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-301 Administrative Topics Outline Form ES-301-1 (Rev_011016) NUREG-1021, Revision 10 Facility:

HB Robinson Date of Examination:

2/2016 Examination Level

RO Operating Test Number:

N16-1 Administrative Topic (see Note) Type Code*

Describe activity to be performed Conduct of Operations D, R 2.1.7 (4.4) Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

JPM: Calculate QPTR Conduct of Operations N, R 2.1.4 (3.3)

Knowledge of individual licensed operator responsibilities related to shift staffing, such as medical requirements, "no

-solo" operation, maintenance of active license status, 10CFR55, etc.

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

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

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)

ES-301 Administrative Topics Outline Form ES-301-1 (Rev_011016) NUREG-1021, Revision 10 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 201 4 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

.

ES-301 Administrative Topics Outline Form ES-301-1 (Rev_011016) NUREG-1021, Revision 10 Facility:

H B Robinson Date of Examination:

2/2016 Examination Level

SRO Operating Test Number:

N16-1 Administrative Topic (see Note) Type Code* Describe activity to be performed Conduct of Operations D, R 2.1.7 (4.7)

Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

JPM: Calculate QPTR Conduct of Operations N, R 2.1.4 (3.8)

Knowledge of individual licensed operator responsibilities related to shift staffing, such as medical requirements, "no

-solo" operation, maintenance of active license status, 10CFR55, etc.

JPM: Determine License Status Equipment Control D, R 2.2.38 (4.5) Knowledge of conditions and limitations in the facility license. JPM: Determine if Mode Change is Permissible Radiation Control N, R 2.3.8 (3.7) Ability to approve release permits.

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

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)

ES-301 Administrative Topics Outline Form ES-301-1 (Rev_011016) NUREG-1021, Revision 10 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 aga in. 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 o f either an airborne attack threat or hostile threat within the Owner Controlled Area, within 15 minutes. Then, the operator must prepare an Emergency ES-301 Administrative Topics Outline Form ES-301-1 (Rev_011016) NUREG-1021, Revision 10 Notification Form for this event in accordance with EPCLA-01 (Emergency Control), also within 15 minutes.

ES-301 Control Room/In

-Plant Systems Outline Form ES-301-2 (REV_120315) NUREG-1021, Revision 10 Facility:

Robinson Date of Examination:

2/2016 Exam Level (circle one):

RO (only) / SRO(I) / SRO (U) Operating Test No.:

N16-1 Control Room Systems

@ (8 for RO; 7 for SRO

-I; 2 or 3 for SRO

-U) System / JPM Title Type Code*

Safety Function A. 062 AC Electrical Distribution System

[062 A2.08 (3.6/3.4)

] Operation With High Switchyard Voltage S, P, D, A 6 B. 045 Main Turbine Generator System [045 A4.1 (3.1/2.9)] High Vibration on Main Turbine S, N, A 4S C. 007 Pzr Relief Tank/Quench Tank System

[007 A1.01 (2.9

/3.1)] Restore PRT to Normal Operating Conditions S, D, A 5 D. 001 Control Rod Drive System [001 A1.06 (4.1/4.4)] Reactor Startup with Ejected Control Rod S, N, A, L 1 E. 011 Large Break LOCA [EPE 011 EA1.11 (4.2/4.2)

] Transfer to Long Term Recirculation S, D, A, EN 3 F. 006 Emergency Core Cooling System

[006 A4.02 (4.0/3.8)

] Fill a Safety Injection Accumulator S, P, D, EN 2 G. 015 Nuclear Instrumentation System

[015 A4.03 (3.8

/3.9)] Remove Source Range Channel N

-31 From Service S, D, L 7 H. 003 Reactor Coolant Pump System

[003 A4.03 (2.8/2.5)] Start a Reactor Coolant Pump S, D, L 4P 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)] Locally Establish AFW Flow from the SDAFW Pump and Control S/G Levels and Pressures D, P, E 6 J. 065 Loss of Instrument Air

[065 AA1.04 (3.5/3.4)] Respond to a Loss of Instrument Air D, R, E 8 ES-301 Control Room/In

-Plant Systems Outline Form ES-301-2 (REV_120315) NUREG-1021, Revision 10 K. APE 062 Loss of Service Water

[APE 062 AA2.01 (2.9/3.5)] Loss of North SW Header in the Auxiliary Building D, R, E 4S @ 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 ES-301 Control Room/In

-Plant Systems Outline Form ES-301-2 (REV_120315) NUREG-1021, Revision 10 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 h ours 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 201 4 NRC Exam, randomly selected for use on the 2016 Exam.

ES-301 Control Room/In

-Plant Systems Outline Form ES-301-2 (REV_120315) NUREG-1021, Revision 10 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.

ES-301 Administrative Topics Outline Form ES-301-1 (Rev_011016) NUREG-1021, Revision 10 Facility:

HB Robinson Date of Examination:

2/2016 Examination Level

RO Operating Test Number:

N16-1 Administrative Topic (see Note) Type Code*

Describe activity to be performed Conduct of Operations D, R 2.1.7 (4.4) Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

JPM: Calculate QPTR Conduct of Operations N, R 2.1.4 (3.3)

Knowledge of individual licensed operator responsibilities related to shift staffing, such as medical requirements, "no

-solo" operation, maintenance of active license status, 10CFR55, etc.

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

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

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: