Text

Initial Exam 2015-301 Draft Administrative Documents
	ML16049A493
Person / Time
Site:	Farley
Issue date:	02/18/2016
From:	; Division of Reactor Safety II
To:	; Southern Nuclear Operating Co
References
	Download: ML16049A493 (17)
	v • d • e

ES-301 Administrative Topics Outline Form ES-301-1 Facility: FARLEY Date of Examination: 10/05/15 Examination Level: RO X SRO Operating Test Number: FA2015-301 Administrative Topic (see Note) Type Describe activity to be performed Code*

A.1.a

Title:

Monitor CSFST. Given a set of conditions, R, D the applicant will be required to use FNP-1-CSF-Conduct of Operations 0.0, Critical Safety Function Status Trees, to determine which FRP entry is required.

RO&SRO G2.1.7 - 4.4 / 4.7 G2.1.20 - 4.6 / 4.6 A.1.b R, D

Title:

Determine maximum RHR flowrate and time to saturation for a loss of RHR event. Given a set Conduct of Operations of conditionsthe applicant will : Determine maximum RHR flowrate and time to saturation for RO a loss of RHR event.

G2.1.25 - 3.9 / 4.2 A.2

Title:

Perform a QPTR. Given a set of conditions, R, M determine the QPTR using STP-7.0, Quadrant Tilt Equipment Control Power Ratio.

RO G2.2.12 - 3.7 /4.1 A.3

Title:

Determine RWP, dose, valve location and determination of task completions. Given a set of Radiation Control R, D conditions, determine the correct RWP, Total Projected Dose And Determine if an Oil Addition RO&SRO and venting can be performed to the 2A RHR pump without exceeding limits defined G2.3.4 - 3.2 / 3.7 G2.3.7 - 3.5 / 3.6 NONE SELECTED Emergency Plan NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics (which would require all five items).

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

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

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

ES-301 Administrative Topics Outline Form ES-301-1 Facility: FARLEY Date of Examination: 10/05/15 Examination Level: RO SRO x Operating Test Number: FA2015-301 Administrative Topic (see Note) Type Describe activity to be performed Code*

A.1.a R, D

Title:

Monitor CSFST. Given a set of conditions, the applicant will be required to use FNP-1-CSF-Conduct of Operations 0.0, Critical Safety Function Status Trees, to determine which FRP entry is required.

RO&SRO G2.1.7 - 4.4 / 4.7 G2.1.20 - 4.6 / 4.6 A.1.b R, M

Title:

Determine Active License Status. Given a set of conditions, the applicant will have to Conduct of Operations determine the status of 3 individuals license.

SRO G2.1.4 - 3.3 / 3.8 A.2 R, D

Title:

Perform a QPTR. Given a set of conditions, determine the QPTR using STP-7.0, Quadrant Tilt Equipment Control Power Ratio. Determine what Tech Specs actions, if any, are required.

SRO G2.2.12 - 3.7 / 4.1 G2.2.40 - 3.4 / 4.7 G2.2.42 - 3.9 / 4.6 A.3 R, D

Title:

Determine RWP, dose, valve location and determination of task completions. Given a set of Radiation Control conditions, determine the correct RWP, Total Projected Dose And Determine if an Oil Addition RO&SRO and venting can be performed to the 2A RHR pump without exceeding limits defined G2.3.4 - 3.2 / 3.7 G2.3.7 - 3.5 / 3.6 A.4 R, M

Title:

Classify an emergency event and complete selected sections of the emergency notification Emergency Plan form.

SRO G2.4.40 - 2.7 / 4.5 G2.4.41 - 2.9 / 4.6 NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics (which would require all five items).

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

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

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

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: FARLEY Date of Examination: 10/05/15 Exam Level: RO X SRO-I X SRO-U X Operating Test No.: FA2015-301 Control Room Systems:* 8 for RO; 7 for SRO-I; 2 or 3 for SRO-U System / JPM Title Type Code* Safety Function

a. CRO-074: Fill the 1A SIS Accumulator: the 1A Accumulator low and will D, S 2 be filled using SOP-8.0, Safety Injection - Accumulators.

006A1.13 - 3.5 / 3.7 006A4.02 - 4.0 / 3.8

b. CRO-333: Perform the required actions for Cold Leg Recirculation. A, D, EN, L, S 3 During the performance of the procedure, a valve will not close requiring an (SRO-U) alternate path.

011EA1.11 - 4.2 / 4.2 011EA1.13 - 4.1 / 4.2

c. 343G: Restore Service water to normal in response to a spurious Safety D, L, S 4S Injection - Applicant will restore Service Water using ESP-1.1, SI Termination.

062AA1.02 - 3.2 / 3.3 076A4.02 - 2.6 / 2.6

d. CRO-043B: Start the 1A RCP - After starting the 1A RCP, a high bearing A, D, S 4P temp alarm will be received requiring the 1A RCP to be secured.

003A1.02 - 2.9 / 2.9 003A2.03 - 2.7 / 3.1

e. CRO-406B (MOD): Verify Phase B Containment Isolation and A, M, S 5 Containment Spray Initiation. Containment pressure will be above 27psig (SRO-U) and Phase B / Containment Spray will not have actuated. Requires manual actions to start Containment spray and isolate valves.

WE14EA1.1 - 3.7 / 3.7 103A3.01 - 3.9 / 4.2

f. CRO-NEW: Perform Corrective Actions to a trip of the On Service CCW A, N, L, S 8 pump. The plant is in Mode 3 and the loss of the On Service train of CCW occurs while shifting Heat Exchangers.

008A2.01 - 3.3 / 3.6 026AA1.02 - 3.2 / 3.3

g. CRO-033 (MOD): Perform step 5.2 of STP-5.0, Full Length Control Rod A, M, S 1 Operability Test. Applicant will insert Shutdown Bank A 10 steps and when (SRO-U) the Rod Control Switch is released, the rods will continue to move. When rods are placed in AUTO, they will continue to move requiring a trip.

001A2.11 - 4.4 / 4.7 001A3.02 - 3.7 / 3.6 001AA1.05 - 4.3 / 4.2

h. CRO-039A: Adjust Setpoint of the N-16 Primary to Secondary Leak D, S 7 Detection System (R-70B). Applicant will change the R-70B setpoint to 75 (RO ONLY) gpd.

073A4.02 - 3.7 / 3.7

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

i. CRO- 607A (UNIT 1) : Perform the required actions to minimize DC loads. D, E, L 6 ECP-0.0 is in progress and the applicant is required to minimize DC loads in (SRO-U) the Non-Rad Aux Building.

055EA1.04 - 3.5 / 3.9

j. SO-444 (UNIT 1): Restore Compressed Air Systems After an Auto D 8 Isolation. Unit 1 has an extra valve that is operated by this JPM.

065AA1.03 - 2.9 / 3.1

k. SO-368A: Align RCDT Discharge to the WHT - Applicant is required to D, R 9 reduce RCT level from 50% to 10% per SOP-50.0, Liquid Waste Processing. (SRO-U) 068K1.07 - 2.7 / 2.9

All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all five 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 / 4-6 / 2-3 5/5/3 (C)ontrol room (D)irect from bank 9/8/4 8/7/3 (E)mergency or abnormal in-plant 1/1/1 1/1/1 (EN)gineered safety feature 1 / 1 / 1 (control room system) 1 / 1 / 1 (L)ow-Power / Shutdown 1/1/1 4/4/2 (N)ew or (M)odified from bank including 1(A) 2/2/1 3/3/2 (P)revious 2 exams 3 / 3 / 2 (randomly selected) 0 / 0 / 0 (R)CA 1/1/1 1/1/1 (S)imulator

ES-401 PWR Examination Outline Form ES-401-2 Facility: Farley Date of Exam: October, 2015 RO K/A Category Points SRO-Only Points Tier Group K K K K K K A A A A G 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 2 2 1 1 N/A 2 1 N/A 2 9 2 2 4 Plant Evolutions Tier Totals 5 4 4 5 4 5 27 5 5 10 1 3 3 2 3 2 3 3 2 3 2 2 28 3 2 5 2.

Plant 2 1 1 1 1 1 1 1 1 1 0 1 10 - 2 1 3 Systems Tier Totals 4 4 3 4 3 4 4 3 4 2 3 38 5 3 8

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

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

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

G* Generic K/As

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

E/APE # / Name / Safety Function K K K A A2 G K/A Topic(s) IR #

1 2 3 1 000007 (BW/E02&E10; CE/E02) Reactor X 007EA2.03; Ability to determine or interpret the 4.4 Trip - Stabilization - Recovery / 1 following as they apply to a reactor trip: Reactor trip breaker position.

000008 Pressurizer Vapor Space X 008G.2.1.32; Ability to explain and apply system 3.8 Accident / 3 limits and precautions.

009EA1.17; Ability to operate and monitor the 000009 Small Break LOCA / 3 X following as they apply to a small break LOCA: PRT 3.4 011EK3.05; Knowledge of the reasons for the 000011 Large Break LOCA / 3 X following responses as they apply to the Large Break 4.0 LOCA: Injection into cold leg.

015AA2.08; Ability to determine and interpret the 000015/17 RCP Malfunctions / 4 X following as they apply to the Reactor Coolant Pump 3.4 Malfunctions (Loss of RC Flow): When to secure RCPs on high bearing temperature.

022AA2.02; Ability to determine and interpret the 000022 Loss of Rx Coolant Makeup / 2 X following as they apply to the Loss of Reactor 3.2 Coolant Makeup: Charging pump problems.

025AG2.4.2; Knowledge of system set points, 000025 Loss of RHR System / 4 X interlocks and automatic actions associated with EOP 4.5 entry conditions.

000026 Loss of Component Cooling X 026AG2.4.46; Ability to verify that the alarms are 4.2 Water / 8 consistent with the plant conditions.

027AK2.03; Knowledge of the interrelations between 000027 Pressurizer Pressure Control X the Pressurizer Pressure Control Malfunctions and the 2.6 System Malfunction / 3 following: Controllers and positioners.

029EK2.06; Knowledge of the interrelations between 000029 ATWS / 1 X the following and the following an ATWS: Breakers, 2.9 relays, and disconnects.

038EK1.02; Knowledge of the operational 000038 Steam Gen. Tube Rupture / 3 X implications of the following concepts as they apply 3.2 to the SGTR: Leak rate vs. pressure drop.

WE12EK1.3; Knowledge of the operational 000040 (BW/E05; CE/E05; W/E12) X implications of the following concepts as they apply 3.4 Steam Line Rupture - Excessive Heat to the (Uncontrolled Depressurization of all Steam Transfer / 4 Generators) Annunciators and conditions indicating signals, and remedial actions associated with the (Uncontrolled Depressurization of all Steam Generators).

054AA1.04 ; Ability to operate and / or monitor the 000054 (CE/E06) Loss of Main X following as they apply to the Loss of Main 4.4 Feedwater / 4 Feedwater (MFW): HPI, under total feedwater loss conditions.

055EK3.02; Knowledge of the reasons for the 000055 Station Blackout / 6 X following responses as they apply to the Station 4.3 Blackout: Actions contained in EOP for loss of offsite and onsite power.

056AG2.2.44; Ability to interpret control room 000056 Loss of Off-site Power / 6 X indications to verify the status and operation of a 4.4 system, and understand how operator actions and directives affect plant and system conditions.

057AA2.16; Ability to determine and interpret the 000057 Loss of Vital AC Inst. Bus / 6 X following as they apply to the Loss of Vital AC 3.0 Instrument Bus: Normal and abnormal PZR level for various modes of plant operation.

058AA1.02; Ability to operate and / or monitor the 000058 Loss of DC Power / 6 X following as they apply to the Loss of DC Power: 3.1 Static inverter dc input breaker, frequency meter, ac output breaker, and ground fault detector.

062AK3.01; Knowledge of the reasons for the 000062 Loss of Nuclear Svc Water / 4 X following responses as they apply to the Loss of 3.2 Nuclear Service Water: The conditions that will initiate the automatic opening and closing of the SWS isolation valves to the nuclear service water coolers.

065AA2.06; Ability to determine and interpret the 000065 Loss of Instrument Air / 8 X following as they apply to the Loss of Instrument Air: 4.2 When to trip reactor if instrument air pressure is de-creasing.

WE04EG2.2.4; (multi-unit license) Ability to explain W/E04 LOCA Outside Containment / 3 X the variations in control board/control room layouts, 3.6 systems, instrumentation, and procedural actions between units at a facility.

4.4 WE04EG2.1.2; Knowledge of operator X responsibilities during all modes of plant operation.

WE11EK1.3; Knowledge of the operational W/E11 Loss of Emergency Coolant X implications of the following concepts as they apply 3.6 Recirc. / 4 to the (Loss of Emergency Coolant Recirculation):

Annunciators and conditions indicating signals, and remedial actions associated with the (Loss of Emergency Coolant Recirculation).

WE05EA2.1; Ability to determine and interpret the BW/E04; W/E05 Inadequate Heat X following as they apply to the (Loss of Secondary 4.4 Transfer - Loss of Secondary Heat Sink / 4 Heat Sink): Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

077AK2.01; Knowledge of the interrelations between 000077 Generator Voltage and Electric X Generator Voltage and Electric Grid Disturbances and 3.1 Grid Disturbances / 6 the following: Motors.

K/A Category Totals: 3 3 3 3 3/3 3/3 Group Point Total: 18/6

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

E/APE # / Name / Safety Function K K K A A2 G K/A Topic(s) IR #

1 2 3 1 000001 Continuous Rod Withdrawal / 1 X 001AG2.1.32; Ability to explain and apply 3.8 system limits and precautions.

003AG2.1.23; Ability to perform specific 000003 Dropped Control Rod / 1 X 4.4 system and integrated plant procedures during all modes of plant operation.

000005 Inoperable/Stuck Control Rod / 1 024AA2.05; Ability to determine and 000024 Emergency Boration / 1 X 3.9 interpret the following as they apply to the Emergency Boration: Amount of boron to add to achieve required SDM.

000028 Pressurizer Level Malfunction / 2 X 028AG2.1.25; Ability to interpret 4.2 reference materials, such as graphs, curves, tables, etc.

000032 Loss of Source Range NI / 7 000033 Loss of Intermediate Range NI / 7 000036 (BW/A08) Fuel Handling Accident / 8 037AK1.02; Knowledge of the operational 000037 Steam Generator Tube Leak / 3 X 3.5 implications of the following concepts as they apply to Steam Generator Tube Leak:

Leak rate vs. pressure drop.

000051 Loss of Condenser Vacuum / 4 X 051G2.2.38; Knowledge of conditions 3.6 and limitations in the facility license.

000059 Accidental Liquid RadWaste Rel. / 9 060AK2.01; Knowledge of the 000060 Accidental Gaseous Radwaste Rel. / 9 X 2.6 interrelations between the Accidental Gaseous Radwaste Release and the following: ARM system, including the normal radiation-level indications and the operability status.

000061 ARM System Alarms / 7 067AA1.06; Ability to operate and / or 000067 Plant Fire On-site / 8 X 3.5 monitor the following as they apply to the Plant Fire on Site: Fire alarm.

068AK3.03; Knowledge of the reasons for 000068 (BW/A06) Control Room Evac. / 8 X 3.7 the following responses as they apply to the Control Room Evacuation: Transfer of AFW flow control valves and pumps to local control.

000069 (W/E14) Loss of CTMT Integrity / 5 000074 (W/E06&E07) Inad. Core Cooling / 4 076AA2.03; Ability to determine and 000076 High Reactor Coolant Activity / 9 X 2.5 interpret the following as they apply to the High Reactor Coolant Activity: RCS radioactivity level meter.

W/EO1 & E02 Rediagnosis & SI Termination / 3 W/E13 Steam Generator Over-pressure / 4

WE15EK1.2; Knowledge of the W/E15 Containment Flooding / 5 X 2.7 operational implications of the following concepts as they apply to the (Containment Flooding): Normal, abnormal and emergency operating procedures associated with (Containment Flooding).

W/E16 High Containment Radiation / 9 WE10EA2.2; Ability to determine and BW/E09; CE/A13; W/E09&E10 Natural Circ. / 4 X 3.9 interpret the following as they apply to the (Natural Circulation with Steam Void in Vessel with/without RVLIS): Adherence to appropriate procedures and operation within the limitations in the Facilitys license and amendments.

WE08EA1.1; Ability to operate and / or CE/A11; W/E08 RCS Overcooling - PTS / 4 X 3.8 monitor the following as they apply to the (Pressurized Thermal Shock):

Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

K/A Category Point Totals: 2 1 1 2 1/2 2/2 Group Point Total: 9/4

ES-401 4 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 (RO / SRO)

System # / Name K K K K K K A A2 A A G K/A Topic(s) IR #

1 2 3 4 5 6 1 3 4 003A2.03; Ability to (a) predict the 003 Reactor Coolant Pump X impacts of the following malfunctions or 2.7 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.

003G2.4.45; Ability to prioritize and X interpret the significance of each 4.3 annunciator or alarm.

004A2.24; Ability to (a) predict the 004 Chemical and Volume X impacts of the following malfunctions or 2.8 Control operations on the CVCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Isolation of both letdown filters at one time: down-stream relief lifts.

004A1.05; Ability to predict and/or 2.9 monitor changes in parameters (to X

prevent exceeding design limits) associated with operating the CVCS controls including: S/G pressure and level.

005A1.03; Ability to predict and/or 005 Residual Heat Removal X monitor changes in parameters (to 2.5 prevent exceeding design limits) associated with operating the RHRS controls including: Closed cooling water flow rate and temperature.

005K3.06; Knowledge of the effect that a X loss or malfunction of the RHRS will 3.1 have on the following: CSS.

006K5.07; Knowledge of the operational 006 Emergency Core Cooling X implications of the following concepts as 2.7 they apply to ECCS: Expected temperature levels in various locations of the RCS due to various plant conditions.

X 006K6.05; Knowledge of the effect of a 3.0 loss or malfunction on the following will have on the ECCS: HPI/LPI cooling water.

007G2.2.44; Ability to interpret control 007 Pressurizer Relief/Quench X room indications to verify the status and 4.2 Tank operation of a system, and understand how operator actions and directives affect plant and system conditions.

X 007A2.03; Ability to (a) predict the 3.9 impacts of the following malfunctions or operations on the P S; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Overpressurization of the PZR.

008 Component Cooling Water X 008K2.02; Knowledge of bus power 3.0 supplies to the following: CCW pump, including emergency backup.

010K6.04; Knowledge of the effect of a 010 Pressurizer Pressure Control X loss or malfunction of the following will 2.9 have on the PZR PCS: PRT.

X 010G2.2.44; Ability to interpret control 4.4 room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions.

012K4.09; Knowledge of RPS design 012 Reactor Protection X feature(s) and/or interlock(s) which 2.8 provide for the following: Separation of control and protection circuits.

013 Engineered Safety Features X 013A4.01; Ability to manually operate 4.5 Actuation and/or monitor in the control room:

ESFAS-initiated equipment which fails to actuate.

022K4.01; Knowledge of PRTS design 022 Containment Cooling X feature(s) and/or interlock(s) which 2.6 provide for the following: Quench tank cooling.

025 Ice Condenser 026A1.03; Ability to predict and/or 026 Containment Spray X monitor changes in parameters (to 3.5 prevent exceeding design limits) associated with operating the CSS controls including: Containment sump level.

4.4 026A2.03; Ability to (a) predict the X impacts of the following malfunctions or operations on the CSS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Failure of ESF.

039K5.08; Knowledge of the operational 039 Main and Reheat Steam X implications of the following concepts as 3.6 they apply to the MRSS: Effect of steam removal on reactivity.

059 Main Feedwater X 059A3.03; Ability to monitor automatic 2.5 operation of the MFW, including:

Feedwater pump suction flow pressure.

061 Auxiliary/Emergency X 061K2.03; Knowledge of bus power 4.0 Feedwater supplies to the following: AFW diesel driven pump.

062A3.01; Ability to monitor automatic 062 AC Electrical Distribution X operation of the ac distribution system, 3.0 including: Vital ac bus amperage.

062K2.01; Knowledge of bus power X 3.3 supplies to the following: Major system loads.

063K3.01; Knowledge of the effect that a 063 DC Electrical Distribution X loss or malfunction of the DC electrical 3.7 system will have on the following: ED/G.

064K6.07; Knowledge of the effect of a 064 Emergency Diesel Generator X loss or malfunction of the following will 2.7 have on the ED/G system: Air receivers.

073K1.01; Knowledge of the physical 073 Process Radiation X connections and/or cause effect 3.4 Monitoring relationships between the RPS and the following systems: 120V vital/instrument power system.

X 073A2.01; Ability to (a) predict the 3.6 impacts of the following malfunctions or operations on the RPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Faulty bistable operation.

076 Service Water X 076A3.02; Ability to monitor automatic 3.7 operation of the SWS, including:

Emergency heat loads.

X 076A4.04; Ability to manually operate 3.5 and/or monitor in the control room:

Emergency heat loads.

078G2.4.34; Knowledge of RO tasks 078 Instrument Air X performed outside the main control room 4.2 during an emergency and the resultant operational effects.

078K1.05; Knowledge of the physical X connections and/or cause-effect 3.4 relationships between the IAS and the following systems: MSIV air.

103K1.08; Knowledge of the physical 103 Containment X connections and/or cause/effect 3.6 relationships between the containment system and the following systems: SIS, including action of safety injection reset.

X 103K4.01; Knowledge of containment 3.0 system design feature(s) and/or interlock(s) which provide for the following: Vacuum breaker protection.

K/A Category Point Totals: 3 3 2 3 2 3 3 2/3 3 2 2/2 Group Point Total: 28/5

ES-401 5 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 2 (RO / SRO)

System # / Name K K K K K K A A2 A A G K/A Topic(s) IR #

1 2 3 4 5 6 1 3 4 001K5.47; Knowledge of the following 001 Control Rod Drive X operational implications as they apply to 2.9 the CRDS: Factors affecting SUR: eff ,

l/.

002 Reactor Coolant 011 Pressurizer Level Control X 011K2.02; Knowledge of bus power 3.1 supplies to the following: PZR heaters.

014K1.01; Knowledge of the physical 014 Rod Position Indication X connections and/or cause/effect 3.2 relationships between the RPIS and the following systems: CRDS.

015 Nuclear Instrumentation 016 Non-nuclear Instrumentation 017K6.01; Knowledge of the effect of a 017 In-core Temperature Monitor X loss or malfunction of the following ITM 2.7 system components: Sensors and detectors.

027 Containment Iodine Removal 028 Hydrogen Recombiner and Purge Control 029A3.01; Ability to monitor automatic 029 Containment Purge X operation of the Containment Purge 3.8 System including: CPS isolation.

033 Spent Fuel Pool Cooling X 034G2.4.30; Knowledge of events related 034 Fuel Handling Equipment to system operation/status that must be 4.1 reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator.

035 Steam Generator X 035A1.02; Ability to predict and/or 3.5 monitor changes in parameters (to prevent exceeding design limits) associated with operating the S/GS controls including: S/G pressure.

041 Steam Dump/Turbine Bypass Control 045 Main Turbine Generator X 045A2.17; Ability to (a) predict the 2.7 impacts of the following malfunctions or operation on the MT/G system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Malfunction of electrohydraulic control.

055 Condenser Air Removal X 055K3.01; Knowledge of the effect that a 2.5 loss or malfunction of the CARS will have on the following: Main condenser.

056 Condensate X 056G2.1.28; Knowledge of the purpose 4.1 and function of major system components and controls.

068 Liquid Radwaste X 068K4.01; Knowledge of design 3.4 feature(s) and/or interlock(s) which provide for the following: Safety and environmental precautions for handling hot, acidic, and radioactive liquids.

071 Waste Gas Disposal 072 Area Radiation Monitoring X 072A2.03; Ability to (a) predict the 2.9 impacts of the following malfunctions or operations on the ARM system- and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Blown power-supply fuses.

075 Circulating Water 079 Station Air X 079A2.01; Ability to (a) predict the 3.2 impacts of the following malfunctions or operations on the SAS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Cross-connection with IAS.

086 Fire Protection K/A Category Point Totals: 1 1 1 1 1 1 1 1/2 1 0 1/1 Group Point Total: 10/3

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: Farley Date of Exam: October, 2015 Category K/A # Topic RO SRO-Only IR # IR #

2.1.18 Ability to make accurate, clear, and concise logs, records, status 3.6 boards, and reports.

1. 2.1.8 Ability to coordinate personnel activities outside the control 3.4 Conduct room.

of Operations 2.1.41 Knowledge of the refueling process. 3.7 Subtotal 2 1 2.2.21 Knowledge of pre- and post-maintenance operability 2.9 requirements.

2.2.22 Knowledge of limiting conditions for operations and safety 4.0

2. limits.

Equipment 2.2.35 Ability to determine Technical Specification Mode of 3.6 Control Operation.

2.2.13 Knowledge of tagging and clearance procedures. 4.3 2.2.40 Ability to apply Technical Specifications for a system. 4.7 Subtotal 3 2 2.3.4 Knowledge of radiation exposure limits under normal or 3.2 emergency conditions.

2.3.15 Knowledge of radiation monitoring systems, such as fixed 2.9

3. radiation monitors and alarms, portable survey instruments, Radiation personnel monitoring equipment, etc.

Control 2.3.12 Knowledge of radiological safety principles pertaining to 3.7 licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.

2.3.14 Knowledge of radiation or contamination hazards that may 3.8 arise during normal, abnormal, or emergency conditions or activities.

Subtotal 2 2 2.4.18 Knowledge of the specific bases for EOPs. 3.3 2.4.27 Knowledge of fire in the plant procedures. 3.4

4. 2.4.43 Knowledge of emergency communications systems and 3.2 Emergency techniques.

Procedures / Plan 2.4.30 Knowledge of events related to system operation/status that 4.1 must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator.

2.4.35 Knowledge of local auxiliary operator tasks during an 4.0 emergency and the resultant operational effects.

Subtotal 3 2 Tier 3 Point Total 10 7

ES-401 Record of Rejected K/As Form ES-401-4 Tier / Randomly Reason for Rejection Group Selected K/A 1/1 011EA2.01 Oversampled. Changed to 007EA2.03.

1/1 025AA2.05 Oversampled. Changed to WE5EA2.1.

1/2 028AK1.01 Oversampled. Changed to 037AK1.02.

1/2 068AA2.11 Oversampled. Changed to 024AA2.05.

1/2 WE09G2.2.38 Oversampled. Changed to 051G2.2.38.

2/1 005A1.05 Oversampled. Changed to 004A1.05.

2/1 022K4.04 Oversampled. Changed to 103K4.01.

2/1 061K2.02 Oversampled. Changed to 062K2.01 2/1 073K3.01 Oversampled. Changed to 005K3.06.

3 G2.3.14 Oversampled. Changed to G2.2.22

ES-301 Administrative Topics Outline Form ES-301-1 Facility: FARLEY Date of Examination: 10/05/15 Examination Level: RO X SRO Operating Test Number: FA2015-301 Administrative Topic (see Note) Type Describe activity to be performed Code*

A.1.a

Title:

Monitor CSFST. Given a set of conditions, R, D the applicant will be required to use FNP-1-CSF-Conduct of Operations 0.0, Critical Safety Function Status Trees, to determine which FRP entry is required.

RO&SRO G2.1.7 - 4.4 / 4.7 G2.1.20 - 4.6 / 4.6 A.1.b R, D

Title:

Determine maximum RHR flowrate and time to saturation for a loss of RHR event. Given a set Conduct of Operations of conditionsthe applicant will : Determine maximum RHR flowrate and time to saturation for RO a loss of RHR event.

G2.1.25 - 3.9 / 4.2 A.2

Title:

Perform a QPTR. Given a set of conditions, R, M determine the QPTR using STP-7.0, Quadrant Tilt Equipment Control Power Ratio.

RO G2.2.12 - 3.7 /4.1 A.3

Title:

Determine RWP, dose, valve location and determination of task completions. Given a set of Radiation Control R, D conditions, determine the correct RWP, Total Projected Dose And Determine if an Oil Addition RO&SRO and venting can be performed to the 2A RHR pump without exceeding limits defined G2.3.4 - 3.2 / 3.7 G2.3.7 - 3.5 / 3.6 NONE SELECTED Emergency Plan NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics (which would require all five items).

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

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

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

ES-301 Administrative Topics Outline Form ES-301-1 Facility: FARLEY Date of Examination: 10/05/15 Examination Level: RO SRO x Operating Test Number: FA2015-301 Administrative Topic (see Note) Type Describe activity to be performed Code*

A.1.a R, D

Title:

Monitor CSFST. Given a set of conditions, the applicant will be required to use FNP-1-CSF-Conduct of Operations 0.0, Critical Safety Function Status Trees, to determine which FRP entry is required.

RO&SRO G2.1.7 - 4.4 / 4.7 G2.1.20 - 4.6 / 4.6 A.1.b R, M

Title:

Determine Active License Status. Given a set of conditions, the applicant will have to Conduct of Operations determine the status of 3 individuals license.

SRO G2.1.4 - 3.3 / 3.8 A.2 R, D

Title:

Perform a QPTR. Given a set of conditions, determine the QPTR using STP-7.0, Quadrant Tilt Equipment Control Power Ratio. Determine what Tech Specs actions, if any, are required.

SRO G2.2.12 - 3.7 / 4.1 G2.2.40 - 3.4 / 4.7 G2.2.42 - 3.9 / 4.6 A.3 R, D

Title:

Determine RWP, dose, valve location and determination of task completions. Given a set of Radiation Control conditions, determine the correct RWP, Total Projected Dose And Determine if an Oil Addition RO&SRO and venting can be performed to the 2A RHR pump without exceeding limits defined G2.3.4 - 3.2 / 3.7 G2.3.7 - 3.5 / 3.6 A.4 R, M

Title:

Classify an emergency event and complete selected sections of the emergency notification Emergency Plan form.

SRO G2.4.40 - 2.7 / 4.5 G2.4.41 - 2.9 / 4.6 NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics (which would require all five items).

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

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

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

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: FARLEY Date of Examination: 10/05/15 Exam Level: RO X SRO-I X SRO-U X Operating Test No.: FA2015-301 Control Room Systems:* 8 for RO; 7 for SRO-I; 2 or 3 for SRO-U System / JPM Title Type Code* Safety Function

a. CRO-074: Fill the 1A SIS Accumulator: the 1A Accumulator low and will D, S 2 be filled using SOP-8.0, Safety Injection - Accumulators.

006A1.13 - 3.5 / 3.7 006A4.02 - 4.0 / 3.8

b. CRO-333: Perform the required actions for Cold Leg Recirculation. A, D, EN, L, S 3 During the performance of the procedure, a valve will not close requiring an (SRO-U) alternate path.

011EA1.11 - 4.2 / 4.2 011EA1.13 - 4.1 / 4.2

c. 343G: Restore Service water to normal in response to a spurious Safety D, L, S 4S Injection - Applicant will restore Service Water using ESP-1.1, SI Termination.

062AA1.02 - 3.2 / 3.3 076A4.02 - 2.6 / 2.6

d. CRO-043B: Start the 1A RCP - After starting the 1A RCP, a high bearing A, D, S 4P temp alarm will be received requiring the 1A RCP to be secured.

003A1.02 - 2.9 / 2.9 003A2.03 - 2.7 / 3.1

e. CRO-406B (MOD): Verify Phase B Containment Isolation and A, M, S 5 Containment Spray Initiation. Containment pressure will be above 27psig (SRO-U) and Phase B / Containment Spray will not have actuated. Requires manual actions to start Containment spray and isolate valves.

WE14EA1.1 - 3.7 / 3.7 103A3.01 - 3.9 / 4.2

f. CRO-NEW: Perform Corrective Actions to a trip of the On Service CCW A, N, L, S 8 pump. The plant is in Mode 3 and the loss of the On Service train of CCW occurs while shifting Heat Exchangers.

008A2.01 - 3.3 / 3.6 026AA1.02 - 3.2 / 3.3

g. CRO-033 (MOD): Perform step 5.2 of STP-5.0, Full Length Control Rod A, M, S 1 Operability Test. Applicant will insert Shutdown Bank A 10 steps and when (SRO-U) the Rod Control Switch is released, the rods will continue to move. When rods are placed in AUTO, they will continue to move requiring a trip.

001A2.11 - 4.4 / 4.7 001A3.02 - 3.7 / 3.6 001AA1.05 - 4.3 / 4.2

h. CRO-039A: Adjust Setpoint of the N-16 Primary to Secondary Leak D, S 7 Detection System (R-70B). Applicant will change the R-70B setpoint to 75 (RO ONLY) gpd.

073A4.02 - 3.7 / 3.7

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

i. CRO- 607A (UNIT 1) : Perform the required actions to minimize DC loads. D, E, L 6 ECP-0.0 is in progress and the applicant is required to minimize DC loads in (SRO-U) the Non-Rad Aux Building.

055EA1.04 - 3.5 / 3.9

j. SO-444 (UNIT 1): Restore Compressed Air Systems After an Auto D 8 Isolation. Unit 1 has an extra valve that is operated by this JPM.

065AA1.03 - 2.9 / 3.1

k. SO-368A: Align RCDT Discharge to the WHT - Applicant is required to D, R 9 reduce RCT level from 50% to 10% per SOP-50.0, Liquid Waste Processing. (SRO-U) 068K1.07 - 2.7 / 2.9

All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all five 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 / 4-6 / 2-3 5/5/3 (C)ontrol room (D)irect from bank 9/8/4 8/7/3 (E)mergency or abnormal in-plant 1/1/1 1/1/1 (EN)gineered safety feature 1 / 1 / 1 (control room system) 1 / 1 / 1 (L)ow-Power / Shutdown 1/1/1 4/4/2 (N)ew or (M)odified from bank including 1(A) 2/2/1 3/3/2 (P)revious 2 exams 3 / 3 / 2 (randomly selected) 0 / 0 / 0 (R)CA 1/1/1 1/1/1 (S)imulator

ES-401 PWR Examination Outline Form ES-401-2 Facility: Farley Date of Exam: October, 2015 RO K/A Category Points SRO-Only Points Tier Group K K K K K K A A A A G A2 G* Total 1 2 3 4 5 6 1 2 3 4

Total