Text

(1) Robinson 2016-301 Draft Administrative Documents
	ML16125A081
Person / Time
Site:	Robinson
Issue date:	04/27/2016
From:	; Division of Reactor Safety II
To:	; Duke Energy Progress
References
	50-261/OL-16-301
	Download: ML16125A081 (23)
	v • d • e

ES-401 PWR Examination Outline Form ES-401-2 Facility: ROBINSON Date of Exam: FEBRUARY 2016 RD K/A CatgoyPots SRO-Only_Points Tier Group K K K K K K AAAA G A2 G* Total 1 2 3 4 5 6 1 2 3 4

Total

1. 1 333 33 318 3 3 6 Emergency &

Abnormal 2 N/A N/A 1 9 2 2 4

Plant Evolutions Tier Totals 4 5 5 4 5 4 27 5 5 10 Rant Systems 2

ITlerTotals llllllt 44334334343 tOil 10 38 5 3 1: 8

3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 3 2 2 3 1 2 2 2 Note: 1. Ensure that at least two topics from every applicable K/A category are sampled within each tier the of RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the Tier Totals in each K/A category shall not be less than two). (One Tier 3 Radiation Control K/A is allowed if the K/A is replaced by a K/A from another Tier 3 Category).

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 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 with justification; operationally important, site-specific systems/evolutions that are not included on the outline should be added. Refer to Section D.1 .b of ES-401 for guidance regarding the elimination of inappropriate 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 RD and SRO-only portions, respectively.

6. Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.

7. The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.1 .b of ES-401 for the applicable K/As.

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 a

category other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #1 does not apply). Use duplicate pages for RD 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.

G* Generic K/As

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

RO SRO 007EK2.02 -

Reactor Trip Stabilization - Recovery 2.6 2.8 Breakers, relays and disconnects

/1 008AG2.1.30 PressurizerVaporSpaceAccident/3 4.4 4.0 Ability to locate and operate components, including local E

controls.

OO9EA1.10 Small Break LOCA/3 3.8 3.9 Safety parameter display system O11EK3.15 Lare Break LOCA/3 Criteria for shifting to recirculation mode 022AA2.03 Loss of Rx Coolant Makeup /2 3.1 3.6 Failures of flow control valve or controller E E D 025AG2.4.47 Loss of RHR System / 4 4.2 4.2 Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.

027AK2.03 Pressurizer Pressure Control System 2.6 2.8 Controllers and positioners Malfunction / 3 029Ek2.06 ATWS / 1 2.9 3.1 Breakers, relays, and disconnects.

038EK1.04 Steam Gen. Tube Rupture /3 3.1 3.3 Reflux boiling O4OAK1.05 Steam Line Rupture -Excessive Heat 4.1 4.4 Reactivity effects of cooldown Transfer / 4 054AA1 .03 Loss of Main Feedwaterl4 3.5 3.7 AFW auxiliaries, including oil cooling water supply Page 1 of 2 06/22/2015 9:28 AM

ES-401, REV 9 TIGI 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 055EK3.02 Station Blackout / 6 4.3 4.6 Actions contained in EOP for loss of offsite and onsite power 056AA2.l 1 Loss of Off-site Power / 6 2.9 2.9 Operational status of service water booster pump 057AA2.06 Loss of Vital AC Inst. Bus / 6 3.2 3.7 AC instrument bus alarms for the inverter and alternate power source 058AA1 .02 Loss of DC Power / 6 3.1 3.1 Static inverter dc input breaker, frequency meter, ac output breaker and ground fault detector weO4EG2.4.4 LOCA Outside Containment! 3 4.2 4.2 : Ability to verify that the alarms are consistent with the E E plant conditions.

WEO5EK3.4 Inadequate Heat Transfer -Loss of 3.7 3.9 RO or SRO function within the control room team as Secondary Heat Sink / 4 appropriate to the assigned position, in such a way that procedures are adhered to and the limitations in the facilities license and amendments are not violated.

WE11EK1.l Loss of Emergency Coolant Recirc. /4 3.7 4.0 Components, capacity, and function of emergency E

systems.

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ES-401, REV 9 TIG2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR 1<1 K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 005AK2.02 Inoperable/Stuck Control Rod / 1 2.5 2.6 Breakers, relays, disconnects and control room switches D

028AK1 .01 Pressurizer Level Malfunction / 2 2.8 3.1 PZR reference leak abnormalities 032AA2.02 Loss of Source Range Nl/7 3.6 3.9 -

D E Expected change in source range count rate when rods are moved 033AK3.01 Loss of Intermediate Range NI / 7 3.2 3.6 Termination of startup following loss of intermediate-E E D D D E range instrumentation 060AK2.01 Accidental Gaseous Radwaste Rel. / 9 2.6 2.9 ARM system, including the normal radiation-level indications and the operability status 067AA1 .09 Plant Fire On-site / 8 3 3.3 Plant fire zone panel (including detector location)

E D D Z D E 068AK3.12 Control Room Evac. / 8 4.1 4.5 Required sequence of actions for emergency evacuation of control room 076AA2.04 High Reactor Coolant Activity / 9 2.6 3 Process effluent radiation chart recorder we09EG2.1.20 Natural Circ./4 4.6 4.6 Ability to execute procedure steps.

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ES-401, REV 9 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 003A3.D1 Reactor Coolant Pump 3.3 3.2 Seal injection flow 003K4.07 Reactor Coolant Pump 3.2 3.4 Minimizing RCS leakage (mechanical seals)

ED 004K2.06 Chemical and Volume Control 2.6 2.7 Control instrumentation 005A2.02 Residual Heat Removal 3.5 3.7 Pressure transient protection during cold shutdown 005K6.03 Residual Heat Removal 2.5 2.6 El fl RHR heat exchanger 006A1.13 Emergency Core Cooling 3.5 3.7 Accumulator pressure (level, boron concentration) 006K5.O1 Emergency Core Cooling 2.8 3.3 Effects of temperatures on water level indications E D E D D E E D E E 007K3.Ol Pressurizer Relief/Quench Tank 3.3 3.6 El Containment fl D 008A4.03 Component Cooling Water 2.7 2.5 -

D Throttling of the CCW pump discharge valve 010K6.04 Pressurizer Pressure Control 2.9 3.2 PRT 012A3.06 Reactor Protection 3.7 3.7 fl D D Trip logic Page 1 of 3 06/22/2015 9:28 AM

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 Ol2Kl.05 Reactor Protection 3.8 3.9 ESFAS 013K5.02 Engineered Safety Features Actuation 2.9 3.3 Safety system logic and reliability 022A4.04 Containment Cooling 3.1 3.2 fl fl ValvesintheCCS 026A2.08 Containment Spray 3.2 3.7 Safe securing of containment spray when it can be done) 039A1.10 Main and Reheat Steam 2.9 3.0 Air ejector PRM 059K4.02 Main Feedwater 3.3 3.5 Automatic turbine/reactor trip runback 061 K5.01 Auxiliary/Emergency Feedwater 3.6 3.9 Relationship between AFw flow and RCS heat transfer 062K1.04 AC Electrical Distribution 3.7 4.2 Off-site power sources 062K2.01 AC Electrical Distiibution 3.3 3.4 DDEDDEiDDEI Major system loads 063A3.0i DC Electrical Distribution 2.7 3.1 E E D El D D LI LI Meters, annunciators, dials, recorders and indicating lights 064A2.18 Emergency Diesel Generator 2.6 2.7 fl Consequences of premature opening of breaker under load Page 2 of 3 06/22/2015 9:28 AM

ES-401, REV 9 T2GI 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 064K2.02 Emergency Diesel Generator 2.8 3.1 Fuel oil pumps 073A4.01 Process Radiation Monitoring 3.9 3.9 Effluent release 073G2.4.9 Process Radiation Monitoring 3.8 4.2 Knowledge of low power / shutdown implications in accident (e.g. LOCA or loss of RHR) mitigation strategies.

076K1.15 Service Water 2.5 2.6 FPS 078K3.03 Instrument Air 3.0 3.4 Cross-tied units 103G2.l.7 Containment 4.4 4.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior and instrument interpretation.

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ES-401, REV 9 T2G2 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 001K6.13 Control Rod Drive 3.6 3.7 Location and operation of RPIS 002K4.01 Reactor Coolant 2.7 3.0 Filling and draining the RCS E D E O11A1.02 Pressurizer Level Control 3.3 3.5 Charging and letdown flows 014K5.01 Rod Position Indication 2.7 3.0 Reasons for differences between RPIS and step counter E

017A4.0l In-core Temperature Monitor 3.8 4.1 Actual in-core temperatures E D D E 027K2.01 Containment Iodine Removal 3.1 3.4 Fans 029G2.l.23 Containment Purge 4.3 4.4 Ability to perform specific system and integrated plant procedures during all modes of plant operation.

033K3.02 Spent Fuel Pool Cooling 2.8 3.2 Area and ventilation radiation monitoring systems 035A2.05 Steam Generator 3.2 3.4 Unbalanced flows to the 5/Gs 068K1 .07 Liquid Radwaste 2.7 2.9 Sources of liquid wastes for LRS Page 1 of 1 06/2212015 9:28 AM

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

RD SRO G2.1.29 Conductof operations 4.1 4.0 D Knowledge of how to conduct system lineups, such as valves, breakers, switches, etc.

G2.1.36 Conduct of operations 3.0 4.1 Knowledge of procedures and mitations involved in core alterations G2.1.45 Conductofoperations 4.3 4.3 Abilty to identify and interpret diverse indications to validate the response of another indication G2.2.38 Equipment Control 3.6 4.5 Knowledge of conditions and limitations in the facility license.

G2.2.39 Equipment Control 3.9 4.5 Knowledge of less than one hour technical specification action statements for systems.

G2.3.13 Radiation Control 3.4 3.8 Knowledge of radiological safety procedures pertaining to licensed operator duties G2.3.4 Radiation Control 3.2 3.7 Knowledge of radiation exposure limits under normal and emergency conditions G2.4.11 Emergency Procedures/Plans 4.0 4.2 Knowledge of abnormal condition procedures.

G2.4.25 Emergency Procedures/Plans 3.3 3.7 Knowledge of fire protection procedures.

G2.4.31 Emergency Procedures/Plans 4.2 4.1 Knowledge of annunciators alarms, indications or response procedures Page 1 of 1 06/22/2015 9:52 AM

ES-401, REV 9 SRO TIGI 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:

RD SRO 029EA2.06 ATWS / 1 3.8 3.9 fl Main turbine trip switch position indication 038EG2.4.47 Steam Gen. Tube Rupture I 3 4.2 4.2 Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.

054AG2.4.9 Loss of Main Feedwater /4 3.8 4.2 Knowledge of low power! shutdown implications in accident (e.g. LOCA or loss of RHR) mitigation strategies.

055EA2.06 Station Blackout / 6 3.7 4.1 Faults and lockouts that must be cleared prior to re energizing buses 058AG2.2.22 Loss of DC Power /6 4.0 4.7 Knowledge of limiting conditions for operations and safety limits.

077AA2.03 Generator Voltage and Electric Grid 3.5 3.6 fl Disturbances / 6 fl fl fl Generator current outside the generator capability curve Page 1 of 1 06/22/2015 9:28 AM

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 4.2 4.2 Position of emergency boration valve 051AG2.4.35 Loss of Condenser Vacuum /4 3.8 4.0 Knowledge of local auxiliary operator tasks during emergency and the resultant operational effects 061 AA2.03 ARM System Alarms / 7 -

3 3.3 E D D E Setpoints for alert and high alarms weO6EG2.1.23 Degraded Core Cooling /4 4.3 4.4 Ability to perform specific system and integrated plant procedures during all modes of plant operation.

Page 1 of 1 06/22/2015 9:28 AM

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 012A2.03 Reactor Protection 3.4 3.7 Incorrect channel bypassing 039A2.03 Main and Reheat Steam 3.4 3.7 Indications and alarms for main steam and area radiation monitors (during SGTR) 076G2.l.7 Service Water 4.4 4.7 Ability to evaluate plant performance and make EE:

operational judgments based on operating characteristics, reactor behavior and instrument interpretation.

078A2.O1 Instrument Air 2.4 2.9 H Air dryer and filter malfunctions D

103G2.4.35 Containment 3.8 4.0 Knowledge of local auxHiary operator tasks during emergency and the resultant operational effects Page 1 of 1 06/22/2015 9:28 AM

ES-401, REV 9 SRO T2G2 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 0l5A2.04 Nuclear Instrumentation 3.3 3.8 Effects on axial flux density of control rod alignment and sequencing, xenon production and decay, and boron vs.

control rod reactivity changes 068A2.02 Liquid Radwaste 2.7 2.8 Lack of tank recirculation prior to release 071 G2.4.21 Waste Gas bisposai 4.0 4.6 Knowledge of the parameters and logic used to assess the status of safety functions Page 1 of 1 06122/2015 9:28 AM

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 G2.1.45 Conductofoperations 4.3 4.3 D D D D E D D Ability to identify and interpret diverse indications to validate the response of another indication G2.2.21 Equipment Control 2.9 4.1 Knowledge of pre- and post-maintenance operability DDJflEE requirements.

G2.2.36 Equipment Control 3.1 4.2 fl Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions of operations G2.3.12 Radiation Control 3.2 3.7 Knowledge of radiological safety principles pertaining to licensed operator duties G2.3.14 Radiation Control -

3.4 3.8 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 Knowledge of events related to system operations/status that must be reported to internal orginizations or outside agencies.

G2.4.46 Emergency Procedures/Plans 4.2 4.2 D D D D D D D Ability to verify that the alarms are consistent with the plant conditions.

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ES-301 Administrative Topics Outline Form ES-301-1 (Rev_011016)

Facility: HB Robinson Date of Examination: 2/2016 Examination Level: RO Operating Test Number: N16-1 Administrative Topic Type Code* Describe activity to be performed (see Note) 2.1.7 (4.4) Ability to evaluate plant performance Conduct of Operations and make operational judgments based on operating characteristics, D, R reactor behavior, and instrument interpretation.

JPM: Calculate QPTR 2.1.4 (3.3) Knowledge of individual licensed operator Conduct of Operations responsibilities related to shift staffing, such as medical requirements, no-solo N, R operation, maintenance of active license status, 10CFR55, etc.

JPM: Determine License Status 2.2.41 (3.5) Ability to obtain and interpret station Equipment Control electrical and mechanical drawings.

D, P, R JPM: Determine Proper Equipment Boundaries 2.3.7 (3.5) Ability to comply with radiation work Radiation Control permit requirements during normal or abnormal conditions.

N, R JPM: Evaluate Stay Time with Lowered SFP Level NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.

Type Codes & Criteria: (C)ontrol room, (0) (S)imulator, (0) or Class(R)oom (4)

(D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes) (2)

(N)ew or (M)odified from bank (> 1) (2)

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

NUREG-1021, Revision 10

ES-301 Administrative Topics Outline Form ES-301-1 (Rev_011016)

RO Admin JPM Summary A1a This is a modified Bank JPM. The operator will be told that the plant is operating at 60%

power and that ERFIS is OOS. The operator will be provided with Power Range Excore Nuclear Instrumentation indicated and normalizing detector currents, and directed to manually calculate Quadrant Power Tilt Ratio, and identify whether or not any limitations have been exceeded. The operator will be expected to calculate QPTR in accordance with FMP-007, Quadrant Power Tilt, and identify that Technical Specification LCO 3.2.4, Quadrant Power Tilt Ratio (QPTR), is NOT met.

A1b This is a new JPM. The operator will be told that they are a Licensed Reactor Operator who was assigned to the day shift staff for a special project, and not routinely standing watch in the Control Room. They will be provided with a work history and various qualification dates, and then directed to identify any requirements that must be met prior to the end of the quarter that are required to maintain their license ACTIVE; and any additional requirements that are required to maintain their qualification to stand watch in the Control Room. The operator will be expected to evaluate their work history and identify that four 12-hour shifts must be completed as either the RO or the BOP prior to the end of the quarter to maintain their license ACTIVE, and that an SCBA quantitative and qualitative fit test must be completed prior to standing watch in the Control Room again.

A2 This is a Bank JPM. The operator will be told that the plant is in Mode 1 at 100%,

Charging Pump A suction relief valve CVC-2080 has failed open, and that the operating crew has entered AOP-016, Excessive Primary Plant Leakage, to control the plant. The operator will be provided with the EDPs, and the P&IDs, and directed to use all available resources to identify the pump boundary valves needed to be closed to isolate the leak, and identify the motor breaker to electrically isolate the pump motor.

The operator will be expected to identify that the leak can be isolated by closing three valves; CVC-270, CVC-290 and CVC-291, and that the pump motor can be electrically isolated by opening Breaker 52/34B. This JPM was previously used on the 2014 NRC Exam, randomly selected for use on the 2016 Exam.

A3 This is a new JPM. The operator will be told that a station wide accident has occurred due to an Earthquake, that the plant is in Mode 6 with a full core off-load, that the Spent Fuel Pool level has lowered to 10 feet above the top of the fuel, and has stabilized at this level, and that the crew is implementing AOP-036 (SFP Events). The operator will be provided with an R-5 reading, a dose limit of 25 mrem, and the assignment of a repetitive task within AOP-036 which will require entry into the Spent Fuel Building for 3 minutes, before exiting; and will be directed to estimate how many times the operator can perform this repetitive task before they must be replaced by another operator. The operator will be expected to determine that the dose rate around the Spent Fuel Pool area is 193 mrem/hour and based on this the operator will determine that the repetitive task can be performed 2 times before another operator will need to perform the task.

NUREG-1021, Revision 10

ES-301 Administrative Topics Outline Form ES-301-1 (Rev_011016)

Facility: H B Robinson Date of Examination: 2/2016 Examination Level: SRO Operating Test Number: N16-1 Administrative Topic Type Describe activity to be performed (see Note) Code*

2.1.7 (4.7) Ability to evaluate plant performance and Conduct of Operations make operational judgments based on operating characteristics, reactor D, R behavior, and instrument interpretation.

JPM: Calculate QPTR 2.1.4 (3.8) Knowledge of individual licensed operator Conduct of Operations responsibilities related to shift staffing, such as medical requirements, no-solo N, R operation, maintenance of active license status, 10CFR55, etc.

JPM: Determine License Status 2.2.38 (4.5) Knowledge of conditions and limitations in Equipment Control the facility license.

D, R JPM: Determine if Mode Change is Permissible 2.3.8 (3.7) Ability to approve release permits.

Radiation Control N, R JPM: Approve a Waste Gas Release Permit 2.4.41 (4.4) Knowledge of the emergency action level Emergency Plan thresholds and classifications.

D, R JPM: Emergency Classification NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.

Type Codes & Criteria: (C)ontrol room, (0) (S)imulator, (0) or Class(R)oom (5)

(D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes) (3)

(N)ew or (M)odified from bank (> 1) (2)

(P)revious 2 exams ( 1; randomly selected) (0)

NUREG-1021, Revision 10

ES-301 Administrative Topics Outline Form ES-301-1 (Rev_011016)

SRO Admin JPM Summary A1a This is a modified Bank JPM. The operator will be told that the plant is operating at 100% power and that ERFIS is OOS. The operator will be provided with Power Range Excore Nuclear Instrumentation indicated and normalized detector currents, and directed to calculate Quadrant Power Tilt Ratio, identify whether or not any limitations have been exceeded, and if so, what, if any ACTION, is required. The operator will be expected to calculate QPTR in accordance with FMP-007, Quadrant Power Tilt, identify that Technical Specification LCO 3.2.4, Quadrant Power Tilt Ratio (QPTR), is NOT met, and identify that all six ACTIONs (A.1-A.6) must be taken for Condition A of LCO 3.2.4, including the maximum permitted power level of 91.3%.

A1b This is a new JPM. The operator will be told that they are a Licensed Senior Reactor Operator who was assigned to the day shift staff for a special project, and not routinely standing watch in the Control Room. They will be provided with a work history and various qualification dates, and then directed to identify any requirements that must be met prior to the end of the quarter that are required to maintain their license ACTIVE; and any additional requirements that are required to maintain their qualification to stand watch in the Control Room. The operator will be expected to evaluate their work history and identify that four 12-hour shifts must be completed as either the SM, CRS, RO or the BOP prior to the end of the quarter to maintain their license ACTIVE, and that an SCBA quantitative and qualitative fit test must be completed prior to standing watch in the Control Room again.

A2 This is a Bank JPM. The operator will be told that the plant is in Mode 5, returning from a refueling outage, that the RCS temperature is 165°F and there is a bubble in the PZR, and that RHR Loop A is maintaining RCS temperature. The operator will be provided with an Inoperable Equipment List and directed to complete the attached OMM-001-12, MINIMUM EQUIPMENT LIST AND SHIFT RELIEF, Attachment 2, 200°F to 350°F (MODE 4) MEL, that was started on the previous shift and to determine if any Mode 4 restrictions exists. The operator will be expected to complete Attachment 2 and determine that the Mode change cannot occur with current plant conditions, per the attached KEY.

A3 This is a new JPM. The operator will be told that the plant is in Mode 1 at 100% power, and that a Waste Gas Release Permit for the A WGDT has been presented to the Shift Manager for review and approval. The operator will be provided with a WGDT Release Permit and directed to review and approve the Waste Gas Release Permit, or to identify all issues found which would prevent approval. The operator will be expected to review the WGDT Release Permit and identify that it cannot be approved because (1) it has been written for the wrong WGDT and (2) the R14C setpoint is less conservative than required.

A4 This is a Bank JPM. The operator will be given an initial set of plant conditions. The operator will be directed to classify the event in accordance with the Robinson Nuclear Plant Emergency Action Level Matrix. The operator will be expected to declare an ALERT based on HA4.1, Confirmed Security event in a plant Protected Area or notification of either an airborne attack threat or hostile threat within the Owner Controlled Area, within 15 minutes. Then, the operator must prepare an Emergency NUREG-1021, Revision 10

ES-301 Administrative Topics Outline Form ES-301-1 (Rev_011016)

Notification Form for this event in accordance with EPCLA-01 (Emergency Control), also within 15 minutes.

NUREG-1021, Revision 10

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 (REV_120315)

Facility: Robinson Date of Examination: 2/2016 Exam Level (circle one): RO (only) / SRO(I) / SRO Operating Test No.: N16-1 (U)

Control Room Systems@ (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U)

Type Code* Safety System / JPM Title Function A. 062 AC Electrical Distribution System [062 A2.08 (3.6/3.4)]

S, P, D, A 6 Operation With High Switchyard Voltage B. 045 Main Turbine Generator System [045 A4.1 (3.1/2.9)]

S, N, A 4S High Vibration on Main Turbine C. 007 Pzr Relief Tank/Quench Tank System [007 A1.01 (2.9/3.1)]

S, D, A 5 Restore PRT to Normal Operating Conditions D. 001 Control Rod Drive System [001 A1.06 (4.1/4.4)]

S, N, A, L 1 Reactor Startup with Ejected Control Rod E. 011 Large Break LOCA [EPE 011 EA1.11 (4.2/4.2)]

S, D, A, EN 3 Transfer to Long Term Recirculation F. 006 Emergency Core Cooling System [006 A4.02 (4.0/3.8)]

S, P, D, EN 2 Fill a Safety Injection Accumulator G. 015 Nuclear Instrumentation System [015 A4.03 (3.8/3.9)]

S, D, L 7 Remove Source Range Channel N-31 From Service H. 003 Reactor Coolant Pump System [003 A4.03 (2.8/2.5)]

S, D, L 4P Start a Reactor Coolant Pump In-Plant Systems@ (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)

I. APE 055 Loss of Offsite and Onsite Power [EPE 055 EA2.01 (3.4/3.7)]

D, P, E 6 Locally Establish AFW Flow from the SDAFW Pump and Control S/G Levels and Pressures J. 065 Loss of Instrument Air [065 AA1.04 (3.5/3.4)]

D, R, E 8 Respond to a Loss of Instrument Air NUREG-1021, Revision 10

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 (REV_120315)

K. APE 062 Loss of Service Water [APE 062 AA2.01 (2.9/3.5)]

D, R, E 4S Loss of North SW Header in the Auxiliary Building

@ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path 4-6 (5) /4-6 (5) / 2-3 (3)

(C)ontrol room (D)irect from bank 9 (9) / 8 (8) / 4 (4)

(E)mergency or abnormal in-plant 1 (3) / 1 (3) / 1 (2)

(EN)gineered Safety Feature 1 (2) / 1 (2)/ 1 (2) (Control Room System)

(L)ow-Power / Shutdown 1 (3) / 1 (2) / 1 (1)

(N)ew or (M)odified from bank including 1(A) 2 (2) / 2 (2) / 1 (1)

(P)revious 2 exams 3 (3) / 3 (3)/ 2 (2) (Randomly Selected)

(R)CA 1 (2 )/ 1 (2) / 1 (1)

(S)imulator JPM Summary JPM A This is a Bank JPM. The operator will be told that the plant is at 100% power, that due to abnormal conditions on the Grid, 480V Bus E-2 currently has exceeded 505 volts, that AOP-031, Operation with High Switchyard Voltage, has been completed up to step 21, and other preliminary information. The operator will be directed to continue with AOP-031 until 480V Bus E-2 voltage is restored to less than 505 Volts. The operator will be expected to transfer 4KV Bus 4 & 5 from the UAT to the SUT (via 4KV Bus 3) in an effort to lower Switchyard Voltage; and when Breaker 50/20 fails to automatically OPEN (Alternate Path), the operator will manually open it per AOP-31. This JPM was previously used on the 2013 NRC Exam, randomly selected for use on the 2016 Exam.

JPM B This is a New JPM. The operator will be told that plant is stabilized at 35% power and directed to monitor the plant and respond as required. The operator will be expected to recognize that the Main Turbine must be tripped and attempt to manually trip the Main Turbine; and then (Alternate Path) manually runback the Main Turbine until the Turbine Governor Valves are closed, all the while the reactor remains critical.

JPM C This is a Bank JPM The operator will be told that the plant is at 100% power, that APP-003-D3, PRT HI/LO LEVEL, has alarmed, that the cause of the low level is known leakage from the PRT to the RCDT, and that the PRT level is stable at 67%. The operator will be directed to restore PRT level to normal IAW OP-103, Pressurizer Relief Tank Control System. The operator will be expected to refill the PRT in accordance with Section 8.2.2 of OP-103; and then diagnose and relieve the hydraulic lock on RC-519B (Alternate Path) in accordance with Section 8.4.1 of OP-103.

JPM D This is a New JPM. The operator will be told that the plant is at 10-8 amps in the Intermediate Range, that the RCS is at normal operating temperature and pressure, and that a plant startup is in progress IAW GP-003, Normal Plant Startup From Hot Shutdown to Critical, and complete through Step 8.4.6. The operator will be directed to pull control NUREG-1021, Revision 10

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 (REV_120315) rods to the POAH and stabilize reactor power between 3-5% by continuing with Step 8.4.7 of GP-003. The operator will raise reactor power to the POAH and then stabilize power between 3-5%. When reactor power reaches 3%, Control Rod H-8 will be ejected from the core (Alternate Path). The operator will raise reactor power to the POAH and then stabilize power between 3-5%. Then, the operator will manually trip or respond to an automatic reactor trip following the ejected rod and manually actuate Safety Injection by depressing both SI pushbuttons.

JPM E This is a Bank JPM. The operator will be told that a large break LOCA has occurred, and that the plant is currently on Cold Leg Recirculation IAW EOP-ES-1.3, Transfer to Cold Leg Recirculation. The operator will be directed to transfer to Long Term Recirculation IAW EOP-ES-1.4, Transfer to Long Term Recirculation. The operator will be expected to align for Long Term Recirculation per EOP-ES-1.4, and align only the B RHR Pump for operation when it is determined that SI-863A has failed to OPEN (Alternate Path).

JPM F This is a Bank JPM. The operator will be told that the plant is at 100% power, that the SI ACCUM C HI/LO LVL (APP-002-E4) alarm has been received and actions have been reviewed by the RO, that OP-202, Section 5.2.1.1 Initial Conditions have been completed, and other preliminary information. The operator will be directed to fill SI Accumulator C to reset the low level alarm IAW OP-202, Section 5.2.1. The operator will be expected to refill SI Accumulator C to reset the low level alarm without exceeding specified limits.

This was previously used on the 2013 NRC Exam, randomly selected for use on the 2016 Exam.

JPM G This is a Bank JPM. The operator will be told that the plant is shutdown 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months after a trip from 100% power, and that SR Channel N-31 has just failed low. The operator will be directed to remove SR Channel N-31 from service IAW OWP-011, Nuclear Instrumentation.

The operator will be expected to remove SR Channel N-31 from service IAW NI-5 of OWP-011.

JPM H This is a Bank JPM. The operator will be told that the plant is shutdown at normal operating temperature and pressure, that the B RCP was stopped 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months earlier for motor inspection, that Section 8.1 of OP-101, Reactor Coolant System and Reactor Coolant Pump Startup and Operation, has been completed through Step 8.1.1.2.y in preparation for starting the Reactor Coolant Pump, and that it is intended to bypass the Degraded Grid Protection prior to the RCP start and return it to service after the RCP is started per OP-101, and an AO is standing by to assist in this process. The operator will be directed to start the B Reactor Coolant Pump by continuing with Step 8.1.1.2.z of OP-101. The operator will be expected to start the B RCP IAW OP-101.

JPM I This is a Bank JPM. The operator will be told that the Plant has experienced a loss of onsite and offsite power, that EOP-ECA-0.0, Loss of All AC Power, has been implemented, that Wide Range levels in all three SGs are 55%, that Steam Generator pressures are 1075 psig, and that the SDAFW Pump has just been started. The operator will be directed to locally perform Attachment 4, Local Control Of S/G Level And Pressure, of EOP-ECA-0.0. The operator will be expected to control AFW flow to the Steam Generators and align the Nitrogen System to the SG PORVs IAW Attachment 4 of EOP-ECA-0.0. This was previously used on the 2014 NRC Exam, randomly selected for use on the 2016 Exam.

NUREG-1021, Revision 10

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 (REV_120315)

JPM J This is a Bank JPM. The operator will be told that the IA Header Pressure is 75 PSIG and lowering, that AOP-017, Loss Of Instrument Air, has been entered, that the Station Air Compressor is under clearance and disassembled, and that the Station Air Receiver is depressurized and vented. The operator will be directed to perform AOP-017 Step 8. The operator will be expected to start IA Compressors A and B and align their discharge to supply air to the Instrument Air Header in accordance with Step 8 of AOP-017.

JPM K This is a Bank JPM. The operator will be told that the plant is at 100% power, that the North SW header has ruptured inside the Auxiliary Building, and that the Control Room has implemented AOP-022 (Loss of Service Water) for a leak in the North header. The operator will be directed to perform the local subsequent actions IAW Attachment 6 of AOP-022. The operator will be expected to isolate the intact SW header from the ruptured header, isolate the leak, and align cooling water to critical loads IAW Attachment 6 of AP-022.

NUREG-1021, Revision 10

ES-401 PWR Examination Outline Form ES-401-2 Facility: ROBINSON Date of Exam: FEBRUARY 2016 RD K/A CatgoyPots SRO-Only_Points Tier Group K K K K K K AAAA G A2 G* Total 1 2 3 4 5 6 1 2 3 4

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