ML15013A251

Harris Initial Exam 2014-302 Final Administrative Documents

ML15013A251
Person / Time
Site:	Harris
Issue date:	01/13/2015
From:	NRC/RGN-II
To:	Progress Energy Carolinas
Shared Package
ML15013A407	List: IR 05000400/2014302 ML15013A231 ML15013A235 ML15013A238 ML15013A241 ML15013A245 ML15013A249 ML15013A251 ML15013A262 ML15013A267 ML15013A271 ML15013A275
References
50-400/OL-14
Download: ML15013A251 (79)

Text

10/10/2014 Rev. FINAL 1 ES-301 Administrative Topics Outline Form ES-301-1 Facility: Harris Nuclear Plant Date of Examination: November 17, 2014 Examination Level: RO SRO Operating Test Number: 05000400/2014302 Administrative Topic (see Note) Type Code* Describe activity to be performed Conduct of Operations N, R Perform RCS Average Temperature Data Sheet and Determine Inverse Count Rate Ratio (1/M) (GP-004) (JPM ADM-072-a) Common K/A G2.1.43 2014 NRC RO / SRO A1-1 Conduct of Operations M, R Perform a manual Shutdown Margin Calculation (OST-1036) (JPM ADM-019-c) K/A G 2.1.25 2014 NRC RO A1-2 Equipment Control M, R Determine clearance requirements for a CSIP per OPS-NGGC-1301 (OPS-NGGC-1301) (JPM ADM-021-d) Common K/A G 2.2.13 2014 NRC RO / SRO A2 Radiation Control M, R Determine TEDE While Working in a High Airborne Area (PD-RP-ALL-0001) (JPM-ADM-022-c) Common K/A G2.3.4 2014 NRC RO / SRO A3 Emergency Procedures/Plan N/A NOT SELECTED FOR RO 2014 NRC RO A4 NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

• Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (4) (D)irect from (0) (N)ew or (M)odified from (4) (P) (0) 10/10/2014 Rev. FINAL 2 2014 NRC RO Admin JPM Summary 2014 NRC RO SRO A1 (Common) - Perform RCS Average Temperature Data Sheet and Determine Inverse Count Rate Ratio (1/M) (GP-004) (JPM ADM-072-a) NEW K/A G2.1.43 - Ability to use procedures to determine the effects on reactivity of plant changes, such as reactor coolant system temperature, secondary plant, fuel depletion, etc. (CFR: 41.10 / 43.6 / 45.6) RO 4.1 SRO 4.3 The plant data for various times during a plant startup will be provided to the candidate. The information provided will allow the candidate complete Attachment 2 and Attachment 3 of GP-004, Reactor Startup (Mode 3 To Mode 2). The candidate must review the plant data provided to plot the results on Attachment 3 and determine the Inverse Count Rate Ratio (1/M). The candidate must predict the reactor will achieve criticality before reaching the 500 pcm below ECC control rod position. 2014 NRC RO A1 Perform a manual Shutdown Margin Calculation (OST-1036) (JPM ADM-019-c) MODIFIED K/A G2.1.25 - Ability to interpret reference materials, such as graphs, curves, tables, etc. (CFR: 41.10 / 43.5 / 45.12) RO 3.9 SRO 4.2 The plant is operating at 92% power and the CRS will direct the candidate to complete OST-1036, Shutdown Margin Calculation Modes 1-5, Section 7.3, for the current plant conditions. NOTE: Modified by changing all values provided as initial conditions and using current cycle curves which will lead the candidate to a new answer that is substantially different than the original. 2014 NRC RO SRO A2 - (Common) - Determine clearance requirements for a CSIP per OPS-NGGC-1301 (JPM ADM-021-d) MODIFIED K/A G2.2.13 - Knowledge of tagging and clearance procedures. (CFR: 41.10 / 45.13) RO 4.1 SRO 4.3 The plant is defueled. CSIP 1A-SA is required to be placed under a clearance for seal replacement. Cooling water and lube oil systems are NOT required to be placed under clearance. The candidate will be directed to determine the clearance requirements for CSIP 1A-SA using the SFDs, and System Operating Procedures, as necessary. The candidate must provide electrical and mechanical protection and provide the necessary vent and drain paths. The candidate will be informed that the SM has approved using single valve isolation. NOTE: The pump was changed from the CSIP 1B-SB to the CSIP 1A-SA. With the change in pumps the candidate must identify different isolation valves, and breakers.

10/10/2014 Rev. FINAL 3 2013 NRC RO Admin JPM Summary (continued) 2014 NRC RO SRO A3 - (Common) - Determine TEDE While Working in a High Airborne Area (PD-RP-ALL-0001) (JPM-ADM-022-c) MODIFIED K/A G2.3.4 - Knowledge of radiation exposure limits under normal or emergency conditions. (CFR: 41.12 / 43.4 / 45.10) RO 3.2 SRO 3.7 The candidate must calculate and determine if a respirator should or should not be worn when working in an area with a known dose rate and airborne contamination for a given length of time. NOTE: Modified by providing different initial conditions and different accumulated dose amounts which leads to a new answer that will NOT require the use of a respirator. This answer is substantially different than the original. 2014 NRC RO A4 - Not selected 10/10/2014 Rev. FINAL 4 Revision Comments 2014 NRC RO Admin JPM Summary JPM A1 N/A JPM A1 N/A JPM A2 - Replace Original NRC Admin JPM with Audit Admin JPM A2 as requested by the Chief Examiner (David Lanyi) to reduce the overall predictability of the JPMs selected for evaluation by the NRC JPM A3 - N/A 10/10/2014 Rev. FINAL 1 ES-301 Administrative Topics Outline Form ES-301-1 Facility: Harris Nuclear Plant Date of Examination: November 17, 2014 Examination Level: RO SRO Operating Test Number: 05000400/2014302 Administrative Topic (see Note) Type Code* Describe activity to be performed Conduct of Operations N, R Perform RCS Average Temperature Data Sheet and Determine Inverse Count Rate Ratio (1/M) (GP-004) (JPM ADM-072-a) Common K/A G2.1.43 2014 NRC RO / SRO A1-1 Conduct of Operations D, R Complete GP-002, Attachment 5 - Minimum Equipment List (MEL) for Entry into Mode 4 (GP-002) (JPM ADM-040-b) K/A G 2.1.20 2014 NRC SRO A1-2 Equipment Control M, R Determine clearance requirements for a CSIP per OPS-NGGC-1301 (OPS-NGGC-1301) (JPM ADM-021-d) Common K/A G 2.2.13 2014 NRC RO / SRO A2 Radiation Control M, R Determine TEDE While Working in a High Airborne Area (PD-RP-ALL-0001) (JPM-ADM-022-c) Common K/A G2.3.4 2014 NRC RO / SRO A3 Emergency Procedures/Plan N, R Classify an Event (EP-EAL) (JPM ADM-064-a) K/A G2.4.41 2014 NRC SRO A4 NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

• Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (5) (D)irect from (1) (N)ew or (M)odified from (4) (0) 10/10/2014 Rev. FINAL 2 2014 NRC SRO Admin JPM Summary 2014 NRC RO SRO A1 (Common) - Perform RCS Average Temperature Data Sheet and Determine Inverse Count Rate Ratio (1/M) (GP-004) (JPM ADM-072-a) NEW K/A G2.1.43 - Ability to use procedures to determine the effects on reactivity of plant changes, such as reactor coolant system temperature, secondary plant, fuel depletion, etc. (CFR: 41.10 / 43.6 / 45.6) RO 4.1 SRO 4.3 The plant data for various times during a plant startup will be provided to the candidate. The information provided will allow the candidate complete Attachment 2 and Attachment 3 of GP-004, Reactor Startup (Mode 3 To Mode 2). The candidate must review the plant data provided to plot the results on Attachment 3 and determine the Inverse Count Rate Ratio (1/M). The candidate must predict the reactor will achieve criticality before reaching the 500 pcm below ECC control rod position. 2014 NRC SRO A1 Complete GP-002, Attachment 5 - Minimum Equipment List (MEL) for Entry into Mode 4 (GP-002) (JPM ADM-040-b) DIRECT K/A G2.1.20 - Ability to interpret and execute procedure steps. (CFR: 41.10 / 43.5 / 45.12) RO 4.6 SRO 4.6 The plant data for current conditions during a plant startup will be provided to the candidate.

The information provided will allow the candidate to complete Attachment 5 of GP-002, Normal Plant Heatup From Cold Solid To Hot Subcritical Mode 5 To Mode 3. The candidate must review the plant data provided and determine that three items (Boric Acid Tank, RCS/RHR Loops and Safety Related Electrical Buses) do NOT meet the minimum required for entry into Mode 4. 2014 NRC RO SRO A2 - (Common) - Determine clearance requirements for a CSIP per OPS-NGGC-1301 (JPM ADM-021-d) MODIFIED K/A G2.2.13 - Knowledge of tagging and clearance procedures. (CFR: 41.10 / 45.13) RO 4.1 SRO 4.3 The plant is defueled. CSIP 1A-SA is required to be placed under a clearance for seal replacement. Cooling water and lube oil systems are NOT required to be placed under clearance. The candidate will be directed to determine the clearance requirements for CSIP 1A-SA using the SFDs, and System Operating Procedures, as necessary. The candidate must provide electrical and mechanical protection and provide the necessary vent and drain paths. The candidate will be informed that the SM has approved using single valve isolation. NOTE: The pump was changed from the CSIP 1B-SB to the CSIP 1A-SA. With the change in pumps the candidate must identify different isolation valves, and breakers.

10/10/2014 Rev. FINAL 3 2014 NRC SRO Admin JPM Summary (continued) 2014 NRC RO SRO A3 - (Common) - Determine TEDE While Working in a High Airborne Area (PD-RP-ALL-0001) (JPM-ADM-022-c) MODIFIED K/A G2.3.4 - Knowledge of radiation exposure limits under normal or emergency conditions. (CFR: 41.12 / 43.4 / 45.10) RO 3.2 SRO 3.7 The candidate must calculate and determine if a respirator should or should not be worn when working in an area with a known dose rate and airborne contamination for a given length of time.

NOTE: Modified by providing different initial conditions and different accumulated dose amounts which leads to a new answer that will NOT require the use of a respirator. This answer is substantially different than the original. 2014 NRC SRO A4 - Classify an Event (EP-EAL) (JPM-ADM-064-a) NEW K/A G2.4.41 - Knowledge of the emergency action level thresholds and classifications (CFR: 41.10 / 43.5 / 45.11) RO 2.9 SRO 4.6 Given a set of initial conditions and the EAL Flow Matrix, the candidate must classify the appropriate Emergency Action Level for the event in progress.

10/10/2014 Rev. FINAL 4 Revision Comments 2014 NRC SRO Admin JPM Summary JPM A1 N/A JPM A1 N/A JPM A2 - Replace Original NRC Admin JPM with Audit Admin JPM A2 as requested by the Chief Examiner (David Lanyi) to reduce the overall predictability of the JPMs selected for evaluation by the NRC JPM A3 - N/A JPM A4 - N/A 10-15-2014 Rev. FINAL 1 ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Harris Nuclear Plant Date of Examination: November 17, 2014 Exam Level: RO SRO-I SRO-U (bold) Operating Test No.: 05000400/2014302 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF - bold) System / JPM Title Type Code* Safety Function a. Perform Control Rod and Rod Position Indicator Exercise (OST-1005) (JPM-CR-256-d) Previous NRC 2013 K/A 001 A2.11 A, D, P, S 1 b. Vent An Un-Isolable SI Accumulator during a Steam Generator Tube Rupture Event (EOP-E-3) (JPM-CR-284-a) Previous NRC 2013 Retake K/A 006 A4.02 A, EN, D, L, P, S 2 c. Align ECCS for long term recirculation (EOP-ES-1.3) (JPM-CR-235-a) K/A 006 A4.05 A, D, L, S 3 d. Start a RCP and respond to a subsequent Spray valve failure (OP-100, AOP-019) (JPM-CR-005-g) K/A 003 A2.02 A, N, L , S 4P e. Using ESW System As A Backup Source of Water To AFW (OP-137) (JPM-CR-107-c) K/A 054 AA1.01 D, S 4S f. Swapping Containment Fan Cooler Lead Fans (OP-169) (JPM-CR-289-a) K/A 022 A4.01 N, S 5 g. Resetting CVIS and Restoring RM-3502A to Operation (AOP-025) (JPM-CR-253-d) RO ONLY K/A 073 A4.02 D, S 7 h. Restoring Control Room Area HVAC to Normal After a CRIS (OP-173) (JPM-CR-171-a) K/A APE 067 AA1.05 A, EN, M, S 8 10-15-2014 Rev. FINAL 2 In-Plant Systems@ (3 for RO); (3 for SRO-I); (2 or 3 for SRO-U - BOLD) i. Shift Battery Chargers (at power, shift from one safety battery charger to the other) (OP-156.01) (JPM IP-074-a) K/A 063 G2.1.30 D, EN 6 j. Isolate the SI Accumulators After a Control Room Evacuation (AOP-004) (JPM-IP-232-a) K/A APE 068 G2.1.30 D, E, L 8 k. Reset TD AFW Pump Mechanical Overspeed (OP-137) (JPM-IP-001-b) K/A 061 A2.04 D, E, EN, L, R 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 (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A) (P)revious 2 exams (R)CA (S)imulator 4-6 / 4-6 / 2-3 (5, 5, 3) (8, 7, 3) (2, 2, 1) - / - (4, 4, 4) (5, 5, 3) (3, 3, 2) (2, 2, 1) (1, 1, 1)

Revision Comments 2014 NRC Control Room/In-Plant JPM Summary 10-15-2014 Rev. FINAL 3 Simulator JPMs JPM a - Perform Control Rod and Rod Position Indicator Exercise per OST-1005 (JPM-CR-256-d) Previous NRC Exam - 2013 *randomly selected from bank - Alternate Path K/A 001 A2.11 - Ability to (a) predict the impacts of the following malfunction or operations on the CRDS- and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Situations requiring a reactor trip (CFR: 41.5/43.5/45.3/45.13) RO 4.4 / SRO 4.7 The candidate will assume the OATC position with the unit operating at 100% power and will be directed to perform OST-1005 commencing with Control Bank D in section 7.2. The candidate will insert and withdraw Control Bank D 10 steps as required. The candidate will continue OST-1005 and select the next Control Bank and insert the Control Bank 10 steps as required. Once the candidate begins to insert the next selected Control Bank, the Alternate Path will begin and a malfunction of the rod control system will result in the Control Rods continuing to insert once the demand for rod motion has stopped. This will cause RCS Tavg, and Reactor Power will lower in response to the control rods inserting and the Control Rod step counter will continue to lower. The candidate should recognize the failure of the rod control system and perform AOP-001 and EOP-E-0 immediate actions. The candidate may or may not select the manual position for rod control. Rod Control is considered to be in manual as long as the Auto position is not selected and being in Control Bank A satisfies this step. Rod motion will continue in either case requiring the candidate to perform the RNO action and initiate a manual reactor trip. Once the candidate verifies that the Reactor and Turbine are tripped this JPM is complete. JPM b - Vent an Un-Isolable SI Accumulator during a Steam Generator Tube Rupture Event (E-3) (JPM-CR-284-a) - SRO Upgrade - Previous NRC Exam - 2013 Retest *randomly selected from bank - Alternate Path K/A 006 A4.02: Emergency Core Cooling System (ECCS) - Ability to manually operate and/or monitor in the control room: Valves (CFR: 41.7 / 45.5 to 45.8) RO 4.0 / SRO 3.8 The candidate will be assigned the OATC position. The initial conditions are a Steam Generator tube rupture has occurred on the 'A' SG. The crew entered AOP-016, Excessive Primary Plant Leakage. During the implementation of AOP-016, RCS leakage exceeded VCT makeup capability and the crew manually tripped the Reactor and Safety Injected. The crew entered EOP-E-0. After identifying the 'A' Steam Generator as ruptured the crew transitioned to and are implementing EOP-E-3, Steam Generator Tube Rupture. The CRS will direct the candidate to continue with E-3 starting at step 90 to check if SI accumulators should be isolated. The candidate will check RCS pressure below 1000 psig (Yes) then contact an Aux Operator to locally unlock and close both breakers for each SI accumulator discharge valve. After the discharge valves are energized the candidate will shut each SI accumulator discharge valve (1SI-246, 1SI-247 and 1SI-248). The 'A' Accumulator discharge valve (1SI-246, Accum 1-A-SA Disc Vlv) will not shut and the Alternate Path with begin requiring the candidate to implement the RNO action to vent the unisolable Accumulator using OP-110, Safety Injection, section 8.3. The OP will require the candidate to shut 1SI-287, Accum N2 Supply Isol valve and open 1SI-295, Accumulator 'A' N2 Supply Revision Comments 2014 NRC Control Room/In-Plant JPM Summary 10-15-2014 Rev. FINAL 4 Simulator JPMs (continued) and Vent valve. They will then slowly adjust HC-936, 1SI-298 Accum Vent Press Cntl control potentiometer output signal to open 1SI-298 and vent the Accumulator to Containment. The goal is to vent the 'A' Accumulator to 0 psig. Verification of 'A' Accumulator pressure reduction will be available by observation of MCB pressure indications, ERFIS screen plots, OSI-PI screen plots and annunciators. After the examiner observes both a low pressure alarm for the 'A' Accumulator (ALB-01-7-1, ACCUMULATOR TANK A HIGH-LOW PRESS, setpoint = 602 psig) and approximately a 5 psig pressure reduction a cue for using "time compression" can be given stating that the 'A' accumulator pressure now reads 0 psig and this JPM is complete. JPM c - Align ECCS for long term recirculation (ES-1.3) (JPM-CR-235-a) Direct - Alternate Path K/A 006 A4.05 - Ability to manually operate and/or monitor in the control room: Transfer of ECCS flowpaths prior to recirculation (CFR: 41.7 / 45.5 to 45.8) RO 3.9 SRO 3.8 The candidate will be assigned to perform the actions of ES-1.3 following a large break LOCA . The candidate will verify the RHR system is aligned to the containment sump and isolate the system from the RWST. The 1SI-340, SI Train A Cold Leg isolation valve will not shut and the Alternate Path begins requiring the candidate to shut 1SI-341, SI Train B Cold Leg isolation. The candidate continues with ES-1.3 to establish the CSIP recirculation alignment and 1CS-746, Train A CSIP alternate miniflow isolation, will fail to shut requiring the candidate to shut 1CS-745, Train A CSIP alternate miniflow block valve before continuing with the CSIP recirculation alignment. Once high head SI Flow is verified to each train of the CSIP this JPM is complete. JPM d - Start a RCP and respond to a subsequent Spray valve failure (OP-100, AOP-019) (JPM-CR-005-g) - SRO Upgrade - New - Alternate Path K/A 002 A1.01 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the RCS controls including: Primary and secondary pressure (CFR: 41.5 / 45.7) RO 3.8 SRO 4.1 A plant startup will be in progress with the 'B' and 'C' RCPs in operation. Maintenance has been completed on the 'A' RCP and the candidate will be directed to start the 'A' RCP IAW OP-100, Reactor Coolant System. Soon after the RCP is started the 'A' RCP Spray valve will fail open resulting in lowering RCS pressure and various MCB annunciators. The Alternate Path begins and the candidate will be expected to determine that entry conditions are met for AOP-019, Malfunction Of RCS Pressure Control and enter the AOP. The candidate is expected to take manual control of the spray valve and shut the valve in accordance with the immediate actions of AOP-019. This will preclude an RCS pressure reduction to a Safety Injection actuation setpoint. When the candidate has shut the RCP 'A' Spray valve, 1RC-107 this JPM is complete.

Revision Comments 2014 NRC Control Room/In-Plant JPM Summary 10-15-2014 Rev. FINAL 5 Simulator JPMs (continued) JPM e - Using ESW System As A Backup Source of Water To AFW (JPM-CR-107-c) Direct K/A 054 AA1.01 - Ability to operate and / or monitor the following as they apply to the Loss of Main Feedwater AFW controls, including the use of alternate AFW sources (CFR 41.7 / 45.5 / 45.6) RO 4.5 SRO 4.4 The candidate will assume shift as the BOP following a LOCA. The candidate is informed that a leak developed in the Condensate Storage Tank (CST). The CST level has lowered to < 10%. The candidate is directed to supply ESW from the A Header to both the A AFW Pump and the Turbine Driven AFW pumps. This will require shutting down the B MDAFW Pump and 'A' Train of Containment Fan Coolers in addition to the ESW valve alignment. JPM f - Swapping Containment Fan Cooler Lead Fans (OP-169) (JPM-CR-289-a) New K/A - 022 A4.01 Ability to manually operate and/or monitor in the control room: CCS fans (CFR: 41.7 / 45.5 to 45.8) RO 3.6 SRO 3.6 The candidate will assume shift as the BOP with the unit operating at 100% power steady state conditions. The oncoming shift will be performing a test of the sequencer requiring the Containment Fan Cooler lead fan selector switches positioned opposite from the current position. The selector switch repositioning is done in accordance with OP-169, Containment Cooling and Ventilation, Section 8.8. The swap will require each running fan unit (2 fans per unit) to be secured prior to switching the selector. After the selector switch is repositioned each fan in the unit must be restarted in slow speed then switched to high speed operation. JPM g - Reset CVIS and Restore RM-3502A to Operation IAW AOP-025, Attachment 3 (JPM-CR-253-d) Direct - RO ONLY K/A 073 A4.02 Ability to manually operate and/or monitor in the control room: Radiation monitoring system control panel (CFR: 41.7 / 45.5 to 45.8)RO 3.7 SRO 3.7 The candidate will be given initial conditions of 100% and breaker 105 opening which resulted in a loss of power to 1A-SA 6.9KV Bus. The bus power has been restored by the 'A' EDG. They will be assigned the BOP position and be directed to perform AOP-025 Attachment 3 to reset and restore Containment Ventilation Isolation System and restore Radiation Monitor RM-3502A to operation. This will require both MCB manipulations and RM-11 control manipulations. Once the candidate has restored RM3502A to service Attachment 3 is complete and the JPM is complete.

Revision Comments 2014 NRC Control Room/In-Plant JPM Summary 10-15-2014 Rev. FINAL 6 Simulator JPMs (continued) JPM h - Restoring Control Room Area HVAC to Normal After a Control Room Isolation Signal (OP-173) (JPM-CR-171-a) - SRO Upgrade - Modified - Alternate Path K/A APE 067 AA1.05 - Ability to operate and / or monitor the following as they apply to the Plant Fire on Site: Plant and control room ventilation systems (CFR 41.7 / 45.5 / 45.6) RO 3.0 SRO 3.1 The candidate will be given initial conditions of the unit is operating at 100% power when a fire occurred at the Emergency Shutdown Diesel Generator during testing. The smoke from the fire caused a Control Room Ventilation Isolation signal to occur. (Smoke detected at the normal intake Zone 1-150). The Fire Brigade has put the fire out and the smoke has been cleared. The candidate will be directed by the CRS to restore Control Room Area HVAC to normal in accordance with OP-173, Control Room Area HVAC System, Section 8.4. The initial conditions are satisfied and the HVAC system is in operation per section 8.1 of OP-173. While the candidate is shutting the Control Room Emergency Filtration Recirc dampers the Alternate Path will begin with the running Control Room Normal Supply Fan breaker tripping open. This will result in annunciator ALB-030-6-4, Cont Room HVAC Normal Supply Fans AH-15 Low Flow - O/L. Using the annunciator panel procedure the candidate will start the standby Normal Supply Fan in accordance with OP-173 section 5.1. Once the candidate has restored the Control Room Normal Supply Fan the JPM is complete.

Revision Comments 2014 NRC Control Room/In-Plant JPM Summary 10-15-2014 Rev. FINAL 7 In-Plant JPMs JPM i - Shift Battery Chargers, At power, shift from one safety battery charger to the other (OP-156.01) (JPM IP-074-a) Direct - SRO Upgrade K/A 063 G2.1.30 Ability to locate and operate components, including local controls. (CFR: 41.7 / 45.7)RO 4.4 / SRO 4.0 The unit is operating at 100%. The CRS will direct the candidate to shift Train A battery chargers from 1A-SA to 1B-SA in service to support scheduled maintenance on the 1A-SA Battery Charger. The candidate will perform OP-156.01 section 8.3. The JPM cues include information of the proper status of the power supply light indications and breaker status. Once the candidate has secured the 1A-SA Battery Charger and verifies the 1A-SB Battery Charger is in service (the No Charge light off and voltage is in the normal band) this JPM is complete. JPM j - Isolate the SI Accumulators After a Control Room Evacuation (AOP-004) (JPM-IP-232-a) Direct K/A APE 068 G2.1.30 Ability to locate and operate components, including local controls. (CFR: 41.7 / 45.7)RO 4.4 / SRO 4.0 The unit Main Control Room has been evacuated due to a fire. The crew is performing a cooldown in accordance with AOP-004, Remote Shutdown. The CRS will direct the candidate to isolate SI Accumulators. The candidate will perform AOP-004 step 31. The JPM cues include information of the proper status of the power supply light indications. The candidate will be required to obtain the key for the Auxiliary Transfer Panel in order to reposition the SI Accumulator isolation valves from this location. Once the CRS is notified that AOP-004, step 31 is complete and the SI Accumulators are isolated then evaluation on this JPM is complete. JPM k - Reset the Turbine Driven AFW Pump Mechanical Overspeed (OP-137) (JPM-IP-001-b) Direct - SRO Upgrade K/A 061 A2.04 Ability to (a) predict the impacts of the following malfunctions or operations on the AFW; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: pump failure or improper operation (CFR: 41.5 / 43.5 / 45.3 / 45.13) RO 3.4 / SRO 3.8 NOTE: This JPM is inside the RCA The unit has tripped from 100% power. The Turbine Driven AFW pump started and has tripped on overspeed. The pump is needed for plant cooldown efforts. The cause of the overspeed trip has been identified and corrected by Maintenance. The CRS has directed the candidate to reset the Turbine Driven AFW mechanical overspeed trip linkage. 1MS-70 and 1MS-72 (steam supply valves to the TDAFW pump) are indicating shut from the MCB. The CRS also notifies the candidate that the Trip and Throttle Valve will be reopened from the Control Room.

Revision Comments 2014 NRC Control Room/In-Plant JPM Summary 10-15-2014 Rev. FINAL 8 Simulator JPM revisions: JPM a - N/A JPM b - N/A JPM c - N/A JPM d - N/A JPM e - N/A JPM f - N/A JPM g - N/A JPM h - N/A In-Plant JPM revisions: JPM i - N/A JPM j - N/A JPM k - N/A

SCENARIO'S 1 AND 2 RO List (4 total) ES-301 Transient and Event Checklist Form ES-301-5 1 10/15/2014 Rev. FINAL Facility: Shearon Harris Date of Exam: November 17, 2014 Operating Test No.: 05000400/2014302 A P P L I C A N T E V E N T T Y P E Scenarios 1 2 T O T A L M I N I M U M(*) CREW POSITION CREW POSITION S R O A T C B O P S R O A T C B O P R I U RO - 1 SRO-I SRO-U RX R1 1 1 NOR N1 N5 2 1 I/C C3, I4 C3, I4 4 4 MAJ M6 M8 2 2 TS 0 0 RO - 2 SRO-I SRO-U RX R1 1 1 NOR N1 N5 2 1 I/C C3, I4 C3, I4 4 4 MAJ M6 M8 2 2 TS 0 0 RO - 3 SRO-I SRO-U RX R1 1 1 NOR N1 N5 2 1 I/C C3, I4 C3, I4 4 4 MAJ M6 M8 2 2 TS 0 0 Instructions: 1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the "at-the-controls (ATC)" and "balance-of-plant (BOP)" positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position. 2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis. 3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicant's competence count toward the minimum requirements specified for the applicant's license level in the right-hand columns.

SCENARIO'S 1 AND 2 RO List (4 total) ES-301 Transient and Event Checklist Form ES-301-5 2 10/15/2014 Rev. FINAL Facility: Shearon Harris Date of Exam: November 17, 2014 Operating Test No.: 05000400/2014302 A P P L I C A N T E V E N T T Y P E Scenarios 1 2 T O T A L M I N I M U M(*) CREW POSITION CREW POSITION S R O A T C B O P S R O A T C B O P R I U RO - 4 SRO-I SRO-U RX R1 1 1 NOR N1 1 1 I/C C2, C5 C2, C7 4 4 MAJ M6 M8 2 2 TS 0 0 Instructions: 1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the "at-the-controls (ATC)" and "balance-of-plant (BOP)" positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position. 2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis. 3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicant's competence count toward the minimum requirements specified for the applicant's license level in the right-hand columns.

SCENARIO'S 1 AND 2 SRO Instant List (2 total) ES-301 Transient and Event Checklist Form ES-301-5 3 10/15/2014 Rev. FINAL Facility: Shearon Harris Date of Exam: November 17, 2014 Operating Test No.: 05000400/2014302 A P P L I C A N T E V E N T T Y P E Scenarios 1 2 T O T A L M I N I M U M(*) CREW POSITION CREW POSITION S R O A T C B O P S R O A T C B O P R I U RO SRO-I 1 SRO-U RX R1 R1 2 1 NOR N1, N5 2 1 I/C C2, C5 C2, C3 I4, C7 6 4 MAJ M6 M8 2 2 TS T3, T6 2 2 RO SRO-I 2 SRO-U RX R1 R1 2 1 NOR N1, N5 2 1 I/C C2, C5 C2, C3 I4, C7 6 4 MAJ M6 M8 2 2 TS T3, T6 2 2 Instructions: 1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the "at-the-controls (ATC)" and "balance-of-plant (BOP)" positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.

2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis. 3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicant's competence count toward the minimum requirements specified for the applicant's license level in the right-hand columns.

SCENARIO'S 1 AND 2 SRO Upgrade List (4 total) ES-301 Transient and Event Checklist Form ES-301-5 4 10/15/2014 Rev. FINAL Facility: Shearon Harris Date of Exam: November 17, 2014 Operating Test No.: 05000400/2014302 A P P L I C A N T E V E N T T Y P E Scenarios 1 2 T O T A L M I N I M U M(*) CREW POSITION CREW POSITION S R O A T C B O P S R O A T C B O P R I U RO SRO-I SRO-U1 RX R1 1 0 NOR N1 1 1 I/C C2, C3 I4, C5 4 2 MAJ M6 1 1 TS T2, T3 2 2 RO SRO-I SRO-U2 RX R1 1 0 NOR N1 N1 2 1 I/C C2, C3 I4, C5 C2, C7 6 2 MAJ M6 M8 2 1 TS T2, T3 2 2 RO SRO-I SRO-U3 RX R1 1 0 NOR N1 N1 2 1 I/C C2, C3 I4, C5 C2, C7 6 2 MAJ M6 M8 2 1 TS T2, T3 2 2 Instructions: 1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the "at-the-controls (ATC)" and "balance-of-plant (BOP)" positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position. 2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis. 3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicant's competence count toward the minimum requirements specified for the applicant's license level in the right-hand columns.

SCENARIO'S 1 AND 2 SRO Upgrade List (4 total) ES-301 Transient and Event Checklist Form ES-301-5 5 10/15/2014 Rev. FINAL Facility: Shearon Harris Date of Exam: November 17, 2014 Operating Test No.: 05000400/2014302 A P P L I C A N T E V E N T T Y P E Scenarios 1 2 T O T A L M I N I M U M(*) CREW POSITION CREW POSITION S R O A T C B O P S R O A T C B O P R I U RO SRO-I SRO-U4 RX R1 1 0 NOR N1, N5 2 1 I/C C2, C3 I4, C7 4 2 MAJ M8 1 1 TS T3, T6 2 2 Instructions: 1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the "at-the-controls (ATC)" and "balance-of-plant (BOP)" positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position. 2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis. 3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicant's competence count toward the minimum requirements specified for the applicant's license level in the right-hand columns.

SCENARIO "SPARE" ES-301 Transient and Event Checklist Form ES-301-5 6 10/15/2014 Rev. FINAL Facility: Shearon Harris Date of Exam: November 17, 2014 Operating Test No.: 05000400/2014302 A P P L I C A N T E V E N T T Y P

E Scenarios 3 T O T A L M I N I M U M(*) CREW POSITION CREW POSITION CREW POSITION S R O A T C B O P R I U RO SRO-I SRO-U RX R1 1 1 1 0 NOR N1, N6 2 1 1 1 I/C I2, I3 C4, C5 4 4 4 2 MAJ M7 1 2 2 1 TS T2, T5 2 0 2 2 RO SRO-I SRO-U RX R1 1 1 1 0 NOR N6 1 1 1 1 I/C I3, C5 2 4 4 2 MAJ M7 1 2 2 1 TS 0 0 2 2 RO SRO-I SRO-U RX 0 1 1 0 NOR N1 1 1 1 1 I/C I2, C4 2 4 4 2 MAJ M7 1 2 2 1 TS 0 0 2 2 Instructions: 1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the "at-the-controls (ATC)" and "balance-of-plant (BOP)" positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position. 2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis. 3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicant's competence count toward the minimum requirements specified for the applicant's license level in the right-hand columns.

1 Rev. FINAL ES-301 Competencies Checklist Form ES-301-6 Facility: Harris Nuclear Plant Date of Examination: November 17, 2014 Operating Test No.: 05000400/2014302 Competencies APPLICANTS RO RO (BOP) SRO-U SRO-I SCENARIO SCENARIO SCENARIO SCENARIO 1 2 1 2 1 2 2-BOP 1-RO 2-SRO Interpret / Diagnose Events and Conditions 2,5,6,8,9,10 2,3,4,5,8,9 2,3,4,6,7 2,7,8,10 2,3,4,5,6,7,8,9,10 2,3,4,6,7,8,9,10 2,7,8,10 2,5,6,8, 9,10 2,3,4,6,7,8,9,10 Comply With and Use Procedures (1) 1,2,5,6,8,9,10 1,3,4,5,8,9 1,2,3,4,6,7 1,2,7,8, 10 1,2,3,4,5,6,7,8,9,10 1,2,3,4,5,6,7,8,9, 10 1,2,7,8, 10 1,2,5,6, 8,9,10 1,2,3,4,5,6,7,8,9, 10 Operate Control Boards (2) 1,2,5,6,8,9,10 1,3,4,5,8,9 1,2,3,4,6,7 1,2,7,8, 10 0 0 1,2,7,8, 10 1,2,5,6, 8,9,10 0 Communicate and Interact 1,2,5,6,8,9,10 1,3,4,5,8,9 1,2,3,4,6,7 1,2,7,8, 10 1,2,3,4,5,6,7,8,9,10 1,2,3,4,5,6,7,8,9, 10 1,2,7,8, 10 1,2,5,6, 8,9,10 1,2,3,4,5,6,7,8,9, 10 Demonstrate Supervisory Ability (3) 0 0 0 0 1,2,3,4,5,6,7,8,9,10 1,2,3,4,5,6,7,8,9, 10 0 0 1,2,3,4,5,6,7,8,9, 10 Comply With and Use Tech. Specs. (3) 0 0 0 0 2,4,5 3,6 0 0 3,6 Notes: (1) Includes Technical Specification compliance for an RO. (2) Optional for an SRO-U. (3) Only applicable to SROs. Instructions: Check the applicants' license type and enter one or more event numbers that will allow the examiners to evaluate every applicable competency for every applicant. ES-301, Page 27 of 27

2 Rev. FINAL ES-301 Competencies Checklist Form ES-301-6 Facility: Harris Nuclear Plant Date of Examination: November 17, 2014 Operating Test No.: 05000400/2014302 Competencies APPLICANTS RO RO (BOP) SRO-U SRO-I SCENARIO SCENARIO SCENARIO SCENARIO Interpret/Diagnose/ Events and Conditions 3,5,6,7,8,9,10 2,4,7 2,3,4,5,6,7,8,9,10 2,3,4,5,6,7,8,9,10 Comply With and Use Procedures (1) 2,5,6,7,8,9 1,2,4,7 1,2,3,4,5,6,7,8,9,10 1,2,3,4,5,6,7,8,9,10 Operate Control Boards (2) 2,5,6,7,8,9 1,2,4,7 0 0 Communicate and Interact 2,5,6,7,8,9 1,2,4,7 1,2,3,4,5,6,7,8,9,10 1,2,3,4,5,6,7,8,9,10 Demonstrate Supervisory Ability (3) 0 0 1,2,3,4,5,6,7,8,9,10 1,2,3,4,5,6,7,8,9,10 Comply With and Use Tech. Specs. (3) 0 0 2,5 2,5 Notes: (1) Includes Technical Specification compliance for an RO. (2) Optional for an SRO-U. (3) Only applicable to SROs. SCENARIO # 3 submitted as a SPARE Scenario Instructions: Check the applicants' license type and enter one or more event numbers that will allow the examiners to evaluate every applicable competency for every applicant. ES-301, Page 27 of 27

= Early Submit Question 1 ES-401 Written Examination Review Worksheet Harris 2014-302 Form ES-401-9 Instructions [Refer to Section D of ES-401 and Appendix B for additional information regarding each of the following concepts.] 1. Enter the level of knowledge (LOK) of each question as either (F)undamental or (H)igher cognitive level. 2. Enter the level of difficulty (LOD) of each question using a 1 - 5 (easy - difficult) rating scale (questions in the 2 - 4 range are acceptable). 3. Check the appropriate box if a psychometric flaw is identified: The stem lacks sufficient focus to elicit the correct answer (e.g., unclear intent, more information is needed, or too much needless information). The stem or distractors contain cues (i.e., clues, specific determiners, phrasing, length, etc). The answer choices are a collection of unrelated true/false statements. The distractors are not credible; single implausible distractors should be repaired, more than one is unacceptable. One or more distractors is (are) partially correct (e.g., if the applicant can make unstated assumptions that are not contradicted by stem). 4. Check the appropriate box if a job content error is identified: The question is not linked to the job requirements (i.e., the question has a valid K/A but, as written, is not operational in content). The question requires the recall of knowledge that is too specific for the closed reference test mode (i.e., it is not required to be known from memory). The question contains data with an unrealistic level of accuracy or inconsistent units (e.g., panel meter in percent with question in gallons). The question requires reverse logic or application compared to the job requirements. 5. Check questions that are sampled for conformance with the approved K/A and those that are designated SRO-only (K/A and license level mismatches are unacceptable). 6. Enter question source: (B)ank, (M)odified, or (N)ew. Check that (M)odified questions meet criteria of ES-401 Section D.2.f. 7. Based on the reviewer's judgment, is the question as written (U)nsatisfactory (requiring repair or replacement), in need of (E)ditorial enhancement, or (S)atisfactory? 8. At a minimum, explain any "U" ratings (e.g., how the Appendix B psychometric attributes are not being met).

Q# 1. LOK (F/H) 2. LOD (1-5) 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. B/M/N 7. U/E/S 8. Explanation Stem Focus Cues T/F Cred. Dist. Partial Job-Link Minutia #/ units Back-ward Q= K/A SRO Only 1 F 2 B S 007EK1.04; Knowledge of the operational implications of the decrease in reactor power following reactor trip (prompt drop and subsequent decay) as it applies to the reactor trip. K/A is met. Very close to GFE question. drl 9/29/14 2 H 3 N E 008AK1.01; Knowledge of the operational implications of thermodynamics and flow characteristics of open or leaking Valves as it applies to a Pressurizer Vapor Space Accident.

K/A is met. Typo on second part of the question "rupture" not "ruture". drl 9/29/14 HNP Response: Corrected typo from "ruture" to "rupture". After a review of the enhancement with David Lanyi on 10/10/14 the question is now SAT. AWL 10/08/14 Question is SAT. drl 10/31/14

= Early Submit Question 2 Q# 1. LOK (F/H) 2. LOD (1-5) 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. B/M/N 7. U/E/S 8. Explanation Stem Focus Cues T/F Cred. Dist. Partial Job-Link Minutia #/ units Back-ward Q= K/A SRO Only 3 H 3 N S/U 009EG2.1.20; Ability to interpret and execute procedure steps. K/A is met. drl 9/29/14 Too much overlap with question 24. HNP Response: Replaced question 24 to avoid overlap concerns. This question was rated SAT/UnSat due to overlap. There is no longer an overlap issue since question 24 was replaced. Reviewed HNP changes with David Lanyi on 10/10/14. David agreed that this question was and is still SAT and the replacement of either question to a topic that would avoid overlap was appropriate. Question #3 is rated SAT and can be considered SAT from the initial evaluation. AWL 10/08/14 Question is SAT. drl 10/31/14 4 F 2 B E 011EA1.15; Ability to operate and monitor the RCS temperature and pressure as they apply to a Large Break LOCA. K/A is met. Another question close to GFE. Could we make this more Harris specific by putting values in the answers. Give specific RCS temperatures. This would require giving the S/G pressures. Instead of stating just below normal accumulator pressure state a specific pressure. Likewise for RHR pressure. drl 9/29/14 HNP Response: Enhanced question to make more Harris specific by adding values for RCS temperature and pressure into the answers as suggested.

After a review of the enhancement with David Lanyi on 10/10/14 the question is now SAT. AWL 10/10/14 Question is SAT. drl 10/31/14 5 H 3 N S 015AA1.16 - Ability to operate and / or monitor the following as they apply to the Reactor Coolant Pump Malfunctions (Loss of RC Flow): Low-power reactor trip block status lights. K/A is met. drl 9/29/14

= Early Submit Question 3 Q# 1. LOK (F/H) 2. LOD (1-5) 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. B/M/N 7. U/E/S 8. Explanation Stem Focus Cues T/F Cred. Dist. Partial Job-Link Minutia #/ units Back-ward Q= K/A SRO Only 6 H 3 N E 022AA2.01; Ability to determine and interpret whether a charging line leak exists as it applies to the Loss of Reactor Coolant Makeup. K/A is met. Only give one RCP seal leakoff alarm. The give all3 leakoff value. Make them 5.1, 5.0, and 4.9. This would give more credence to the seal failure answer. drl 9/29/14. HNP Response: Enhanced question to have ONLY the 'C' RCP seal leakoff high/low flow annunciator in alarm and provided the individual seal injection flows as requested. After a review of the enhancement with David Lanyi on 10/10/14 the question is now SAT. AWL 10/10/14 Question is SAT. drl 10/31/14 7 H 3 B E 025AK1.01; Knowledge of the operational implications of the loss of RHRS during all modes of operation as it applies to Loss of Residual Heat Removal System. K/A is met. I know answer C is the words straight out of the TS, but it flags the answer. Can we change it to "Suspend fuel movement immediately"? If you like, we can also change D to read "Immediately verify all containment penetrations closed". Add reference to procedure that contains requirement to trip the plant. drl 9/29/14drl 9/29/14 HNP Response: Enhanced question answers C and D as requested. Did NOT make any reference to a procedure that contains requirements to trip the plant since the plant is in Mode 6 (Defueled). Discussed the no reference added with David Lanyi on 10/10/14 and he agreed we didn't need one. After a review of the enhancement with David Lanyi on 10/10/14 the question is now SAT. AWL 10/10/14 Question is SAT. drl 10/31/14 8 F 2 B S 026AK3.01; Knowledge of the reasons for the conditions that will initiate the automatic opening and closing of the SWS isolation valves to the CCWS coolers as they apply to the Loss of Component Cooling Water. K/A is kind of met. drl 9/29/14

= Early Submit Question 4 ES-401 2 Form ES-401-9 Q# 1. LOK (F/H) 2. LOD (1-5) 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. B/M/N 7. U/E/S 8. Explanation Stem Focus Cues T/F Cred. Dist. Partial Job-Link Minutia #/ units Back-ward Q= K/A SRO Only 9 F 2 N S 029EK3.06; Knowledge of the reasons for verifying a main turbine trip; methods as they apply to the ATWS. K/A is met. drl 9/29/14 10 H 3 N S 040AK2.01; Knowledge of the interrelations between the Steam Line Rupture and valves. K/A is met. drl 9/29/14 11 H 3 N S 054AG2.4.9; Knowledge of low power/shutdown implications in accident (e.g., loss of coolant accident or loss of residual heat removal) mitigation strategies. K/A is met. drl 9/29/14 12 H 3 X N U/E 056AA1.08; Ability to operate and / or monitor HVAC chill water pump and unit as they apply to the Loss of Offsite Power. K/A is met. C & D are not very plausible. The chiller is a safety related piece of equipment and is required to be operable for TS. Therefore not having them restart on an ESF is unlikely. Could we reword the question to stating that they only one chiller is operating and they swapped chillers 1 minute prior to the loss of power. Then C and D answers would mimic A and B except you would add that they had to wait the 30 minute anti-cycle time. Correct answer remains the same. drl 9/29/14 HNP Response: We have enhanced the question by changing the stem as follows: 1 minute ago the crew completed an ESCW Chiller swap from the 'A' Chiller to the 'B' Chiller. All other parts of the question were left as is. After a review of the enhancement with David Lanyi on 10/10/14 the question is now SAT. David also agreed that the original assessment of this question should be graded an "Enhancement". AWL 10/10/14 Question is SAT. drl 10/31/14

= Early Submit Question 5 Q# 1. LOK (F/H) 2. LOD (1-5) 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. B/M/N 7. U/E/S 8. Explanation Stem Focus Cues T/F Cred. Dist. Partial Job-Link Minutia #/ units Back-ward Q= K/A SRO Only 13 H 3 B E 062AG2.4.1; Knowledge of EOP entry conditions and immediate action steps. K/A is kind of met. C is not plausible. Given answer D exists, no one would choose C. Could we ask the required IMMEDIATE ACTIONS per AP-22? The answers could look like this: a. Secure the B CSIP.and isolate letdown b.Secure the A CSIP and isolate letdown c.Emergency Stop the A EDG d.Trip the Turbine and Reactor. drl 9/29/14 After a review of the question wording and content with David Lanyi on 10/10/14 there is no need for any modification and the question. Question is SAT. AWL 10/10/14 Question is SAT. drl 10/31/14 14 F 2 N E 065AA2.05; Ability to determine and interpret the following as they apply to the Loss of Instrument Air: When to commence plant shutdown if instrument air pressure is decreasing. K/A is met. Add reference to procedure that contains requirement to trip the plant. drl 9/29/14 HNP Response: Enhanced question by adding the requested reference. After a review of the enhancement with David Lanyi on 10/10/14 the question is now SAT. AWL 10/10/14 Question is SAT. drl 10/31/14 15 F 3 B S WE04EK2.1; Knowledge of the interrelations between the (LOCA Outside Containment) and components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features. K/A is met. drl 9/29/14 16 F 2 M S WE05EK2.2; Knowledge of the interrelations between the (Loss of Secondary Heat Sink) and the Facility's heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility. K/A is mostly met. drl 9/29/14

= Early Submit Question 6 Q# 1. LOK (F/H) 2. LOD (1-5) 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. B/M/N 7. U/E/S 8. Explanation Stem Focus Cues T/F Cred. Dist. Partial Job-Link Minutia #/ units Back-ward Q= K/A SRO Only 17 H 3 B S WE11EA2.2; Ability to determine and interpret adherence to appropriate procedures and operation within the limitations in the facility's license and amendments as they apply to the (Loss of Emergency Coolant Recirculation). K/A is met.drl 9/29/14 18 H 3 B S 077AK3.02; Knowledge of the reasons for the actions contained in abnormal operating procedure for voltage and grid disturbances as they apply to Generator Voltage and Electric Grid Disturbances. K/A is met. drl 9/29/14 19 F 3 X N U 001AK3.02; Knowledge of the reasons for Tech-Spec limits on rod operability as they apply to the Continuous Rod Withdrawal. K/A is NOT met. The K/A is asking for the applicants to show knowledge of the reasons for the limits, not just when one is exceeded. What are the limits protecting you from? drl 9/29/14 HNP Response: Our question asks for the TS associated with rod operability for Continuous Rod Motion and the "reason" for the condition which was that "two rods are not within the proper alignment". We think that that met the K/A but if you interpret the K/A "Knowledge of the reasons for Tech-Spec limits" as "what are the limits protecting you from" we will enhance the question to ask it that way. HNP Response: After a review of the question to discuss the intent of the question content with David Lanyi on 10/10/14 David agrees that we have met the K/A and the question does not need to be enhanced or changed in any way. David stated that now that he has an understanding of our intent that this question can be considered SAT from the initial evaluation. AWL 10/10/14 Question is SAT. drl 10/31/14 20 H 3 B S 036AA2.01; Ability to determine and interpret ARM system indications as they apply to the Fuel Handling Incidents. K/A is met. drl 9/29/14 21 H 3 N S 037AK1.01; Knowledge of the operational implications of the use of steam tables as it applies to Steam Generator Tube Leak. K/A is met. drl 9/29/14

= Early Submit Question 7 Q# 1. LOK (F/H) 2. LOD (1-5) 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. B/M/N 7. U/E/S 8. Explanation Stem Focus Cues T/F Cred. Dist. Partial Job-Link Minutia #/ units Back-ward Q= K/A SRO Only 22 H 3 N S/E 051AG2.4.46; Ability to verify that the alarms are consistent with the plant conditions. K/A is met. As long as the applicants will know what the C-7A interlock is without the noun name being on the question, this is SAT. If you want to put the noun name in the question, that is acceptable. drl 9/29/14 HNP Response: Reviewed the need for adding the noun name with the validation operator crew that were present for the question review with David Lanyi on 10/10/14. The operators present did NOT think that the enhancement would be needed since the noun name for this interlock is commonly known and not used in discussions. There is no need to make any enhancement to this question. David Lanyi stated that the question can be considered SAT from the initial evaluation. AWL 10/10/14 Question is SAT. drl 10/31/14 23 H 3 B E 068AK2.07; Knowledge of the interrelations between the Control Room Evacuation and the ED/G. K/A is met. The detail in C and D make the answers to A and B seem improbable. Shorten C and D to "Check that the 'B' EDG has energized its emergency bus" and "Check that both emergency busses are energized." drl 9/30/14 HNP Response: Enhanced both answers C and D per request. Question enhancement was reviewed with David Lanyi on 10/10/14 and the question is now SAT. AWL 10/10/14 Question is SAT. drl 10/31/14

= Early Submit Question 8 Q# 1. LOK (F/H) 2. LOD (1-5) 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. B/M/N 7. U/E/S 8. Explanation Stem Focus Cues T/F Cred. Dist. Partial Job-Link Minutia #/ units Back-ward Q= K/A SRO Only 24 H 3 B S/U WE03EK2.2; Knowledge of the interrelations between the (LOCA Cooldown and Depressurization) and the facility's heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility. K/A is met. Too much overlap with question 3. One or the other needs changed. drl 9/30/14 HNP Response: Replaced question 24 to remove the overlap issue with question 3. Reviewed new question with David Lanyi on 10/10/14. David has approved the replacement question and has graded the replacement question as SAT. AWL 10/10/14 WE09EK2.2; Knowledge of the interrelations between the (Natural Circulation Operations) and the facility*s heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility. K/A is met. Question is SAT. drl 10/31/14 25 X B E WE06EK3.2; Knowledge of the reasons for normal, abnormal and emergency operating procedures associated with (Degraded Core Cooling) as they apply to the (Degraded Core Cooling). K/A is met. D is not plausible. "Until orange condition clears" is too nebulous of a statement. Perhaps you can use "as long as adequate NPSH exists." drl 9/30/14 HNP Response: Enhanced answer D to read as suggested.

After a review of the enhancement with David Lanyi on 10/10/14 the question is now SAT. AWL 10/10/14 Question is SAT. drl 10/31/14 26 H 2 N S WE08EA2.2; Ability to determine and interpret adherence to appropriate procedures and operation within the limitations in the facility's license and amendments as they apply to (Pressurized Thermal Shock). K/A is met. drl 9/30/14

= Early Submit Question 9 Q# 1. LOK (F/H) 2. LOD (1-5) 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. B/M/N 7. U/E/S 8. Explanation Stem Focus Cues T/F Cred. Dist. Partial Job-Link Minutia #/ units Back-ward Q= K/A SRO Only 27 H 3 N E WE15EA1.3; Ability to operate and / or monitor desired operating results during abnormal and emergency situations as they apply to the (Containment Flooding). K/A is met. Why not have the second answer be ESW return header? Supply header would never make sense. drl 9/30/14 HNP Response: Enhanced second part of answers C and D to read as requested. After a review of the enhancement with David Lanyi on 10/10/14 the question is now SAT. AWL 10/10/14 Question is SAT. drl 10/31/14 28 H 3 X X N U 003A3.01; Ability to monitor automatic operation of the RCPS, including Seal injection flow. K/A is met. If I wasn't sure if C or D was correct, I would choose D as a subset of C. Is there some semi-auto action that could be used for C? Is manual actuation an actual possible solution to make a correct answer as written? If so, would there be multiple correct answers? drl 9/30/14 HNP Response: Enhanced answers C and D to remove subset issue. After a review of the enhancement with David Lanyi on 10/10/14 the question is now SAT. AWL 10/10/14 Question is SAT. drl 10/31/14 29 F 2 N S 004A3.10; Ability to monitor automatic operation of the CVCS, including PZR level and pressure. K/A is met. drl 9/30/14 30 F 2 N S 004K4.05; Knowledge of CVCS design feature(s) and/or interlock(s) which provide for the interrelationships and design basis, including fluid flow splits in branching networks (e.g., charging and seal injection flow). K/A is met. drl 9/30/14 31 H 3 B S 005K6.03; Knowledge of the effect of a loss or malfunction on the RHR heat exchanger will have on the RHRS. K/A is met. drl 9/30/14

= Early Submit Question 10 Q# 1. LOK (F/H) 2. LOD (1-5) 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. B/M/N 7. U/E/S 8. Explanation Stem Focus Cues T/F Cred. Dist. Partial Job-Link Minutia #/ units Back-ward Q= K/A SRO Only 32 H 2 X N U 005 G2.4.1 Knowledge of EOP entry conditions and immediate action steps. K/A is NOT met. This does not provide any insight as to their knowledge of Immediate Action steps. drl 9/30/14 HNP Response: Reviewed discussion that took place on 5/07/14 with David Lanyi where David said it was OK to write the question to the AOP entry conditions since the EOPs don't have any relationship with this system with regard to entry conditions or immediate actions. This discussion was captured in the question "comments" area. After reviewing this with David he stated that the question should not have been graded as UnSat and can be considered SAT from the initial submittal. AWL 10/10/14 Question is SAT. drl 10/31/14 33 F 2 N E 006A1.15; Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the ECCS controls including RWST level and temperature.

K/A is mostly met. Does this question require the use of a strapping table to translate % level into gallons? Do you really need the first two sets of data? The only thing of use is the last set. You could change it to a two by two question with only level and temperature or boron concentration and ask what is the latest time you had to restore the values?. This would fully meet the K/A then. drl 9/30/14 HNP Response: Question doesn't need the use of a table. Enhanced the question to only address the last set of data and provided ONLY the level and temperature parameter values. Question was then enhanced into a 2 x 2 question as requested to fully meet the K/A. Revised question plausibility to reflect the changes. AWL 10/22/14 Question is SAT. drl 10/31/14 34 F 3 N S 006K2.01; Knowledge of bus power supplies to the ECCS pumps. K/A is met. drl 9/30/14 35 F 2 N S 007A1.03; Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the PRTS controls including monitoring quench tank temperature. K/A is met. drl 9/30/14

= Early Submit Question 11 Q# 1. LOK (F/H) 2. LOD (1-5) 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. B/M/N 7. U/E/S 8. Explanation Stem Focus Cues T/F Cred. Dist. Partial Job-Link Minutia #/ units Back-ward Q= K/A SRO Only 36 H 3 X B E 003 K5.02 Knowledge of the operational implications of the following concepts as they apply to the RCPS: Effects of RCP coastdown on RCS parameters. K/A is kind of met. The K/A is really looking at the effects of the coastdown (i.e., what the extended flow time does to RCS parameters. Really this should be looking at what flow really is compared with OTT setpoints. If this is the best you can do with this, we'll call it SAT, but let's look at it again first. drl 9/30/14. HNP Response: Reviewed the question content with David Lanyi on 10/10/14. After explaining how HNP is meeting the intent of the K/A David agreed that the question did not need to be enhanced. David stated that the question can be considered SAT from the initial submittal. AWL 10/10/14 Question is SAT. drl 10/31/14 37 H 2 B S 008K4.02; Knowledge of CCWS design feature(s) and/or interlock(s) which provide for the operation of the surge tank, including the associated valves and controls. K/A is met. drl 9/30/14 38 H 2 N S 010G2.1.28; Knowledge of the purpose and function of major system components and controls. K/A is met. drl 9/30/14 39 H 3 B E 012K6.02 Knowledge of the effect of a loss or malfunction of the following will have on the RPS: Redundant channels. K/A is met. Typo in question: "Given" not "Fiven". Drl 9/30/14 HNP Response: Fixed typo.

After a review of the enhancement with David Lanyi on 10/10/14 the question is now SAT. AWL 10/10/14 Question is SAT. drl 10/31/14 40 H 3 N S 012A4.02; Ability to manually operate and/or monitor in the control room components for individual channels. K/A is met. drl 9/29/14 41 H 3 B S 013K5.02; Knowledge of the operational implications of safety system logic and reliability as they apply to the ESFAS. K/A is met. drl 9/30/14

= Early Submit Question 12 Q# 1. LOK (F/H) 2. LOD (1-5) 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. B/M/N 7. U/E/S 8. Explanation Stem Focus Cues T/F Cred. Dist. Partial Job-Link Minutia #/ units Back-ward Q= K/A SRO Only 42 F 2 B S 022A4.03; Ability to manually operate and/or monitor in the control room Dampers in the CCS. K/A is met. Slow speed fans for Maximum Cooling doesn't make a whole lot of sense. I'm not fond of this question, but I don't see any better way to meet the K/A. drl 9/30/14 43 H 3 X X N S/U 026A2.08; Ability to (a) predict the impacts of Safe securing of containment spray (when it can be done) on the CSS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences. K/A is met. Move "After plant operations staff consultation" to the stem of the question (which will remove the typo in C. that required making the staff feel better). This should be common for all four answers. Distractor A is illogical. You can secure it whenever you decide it is a secondary leak? It needs some sort of setpoint. Why not make this a 2x2 with 10 psig/ 8 psig and Phase A&B and CS reset /CS Reset? drl 9/30/14 062A2.05; Ability to (a) predict the impacts of the following malfunctions or operations on the ac distribution system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Methods for energizing a dead bus. K/A is met. Question is SAT. drl 11/3/14 44 H 3 N S/U 026K3.02; .Knowledge of the effect that a loss or malfunction of the CSS will have on the following: Recirculation spray system.

K/A is met. Too much overlap with question 43. Which one do you want the K/A changed? This question would be SAT otherwise. drl 9/30/14 HNP Response: We agree that there was overlap with question 43 due to the question content. HNP will replace question 43. David Lanyi reviewed proposal to replace question 43 and agreed that question 44 is and was SAT from the initial evaluation. AWL 10/10/14 Question is SAT. drl 10/31/14 45 H 3 N S 039A3.02; Ability to monitor automatic operation of the MRSS, including isolation of the MRSS. K/A is met. drl 9/30/14

= Early Submit Question 13 Q# 1. LOK (F/H) 2. LOD (1-5) 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. B/M/N 7. U/E/S 8. Explanation Stem Focus Cues T/F Cred. Dist. Partial Job-Link Minutia #/ units Back-ward Q= K/A SRO Only 46 H 2 B S 059K4.02; Knowledge of MFW design feature(s) and/or interlock(s) which provide for automatic turbine/reactor trip runback. K/A is met. drl 10/1/14 47 F 2 B S 061K2.01; Knowledge of bus power supplies to the AFW system MOVs. K/A is met. drl 10/1/14 48 H 3 N S 061K3.02; Knowledge of the effect that a loss or malfunction of the AFW will have on the S/G. K/A is met. drl 10/1/14 49 F 3 B S 062K2.01; Knowledge of bus power supplies to major system loads. K/A is met. drl 10/1/14 50 H 3 N S 063A2.01; Ability to (a) predict the impacts of grounds on the DC electrical systems; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences. K/A is met. drl 10/1/14 51 H 3 N E 064A2.04; Ability to (a) predict the impacts of Unloading prior to securing an ED/G on the ED/G system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences. K/A is met. I'm ok with this if you feel certain that your applicants need to know the time to unload the EDG. Add "IAW OP-155"right before the question mark. drl 10/1/14 HNP Response: Reviewed concern about EDG unload time with David Lanyi and the validation crew operators on10/10/14. The operators all stated that licensed operators need to know by memory the time to unload the EDGs. HNP has added the enhancement for the procedure reference "IAW OP-155" as requested. .

After a review of the enhancement with David Lanyi on 10/10/14 the question is now SAT. AWL 10/10/14 Question is SAT. drl 10/31/14

= Early Submit Question 14 Q# 1. LOK (F/H) 2. LOD (1-5) 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. B/M/N 7. U/E/S 8. Explanation Stem Focus Cues T/F Cred. Dist. Partial Job-Link Minutia #/ units Back-ward Q= K/A SRO Only 52 F 3 N E 073G2.1.30; Ability to locate and operate components, including local controls. K/A is met. Again, I'm ok with this as long as you expect your operators to know the locations from memory. drl 10/1/14 HNP Response: Reviewed concern about memorization of component location with David Lanyi and the validation crew operators on10/10/14. The operators all stated that they felt that the applicants do need to know the locations from memory. David Lanyi accepted the operators response to his question and has agreed that question is SAT. Since no enhancements were needed the question should be considered SAT from the initial review. AWL 10/10/14 Question is SAT. drl 10/31/14 53 F 2 B E 076 K1.01 Knowledge of the physical connections and/or cause- effect relationships between the SWS and the following systems: CCW system.

K/A is met. Too many options. Let's go with 1, 2, and 4. Then you have 1&2, 1&4. 2&4, 1,2&4. Right now it is too easy to get rid of 2 choices. drl 10/1/14 HNP Response: Enhanced the question to suggestion by eliminating some of the responses. The question now has 3 option choices and combinations of those choices.

After a review of the enhancement with David Lanyi on 10/10/14 the question is now SAT. The plausibility statements were revised to reflect the question enhancement. AWL 10/10/14 Question is SAT. drl 10/31/14 54 H 2 B S 078K3.03; Knowledge of the effect that a loss or malfunction of the IAS will have on the cross-tied units. K/A is met. drl 10/1/14

= Early Submit Question 15 Q# 1. LOK (F/H) 2. LOD (1-5) 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. B/M/N 7. U/E/S 8. Explanation Stem Focus Cues T/F Cred. Dist. Partial Job-Link Minutia #/ units Back-ward Q= K/A SRO Only 55 H 3 B E 103K1.03 Knowledge of the physical connections and/or cause effect relationships between the containment system and the following systems: Shield building vent system. K/A is met. Would it make sense to change the containment fan coil unit to reactor support cooling? drl 10/1/14 HNP Response: If we used the "containment fan coil units" in the question it would have 2 correct answers. Discuss with David Lanyi.

After a review of the question on 10/10/14 the question is will remain as originally submitted and can be considered SAT from the initial evaluation. AWL 10/10/14 Question is SAT. drl 10/31/14 56 F 3 B S 001K2.03; Knowledge of bus power supplies - One-line diagram of power supplies to logic circuits. This K/A is met drl 10/1/14 57 H 2 B S 011A4.04; Ability to manually operate and/or monitor in the control room the Transfer of PZR LCS from automatic to manual control. K/A is met. drl 10/1/14 58 H 2 B S 017K4.03; Knowledge of ITM system design feature(s) and/or interlock(s) which provide for the range of temperature indication. K/A is met. drl 10/1/14

= Early Submit Question 16 Q# 1. LOK (F/H) 2. LOD (1-5) 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. B/M/N 7. U/E/S 8. Explanation Stem Focus Cues T/F Cred. Dist. Partial Job-Link Minutia #/ units Back-ward Q= K/A SRO Only 59 H 2 B U 027A2.01; Ability to (a) predict the impacts of high temperature in the filter system on the CIRS; and (b) based on those predictions, use Procedures to correct, control, or mitigate the consequences. K/A is met Typo "midigate" The high P answer doesn't work with either second part answer. This probably needs a better K/A. How many questions are available that this was selected randomly? drl 10/1/14 This question submitted for this K/A was developed and approved for the 2013 HNP NRC Written Examination and identified as "PREVIOUS" as required in accordance with the guidelines of NuReg 1021 Rev. 9 Supplement 1, ES-401. During the review of all HNP submitted questions with David Lanyi on 10/10/2014 the HNP exam team and David could not come to an agreeable solution to the issue of 2 implausible distractors. At that time HNP requested a replacement K/A which David agreed to.

On 10/14/2014 David Lanyi contacted the HNP exam development team and provided a replacement K/A. The new K/A is 035A2.04; Ability to (a) predict the impacts of the following malfunctions or operations on the GS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Steam flow/feed mismatch HNP Response: On 10/22/14 the HNP exam development team has created a new question for K/A 035A2.04. AWL 10/22/2014 035A2.04, Ability to (a) predict the impacts of the following malfunctions or operations on the GS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of Steam flow/feed mismatch.

K/A is met. Question is SAT 11/3/14 drl

= Early Submit Question 17 Q# 1. LOK (F/H) 2. LOD (1-5) 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. B/M/N 7. U/E/S 8. Explanation Stem Focus Cues T/F Cred. Dist. Partial Job-Link Minutia #/ units Back-ward Q= K/A SRO Only 60 H 3 N E 029K3.02; Knowledge of the effect that a loss or malfunction of the Containment Purge System will have on Containment entry. K/A is met. I'm OK with this one if you expect your operators to know the oxygen limits. drl 10/1/14 HNP Response: Discussed David's concern about whether or not operators should know the oxygen limits with the operators present on 10/10/14. The operators stated that they have to go into areas of the RAB where the oxygen content is constantly monitored with visual electronic readouts. They felt that it is expected operator knowledge. David Lanyi accepted the operators response to his question and has agreed that question is SAT. Since no enhancements were needed the question should be considered SAT from the initial review. AWL 10/10/14 Question is SAT. drl 10/31/14 61 H 3 B S 041K6.03; Knowledge of the effect of a loss or malfunction on controller and positioners, including ICS, S/G, CRDS will have on the SDS. K/A is met. drl 10/1/14 62 H 2 B E 045A1.06; Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the MT/G system controls including expected response of secondary plant parameters following T/G trip. K/A is met. Typo: Need a comma after the phrase "Assuming NO operator actions have occured after the Turbine has tripped". Also, need to correct spelling of "occurred". drl 10/1/14 HNP Response: Corrected identified typos. David Lanyi reviewed and accepted the question enhancement and has graded the question as SAT. AWL 10/10/14 Question is SAT. drl 10/31/14

= Early Submit Question 18 Q# 1. LOK (F/H) 2. LOD (1-5) 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. B/M/N 7. U/E/S 8. Explanation Stem Focus Cues T/F Cred. Dist. Partial Job-Link Minutia #/ units Back-ward Q= K/A SRO Only 63 F 3 B E 055G2.1.28; Knowledge of the purpose and function of major system components and controls. K/A is met. Most of the stem is irrelevant. You can get by with just stating, "The unit is at 100% power when Main Condenser backpressure begins to degrade. For the B Vacuum pump -." drl 10/1/14 HNP Response: Enhanced the question per suggestion. David Lanyi reviewed and accepted the question enhancement and has graded the question as SAT. AWL 10/10/14 Question is now SAT. drl 10/31/14 64 H 3 B S 056K1.03; Knowledge of the physical connections and/or cause-effect relationships between the Condensate System and MFW. K/A is met. drl 10/1/14 65 H 3 N S 068K5.04 Knowledge of the operational implication of the following concepts as they apply to the Liquid Radwaste System: Biological hazards of radiation and the resulting goal of ALARA. K/A is met drl 10/1/14 66 H 3 B E G2.1.38 Knowledge of the station's requirements for verbal communications when implementing procedures. K/A is met. Make the question read "For which ONE of the following events will normal alarm response protocol be AUTOMATICALLY suspended in accordance with AD-OP-ALL-1000, Fleet Conduct of Operations?" drl 10/2/14 HNP Response: Enhanced the question per suggestion. David Lanyi reviewed and accepted the question enhancement and has graded the question as SAT. AWL 10/10/14 Question is now SAT. drl 10/31/14

= Early Submit Question 19 Q# 1. LOK (F/H) 2. LOD (1-5) 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. B/M/N 7. U/E/S 8. Explanation Stem Focus Cues T/F Cred. Dist. Partial Job-Link Minutia #/ units Back-ward Q= K/A SRO Only 67 H 3 B E G2.1.44 Knowledge of RO duties in the control room during fuel handling, such as responding to alarms from the fuel handling area, communication with the fuel storage facility, systems operated from the control room in support of fueling operations, and supporting instrumentation. K/A is met. I'm concerned that B could be argued as not incorrect. Could we not give them the audio count rate channel selection as a given answer? Then we can use: a. the Wide Range Neutron Flux Monitor on the opposite side of the core from NI-32 b. the Wide Range Neutron Flux Monitor on the same side of the core as NI-32 c. the Wide Range Neutron Flux Monitor on the opposite side of the core from NI-32 and the audio count rate channel is selected to Source Range NI-32 d. the Wide Range Neutron Flux Monitor on the same side of the core as NI-32 and the audio count rate channel is selected to Source Range NI-32 drl 10/2/14 HNP Response: David Lanyi reviewed the question with Exam Development team and the validation Operators that were present on 10/10/14. David Lanyi stated that after clarification that this question does NOT require any enhancements is and was SAT without issues from initial evaluation. AWL 10/10/14 Question is now SAT. drl 10/31/14 68 F 3 B S G2.2.35 Ability to determine Technical Specification Mode of Operation. K/A is met. drl 10/2/14 69 H 2 N S G2.2.41 Ability to obtain and interpret station electrical and mechanical drawings. K/A is met drl 10/2/14 70 F 2 B S G2.3.15 Knowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc. K/A is met. drl 10/2/14 71 F 2 B S G2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions. K/A is met. drl 10/2/14

= Early Submit Question 20 Q# 1. LOK (F/H) 2. LOD (1-5) 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. B/M/N 7. U/E/S 8. Explanation Stem Focus Cues T/F Cred. Dist. Partial Job-Link Minutia #/ units Back-ward Q= K/A SRO Only 72 F 2 B S G2.3.7 Ability to comply with radiation work permit requirements during normal or abnormal conditions. K/A is met. This is very close to GFE information. drl 10/2/14 73 H 2 B E G2.4.17 Knowledge of EOP terms and definitions. K/A is met. Make distractor C read "LOWERING because RCS pressure is lowering". drl 10/2/14 HNP Response: Enhanced question per directions provided. Reviewed question enhancement with David Lanyi and question is now SAT. AWL 10/10/14 Question is now SAT. drl 10/31/14 74 H 3 B S G2.4.20 Knowledge of the operational implications of EOP warnings, cautions, and notes. K/A is met. 75 H 3 B E G2.4.9 Knowledge of low power/shutdown implications in accident (e.g., loss of coolant accident or loss of residual heat removal) mitigation strategies. K/A is met. Not sure why anyone would choose D. Could we make that answer to start bot RHR pumps through their respective cold leg valves. Might need to modify question a little to ensure that they choose the first required action. Drl 10/2/14 HNP Response: David Lanyi reviewed the question with the HNP Exam Development team and the validation crew Operators on 10/10/14. After clarification of the question content with David he has accepted the question as SAT and does NOT require any enhancements.

Question is and was SAT without issues from initial evaluation. AWL 10/10/14 Question is now SAT. drl 10/31/14 SRO QUESTIONS 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

= Early Submit Question 21 Q# LOK (F/H) LOD (1-5) Stem Focus Cues T/F Cred. Dist. Partial Job-Link Minutia #/ units Back-ward Q= K/A SRO Only B/M/N U/E/S Explanation 76 S1 H 3 M S 008AA2.30; Ability to determine and interpret Inadequate core cooling as it applies to the Pressurizer Vapor Space Accident. K/A is met. drl10/2/14 77 S2 H 3 X N U 011EG2.2.44; Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions. K/A is met. Question is NOT SRO only. RO knowledge is required to determine if cold leg recirc is available based upon the position of 1SI-341. The titles to the subsequent EOPs give enough information for an RO to answer this question. drl 10/2/14 HNP Response: Corrected question non-SRO flaw. Revised second part question to meet SRO level. JRH 10/22/14 Question is now SAT. drl 10/31/14 78 S3 H 2 B S 025AG2.4.3: Ability to identify post-accident instrumentation. K/A is met. drl 10/2/14 79 S4 H 3 N S 056AA2.54; Ability to determine and interpret breaker position (remote and local) as it applies to the Loss of Offsite Power. K/A is met. drl 10/2/14 80 S5 H 3 N S 065AG2.2.44; Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions. K/A is met. drl 10/2/14 81 S6 H 2 B S WE04EA2.1; Ability to determine and interpret facility conditions and selection of appropriate procedures during abnormal and emergency operations as they apply to the (LOCA Outside Containment). K/A is met. drl 10/2/14 82 S7 H 3 N S 003G2.2.22; Knowledge of limiting conditions for operations and safety limits. K/A is met drl 10/2/14

= Early Submit Question 22 Q# 1. LOK (F/H) 2. LOD (1-5) 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. B/M/N 7. U/E/S 8. Explanation Stem Focus Cues T/F Cred. Dist. Partial Job-Link Minutia #/ units Back-ward Q= K/A SRO Only 83 S8 H 3 N E 060AG2.2.12; Knowledge of surveillance procedures. K/A is met. Change the wording for the second answer to: "2 Rem exposure to the public in the event" Or "0.5 Rem exposure to a radiation worker near the tank" drl10/2/14 HNP Response: Enhanced question per recommendations provided. JRH 10/08/14 After a review of the enhancement with David Lanyi on 10/10/14 the question is now SAT. AWL 10/10/14 Question is now SAT. drl 10/31/14 84 S9 H 3 B S 061AA2.05; Ability to determine and interpret the need for area evacuation; check against existing limits as it applies to the Area Radiation Monitoring (ARM) System Alarms. K/A is met. drl10/2/14 85 S10 H 3 B S WE14EA2.2; Ability to determine and interpret adherence to appropriate procedures and operation within the limitations in the facility's license and amendments as they apply to the (High Containment Pressure). K/A is met. drl 10/2/14 86 S11 H 3 B S 012G2.4.11; Knowledge of abnormal condition procedures. K/A is met. drl 10/2/14 87 S12 H 2 N S 039G2.1.19; Ability to use plant computers to evaluate system or component status. K/A is met. drl 10/2/14 88 S13 H 3 N S 022 A2.04; Ability to (a) predict the impacts of the following malfunctions or operations on the CCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of service water. K/A is met. drl 102/14 89 S14 H 3 M S 076 A2.01 Ability to (a) predict the impacts of the following malfunctions or operations on the SWS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of SWS. K/A is met. drl 10/2/14

= Early Submit Question 23 Q# 1. LOK (F/H) 2. LOD (1-5) 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. B/M/N 7. U/E/S 8. Explanation Stem Focus Cues T/F Cred. Dist. Partial Job-Link Minutia #/ units Back-ward Q= K/A SRO Only 90 S15 F 3 N S 103A2.04; Ability to (a) predict the impacts of Containment evacuation (including recognition of the alarm) on the containment system and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences. K/A is met. drl 10/3/14 91 S16 H 3 N E 015G2.1.23; Ability to perform specific system and integrated plant procedures during all modes of plant operation. K/A is met. Until the instrument is tripped, either second answer will satisfy TS. Why not just ask if continued power ascension is allowed? drl 10/2/14 HNP Response: Enhanced question per recommendation. JRH 10/20/14 Based on discussion with David Lanyi on 10/10/14 after completion of the above corrections the question will be SAT. AWL Question is now SAT. drl 10/31/14 92 S17 H 2 X M E 033G2.4.18; Knowledge of the specific bases for EOPs. K/A is met. The second answers are not logical with the first answers in A and D. It's OK to not have the same 2 answers for the second part as long as that does not make you able to answer the question without knowing the first part. In this case part 2 of A could be "To prevent elevated radiation levels in the spent fuel pool area." Consider D2 to be something like "To prevent boiling in the spent fuel pools that will lower water level." You don't have to use these exact words, but you get the idea. drl 10/3/14 HNP Response: Enhanced question per recommendation. JRH 10/20/14 Based on discussion with David Lanyi on 10/10/14 after completion of the above enhancements the question will be SAT. AWL Question is now SAT. drl 10/31/14

= Early Submit Question 24 Q# 1. LOK (F/H) 2. LOD (1-5) 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. B/M/N 7. U/E/S 8. Explanation Stem Focus Cues T/F Cred. Dist. Partial Job-Link Minutia #/ units Back-ward Q= K/A SRO Only 93 S18 H 3 X N E 071A2.06: Ability to (a) predict the impacts of a supply failure to the isolation valve on the Waste Gas Disposal System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences. K/A is met. I understand why you say that OP-100 could be thought to be required, but it is such a contorted path to get there that it makes it unlikely any SRO would choose it. Instead let them choose between OP-120.07 Section 7.1 and 8.37 (give them titles of the section). drl 10/3/14 HNP Response: Enhanced question per recommendation JRH 10/08/14 After a review of the enhancement with David Lanyi on 10/10/14 the question is now SAT. AWL Question is now SAT. drl 10/31/14 94 S19 H 3 B S G2.1.34 Knowledge of primary and secondary plant chemistry limits. K/A is met. drl 10/3/14 95 S20 H 3 N S G2.1.45 Ability to identify and interpret diverse indications to validate the response of another indication. K/A is met. drl 103/14 96 S21 H 2 B E G2.2.17 Knowledge of the process for managing maintenance activities during power operations, such as risk assessments, work prioritization, and coordination with the transmission system operator. K/A is met. Two of the potential answers would not be on-site and could be unavailable during off-shift hours. Could we make this happen during the work week and make the correct choice the WWM? I know I had previously approved this one, so we can discuss. drl 10/3/14 HNP Response: Enhanced question per recommendation JRH 10/10/14 After a review of the enhancement with David Lanyi on 10/10/14 the question is now SAT. AWL Question is now SAT. drl 10/31/14 97 S22 F 2 B S G2.2.25 Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits. K/A is met. drl 10/3/14

= Early Submit Question 25 Q# 1. LOK (F/H) 2. LOD (1-5) 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. B/M/N 7. U/E/S 8. Explanation Stem Focus Cues T/F Cred. Dist. Partial Job-Link Minutia #/ units Back-ward Q= K/A SRO Only 98 S23 H 2 B S G2.3.14 Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities. K/A is met. drl 10/3/14 99 S24 H 2 B S G2.3.6 Ability to approve release permits. K/A is met. drl 10/3/14 100 S25 H 2 B S G2.4.38 Ability to take actions called for in the facility emergency plan, including supporting or acting as emergency coordinator if required. K/A is met. drl 10/3/14

ES-401, Rev. 9 PWR Examination Outline Form ES-401-2 Facility: Harris Date of Exam: December, 2013 Tier Group RO K/A Category Points SRO-Only Points K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G

• Total A2 G* Total 1. Emergency & Abnormal Plant Evolutions 1 3 3 3 N/A 3 3 N/A 3 18 3 3 6 2 1 2 2 1 2 1 9 2 2 4 Tier Totals 4 5 5 4 5 4 27 5 5 10 2. Plant Systems 1 2 3 3 3 2 2 2 3 3 2 3 28 3 2 5 2 1 1 1 1 1 1 1 1 0 1 1 10 0 1 2 3 Tier Totals 3 3 4 4 3 3 3 4 3 3 4 38 4 4 8 3. Generic Knowledge and Abilities Categories 1 2 3 4 10 1 2 3 4 7 2 2 3 3 2 2 2 1 Notes: 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). 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 and justified; operationally important, site-specific systems that are not included on the outline should be added. Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate K/A statements. 4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution. 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. 8. On the following pages, enter the K/A numbers, a brief description of each topic, the topics= importance ratings (IRs) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above; if fuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note # 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.

ES-401, Rev. 9 2 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (RO / SRO) E/APE # / Name / Safety Function K1 K 2 K 3 A 1 A2 G K/A Topic(s) IR # 000007 (BW/E02&E10; CE/E02)

Reactor Trip - Stabilization - Recovery / 1 X 007EK1.04; Knowledge of the operational implications of the Decrease in reactor power following reactor trip (prompt drop and subsequent decay) as it applies to the reactor trip. 3.6 000008 Pressurizer Vapor Space Accident / 3 X X 008AK1.01; Knowledge of the operational implications of thermodynamics and flow characteristics of open or leaking Valves as it applies to a Pressurizer Vapor Space Accident. 008AA2.30; Ability to determine and interpret Inadequate core cooling as it applies to the Pressurizer Vapor Space Accident. 3.2 4.7 000009 Small Break LOCA / 3 X 009EG2.1.20; Ability to interpret and execute procedure steps. 4.6 000011 Large Break LOCA / 3 X X 011EA1.15; Ability to operate and monitor the RCS temperature and pressure as they apply to a Large Break LOCA. 011EG2.2.44; Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions. 4.2 4.4 000015/17 RCP Malfunctions / 4 X 015AA1.16; Ability to operate and / or monitor Low-power reactor trip block status lights as they apply to the Reactor Coolant Pump Malfunctions (Loss of RC Flow). 3.2 000022 Loss of Rx Coolant Makeup / 2 X 022AA2.01; Ability to determine and interpret whether a charging line leak exists as it applies to the Loss of Reactor Coolant Makeup. 3.2 000025 Loss of RHR System / 4 X X 025AK1.01; Knowledge of the operational implications of the loss of RHRS during all modes of operation as it applies to Loss of Residual Heat Removal System. 025AG2.4.3: Ability to identify post-accident instrumentation. 3.9 3.9 000026 Loss of Component Cooling Water / 8 X 026AK3.01; Knowledge of the reasons for the conditions that will initiate the automatic opening and closing of the SWS isolation valves to the CCWS coolers as they apply to the loss of Component Cooling Water. 3.2 000027 Pressurizer Pressure Control System Malfunction / 3 000029 ATWS / 1 X 029EK3.06; Knowledge of the reasons for verifying a main turbine trip; methods as they apply to the ATWS. 4.2 000038 Steam Gen. Tube Rupture / 3 000040 (BW/E05; CE/E05; W/E12) Steam Line Rupture - Excessive Heat Transfer / 4 X 040AK2.01; Knowledge of the interrelations between the Steam Line Rupture and valves. 2.6 000054 (CE/E06) Loss of Main Feedwater / 4 X 054AG2.4.9; Knowledge of low power/shutdown implications in accident (e.g., loss of coolant accident or loss of residual heat removal) mitigation strategies. 3.8 000055 Station Blackout / 6 000056 Loss of Off-site Power / 6 X X 056AA1.08; Ability to operate and / or monitor HVAC chill water pump and unit as they apply to the Loss of Offsite Power. 056AA2.54; Ability to determine and interpret breaker position (remote and local) as it applies to the Loss of Offsite Power. 2.5 3.0 000057 Loss of Vital AC Inst. Bus / 6 000058 Loss of DC Power / 6 000062 Loss of Nuclear Svc Water / 4 X 062AG2.4.1; Knowledge of EOP entry conditions and immediate action steps. 4.6 000065 Loss of Instrument Air / 8 X X 065AA2.05; Ability to determine and interpret when to commence plant shutdown if instrument air pressure is decreasing as it applies to the Loss of Instrument Air 065AG2.2.44; Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions. 3.4 4.4 W/E04 LOCA Outside Containment / 3 X X WE04EK2.1; Knowledge of the interrelations between the (LOCA Outside Containment) and components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features. WE04EA2.1; Ability to determine and interpret facility conditions and selection of appropriate procedures during abnormal and emergency operations.as they apply to the (LOCA Outside Containment). 3.5 4.3 W/E05 Inadequate Heat Transfer - Loss of Secondary Heat Sink / 4 X WE05EK2.2; Knowledge of the interrelations between the (Loss of Secondary Heat Sink) and the Facility*s heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility. 3.9 W/E11 Loss of Emergency Coolant Recirc. / 4 X WE11EA2.2; Ability to determine and interpret adherence to appropriate procedures and operation within the limitations in the facility*s license and amendments as they apply to the (Loss of Emergency Coolant Recirculation). 3.4 000077 Generator Voltage and Electric Grid Disturbances / 6 X 077AK3.02; Knowledge of the reasons for the actions contained in abnormal operating procedure for voltage and grid disturbances as they apply to Generator Voltage and Electric Grid Disturbances. 3.6 K/A Category Totals: 3 3 3 3 3/3 3/3 Group Point Total: 18/6 ES-401, Rev. 9 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 K1 K2 K 3 A 1 A2 G K/A Topic(s) IR # 000001 Continuous Rod Withdrawal / 1 X 001AK3.02; Knowledge of the reasons for Tech-Spec limits on rod operability as they apply to the Continuous Rod Withdrawal. 3.2 000003 Dropped Control Rod / 1 X 003G2.2.22; Knowledge of limiting conditions for operations and safety limits. 4.7 000005 Inoperable/Stuck Control Rod / 1 000024 Emergency Boration / 1 000028 Pressurizer Level Malfunction / 2 000032 Loss of Source Range NI / 7 000033 Loss of Intermediate Range NI / 7 000036 (BW/A08) Fuel Handling Accident / 8 X 036AA2.01; Ability to determine and interpret ARM system indications as they apply to the Fuel Handling Incidents. 3.2 000037 Steam Generator Tube Leak / 3 X 037AK1.01; Knowledge of the operational implications of the use of steam tables as it applies to Steam Generator Tube Leak. 2.9 000051 Loss of Condenser Vacuum / 4 X 051AG2.4.46; Ability to verify that the alarms are consistent with the plant conditions. 4.2 000059 Accidental Liquid RadWaste Rel. / 9 000060 Accidental Gaseous Radwaste Rel. / 9 X 060AG2.2.12; Knowledge of surveillance procedures. 4.1 000061 ARM System Alarms / 7 X 061AA2.05; Ability to determine and interpret the need for area evacuation; check against existing limits as it applies to the Area Radiation Monitoring (ARM) System Alarms. 4.2 000067 Plant Fire On-site / 8 000068 (BW/A06) Control Room Evac. / 8 X 068AK2.07; Knowledge of the interrelations between the Control Room Evacuation and the ED/G. 3.3 000069 (W/E14) Loss of CTMT Integrity / 5 000076 High Reactor Coolant Activity / 9 W/EO1 & E02 Rediagnosis & SI Termination / 3 W/E03 LOCA Cooldown - Depress / 4 W/E06 Degraded Core Cooling / 4 X WE06EK3.2; Knowledge of the reasons for normal, abnormal and emergency 3.5 operating procedures associated with (Degraded Core Cooling) as they apply to the (Degraded Core Cooling). W/E08 RCS Overcooling - PTS / 4 X WE08EA2.2; Ability to determine and interpret adherence to appropriate procedures and operation within the limitations in the facility's license and amendments as they apply to (Pressurized Thermal Shock). 3.5 W/E09&E10 Natural Circ. / 4 X WE09EK2.2; Knowledge of the interrelations between the (Natural Circulation Operations) and the facility*s heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility. 3.6 W/E13 Steam Generator Over-pressure / 4 W/E14 Loss of CTMT Integrity / 5 X WE14EA2.2; Ability to determine and interpret adherence to appropriate procedures and operation within the limitations in the facility's license and amendments as they apply to the (High Containment Pressure). 3.8 W/E15 Containment Flooding / 5 X WE15A1.3; Ability to operate and / or monitor desired operating results during abnormal and emergency situations as they apply to the (Containment Flooding). 2.8 W/E16 High Containment Radiation / 9 K/A Category Point Totals: 1 2 2 1 2/2 1/2 Group Point Total: 9/4 ES-401, Rev. 9 4 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 (RO / SRO) System # / Name K1 K 2 K 3 K 4 K 5 K 6 A 1 A2 A 3 A 4 G K/A Topic(s) IR # 003 Reactor Coolant Pump X 003A3.01; Ability to monitor automatic operation of the RCPS, including Seal injection flow. 3.3 004 Chemical and Volume Control X X 004A3.10; Ability to monitor automatic operation of the CVCS, including PZR level and pressure. 004AK4.05; Knowledge of CVCS design feature(s) and/or interlock(s) which provide for the interrelationships and design basis, including fluid flow splits in branching networks (e.g., charging and seal injection flow). 3.9 3.3 005 Residual Heat Removal X X 005K6.03; Knowledge of the effect of a loss or malfunction on the RHR heat exchanger will have on the RHRS. 005G2.4.1; Knowledge of EOP entry conditions and immediate action steps. 2.5 4.6 006 Emergency Core Cooling X X 006A1.15; Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the ECCS controls including RWST level and temperature. 006K2.01; Knowledge of bus power supplies to the ECCS pumps. 3.3 3.6 007 Pressurizer Relief/Quench Tank X X 007A1.03; Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the PRTS controls including monitoring quench tank temperature. 007K5.02; Knowledge of the operational implications of Method of forming a steam bubble in the PZR as it applies to PRTS. 2.6 3.1 008 Component Cooling Water X 008K4.02; Knowledge of CCWS design feature(s) and/or interlock(s) which provide for the operation of the surge tank, including the associated valves and controls. 2.9 010 Pressurizer Pressure Control X 010G2.1.28; Knowledge of the purpose and function of major system components and controls. 4.1

X 010K6.02; Knowledge of the effect of a loss or malfunction of the PZR will have on the PZR PCS. 3.2 012 Reactor Protection X X 012A4.02; Ability to manually operate and/or monitor in the control room components for individual channels. 012G2.4.11; Knowledge of abnormal condition procedures. 3.3 4.2 013 Engineered Safety Features Actuation X 013K5.02; Knowledge of the operational implications of safety system logic and reliability as they apply to the ESFAS. 2.9 022 Containment Cooling X X 022A4.03; Ability to manually operate and/or monitor in the control room Dampers in the CCS. 022A2.04; Ability to (a) predict the impacts of the loss of service water on the CCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences. 3.2 3.2 025 Ice Condenser 026 Containment Spray X 026K3.02; Knowledge of the effect that a loss or malfunction of the CSS will have on the Recirculation spray system. 4.2 039 Main and Reheat Steam X X 039A3.02; Ability to monitor automatic operation of the MRSS, including isolation of the MRSS. 039G2.1.19; Ability to use plant computers to evaluate system or component status. 3.1 3.8 059 Main Feedwater X 059K4.02; Knowledge of MFW design feature(s) and/or interlock(s) which provide for automatic turbine/reactor trip runback. 3.3 061 Auxiliary/Emergency Feedwater X X 061K2.01; Knowledge of bus power supplies to the AFW system MOVs. 061K3.02; Knowledge of the effect that a loss or malfunction of the AFW will have on the S/G. 3.2

4.2 062 AC Electrical Distribution X X 062K2.01; Knowledge of bus power supplies to major system loads. 062A2.05: Ability to (a) predict the impacts of the methods for energizing a dead bus on the ac distribution system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations 3.3 2.9 063 DC Electrical Distribution X 063A2.01; Ability to (a) predict the impacts of grounds on the DC electrical systems; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences. 2.9 064 Emergency Diesel X 064A2.04; Ability to (a) predict the impacts of Unloading prior to securing 2.7 Generator an ED/G on the ED/G system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences. 073 Process Radiation Monitoring X 073G2.1.30; Ability to locate and operate components, including local controls. 4.4 076 Service Water X X 076K1.01; Knowledge of the physical connections and/or cause- effect relationships between the SWS and the CCW system. 076A2.01; Ability to (a) predict the impacts of loss of SWS on the SWS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences. 3.4 3.7 078 Instrument Air X 078K3.03; Knowledge of the effect that a loss or malfunction of the IAS will have on the cross-tied units. 3.0 103 Containment X X 103K1.03; Knowledge of the physical connections and/or cause-effect relationships between the containment system and the shield building vent system. 103A2.04; Ability to (a) predict the impacts of Containment evacuation (including recognition of the alarm) on the containment system and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences. 3.1 3.6 K/A Category Point Totals: 2 3 3 3 2 2 2 3/3 3 2 3/2 Group Point Total: 28/5 ES-401, Rev. 9 5 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 2 (RO / SRO) System # / Name K1 K 2 K 3 K 4 K 5 K 6 A 1 A2 A 3 A 4 G K/A Topic(s) IR # 001 Control Rod Drive X 001K2.03; Knowledge of bus power supplies - One-line diagram of power supplies to logic circuits. 2.7 002 Reactor Coolant 011 Pressurizer Level Control X 011A4.04; Ability to manually operate and/or transfer PZR LCS from automatic to manual control in the control room. 3.2 014 Rod Position Indication 015 Nuclear Instrumentation X 015G2.1.23; Ability to perform specific system and integrated plant procedures during all modes of plant operation. 4.0 016 Non-nuclear Instrumentation 017 In-core Temperature Monitor X 017K4.03; Knowledge of ITM system design feature(s) and/or interlock(s) which provide for the range of temperature indication. 3.1 027 Containment Iodine Removal 028 Hydrogen Recombiner and Purge Control 029 Containment Purge X 029K3.02; Knowledge of the effect that a loss or malfunction of the Containment Purge System will have on Containment entry. 2.9 033 Spent Fuel Pool Cooling X 033G2.4.18; Knowledge of the specific bases for EOPs. 4.0 034 Fuel Handling Equipment 035 Steam Generator X 035A2.04; Ability to (a) predict the impacts of the following malfunctions or operations on the GS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of Steam flow/feed mismatch. 3.6 041 Steam Dump/Turbine Bypass Control X 041K6.03; Knowledge of the effect of a loss or malfunction on controller and positioners, including ICS, S/G, CRDS will have on the SDS. 2.7 045 Main Turbine Generator X 045A1.06; Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the MT/G system controls including expected response of secondary plant 3.3 parameters following T/G trip. 055 Condenser Air Removal X 055G2.1.28; Knowledge of the purpose and function of major system components and controls. 4.1 056 Condensate X 056K1.03; Knowledge of the physical connections and/or cause-effect relationships between the Condensate System and MFW. 2.6 068 Liquid Radwaste X 068K5.04; Knowledge of the operational implication of the biological hazards of radiation and the resulting goal of ALARA as they apply to the Liquid Radwaste System. 3.2 071 Waste Gas Disposal X 071A2.06: Ability to (a) predict the impacts of a supply failure to the isolation valve on the Waste Gas Disposal System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences. 2.5 072 Area Radiation Monitoring 075 Circulating Water 079 Station Air 086 Fire Protection K/A Category Point Totals: 1 1 1 1 1 1 1 1/1 0 1 1/2 Group Point Total: 10/3 ES-401, Rev. 9 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: Date of Exam: Category K/A # Topic RO SRO-Only IR # IR # 1. Conduct of Operations 2.1.38 Knowledge of the station's requirements for verbal communications when implementing procedures. 3.7 2.1.44 Knowledge of RO duties in the control room during fuel handling, such as responding to alarms from the fuel handling area, communication with the fuel storage facility, systems operated from the control room in support of fueling operations, and supporting instrumentation. 3.9 2.1.34 Knowledge of primary and secondary plant chemistry limits. 3.5 2.1.45 Ability to identify and interpret diverse indications to validate the response of another indication. 4.3 2.1. 2.1. Subtotal 2 2 2. Equipment Control 2.2.35 Ability to determine Technical Specification Mode of Operation. 3.6 2.2.41 Ability to obtain and interpret station electrical and mechanical drawings. 3.5 2.2.17 Knowledge of the process for managing maintenance activities during power operations, such as risk assessments, work prioritization, and coordination with the transmission system operator. 3.8 2.2.25 Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits. 4.2 2.2. Subtotal 2 2 3. Radiation Control 2.3.15 Knowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc. 2.9 2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions. 3.2 2.3.7 Ability to comply with radiation work permit requirements during normal or abnormal conditions. 3.5 2.3.14 Knowledge of radiation or contamination hazards that may arise during normal, l abnormal, or emergency conditions or activities. 3.8 2.3.6 Ability to approve release permits. 3.8 2.3. Subtotal 3 2 4. Emergency Procedures / Plan 2.4.17 Knowledge of EOP terms and definitions. 3.9 2.4.37 Knowledge of the lines of authority during implementation of the emergency plan. l 3.0 2.4.9 Knowledge of low power/shutdown implications in accident (e.g., loss of coolant accident or loss of residual heat removal) mitigation strategies. 3.8 2.4.38 Ability to take actions called for in the facility emergency plan, including supporting or acting as emergency coordinator if required. 4.4 2.4. 2.4. Subtotal 3 1 Tier 3 Point Total 10 10 7 7