)imulator Sim A This JPM has the candidate identify misaligned control rods while attempting to withdraw the Shutdown banks in preparation for a reactor start-up. This is a Modified Bank, Low Power, Alternate Path JPM.

Sim B This JPM has the candidate refill a cold leg accumulator to its normal level, and then has the fill valve stick open requiring alternate methods to stop the fill. This is an Alternate Path, Bank JPM Sim C This JPM has the candidate return the PAT to normal temperature and pressure following a leaking PZR PORV. This is Bank JPM.

Sim D This JPM has the candidate determine that a loss of cooling has occurred to the RCP oil coolers which will require them to stop the affected RCP. This is a New JPM.

SIM E This JPM has the candidate shutdown an EDG that has been running unloaded for an extended period of time following an auto start. This will require the diesel be paralleled and loaded prior to shutdown. This is a bank JPM.

SIM F This JPM has the candidate review the NIS readings against a calorimetric power calculation.

The Alternate path is that a calibration adjustment is required to be made to a power range NI. This is a Alternate Path, Bank JPM.

SIM G This JPM has the candidate respond to lowering level in the Refueling Cavity. The Alternate path is that the normal supply of fill from the charging pumps will be unavailable and will require re-alignment of the suction of RHR pumps to provide the fill. This is a Modified Bank, Low Power, Alternate path JPM.

SIM H This JPM directs that candidate to respond to continued High CNMT pressure following a LOCA by aligning RHR to provide CNMT spray. The Alternate path develops when the normal spray supply valve will not open. This is a Alternate Path, Bank JPM.

In-plant I This JPM has the candidate walk through process of placing the spare battery charger in service and removing the normal charger. This is Bank JPM.

In-plant J This JPM has the candidate take local control of AFW supply to #3 SG due to valve not responding from the control room. This is an Alternate Path, Bank JPM performed in the RCA.

In-plant K This JPM directs the candidate to locally realign 2-RM-90-1 12 to monitor Lower Containment as part of the Unit 2 RCS leak detection system. This is a Bank JPM performed in the RCA.

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