ML21028A405

301 ADAMS 2A-2

ML21028A405
Person / Time
Site:	Harris
Issue date:	01/25/2021
From:	Progress Energy Carolinas
To:	NRC/RGN-II
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Download: ML21028A405 (613)

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ML21028A405 Appendix D Scenario Outline Form ES-D-1 HARRIS 2020 NRC SCENARIO 1 Facility: Harris Nuclear Plant Scenario No.: 1 Op Test No.: 05000400/2020301 Examiners: Operators: SRO:

RO:

BOP:

Initial Conditions: IC-26 MOL, 88% power

• B MDAFW Pump is under clearance for pump packing repairs

• 1SI-3 Out Of Service

• B DEH Pump Out of Service The plant is at 88% power, middle of core life. GP-006 step 10 to Adjust MS Flow to Turnover:

HP Turbine per OP-131.04 Section 8.6 as applicable

• Manually align at least one high head ECCS pump flow path to prevent RVLIS Dynamic Range Level from lowering below 60%

Critical Task:

• Depressurize the RCS to minimize primary to secondary leakage to prevent SG C exceeding 95% level Event Malf. No. Event Type* Event Description No.

R - RO/SRO 1 N/A Power reduction from 88% power N - BOP/SRO C - RO/SRO Control rods fail to move in Auto - continue down power with 2 crf14b rods in manual (AOP-001)

Failure of VCT LT-112 to 100%, which will full divert 3 lt:112 I - RO/SRO letdown to RHT (AOP-003) hva011 C - BOP/SRO 4 Trip of running AH-85C fan, standby fails to Auto Start z3274tib TS - SRO 5 pt:2307 I - BOP/SRO MFW Pump Suction Pressure to CBP controller failure C - RO/SRO 6 sgn05c 'C' Steam Generator Tube Leak (AOP-016)

TS - SRO sgn05c M - ALL 'C' Steam Generator Tube Rupture of 250 gpm (EOP-E-0 and 7

EOP-E-3) 8 zrpk603a C - BOP/SRO Relay failure on resultant SI signal K603A zdsq2:6b 9 C - RO/SRO B ESW Pump fails to auto start on SI jpb9101b

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Harris 2020 NRC Exam Scenario 1 Rev FINAL

Appendix D Scenario Outline Form ES-D-1 HARRIS 2020 NRC SCENARIO 1 SCENARIO

SUMMARY

2020 NRC EXAM SCENARIO 1 The plant is at 88% power, middle of core life. Due to the B MDAFW pump LCO expiring, a normal shutdown in accordance with GP-006, Normal Plant Shutdown From Power Operation To Hot Standby (Mode 1 To Mode 3) is in progress as directed by plant management. It is to continue after shift turnover at 4 MW / minute.

The following equipment is under clearance:

• MDAFW Pump B-SB is under clearance for pump packing repairs. The pump has been inoperable for 68 hours7.87037e-4 days <br />0.0189 hours <br />1.124339e-4 weeks <br />2.5874e-5 months <br /> and cannot be restored to operable status. Tech Spec 3.7.1.2 Action a and Tech Spec 3.3.3.5.b Action c applies.

Harris 2020 NRC Exam Scenario 1 Rev FINAL

Appendix D Scenario Outline Form ES-D-1 HARRIS 2020 NRC SCENARIO 1 SCENARIO

SUMMARY

2020 NRC EXAM SCENARIO 1 continued The following equipment is under clearance (continued):

• B DEH Pump is under clearance for motor repairs. The pump has been unavailable for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. Repairs are expected to be completed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

• 1SI-3, Boron Injection Tank Outlet valve has been under clearance the last 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for breaker repairs. The repairs are close to completion and the valve is expected to be returned to service within the next hour. The valve is currently shut with power removed.

OWP-SI-01 has been completed. Tech Specs 3.5.2 Action a and Tech Specs 3.6.3 applies.

Harris 2020 NRC Exam Scenario 1 Rev FINAL

Appendix D Scenario Outline Form ES-D-1 HARRIS 2020 NRC SCENARIO 1 SCENARIO

SUMMARY

2020 NRC EXAM SCENARIO 1 (Continued)

Harris 2020 NRC Exam Scenario 1 Rev FINAL

Appendix D Scenario Outline Form ES-D-1 HARRIS 2020 NRC SCENARIO 1 SCENARIO

SUMMARY

2020 NRC EXAM SCENARIO 1 (Continued)

Event 1: Plant Shutdown (GP-006). Turnover takes place with the unit at 88% Reactor power.

The crew will be given credit for a reactivity manipulation during the down power.

Verifiable Action: It is expected that the SRO will conduct a reactivity brief, the RO will borate and monitor auto rod insertion per the reactivity plan. The BOP will operate the TCS Load control to adjust the Turbine ramp rate from 1 GVPC units to 4 GVPC units per minute then ensure the controls are set correctly to lower power. After power is reduced 3% - 5% and the crew has demonstrated that they have control of the plant during a shutdown Event 2 is pre- inserted and will be identified once the Tavg/Tref mismatch is greater than 2°F.

Event 2: Control rods fail to move in Auto. Tavg/Tref recorder TR-408 along with ERFIS quick plot Tave will provide indication of the Tavg/Tref mismatch. If the crew allows the mismatch to reach

+/- 5°F ALB 010-6-4B, RCS Tref/Tavg High-Low, will alarm.

Verifiable Action: The crew will enter AOP-001 and carry out the immediate actions. The RO will perform the immediate actions of AOP-001 by verifying that <2 rods are dropped (no rods have dropped), place Rod Control in MANUAL and then verify no rod motion. Once the immediate actions are complete the BOP should place the Turbine in Hold it stabilize the plant. With concurrence from the SRO the RO will restore Tavg to match Tref by inserting the rods in manual.

The SRO should evaluate Tech Spec 3.1.3.1, Reactivity Control Systems- Movable Control Assemblies - Group Height and 3.1.3.5, Reactivity Control Systems- Shutdown Rod Insertion Limit both conditions are satisfied based on AOP-001 Attachment 5.

Harris 2020 NRC Exam Scenario 1 Rev FINAL

Appendix D Scenario Outline Form ES-D-1 HARRIS 2020 NRC SCENARIO 1 SCENARIO

SUMMARY

2020 NRC EXAM SCENARIO 1 (Continued)

Event 2: Tech Spec evaluation continued AOP-001 Attachment 5 The SRO should provide a temperature band of +/- 5°F to the RO in accordance with OMM-001, 1, Control Bands And Administrative Limits. The SRO should refer to AD-OP-ALL-1000 Attachment 4, Emergent Issue Checklists for the failure and request assistance from the WCC.

Event 3: Failure of VCT LT-112 to 100% which will full divert letdown to RHT. ALB 007-5-5, Computer Alarm Chem & Vol Systems, will alarm due to LT-112 being greater than 75%. If the crew allows actual level on LT-115 to reach 20% an auto makeup from the Reactor Makeup System will occur.

Verifiable Action: The crew will respond by entering AOP-003 which has NO immediate actions.

A failure of LT-112 high will cause 1CS-120, Letdown VCT/Hold Up Tank valve to shift to the Hold Up Tank. The RO will have to return the MCB switch to the VCT position. Since VCT level has failed HIGH auto CSIP suction switch over on 5% VCT level to the RWST will not occur until Maintenance has lifted the leads associated with LT-112. The operator will have to monitor VCT level and communicate with Maintenance to resolve this failure.

The SRO should provide a level band of 20 to 70% to the RO in accordance with AOP-003, Section 3.1, Step 4 RNO. The SRO should refer to AD-OP-ALL-1000 Attachment 4, Emergent Issue Checklists for the failure and request assistance from the WCC.

Harris 2020 NRC Exam Scenario 1 Rev FINAL

Appendix D Scenario Outline Form ES-D-1 HARRIS 2020 NRC SCENARIO 1 SCENARIO

SUMMARY

2020 NRC EXAM SCENARIO 1 (Continued)

Event 4: Trip of running AH-85C fan, standby fails to Auto Start. This will cause the running Diesel Generator electrical equipment room supply fan AH-85 1C-SB. ALB 027-1-4, Diesel Gen Elec Equip Rm Sup Fans AH-85 Low Flow - O/L, will alarm and the standby fan AH-85 1D-SB fails to automatically start.

Verifiable Action: The BOP should identify that the auto start feature of the standby AH-85 1D-SB has failed. The crew will use the APP-ALB 027 to start the standby fan AH-85 1D-SB.

The SRO should evaluate Tech Spec 3.8.1.1, Electrical Power Systems - AC Sources -

Operating and 3.3.3.5.b, Instrumentation - Remote Shutdown System Action: b and c respectively.

Harris 2020 NRC Exam Scenario 1 Rev FINAL

Appendix D Scenario Outline Form ES-D-1 HARRIS 2020 NRC SCENARIO 1 SCENARIO

SUMMARY

2020 NRC EXAM SCENARIO 1 (Continued)

Event 4: Tech Spec evaluation continued OWP-HVAC Attachment 1, HVAC Support System Requirements, lists AH-85 1C-SB TS 3.3.3.5.b since ONLY AH-85 1C-SB can be credited for supported system operability, since AH-85 1D-SB does not start automatically during an accident.

The SRO should refer to AD-OP-ALL-1000 Attachment 4, Emergent Issue Checklists for the failure and request assistance from the WCC.

Event 5: MFW Pump Suction Pressure to CBP controller failure. A transmitter failure will cause the Condensate Booster Pump controller to reject to manual. ALB 019-4-1A and 4-1B, Cndbstr Pmps 10% Deviation and Cndbstr Pmps 20% Dev/Man Rej, respectively will alarm and both Condensate Booster pump M/A stations to go manual. There will also be alarms on Feedwater heater levels and if the crew does not respond quickly then SG level deviation alarms will alarm.

The failure will cause SG levels increase due to the higher suction pressure being supplied to the MFW pumps.

Harris 2020 NRC Exam Scenario 1 Rev FINAL

Appendix D Scenario Outline Form ES-D-1 HARRIS 2020 NRC SCENARIO 1 SCENARIO

SUMMARY

2020 NRC EXAM SCENARIO 1 (Continued)

Verifiable Action: The BOP will respond to the failure by taking actions contained in the APP-ALB 019 4-1B by manually controlling PI-2200, FW pumps suction header pressure at 430 psig using both Condensate Booster pump M/A stations (PK-2307 and PK-2308). Both controls will quickly reach 100% and must be individually lowered to regain normal supply pressure.

The SRO should provide a pressure band of 430 psig +/- 5 psig to the BOP in accordance with AD-OP-ALL-1000, Conduct of Operations, (5.5.6) for operation Control Bands and APP-ALB 019-4-1B. The SRO should refer to AD-OP-ALL-1000 Attachment 4, Emergent Issue Checklists for the failure and request assistance from the WCC.

Event 6: 'C' Steam Generator Tube Leak (AOP-016). The RCS Loop C will leak into its associated SG requiring the crew to implement the actions for AOP-016. Minor changes in Pressurizer Level and Charging flow will occur. Radiation monitors will alarm on the RMS computer for CVPETS and MSL C. Additionally ALB 010-4-5, Rad Monitor System Trouble, will alarm due to the MSL C RM-23 alarming.

Verifiable Action: The crew will respond by entering AOP-016 which has NO immediate actions.

The RO will perform a leak rate calculation and determine the leakage is ~30 gpm. The BOP will make plant announcements and contact various support organizations (HP, Chemistry, etc.) as directed by the AOP. The SRO should determine that leak rate is in excess of Action Level 3 and the unit must be less than 50% within the hour and removed from service within the next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

The crew will implement AOP-038, Rapid Down power to complete this action.

The SRO should evaluate Tech Spec 3.4.6.2, Reactor Coolant System - Operational Leakage Action: a. which will be completed by performing the more restrictive PSAL 3 requirements.

Harris 2020 NRC Exam Scenario 1 Rev FINAL

Appendix D Scenario Outline Form ES-D-1 HARRIS 2020 NRC SCENARIO 1 SCENARIO

SUMMARY

2020 NRC EXAM SCENARIO 1 (Continued)

The SRO should refer to AD-OP-ALL-1000 Attachment 4, Emergent Issue Checklists for the failure and request assistance from the WCC.

Event 7: 'C' Steam Generator Tube Rupture of 250 gpm (EOP-E-0 and EOP-E-3). The major event is a Steam Generator Tube Rupture. The RCS Loop C leak will degrade to a rupture into its associated SG requiring the crew to implement the continuous actions for AOP-016 with leak rate in excess of VCT makeup ability and trip the Reactor and actuate Safety Injection. Major changes in Pressurizer Level and Charging flow will occur.

Verifiable Action: The RO will manually trip the Reactor in accordance with AOP-016, then following verification of the Turbine trip actuate Safety Injection and the crew will continue with EOP-E-0. The crew will then transition from EOP-E-0 and go to EOP-E-3, Steam Generator Tube Rupture.

Event 8: Relay failure on resultant SI signal K603A. The failure of K603A will result in the failure of 3 A train SI signals 1SI-4 fails to open, 1CS-238 fails to shut and CRI fails to occur.

Verifiable Action: The RO will manually open 1SI-4 (Critical Task #1) and shut 1CS-238 in accordance with EOP-E-0, Attachment 1, SI Emergency Alignment. The BOP should identify the A train Control Room Area Ventilation are not properly aligned and will manually align the components in accordance with EOP-E-0, Attachment 3, Safeguards Actuation Verification or AD-OP-ALL-1000, Conduct of Operations, (5.6.3.8) for Equipment Manipulation and Status Control.

Event 9: B ESW Pump fails to auto start on SI.

Verifiable Action: The crew should identify this failure and manually start the Emergency Service Water Pump once the B Sequencer reaches Load Block 9, Automatic Manual Loading Permissive, in accordance with AD-OP-ALL-1000, Conduct of Operations, (5.6.3.8) for Equipment Manipulation and Status Control or EOP-E-0, Attachment 3, Safeguards Actuation Verification.

The crew may elect to perform the immediate actions of AOP-022, Service Water Malfunctions, and secure both the B EDG and the B CSIP with service water loss to the respective running component.

The scenario termination is met in EOP-E-3 after the RCS has been depressurized to minimize primary to secondary leakage prior to SG B exceeding 95% level (Critical Task #2) and all but one CSIP is secured.

Harris 2020 NRC Exam Scenario 1 Rev FINAL

Appendix D Scenario Outline Form ES-D-1 HARRIS 2020 NRC SCENARIO 1 CRITICAL TASK JUSTIFICATION:

1. Manually align at least one high head ECCS pump flow path to prevent RVLIS Dynamic Range Level from lowering below 60%.

In this scenario the 1SI-3 is out of service and the 1SI-4 does not automatically open from sequencer actuation. The operator must manually open 1SI-4 which was currently in the shut position. Plant parameter grading criteria for the task is opening 1SI-4 to prevent RVLIS Dynamic Range Level from lowering below 60% which constitutes a significant core uncover with 3 Reactor Coolant Pumps in operation.

2. Depressurize the RCS to minimize primary to secondary leakage to prevent SG C exceeding 95% level Failure to depressurize the RCS needlessly complicates mitigation of a SGTR event by allowing the reactor coolant leak to continue. It constitutes a significant reduction of safety margin beyond that introduced by the SGTR event analysis.

If primary to secondary leakage is not stopped the SG pressure will increase until either the SG PORV or Safety valve(s) open releasing radioactivity to the environment. If leakage is allowed to continue the increased inventory will result in water release through the PORV once SG overfill conditions are reached.

At Harris the plant 95% level on the narrow range indicators is the value at which overfill conditions will start to exist and the adverse effects of the condition may start to manifest themselves.

Note: Causing an unnecessary plant trip or ESF actuation (automatic or manual) may constitute a CT failure. Actions taken by the applicant(s) will be validated using the methodology for critical tasks in Appendix D to NUREG-1021.

Harris 2020 NRC Exam Scenario 1 Rev FINAL

Appendix D Scenario Outline Form ES-D-1 HARRIS 2020 NRC SCENARIO 1 Simulator Setup Reset to IC-141 password NRC3sros Go to RUN Silence and Acknowledge annunciators GO TO FREEZE and inform the lead examiner the Simulator is ready. DO NOT GO TO RUN until directed by the lead examiner.

Set ERFIS screens for normal full power conditions, ensure VCT Level Channel LCS0112 is indicated on QP VCT (The examiner has provided to the candidate with initial conditions and the initiating cues prior to placing the simulator in RUN.)

SPECIAL INSTRUCTIONS Provide a Reactivity Plan to candidates for shutting down the plant Provide a copy of the following procedures:

• GP-006, NORMAL PLANT SHUTDOWN FROM POWER OPERATION TO HOT STANDBY (MODE 1 TO MODE 3) marked up through section 6.2 step 10 Press START on Counter Scaler Post conditions for status board from IC-26 Reactor Power 88%

Control Bank D at 201 steps RCS boron 980 ppm Turnover: The plant is at 88% power, middle of core life. Due to the B MDAFW pump LCO expiring, a normal shutdown in accordance with GP-006, Normal Plant Shutdown From Power Operation To Hot Standby (Mode 1 To Mode 3) is in progress as directed by plant management.

It is to continue after shift turnover at 4 MW / minute.

Equipment Under Clearance:

• B-SB MDAFW Pump is under clearance for motor high vibrations. The pump has been inoperable for 68 hours7.87037e-4 days <br />0.0189 hours <br />1.124339e-4 weeks <br />2.5874e-5 months <br /> and cannot be restored to operable status. Tech Spec 3.7.1.2 LCO Action a and Tech Spec 3.3.3.5.b Action c applies.

• B DEH Pump is under clearance for motor repairs. The pump has been unavailable for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. Repairs are expected to be completed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

• 1SI-3, Boron Injection Tank Outlet valve has been under clearance the last 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for breaker repairs. The repairs are close to completion and the valve is expected to be returned to service within the next hour. The valve is currently shut with power removed.

OWP-SI-01 has been completed. Tech Specs 3.5.2 Action a and Tech Specs 3.6.3 applies.

Harris 2020 NRC Exam Scenario 1 Rev FINAL

Appendix D Scenario Outline Form ES-D-1 HARRIS 2020 NRC SCENARIO 1 Simulator Setup (continued)

Align equipment for repairs:

Place CIT on 'B-SB' MDAFW pump MCB Switch Place protected train placards in accordance with OMM-001 Attachment 5 Protected Train placards on 'A-SA' MDAFW pump, 'B-SB' RHR Pump, 'B-SB' CCW Pump,

'B-SB' ESW Pump, 1MS-70 and 1MS-72 Place the B DEH Pump in PTL and then hang a CIT on MCB switch Place protected train placards in accordance with AD-OP-ALL-0210, Single Point Vulnerabilities Protected Train placards on A DEH Pump Place a CIT on the switch for 1SI-3.

Place protected train placards in accordance with Response to Industry Best Practices, Expectations Protected train placards on A-SA ESW Pump, A-SA CCW Pump, and A-SA SFP Hx Place filled out copies of OWPs into the OWP book - ensure they are removed at end of day

• OWP-SI-01 and place in MCR OWP book for 1SI-3 clearance Hang restricted access signs on MCR entry swing gates Harris 2020 NRC Exam Scenario 1 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 1 Page 14 of 83 Event

Description:

Power Reduction Time Position Applicants Actions or Behavior The crew has been directed to re-commence a power reduction from 88% to the unit is off line. The power reduction is on hold for turnover. The SRO is expected to conduct a reactivity brief prior to commencing the power reduction. This brief may be conducted outside the simulator prior to starting the scenario.

Lead Evaluator:

When the crew has completed their board walk down and are ready to take the shift inform the Simulator Operator to place the Simulator in Run. When the Simulator is in run announce:

CREW UPDATE - (SROs Name) Your crew has the shift.

END OF UPDATE When directed by the Lead Evaluator, ensure that the Simulator Operator:

annunciator horns are on and place the Simulator in RUN.

The crew may elect to begin Boration prior to lowering Evaluator Note:

turbine load.

RO OP-107.01, Section 5.2

1. DETERMINE the volume of boric acid to be added.

RO (Current OPT-1536 data or approved reactivity plan from Engineering may be used.)

SRO Directs Boration FIS-113, BORIC ACID BATCH COUNTER, has a tenths Procedure Note:

position.

Harris 2020 NRC Exam Scenario 1 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 1 Page 15 of 83 Event

Description:

Power Reduction Time Position Applicants Actions or Behavior If the translucent covers associated with the Boric Acid and Total Makeup Batch counters FIS-113 and FIS-114, Procedure Caution:

located on the MCB, are not closed, the system will not automatically stop at the preset value.

2. SET FIS-113, BORIC ACID BATCH COUNTER, to obtain the desired quantity.

RO 3. ENSURE the RMW CONTROL switch has been placed in the STOP position.

4. ENSURE the RMW CONTROL switch green light is lit.

• Boric Acid flow controller must be set between 0.2 and 6 (1 and 30 gpm.).

• Performing small borations at high flow rates may Procedure Note: result in an overboration based on equipment response times. Boration flow should be set such that the time required to reach the desired setpoint will happen after release of the control switch.

5. IF the current potentiometer setpoint of controller 1CS-RO 283, FK-113 BORIC ACID FLOW, needs to be changed to obtain makeup flow, THEN: (N/A)

a. RECORD the current potentiometer setpoint of controller 1CS-283, FK-113 BORIC ACID FLOW, in Section 5.2.3.

b. SET controller 1CS-283, FK-113 BORIC ACID FLOW, for the desired flow rate.

6. PLACE control switch RMW MODE SELECTOR to the BOR RO position.

Harris 2020 NRC Exam Scenario 1 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 1 Page 16 of 83 Event

Description:

Power Reduction Time Position Applicants Actions or Behavior

• Boration may be manually stopped at any time by turning control switch RMW CONTROL to STOP.

• During makeup operations following an alternate Procedure Note:

dilution, approximately 10 gallons of dilution should be expected due to dilution water remaining in the primary makeup lines.

7. START the makeup system as follows:

a. TURN control switch RMW CONTROL to START momentarily.

b. ENSURE the RED indicator light is LIT.

RO

c. IF expected system response is not obtained, THEN TURN control switch RMW CONTROL to STOP.

8. ENSURE boration automatically terminates when the desired quantity of boron has been added.

9. IF controller 1CS-283, FK-113 BORIC ACID FLOW, was RO changed in Step 5.2.2.5, THEN: (N/A)

a. REPOSITION controller 1CS-283, FK-113 BORIC ACID FLOW, to the position recorded in Step 5.2.2.5.a.

b. INDEPENDENTLY VERIFY controller 1CS-283, FK-113 BORIC ACID FLOW, position.

10. Monitor Tavg and rod control for proper operation.

11. Establish VCT pressure between 20-30 psig.

12. Turn control switch RMW MODE SELECTOR to AUTO.

13. START the makeup system as follows:

RO a. TURN control switch RMW CONTROL to START momentarily.

b. ENSURE the RED indicator light is LIT.

IF expected system response is not obtained, THEN TURN control switch RMW CONTROL to STOP. (Ref.

4.0.31)

Harris 2020 NRC Exam Scenario 1 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 1 Page 17 of 83 Event

Description:

Power Reduction Time Position Applicants Actions or Behavior The following steps have been completed to achieve the current power level. The crew should validate status of the Evaluator Note:

turbine load reduction in accordance with GP-006 section 6.2 step 5 before re-initiating the turbine load reduction.

GP-006 GP-006, Section 6.2 Routine load changes must be coordinated with the Load Dispatcher to meet system load demands GVPC is the preferred method of Load Control. Megawatt Control is normally used only during GV and TV testing Procedure Note: Controls and indications in following steps are on the TCS Load Control screen If Oper Entry is selected with the Turbine in GO, the value currently in the Ramp Rate Entry Window will become the load rate in effect. It may be desirable to place the turbine in HOLD to avoid undesirable ramp rates There is no procedural guidance directing when the Evaluator Note: boration to lower power is required. The crew may elect to perform the boration prior to placing the Turbine in GO.

DIRECTS BOP to start power reduction at 4 MW/Min. May SRO direct initiation of a boration before the power reduction begins.

Requests PEER check prior to manipulations of TCS Load BOP Control screen Harris 2020 NRC Exam Scenario 1 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 1 Page 18 of 83 Event

Description:

Power Reduction Time Position Applicants Actions or Behavior

5. On TCS Load Control screen, Load Control section, perform the following:

a. IF GVPC indicator is TRUE, THEN go to Step 5.c

c. Select Ramp Rate Selection, Select button

d. Select the desired ramp rate OR Oper Entry on Load Ramp Rate Selection menu BOP

• ENTER the desired rate, NOT to exceed 5 MW/MIN, in the DEMAND display. (4 DEH Units/minute)

e. IF Oper Entry is selected, THEN enter the desired loading rate in the Ramp Rate Entry window and depress Enter.

• ENTER the desired rate, NOT to exceed 5 MW/MIN, in the DEMAND display. (4 DEH Units/minute)

• DEPRESS the ENTER push-button.

The unloading of the unit can be stopped at any time by Procedure Note: selecting the Hold button. The load reduction can be resumed by selecting the Go button

6. Reduce turbine load as follows:

a. Enter desired Target Load (120 MW if shutting down) in Target Entry window and depress Enter BOP b. Select the Go button

c. Check that Demand window indication counts down towards desired Target Load

d. Check that load ramps towards desired Target Load Once a raise/lower command button is activated, it will remain in the visually depressed state as an indication the button cannot be activated again for approximately two Procedure Note:

seconds. After two seconds, command buttons automatically return to their default visual state indicating the button may be activated again Harris 2020 NRC Exam Scenario 1 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 1 Page 19 of 83 Event

Description:

Power Reduction Time Position Applicants Actions or Behavior

7. IF AT ANY TIME, a small incremental change of Target Load value (1 or 5 megawatts) is desired, THEN select any of the following buttons:

BOP

• 1 MW

• 5 MW

• 1 MW

• 5 MW BOP 8. Ensure Generator load is lowering As the crew demonstrates a satisfactory load reduction Event 2, Control rods fail to move in AUTO (AOP-001) will Evaluator Note: become apparent as Tavg/Tref mismatch continues to grow with no rod motion. NO Trigger is required for this event.

Harris 2020 NRC Exam Scenario 1 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 2 Page 20 of 83 Event

Description:

Control rods fail to move in AUTO (AOP-001)

Time Position Applicants Actions or Behavior Event 2 (Rods do not move in AUTO) will become apparent when the crew identifies that rod control system signals Evaluator Note:

from power and temperature mismatches have no effect on the rod control system.

No triggers are required for this malfunction. The Simulator Operator:

malfunction is pre-loaded The crew may take action to enter AOP-001 prior to receiving any alarms based on monitoring TAVG-TREF Evaluator Note: deviation indicated by ERFIS points TRC0408Z (median TAVG) and TRC0408b (TREF). The first section of the guide is written to the response of the APP and then AOP-001.

• ALB 010-6-4B, RCS TREF/TAVG HIGH-LOW o NOTE: This alarm is only expected if the Tavg/Tref Indications Available mismatch reaches the alarm setpoint of +5°F/-5°F

• Tavg/Tref recorder indications Responds to ALB-010-6-4B, RCS TREF/TAVG HIGH-LOW OR RO identifies that the Tavg/Tref indications should have provided a step signal to rod control and has not

1. CONFIRM alarm using:

CREW a. Tavg/Tref recorder TR-408 (MCB)

b. Turbine first stage pressure indicators (PI-446 and PI 447)

If I&C is contacted to investigate the rod control failure, Simulator wait approximately 3 minutes and report back that an I&C Communicator technician is at the rod control system and looking for indications of a failure.

Harris 2020 NRC Exam Scenario 1 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 2 Page 21 of 83 Event

Description:

Control rods fail to move in AUTO (AOP-001)

Time Position Applicants Actions or Behavior

2. VERIFY Automatic Functions: None

3. PERFORM Corrective Actions:

RO c. IF there is an indication of a control rod malfunction (MCB and AEP-1), THEN GO TO AOP-001, Malfunction of Rod Control and Indication System.

AOP-001 Malfunction of Rod Control and Indication System ENTERS and directs actions of AOP-001 SRO Conducts a Crew Update Makes PA announcement for AOP entry RO PERFORMS immediate actions.

Immediate 1. CHECK that LESS THAN TWO control rods are Action RO (YES) dropped.

Immediate Action RO 2. POSITION Rod Bank Selector Switch to MAN.

Immediate Action RO 3. CHECK Control Bank motion STOPPED. (YES)

4. READS immediate actions and proceeds to Section 3.3, Failure of a Control Bank To Move.

SRO Directs BOP to place Turbine to HOLD if in GO.

BOP Places Turbine to HOLD if in GO.

1. CHECK that AT LEAST ONE of the following conditions is present:

• ALB 13-7-1, ROD CONTROL URGENT RO ALARM, is ALARMED (NO)

• Control Bank will NOT move (YES)

• Shutdown Bank will NOT move (NO)

Harris 2020 NRC Exam Scenario 1 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 2 Page 22 of 83 Event

Description:

Control rods fail to move in AUTO (AOP-001)

Time Position Applicants Actions or Behavior

2. ADJUST Turbine load OR Boron concentration to equalize RO Tavg with Tref DIRECTS RO to equalize Tavg with Tref (Boron or Turbine adjustments) then proceeds to step 6 Directs RO to maintain TAVG within 2°F of Tref per OMM-001 attachment 11.

(NOTE: during a transient such as continuation of the power reduction the control band will change to TAVG within 5°F of SRO Tref)

RO/ Adjusts RCS Boron or turbine load to equalize Tavg with Tref.

BOP (may borate based on SRO direction)

• Surveillance Requirement 4.1.1.1.1.a requires performing a shutdown margin calculation upon detecting an inoperable rod. [C.1]

Procedure Note:

• It is acceptable to use incore detectors or ERFIS Point from DRPI (or other methods if developed) to meet 4.1.3.1.1 and the Rod Insertion Limit SRs 4.1.3.5 and 4.1.3.6.

SRO Reviews note

3. Refer To the following AND CHECK that ALL control rods are operable:

• Tech Spec 3.1.3.1 (does not apply)

• Tech Spec 3.1.3.5 (does not apply)

SRO Does not apply in this situation since rod control can be demonstrated operable by rods moving in MANUAL

• Attachment 5, Determination of Control Rod Trippability (can determine rods are trippable)

Harris 2020 NRC Exam Scenario 1 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 2 Page 23 of 83 Event

Description:

Control rods fail to move in AUTO (AOP-001)

Time Position Applicants Actions or Behavior

4. DETERMINE if the Westinghouse Rod Control System Troubleshooting Guidelines should be initiated. (Priority 1 Work Request is required)

SRO May contact Reactor Engineering or asks for help when contacting Work Control Determines Tref based on 1st Stage pressure using Curve G-4.

RO He/she may instead use Tref just before the failure to determine the current value of Tref or use OSI-PI plot values.

If ALB-13-7-1, ROD CONTROL URGENT ALARM, is alarming due to a logic error, resetting the alarm before correcting the Procedure Caution:

cause could result in dropping rods supplied from the affected power cabinet.

SRO Reviews Caution

5. CHECK that ALB-13-7-1, ROD CONTROL (YES)

SRO URGENT ALARM, is CLEARED.

6. CHECK automatic AND manual Rod Control (NO)

SRO FUNCTIONING PROPERLY.

Step 6 of AOP-001 will not be met until rod control has Evaluator Note: been repaired. Plant shutdown will need to continue with rod control in MANUAL.

Completes an Emergent Issue Checklists and contacts WCC SRO for assistance. (WR, LCOTR and Maintenance support)

Dispatch operators to rod control cabinets to determine if CREW urgent failure alarms are on locally.

2-3 minutes after WCC/Engineering or Maintenance has Simulator been contacted, report that System Engineer has identified Communicator the problem exists in the AUTO circuit only inside PIC-8.

Harris 2020 NRC Exam Scenario 1 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 2 Page 24 of 83 Event

Description:

Control rods fail to move in AUTO (AOP-001)

Time Position Applicants Actions or Behavior If necessary - prompt the crew to continue the plant shutdown by having the Manager of Ops call and direct that the plant shutdown continue with rod control in manual. The SM and AOM-Shift concur that JITT is not required for Maneuvering Plant with a Controller in Manual.

Crew resumes load reduction.

Evaluator Note: SRO asks RO for reactivity addition recommendation.

BOP places the Turbine in GO to lower load With Turbine load lowering cue Simulator Operator to insert Trigger 3 Event 3: Failure of VCT LT-112 to 100%, which will full divert letdown to RHT (AOP-003)

Harris 2020 NRC Exam Scenario 1 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 3 Page 25 of 83 Failure of VCT LT-112 to 100%, which will full divert letdown to RHT Event

Description:

(AOP-003)

Time Position Applicants Actions or Behavior On cue from the Lead Evaluator actuate Trigger 3 Simulator Operator: Failure of VCT LT-112 to 100%, which will full divert letdown to RHT (AOP-003)

• ALB 007-5-5, COMPUTER ALARM CHEM & VOL Indications SYSTEMS Available:

• 1CS-120 (LCV-115A), Letdown VCT / Holdup Tank, aligns to HUT Refers to ALB-007-5-5, COMPUTER ALARM CHEM & VOL RO SYSTEMS Crew may place 1CS-120 (LCV-115A) to the VCT position Evaluator Note:

per AD-OP-ALL-1000.

3. PERFORM Corrective Actions:

a. CHECK instrumentation on MCB associated with alarm RO point.

b. DISPATCH an operator to check local indications associated with alarming points.

Simulator Acknowledge the request to check for local indications of Communicator: alarming points.

Identifies entry conditions to AOP-003, Malfunction of Reactor CREW Makeup Control are met AOP-003 Malfunction of Reactor Makeup Control ENTERS and directs actions of AOP-003, SRO Conducts a Crew Update Makes PA announcement for AOP entry RO 1. Check IA available (YES)

Harris 2020 NRC Exam Scenario 1 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 3 Page 26 of 83 Failure of VCT LT-112 to 100%, which will full divert letdown to RHT Event

Description:

(AOP-003)

Time Position Applicants Actions or Behavior

2. CHECK BOTH LT-112 and LT-115 functioning properly.

3. Determines LK-112 output has failed and goes to Section SRO 3.1, LT-112 or LT-115 Malfunction.

RO 1. Assesses effects of LT-112 failure (Attachment 1)

Simulator When directed to report local indication for LT:112, Communicator: Wait 1 minute then report that local indication is 100%.

An instrument malfunction may manifest itself as a slow drift rather than a full high or full low failure. Until the instrument Procedure Note:

has failed fully high or fully low, all steps should be reviewed for applicability periodically, even if not continuously applicable.

2. CHECK that LT-115 is FAILING. (NO)

SRO Determines that LT-112 is failed high and DIRECTS RO to place 1CS-120 (LCV-115A), Letdown VCT / Holdup Tank, to SRO VCT position

2. Determines failure is NOT due to LT-115 and go to Step 8

8. Determines failure caused by LT-112

9. Monitor VCT level using either:

• ERFIS point LCS0115 RO

• LT-115

10. Check LT-112 is failing LOW - NO RNO action: Place 1CS-120 (LCV-115A), Letdown VCT /

Holdup Tank, to VCT position - (places control to VCT)

Normally, VCT level is maintained between 20 and 40% by Procedure Note:

auto makeup.

• Reviews note SRO

11. DIRECTS RO to CONTROL VCT level in AUTO RO 12. Maintains VCT level > 5%

Harris 2020 NRC Exam Scenario 1 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 3 Page 27 of 83 Failure of VCT LT-112 to 100%, which will full divert letdown to RHT Event

Description:

(AOP-003)

Time Position Applicants Actions or Behavior Lifting leads in the following Step will simulate a low-low level signal from the failed instrument. This allows a valid low-low Procedure Note: level signal from the good instrument to initiate emergency makeup.

• Reviews note:

SRO 19. Determines LT-112 has failed high and directs Maintenance to lift leads in SSPS for auto switchover to RWST

20. DIRECT Maintenance to investigate and repair the instrument malfunction.

• Completes an Emergent Issue Checklist and contacts WCC for assistance. (WR, and Maintenance support)

Simulator Acknowledge requests for assistance.

Communicator:

After VCT level has been stabilized, cue Simulator Operator to insert Trigger 4 Evaluator Note:

Event 4: Trip of running AH-85C fan, standby fails to Auto Start.

Harris 2020 NRC Exam Scenario 1 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 4 Page 28 of 83 Event

Description:

Trip of running AH-85C fan, standby fails to Auto Start Time Position Applicants Actions or Behavior On cue from the Lead Evaluator actuate Trigger 4 Simulator Operator:

Trip of running AH-85C fan, standby fails to Auto Start Indications

• ALB 027-1-4, DIESEL GEN ELEC EQUIP RM SUP FANS Available: AH-85 LOW FLOW - O/L ALB-027 BOP RESPONDS to alarm on APP-ALB-027-1-4 BOP IDENTIFIES the tripped fan, AH-85 1C-SB BOP REPORTS failure of the AH-85 1D-SB standby fan to start

3. PERFORM Corrective Actions:

BOP a. STARTS standby AH-85 1D-SB

b. Contacts AOs to investigate breaker failure Breaker failure was overcurrent - IF requested to take Simulator breaker to OFF acknowledge the request.

Communicator: Simulator Operator - do not take breaker off - not required to continue with scenario (Any Tech Spec evaluation can be conducted with a follow Evaluator Note:

up question after the scenario).

REFER to Tech Specs

• T.S 3.8.1.1.b, Action b, items 1-4 One EDG Inoperable Restore EDG to operable within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Requests BOP to contact AOs to perform OST-1023 SRO Verify required features powered from the Operable EDG are operable

• T.S. 3.3.3.5.b, Remote Shutdown System (7 days)

OWP-HVAC - Attachment 1, Only AH-85 1C-SB can be credited for supported system operability, since AH-85 1D-SB does not start automatically during an accident.

Harris 2020 NRC Exam Scenario 1 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 4 Page 29 of 83 Event

Description:

Trip of running AH-85C fan, standby fails to Auto Start Time Position Applicants Actions or Behavior Simulator Acknowledge the request wait approximately 30 minutes Communicator: and report back that OST-1023 is complete.

Completes an Emergent Issue Checklist and contacts WCC for SRO assistance. (WR, LCOTR, and Maintenance support)

Simulator Acknowledge requests for assistance.

Communicator:

Crew will probably place the Turbine on HOLD.

Once the crew completes starts the standby Air Handler and Tech Specs have been evaluated, cue Simulator Lead Evaluator: Operator to insert Trigger 5 Event 5: MFW Pump Suction Pressure to CBP controller failure Harris 2020 NRC Exam Scenario 1 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 5 Page 30 of 83 Event

Description:

MFW Pump Suction Pressure to CBP controller failure Time Position Applicants Actions or Behavior On cue from the Lead Evaluator insert Trigger 5 Simulator Operator:

MFW Pump Suction Pressure to CBP controller failure

• ALB 019 4-1A CNDBSTR PMPS 10% DEVIATION

• ALB 019 4-1B CNDBSTR PMPS 20% DEVIATION

• ALB 019 5-5 COMPUTER ALARM CONDENSATE SYSTEM

• Both Condensate Booster Pump discharge pressures Available Indications rises to >600 psig

• FW Pump suction pressure PI-220 lowering

• Both Condensate Booster Pump controllers PK-2307 and PK-2308 shift from Auto to Manual control

• SG levels rising Responds to multiple Condensate Booster Pump alarms and diagnoses that a failure has occurred in the Condensate Crew Booster pump controller that caused both pump M/A stations to go to manual.

The crew may enter AOP-010 based on the changes to Feedwater flow (may be considered a flow transient but it really is a pressure transient). Page 32 lists the AOP-010 response.

Evaluator Note:

NOTE: Responding with ONLY AOP-010 guidance and NOT lowering the output of PK-2307 and PK-2308 in accordance with the APP directions will cause all SG levels to continue to rise.

Directs BOP to manually control PI-2200, FW Pumps Suction ALB-019 Hdr Press, at 430 psig using PK-2307 and PK-2308, SRO 4-1B Condensate Booster Pump A and B speed controllers in accordance with ALB-019 4-1B.

4. PERFORM Corrective Actions:

a. Takes PK-2307 and PK-2308 controllers and lowers the BOP output to reduce PI-2200, FW Pumps Suction Hdr Press to 430 psig; verifies that SG levels are recovering and FRVs are responding correctly.

Harris 2020 NRC Exam Scenario 1 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 5 Page 31 of 83 Event

Description:

MFW Pump Suction Pressure to CBP controller failure Time Position Applicants Actions or Behavior

b. VERIFY 1CE-227 (1CE-268), Condensate Booster Pump A (B) Discharge OPEN.

c. VERIFY the position of 1CE-220 (1CE-261),

Condensate Booster Pump A (B) Recirc.

d. DISPATCH an Operator to perform the following:

(1) CHECK system line up using OP-134, Condensate SRO System.

(2) CHECK pump operation normal.

(3) CHECK for leakage.

(4) CHECK normal P at Condensate Polishing Demins, AND BYPASS as necessary.

e. IF necessary, THEN GO TO AOP-010, Feedwater Malfunctions.

b. Verifies1CE-227 (1CE-268), Condensate Booster Pump A (B) Discharge is OPEN.

BOP

c. Verifies the position of 1CE-220 (1CE-261), Condensate Booster Pump A (B) Recirc (as seen)

Dispatches AO to check for system leakage and other BOP abnormal system indications.

Acknowledge communications Simulator Communicator: After 2-3 minutes report back that nothing is abnormal with the system and no leaks were found If the SRO enters AOP-010 then the crew will perform the immediate actions of the AOP and enter the AOP. The AOP will address SG level issues but will not provide directions for the CBP speed control problems.

Evaluator Note:

The BOP will have to maintain FW pump suction pressure with both CBP speed controllers in manual for the remainder of this scenario.

AOP-010 actions are on the next page.

Harris 2020 NRC Exam Scenario 1 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 5 Page 32 of 83 Event

Description:

MFW Pump Suction Pressure to CBP controller failure Time Position Applicants Actions or Behavior AOP-010 Feedwater Malfunctions ENTERS and directs actions of AOP-010 SRO Conducts a Crew Update Makes PA announcement for AOP entry Procedure Note: Steps 1 through 4 are immediate actions.

Immediate 1. CHECK Feedwater Regulator valves operating Action BOP (YES) properly.

2. CHECK ANY Main Feedwater Pump TRIPPED (NO)

Immediate Action BOP RNO GO TO STEP 6

6. MAINTAIN ALL of the following:

• At least ONE Main Feedwater Pump RUNNING BOP

• Main Feedwater flow to ALL Steam Generators

• ALL Steam Generator levels greater than 30%

Maintains all of the above

7. CHECK Feedwater Regulator Valves operating properly in AUTO: (YES)

BOP

• Response to SG levels

• Valve position indication

• Response to feed flow/steam flow mismatch Inability to monitor one or more Safety System Parameters concurrent with a turbine runback of greater than 25%, requires Procedure Note:

a change of event classification per the HNP Emergency Plan.

[C.2, C.3]

8. CHECK turbine runs back less than 25% turbine BOP YES load Harris 2020 NRC Exam Scenario 1 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 5 Page 33 of 83 Event

Description:

MFW Pump Suction Pressure to CBP controller failure Time Position Applicants Actions or Behavior A feedwater train consists of a Condensate Pump, Condensate Procedure Note:

Booster Pump and Main Feedwater Pump.

9. GO TO the applicable section:

SRO EVENT: All Condensate/Feedwater flow malfunctions (other than pump trips) Section 3.1 Page 10

1. CHECK the following Recirc and Dump Valves operating properly in MODU:

• Main Feedwater Pumps (YES)

• Condensate Booster Pumps (YES)

BOP

• Condensate Pumps (YES)

• 1CE-293, Condensate Recirc (YES)

• 1CE-142, Condensate Dump To CST Isolation (YES)

Valve (SLB-4/7-1)

BOP 2. CHECK the Condensate and Feedwater System INTACT.

Pumps should be stopped in the order of higher to lower pressure. (To stop a Condensate Pump, stop a Main Procedure Note:

Feedwater Pump followed by a Condensate Booster Pump and then the Condensate Pump.)

BOP 3. CHECK pumps for NORMAL OPERATION. (YES)

4. NOTIFY Load Dispatcher of ANY load limitations.

SRO (No load limitations so Dispatcher will not be called)

5. CHECK Reactor thermal power changed by less SRO (YES) than 15% in any one hour period.

SRO 6. EXIT this procedure.

Harris 2020 NRC Exam Scenario 1 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 5 Page 34 of 83 Event

Description:

MFW Pump Suction Pressure to CBP controller failure Time Position Applicants Actions or Behavior Completes an Emergent Issue Checklist and contacts WCC for SRO assistance. (WR, LCOTR, and Maintenance support)

Once the plant has stabilized, cue Simulator Operator to insert Trigger 6 Lead Evaluator:

Event 6: 'C' Steam Generator Tube Leak (AOP-016)

Harris 2020 NRC Exam Scenario 1 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 6 Page 35 of 83 Event

Description:

'C' Steam Generator Tube Leak (AOP-016)

Time Position Applicants Actions or Behavior On cue from the Lead Evaluator actuate Trigger 6 Simulator Operator:

'C' Steam Generator Tube Leak (AOP-016)

• Charging Flow rising

• VCT Level lowering Indications Available:

• Pressurizer Level and Pressure lowering

• C MSL Rad monitor Identifies entry conditions to AOP-016, Excessive Primary Plant CREW Leakage are met AOP-016 Excessive Primary Plant Leakage ENTERS and directs actions of AOP-016, SRO Conducts a Crew Update Makes PA announcement for AOP entry Procedure Note: This procedure contains no immediate actions.

RO 1. CHECK RHR in operation (NO)

3. REFER TO PEP-110, Emergency Classification And SRO Protective Action Recommendations, AND ENTER the EAL Matrix.

4. CHECK RCS leakage within VCT makeup capability (YES)

RO May report that the leak is exceeding Tech Spec SG leakage.

If CSIP suction is re-aligned to the RWST, negative reactivity Procedure Note:

addition should be anticipated.

5. MAINTAIN VCT level GREATER THAN 5%.

RO (YES)

6. GO TO STEP 10.

Harris 2020 NRC Exam Scenario 1 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 6 Page 36 of 83 Event

Description:

'C' Steam Generator Tube Leak (AOP-016)

Time Position Applicants Actions or Behavior

10. CHECK valid CNMT Ventilation Isolation monitors (YES)

(REM-3561A, B, C and D) ALARM CLEAR

11. CHECK RM 3502A, RCS Leak Detection Radiation (YES)

SRO Monitor, ALARM CLEAR

12. CHECK ALL valid Area Radiation Monitors ALARM (YES)

CLEAR

13. CHECK valid Stack Monitors ALARM CLEAR (YES)

14. DETERMINE if unnecessary personnel should be evacuated from affected areas, as follows:

SRO a. CHECK that a valid RMS Secondary Monitor HIGH ALARM Indicates a SG tube leak may exist.

b. SOUND local evacuation alarm.

c. ANNOUNCE on the PA:

Attention all personnel. High radiation levels may exist BOP in portions of the power block due to SG tube leakage.

Unnecessary personnel evacuate the RAB and Turbine Building, including the Steam Tunnel. Further announcements will be made as surveys are performed.

BOP 15. NOTIFY Chemistry to stop any primary sampling activities.

Simulator Acknowledge request to stop primary sampling activities.

Communicator:

• The following qualitative flow balance is to quickly determine if RCS leakage exceeds Tech Spec limits, EAL classification thresholds, or RCS makeup capability.

Procedure Note:

• RCS influent and effluent flow rates are compared and PRZ level rate of change is used to determine the RCS flow balance.

Harris 2020 NRC Exam Scenario 1 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 6 Page 37 of 83 Event

Description:

'C' Steam Generator Tube Leak (AOP-016)

Time Position Applicants Actions or Behavior

16. PERFORM a qualitative RCS flow balance, as follows:

a. ESTIMATE leak rate considering the following parameters:

• PRZ level rate of change (~55 gal/% at 653°F)

RO

• Charging flow

• Total seal injection flow

• Letdown flow

• Total seal return flow Reports estimate to SRO of 30 gpm (25 to 75 gpm)

b. OPERATE the following letdown orifice valves as necessary to maintain charging flow on scale:

• 1CS-7, 45 gpm Letdown Orifice A

• 1CS-8, 60 gpm Letdown Orifice B

• 1CS-9, 60 gpm Letdown Orifice C (No changes required)

Performance of surveillance tests to determine if leakage Procedure Note: exceeds Tech Spec limits, or to more accurately quantify leakage is up to CRS discretion.

Determines that more accurate quantification is not needed SRO due to excessive leakage indications present.

Any Tech Spec evaluation can be conducted as a follow up Evaluator Note:

question after the scenario.

SRO 18. EVALUATE RCS leakage (refer to Tech Spec 3.4.6.2).

Reviews Reactor Coolant System TS 3.4.6.2 Reactor Coolant System operational leakage shall be limited to:

c. 150 gallons per day primary-to-secondary leakage through any one steam generator.

ACTION a. - With any PRESSURE BOUNDARY LEAKAGE or with primary-to-secondary leakage not within limits, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

Harris 2020 NRC Exam Scenario 1 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 6 Page 38 of 83 Event

Description:

'C' Steam Generator Tube Leak (AOP-016)

Time Position Applicants Actions or Behavior

19. DETERMINE leak location from one or more of the SRO following:

• MCB indications and Valid Radiation Monitors

20. NOTIFY Health Physics of the following:

a. Leak location:

BOP

• Source inside or outside CNMT

• To closed system, SG or to atmosphere

b. Applicable radiation levels.

Simulator Acknowledge communications Communicator:

21. WHEN leakage location has been determined, THEN SRO PERFORM the applicable

Attachment:

Primary-to-Secondary Attachment 1 page 13

1. DIRECT Chemistry to implement CRC-804, Primary-To-Secondary Leak Rate Monitoring, to accomplish the following:

a. NOTIFY the MCR as soon as the leaking SG has been BOP determined.

b. NOTIFY the MCR when the following results are obtained:

• Quantify leak rate

• Quantify leak rate trend Simulator Acknowledge communications Communicator:

For a known leak rate greater than 100 gpd (PSAL 3 threshold), the CRS may direct performance of Attachments 9, Procedure Note:

10 and 11 while the remaining steps of Attachment 1 are being completed.

Harris 2020 NRC Exam Scenario 1 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 6 Page 39 of 83 Event

Description:

'C' Steam Generator Tube Leak (AOP-016)

Time Position Applicants Actions or Behavior

2. CHECK known leak rate is LESS THAN 100 gpd (0.0694 SRO gpm).- NO leak is > 100 gpm - GO TO STEP 4

4. DETERMINE leaking SG(s) using the following information:

a. Individual SGBD samples

b. Main Steam Line radiation monitor levels SRO

c. Local surveys of SGBD lines Determines leak is from C SG from various indication sources.

5. CHECK the following valid radiation monitors ALARM CLEAR:

• RM-01MS-3593 SB, Main Steam Line C (DICSP Grids 5, 6)

REM-01TV-3534, Condenser Vacuum Pump Effluent (DICSP Grid 2)

SRO REM-01BD-3527, Steam Generator Blowdown (DICSP Grid 2)

RM-01TV-3536-1, Turbine Building Vent Stack Effluent (DICSP Grids 2, 5, 6)

NO not clear Harris 2020 NRC Exam Scenario 1 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 6 Page 40 of 83 Event

Description:

'C' Steam Generator Tube Leak (AOP-016)

Time Position Applicants Actions or Behavior

5. PERFORM the following:

a. DIRECT Health Physics to survey the following outside the RCA:

• SG Blowdown piping

• Vicinity of Main Steam piping

b. IF ANY valid monitor is in HIGH ALARM, THEN:

(1) DIRECT HP to evaluate the alarm (refer to HPP-780, Radiation Monitoring Systems Operators BOP Manual).

(2) SOUND the local evacuation alarm.

(3) ANNOUNCE evacuation of the following areas:

• Steam Tunnel

• SG PORVs/SG Safety valves area

• Turbine Building 314 elevation (4) REPEAT sounding the local evacuation alarm AND the announcement.

(5) IF ANY valid Main Steam Line Monitor is in HIGH ALARM, THEN PERFORM an Offsite Dose SRO Calculation (Refer to PEP-340, Dose Assessment).

- Refers to the STA for this assessment.

6. CHECK BOTH of the following:

• Turbine Building Vent Stack radiation monitor HIGH ALARM CLEAR

• SG tube leakage is less than Tech Spec limits.

SRO NO - RNO actions:

START CVPETS (refer to OP-133, Main Condenser Air Removal System).

BOP Contacts TB AO to Start CVPETS in accordance with OP-133 Simulator Acknowledge communications to start CVPETS Communicator:

Harris 2020 NRC Exam Scenario 1 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 6 Page 41 of 83 Event

Description:

'C' Steam Generator Tube Leak (AOP-016)

Time Position Applicants Actions or Behavior Perform the following actions from Sim Diagram CVP01 to operate start the CVPETS A fan:

Simulator Operator:

Start CVPETS A fan modify rf cnd035 ON, then have Communicator report back when completed B train Aux Condensate Equipment is in long term shutdown Procedure Note:

per EC 264640.

7. CHECK valid Aux Steam Condensate radiation monitors ALARM CLEAR:

• REM-21AC-3525, RAB Auxiliary Steam Condensate (DICSP Grid 1)

SRO

• REM-21AC-3543A, AUX Steam Condensate Tank Pump Discharge A (DICSP Grid 4)

YES - clear

8. DIRECT Chemistry to sample the Auxiliary Steam System BOP for activity.

Simulator Acknowledge communications Communicator:

9. CHECK Chemistry reports Auxiliary Steam System activity SRO is satisfactory.

(No reports yet - continues with procedure)

• For initial leakage reports, where no previous leakage existed, leakage should be assumed to have changed from Procedure Note: zero to the current value in the last hour.

• The monitoring requirements of Step 3 become optional if Step 10 directs performance of Attachment 9, 10, or 11.

Harris 2020 NRC Exam Scenario 1 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 6 Page 42 of 83 Event

Description:

'C' Steam Generator Tube Leak (AOP-016)

Time Position Applicants Actions or Behavior

10. PERFORM the required actions based on the following:

Action Level 3 - Greater than or equal to 150 gpd PERFORM Attachment 11 to obtain the following:

SRO

• Reduce power to 50% within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of entering Action Level 3.

• Mode 3 within the next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> (total of 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />)

• Mode 5 within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> (total of 33 hours3.819444e-4 days <br />0.00917 hours <br />5.456349e-5 weeks <br />1.25565e-5 months <br />)

Determines that SG leakage will require the unit power level to be reduced to <50% within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and Mode 3 in next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

SRO

• Requires AOP-038 entry to accomplish these time limits per Attachment 11 step 7 RNO

11. WHEN required actions are complete OR leaking SG(s) are cooled down and depressurized to Mode 5, THEN:

SRO a. CONSULT plant operations staff concerning plant conditions needed to support recovery efforts.

b. EXIT this procedure.

SRO Informs crew that they are transitioning to AOP-038 AOP-038 Rapid Downpower Enters AOP-038, RAPID DOWNPOWER SRO Makes PA announcement Conducts a crew brief The crew may make calls to notify plant management in accordance with AD-OP-ALL-1000, Section 5.5.13 before or Simulator during the power reduction. Acknowledge and request a Communicator:

report from the MCR when more information becomes available.

Harris 2020 NRC Exam Scenario 1 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 6 Page 43 of 83 Event

Description:

'C' Steam Generator Tube Leak (AOP-016)

Time Position Applicants Actions or Behavior

• This procedure contains no immediate actions.

• Steps may be performed simultaneously or out of sequence at the discretion of the Shift Manager.

• If the ASI System is supplying RCP seal injection and no CSIP is available, boration is accomplished by the operation Procedure Note: of the ASI pump and is not under control of the operator.

Steps that perform boration or dilution cannot be performed and should be marked NA. Turbine load should be reduced at a rate between 5 MW/MIN (EOL) and 10 MW/MIN (BOL).

Target rod heights as a function of power in Attachment 2 remain valid.

1. ENTER the EAL Matrix (Refer to the following): [C.1]

SRO

• AD-EP-ALL-0101, Emergency Classification

• AD-EP-ALL-0109, Offsite Protective Action Recommendations BOP 2. NOTIFY Load Dispatcher that the Unit is reducing load.

Procedure Note: Boration of the RCS commences at Step 9.

3. DETERMINE required boric acid addition as follows:

1. CHECK BOTH of the following conditions exist:

RO

• Reactor power is 100%

• Target power level is provided in OPT-1536, Routine Reactivity Data Calculation. [C.3]

Evaluator Note: AOP-038 Attachment 2 is located in this guide on page 77.

NO - RNO actions:

OBTAIN values from Attachment 2, Gallons of Boric Acid/Target Rod Height Required for Power Reduction. [C.3]

• Desired Boration _______ gal

• Target Rod height (D Bank) _______

Harris 2020 NRC Exam Scenario 1 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 6 Page 44 of 83 Event

Description:

'C' Steam Generator Tube Leak (AOP-016)

Time Position Applicants Actions or Behavior

• If load reduction rates in excess of 45 MW/min are required, the Unit should be tripped.

• GVPC is the preferred method of Load Control. Megawatt Procedure Note: Control is normally used only during GV and TV testing.

• If Oper Entry is selected with the Turbine in GO, the value currently in the Ramp Rate Entry Window will become the load rate in effect. It may be desirable to place the turbine in HOLD to avoid undesirable ramp rates.

4. PERFORM the following on TCS Load Control screen, Load Control section:

a. CHECK GVPC indicator is TRUE - YES

b. SELECT Ramp Rate Selection, Select button

c. CHECK desired ramp rate is listed on Load Ramp Rate Selection - YES BOP d. SELECT desired ramp rate (NOT to exceed 45 MW/min).

(Should select 25 MW/min)

e. ENTER desired load (120 MW if shutting down) in Target Entry window.

(Should be previously select for 120 MW)

f. DEPRESS Enter.

5. CHECK Rod Control in AUTO (NO - auto is failed)

RO

• MANUALLY POSITION Control Rods to maintain Tavg within 5°F of Tref.

RO 6. ENERGIZE ALL available PRZ Backup heaters. (ALL ON)

7. DISCUSS Attachment 3, Reactivity Brief, with the MCR SRO staff.

The MW output indication is displayed on the TCS Turbine Load Control screen. An accurate indication of Main Generator Procedure Note:

output can also be obtained from ERFIS point JEE1568B (Gross MWe).

Harris 2020 NRC Exam Scenario 1 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 6 Page 45 of 83 Event

Description:

'C' Steam Generator Tube Leak (AOP-016)

Time Position Applicants Actions or Behavior

8. COMMENCE turbine load reduction at the TCS Load Control screen:

BOP

• SELECT GO pushbutton.

• CHECK that Demand value counts-down to Target Load value.

• To prevent over-boration, only the amount of boron required to reduce power to the desired power level should be added. If the situation merits that the downpower may have to be halted for any substantial time (>2 hours) at lower powers prior to taking the plant off-line, the effects of Procedure Note:

Xenon and changes in feed flow should be considered.

Reactivity control may become challenging if boron manipulations are not appropriately implemented.

• Adjustments should be made to boric acid flow based on actual core/rod response.

9. COMMENCE RCS boration as required to maintain RO Control Rods above the Rod Insertion Limit (ROD Manual Sect 2.2).

The following boration steps of OP-107.01 are provided for Evaluator Note: evaluator use. They are not in AOP-038.

Section 8.7 is provided below.

OP- CVCS Boration, Dilution, And Chemistry Control 107.01 Section 8.7, Rapid Addition of Boric Acid to the RCS Harris 2020 NRC Exam Scenario 1 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 6 Page 46 of 83 Event

Description:

'C' Steam Generator Tube Leak (AOP-016)

Time Position Applicants Actions or Behavior

• If performing a rapid shutdown of the plant per AOP-038, the following calculation does not have to be completed before boration begins, but should be completed before half of the estimated (or before 500 gallons whichever is less) boron addition has been dispensed.

Procedure Note:

• Reactivity Evolution category to be determined by the CRS.

• If an RCS leak or SGTL is occurring and an Auto Makeup is in progress, it may be necessary to take RMUW control to stop in order to avoid flow deviations on RMUW system while performing the boration.

1. IF it is desired to stop Auto Makeup due to RCS leakage, THEN PERFORM the following:

RO a. PLACE RMW CONTROL switch to stop.

b. CHECK the green light is lit on the RMW Control switch.

2. DETERMINE the volume of boric acid necessary to achieve the required RCS boron concentration.

Required gallons of Boric Acid _____________Gal.

3. ENSURE the backup Boric Acid Transfer Pump control switch is in STOP.

• Required boration flow rate of greater than 45 gpm, is best achieved by using Step 8.7.2.4, 1CS 278 SB, EMERGENCY BORIC ACID ADDITION.

Procedure Note:

• Required boration flow rate of less than 45 gpm, is best achieved by using Step 8.7.2.5, 1CS 283, BORIC ACID TO BORIC ACID BLENDER FCV-113A, and 1CS 156, MAKE UP TO CSIP SUCTION FCV 113B.

Harris 2020 NRC Exam Scenario 1 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 6 Page 47 of 83 Event

Description:

'C' Steam Generator Tube Leak (AOP-016)

Time Position Applicants Actions or Behavior

4. IF using 1CS-278 SB, EMERGENCY BORIC ACID ADDITION for Boric Acid addition, THEN PERFORM the following:

a. RECORD the initial BAT level for backup calculation of Boric Acid addition.

Initial BAT level: _____________ %

b. START the Boric Acid Transfer Pump aligned for Auto Makeup (switch in AUTO) by placing the control switch to START.

c. SIMULTANEOUSLY PERFORM the following:

• OPEN 1CS-278 SB, EMERGENCY BORIC ACID RO ADDITION.

• MARK the START time.

Time 1CS-278 opened. Time _____________

d. RECORD the Boric Acid flowrate from FI-110.

Boric Acid flowrate (FI-110) _____________ Gpm

e. CALCULATE the amount of time in minutes it will take to deliver the required amount of Boric Acid.

Required gallons BA / BA flowrate = Time

f. CONTROL charging and letdown to maintain normal PRZ and VCT levels.

g. CALCULATE the final BAT level for the required amount of Boric Acid being added.

Initial BAT Lvl % - [(Required gallons BA) / (330 gal/%)]

= Final BAT Lvl %

• Boration flow may be interrupted as needed by cycling Procedure Note: 1CS-278, while maintaining the total boration time calculated in Step 8.7.2.4.e Harris 2020 NRC Exam Scenario 1 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 6 Page 48 of 83 Event

Description:

'C' Steam Generator Tube Leak (AOP-016)

Time Position Applicants Actions or Behavior

h. WHEN the calculated amount of time has elapsed, THEN SIMULTANEOUSLY:

• SHUT 1CS-278 SB.

RO

• MARK the STOP time.

Time 1CS-278 shut. Time _____________

i. ENSURE, using calculated final BAT level, that the required amount of Boric Acid has been dispensed.

Boration flow may be interrupted as needed by cycling 1CS-278, while maintaining the total boration time calculated.

Procedure Note: During makeup operations following an alternate dilution, approximately 10 gallons of dilution should be expected due to dilution water remaining in the primary makeup lines.

6. REQUEST Chemistry to sample the RCS boron RO concentration.

8. PLACE Reactor Makeup in Auto per Section 5.1.

AOP-038 Rapid Downpower Actions - Continued (step 11)

BOP 10. ENSURE Generator load AND Reactor power LOWERING.

11. MAINTAIN Generator reactive load (VARs) within BOP guidelines.

Opening 3A and 3B Feedwater Heater vents helps minimize Procedure Note:

water hammer in 3A and 3B Feedwater Heaters.

RO 13. CHECK Tavg within 5°F of Tref (YES)

14. PERFORM the following:

CREW a. NOTIFY Chemistry of the following: Reactor power change will exceed 15% in a one hour period.

Harris 2020 NRC Exam Scenario 1 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 6 Page 49 of 83 Event

Description:

'C' Steam Generator Tube Leak (AOP-016)

Time Position Applicants Actions or Behavior

b. DIRECT Chemistry to initiate surveillances specified in the applicable sections of the following:

• RST-204, Reactor Coolant System Chemistry and SRO Radiochemistry Surveillance

• RST-211, Gaseous Effluent Radiochemistry Surveillance

15. CHECK that a planned load reduction will take the (YES)

SRO Unit to Turbine shutdown

16. DISPATCH an operator to start the Auxiliary Boiler using OP-130.02, Auxiliary Boiler and Fuel Oil.

SRO

17. DIRECT Radwaste Control Room to be prepared for the increased water processing requirements due to boration.

CREW 18. CHECK Power level at the target value (NO)

With AOP-038 in progress, cue Simulator Operator to insert Trigger 7 Examiner Note:

Event 7: 'C' Steam Generator Tube Rupture of 250 gpm (EOP-E-0 and EOP-E-3).

Harris 2020 NRC Exam Scenario 1 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 7 Page 50 of 83

'C' Steam Generator Tube Rupture of 250 gpm Event

Description:

(EOP-E-0)

Time Position Applicants Actions or Behavior On cue from the Lead Evaluator actuate Trigger 7 Simulator Operator: 'C' Steam Generator Tube Rupture of 250 gpm (EOP-E-0 and EOP-E-3)

• ALB-009-2-2, Pressurizer Control Low Level Deviation

• ALB-010-4-5 Rad Monitor System Trouble

• Pressurizer Level and Pressure lowering Indications Available:

• Charging Flow rising

• VCT Level lowering

• C MSL Rad monitor

• C SG level rising Identifies re-entry conditions to AOP-016, Excessive Primary CREW Plant Leakage are met AOP-016 Excessive Primary Plant Leakage RE-ENTERS and directs continuous action step 4 of AOP-016, SRO Conducts a Crew Update RO 4. CHECK RCS leakage within VCT makeup capability. NO NO - RNO actions

4. PERFORM the following:

a. TRIP the Reactor, AND GO TO EOP-E-0. (Perform RNO substeps 4.b. and 4.c as time permits)

(Actuates Manually Rx Trip using MCB switch)

EOP-E-0 Reactor Trip Or Safety Injection Enters EOP-E-0 SRO Holds crew update RO/BOP Performs E-0 Immediate Actions.

Harris 2020 NRC Exam Scenario 1 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 7 Page 51 of 83

'C' Steam Generator Tube Rupture of 250 gpm Event

Description:

(EOP-E-0)

Time Position Applicants Actions or Behavior Ensure Reactor Trip.

Immediate YES Actions RO YES YES Check Turbine Trip - ALL THROTTLE VALVES SHUT YES YES Immediate Actions BOP YES YES AOP-016 Excessive Primary Plant Leakage If SI Actuation is required, the Reactor and Turbine should be Procedure Note:

verified tripped in EOP-E-0 before manually actuating SI.

b. MANUALLY INITIATE Safety Injection. [C.1]

RO (Actuates Manually Safety Injection using MCB switch)

SRO c. EXIT this procedure.

EOP-E-0 SRO E-0, Reactor Trip Or Safety Injection Harris 2020 NRC Exam Scenario 1 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 7 Page 52 of 83

'C' Steam Generator Tube Rupture of 250 gpm Event

Description:

(EOP-E-0)

Time Position Applicants Actions or Behavior

3. Perform The Following:

Immediate a. AC Emergency Buses - AT LEAST ONE YES Actions BOP ENERGIZED YES

b. AC Emergency Buses - BOTH ENERGIZED

4. Safety Injection - ACTUATED (BOTH TRAINS) YES Immediate Actions RO Steps 1 through 4 are immediate action steps Procedure Note:

Foldout applies. (Immediate actions should be completed prior implementing Foldout Page items.)

SRO Reviews Foldout page Harris 2020 NRC Exam Scenario 1 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 7 Page 53 of 83

'C' Steam Generator Tube Rupture of 250 gpm Event

Description:

(EOP-E-0)

Time Position Applicants Actions or Behavior Evaluator Note:

If C SG previously identified as the Ruptured Generator due to rising SG level, then Ruptured SG AFW Isolation foldout will apply

5. Perform the following:

a. Assigns Foldout Page: RCP Trip Criteria, Alternate Miniflow Open/Shut Criteria, RHR Restart Criteria, SRO Ruptured SG AFW Isolation criteria, AFW Supply Switchover Criteria

b. Directs Shift Manager to Evaluate EAL Matrix SRO b. Evaluate EAL Matrix (Refer to PEP-110)

RO 6. Verify CSIPs - ALL RUNNING (YES)

RO 7. Verify RHR pumps - ALL RUNNING (YES)

Harris 2020 NRC Exam Scenario 1 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 8 Page 54 of 83 Event

Description:

Relay failure on resultant SI signal K603A Time Position Applicants Actions or Behavior RO 8. Safety Injection flow - GREATER THAN 200 GPM NO NO - RNO actions

8. Perform the following:

a) Ensure high head safety injection alignment:

(1) CSIP suction from RWST valves - OPEN YES (Event 8) (2) VCT outlet valves - SHUT YES (3) Charging line isolation valves - SHUT NO RO (Shut 1CS-238 manually)

Critical (4) BIT outlet valves - OPEN Task #1 (Open 1SI-4 manually) NO Critical to manually align at least one high head ECCS pump flow path to prevent RVLIS Dynamic Range Level from lowering below 60%

RO 9. RCS pressure - LESS THAN 230 PSIG (NO)

SRO 9. RNO: GO TO Step 12.

BOP 12. MAIN Steam Line Isolation - ACTUATED (NO)

SRO 12. RNO: Perform the following:

• Check MAIN Steam isolation - REQUIRED (NO)

BOP

• IF Main Steam Isolation is NOT required , THEN GO TO Step 16.

Harris 2020 NRC Exam Scenario 1 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 7 Page 55 of 83

'C' Steam Generator Tube Rupture of 250 gpm Event

Description:

(EOP-E-0)

Time Position Applicants Actions or Behavior

16. CHECK CNMT Pressure - HAS REMAINED LESS (YES)

RO THAN 10 PSIG

17. Verify AFW flow - AT LEAST 200 KPPH BOP (YES)

ESTABLISHED

18. Sequencer Load Block 9 (Manual Loading BOP (YES)

Permissive) - ACTUATED (BOTH TRAINS)

BOP 19. Energize AC buses 1A1 AND 1B1 The RO will perform all board actions until the BOP completes Attachment 3. The BOP is permitted to properly align plant equipment in accordance with Attachment 3 without SRO approval. The Scenario Guide still identifies Evaluator Note: tasks by board position because the time frame for completion of Attachment 3 is not predictable.

To follow BOP actions E-0 Attachment 3 is located in the back of this guide.

20. VERIFY Alignment of Components From Actuation of BOP ESFAS Signals Using Attachment 3, Safeguards Actuation Verification, While Continuing with this Procedure.

Directs TB AO - Place air compressor 1A and 1B in the Local Control mode.

BOP Directs RAB AO - Locally unlock and turn on the breakers for the CSIP Suction and Discharge Cross-Connect valves Harris 2020 NRC Exam Scenario 1 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 8/9 Page 56 of 83 Event

Description:

Failure of Control Room Isolation to actuate B ESW Pump fails to auto start on SI Time Position Applicants Actions or Behavior When contacted to place A/B air compressors in Local Simulator Operator:

Control mode, run CAEP :\air\ACs_to_local.txt.

Simulator When CAEP is complete, report that the air compressors Communicator: are running in local control mode.

When contacted to Unlock and Turn ON the breakers for Simulator Operator: the CSIP suction and discharge cross-connect valves, run CAEP :\cvc\E-0 Att 2 CSIP suct & disc valve power.txt.

Simulator When the CAEP is complete, report task to the MCR.

Communicator:

Ensure All ESW AND ESW Booster Pumps - RUNNING Event 9 RO Identifies that the B ESW Pump is NOT running and manually starts pump.

Ensure Control Room Area Ventilation - Main Control Room Aligned For Emergency Operation (Refer to OMM-004, "Post Trip/Safeguards Actuation Review", Attachment 5, Sheets 1 and 2, Sections for Main Control Board, SLB-5 and SLB-6.)

BOP Event 8 Identifies that the Control Room Area Ventilation is NOT aligned for Emergency Operation and aligns the ventilation system correctly.

OMM-004 Attachment 5 is located in the back of this guide on page 80.

The following items should be completed due to Control Room Ventilation not being aligned:

Opens CZ-D66 Starts R2 A-SA fan (Emergency Filtration)

BOP Stops E9A fan (Normal Exhaust)

Opens Battery Room A Return Dampers AC-D4 Harris 2020 NRC Exam Scenario 1 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 7 Page 57 of 83 Event

Description:

'C' Steam Generator Tube Rupture of 250 gpm (E-0) Continued Time Position Applicants Actions or Behavior

21. Stabilize AND maintain temperature between 555°F AND 559°F using Table 1.

BOP

• Control feed flow and steam dump to stabilize temperature between 555F AND 559F Harris 2020 NRC Exam Scenario 1 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 7 Page 58 of 83 Event

Description:

'C' Steam Generator Tube Rupture of 250 gpm (E-0) Continued Time Position Applicants Actions or Behavior RO 22. PRZ PORVs - SHUT (YES)

RO 23. PRZ spray valves - SHUT (YES)

24. PRZ PORV block valves - AT LEAST ONE OPEN (YES)

RO (All OPEN)

25. ANY SG pressures - DROPPING IN AN (NO)

UNCONTROLLED MANNER OR BOP/SRO COMPLETELY DEPRESSURIZED (NO)

Go to Step 27.

27. ANY SG ABNORMAL RADIATION (YES)

OR BOP/SRO UNCONTROLLED LEVEL RISE (YES)

Crew identifies C SG.

28. Check Feed Flow to Ruptured SG(s) - ISOLATED SRO (The crew should have isolated the C SG Feed Flow (YES) earlier utilizing the Ruptured SG AFW Isolation Criteria Foldout)

29. Go to E-3, "STEAM GENERATOR TUBE RUPTURE",

SRO Step 1.

Harris 2020 NRC Exam Scenario 1 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 7 Page 59 of 83

'C' Steam Generator Tube Rupture of 250 gpm Event

Description:

(EOP-E-3)

Time Position Applicants Actions or Behavior Enters E-3, Steam Generator Tube Rupture EOP-E-3 SRO Holds crew update Procedure Note: Foldout applies.

Evaluator Note:

No actions should result from FOLDOUT page during the remainder of the scenario.

Harris 2020 NRC Exam Scenario 1 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 7 Page 60 of 83

'C' Steam Generator Tube Rupture of 250 gpm Event

Description:

(EOP-E-3)

Time Position Applicants Actions or Behavior Assigns Foldout items:

Alternate Miniflow Open/Shut Criteria, RHR Restart Criteria, SI Reinitiation Criteria, Cold Leg Recirculation Switchover Criteria SRO Secondary Integrity Criteria, Multiple Tube Rupture Criteria, AFW Supply Switchover Criteria

1. Initiates Monitoring Of Critical Safety Function Status Trees.

RO 2. Any RCP - RUNNING (YES)

The RCP Trip Criteria is in effect until an RCS cooldown is Procedure Note:

initiated.

3. CHECK RCP Trip Criteria:

a. Check all of the following:

RO

• SI flow - GREATER THAN 200 GPM (YES)

• RCS pressure - LESS THAN 1400 PSIG (NO)

SRO RNO: GO TO Step 4.

4. CHECK RCP Ruptured SG(s) - IDENTIFIED (YES)

BOP Harris 2020 NRC Exam Scenario 1 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 7 Page 61 of 83

'C' Steam Generator Tube Rupture of 250 gpm Event

Description:

(EOP-E-3)

Time Position Applicants Actions or Behavior

5. ADJUST ruptured SG PORV controller setpoint to 88%

BOP (1145 PSIG) AND place in AUTO.

BOP 6. CHECK ruptured SG PORV - SHUT. (YES)

7. Check Feed Flow To Intact SG(s) - AVAILABLE (YES)

BOP FROM MDAFW PUMP The steam supply valve from the ruptured SG to the TDAFW pump should be shut OR isolated before initiating RCS Procedure Caution: cooldown (unless this prevents feeding SGs to be used for cooldown).

8. SHUT ruptured SG steam supply valve to TDAFW pump:

BOP (May have been closed previously in E-0)

9. VERIFY blowdown isolation valves from ruptured (YES)

SG - SHUT BOP

10. SHUT ruptured SG main steam drain isolation (YES) before MSIV:

BOP Harris 2020 NRC Exam Scenario 1 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 7 Page 62 of 83

'C' Steam Generator Tube Rupture of 250 gpm Event

Description:

(EOP-E-3)

Time Position Applicants Actions or Behavior BOP 11. SHUT ruptured SG MSIV AND BYPASS valve. (YES)

IF ruptured SG is faulted AND is NOT needed for RCS Procedure Caution:

cooldown, THEN feed flow to that SG should remain isolated.

BOP 12. Ruptured SG Level - GREATER THAN 25% [40%] (YES)

BOP 13. Ensure Feed Flow To Ruptured SG(s) - ISOLATED (YES)

14. CHECK Ruptured SG(s) Pressure - GREATER (YES)

BOP THAN 260 PSIG [350 PSIG]

RO 15. Check PRZ Pressure - LESS THAN 2000 PSIG (NO)

RNO:

15. WHEN pressure lowers to less than 2000 PSIG during RCS SRO cooldown, THEN perform Steps 16 AND 17.

Continue with Step 18.

During validation the pressure was greater than 2000 psig The Check PRZ Pressure could be answered YES or NO, depending on the pace at which the SRO progresses Evaluator Note:

through the EOP network. The following two steps are the actions to be taken once PRZ Pressure is less than 2000 psig.

Harris 2020 NRC Exam Scenario 1 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 7 Page 63 of 83

'C' Steam Generator Tube Rupture of 250 gpm Event

Description:

(EOP-E-3)

Time Position Applicants Actions or Behavior

16. Check Steamline High Pressure Rate Bistables - (YES)

CLEAR (NOT LIT)

RO After the low steam pressure SI signal is blocked, main Procedure Note: steamline isolation will occur if the high steam pressure rate setpoint is exceeded.

RO 17. Block Low Steam Pressure SI.

18. At least one intact SG - AVAILABLE FOR RCS (YES)

SRO COOLDOWN SRO 19. Go to Step 23.

Harris 2020 NRC Exam Scenario 1 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 7 Page 64 of 83

'C' Steam Generator Tube Rupture of 250 gpm Event

Description:

(EOP-E-3)

Time Position Applicants Actions or Behavior

23. Determine required core exit temperature based on lowest ruptured SG pressure:

SRO

24. Condenser - Available For Steam Dump: (YES)

BOP

25. Place steam dump pressure controller in manual AND BOP decrease output to 0%.

Harris 2020 NRC Exam Scenario 1 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 7 Page 65 of 83

'C' Steam Generator Tube Rupture of 250 gpm Event

Description:

(EOP-E-3)

Time Position Applicants Actions or Behavior BOP 26. Place steam dump mode select switch in STEAM PRESS.

27. Check RCS temperature - LESS THAN OR (YES)

EQUAL 553F (P-12)

BOP

28. Momentarily place both steam dump interlock bypass BOP switches to INTLK BYP.

29. Check LOW-LOW STEAM DUMP (P-12) (YES)

BYPASSED Status Light - ILLUMINATED BOP

30. Dump steam from intact SGs to Condenser at Maximum BOP Rate

31. Core Exit TCs - LESS THAN REQUIRED (NO)

SRO TEMPERATURE

31. RNO: WHEN core exit TCs less than required temperature, THEN perform Steps 32 AND 33.

SRO Observe CAUTION Prior To Step 34 AND Continue with Step 34.

Harris 2020 NRC Exam Scenario 1 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 7 Page 66 of 83

'C' Steam Generator Tube Rupture of 250 gpm Event

Description:

(EOP-E-3)

Time Position Applicants Actions or Behavior During cooldown at Max Rate, Main Steam Line Isolation may occur, requiring use of SG A and B PORVs to continue cooling down.

Evaluator Note: The crew will continue with the procedure while the cooldown is in progress. When the CET temperature is less than the target then the crew should terminate the cooldown and continue with the procedure.

If no RCPs running, the following actions may cause a false Procedure Caution: indication for the INTEGRITY CSFST. Disregard ruptured SG wide range cold leg temperature until Step 94 complete.

34. Maintain RCP Seal Injection Flow Between 8 GPM And 13 RO GPM.

If an AFW isolation to an intact SG occurs, the signal may be reset to allow restoration of AFW. (An AFW isolation will occur if a main steam line isolation signal is present AND one SG pressure decreases 100 PSIG below the other two SGs.)

Procedure Caution:

If the steam supply valve from the ruptured SG to TDAFW pump reopens due to decreasing SG level, it must be restored to the shut position. (Two out of three SG levels decreasing below 25% will open both steam supply vales to the TDAFW pump.)

BOP 35. Any Intact SG Level - GREATER THAN 25% [40%] (YES)

BOP 36. AFW flow - AT LEAST 200 KPPH AVAILABLE (YES)

37. Control Feed Flow To Maintain Intact SG Levels Between BOP 25% And 50% [40% and 50%]

38. Ensure Power To PORV Block Valves - (YES)

RO AVAILABLE RO 39. PRZ PORVs - SHUT (YES)

Harris 2020 NRC Exam Scenario 1 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 7 Page 67 of 83

'C' Steam Generator Tube Rupture of 250 gpm Event

Description:

(EOP-E-3)

Time Position Applicants Actions or Behavior RO 40. Check block valves - AT LEAST ONE OPEN (YES)

RO 41. Reset SI.

42. Manually Realign Safeguards Equipment Following A Loss SRO Of Offsite Power. (Directs RO)

43. Reset Phase A AND Phase B Isolation Signals.

RO (Phase A only is actuated)

44. Open Instrument Air AND Nitrogen Valves To CNMT:

RO

45. Check RHR pump suction - ALIGNED TO RWST (YES)

RO RO 46. RCS pressure - GREATER THAN 230 PSIG (YES)

RO 47. Stop RHR pumps.

48. Core exit TCs - LESS THAN REQUIRED (YES/NO)

RO TEMPERATURE Harris 2020 NRC Exam Scenario 1 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 7 Page 68 of 83

'C' Steam Generator Tube Rupture of 250 gpm Event

Description:

(EOP-E-3)

Time Position Applicants Actions or Behavior BOP 49. Stop RCS cooldown BOP 50. Maintain core exit TCs less than required temperature.

51. Check ruptured SG pressure - STABLE OR (YES)

BOP RISING

52. Check RCS Subcooling - GREATER THAN 30 F (YES)

RO

-C

53. Normal PRZ spray - AVAILABLE (INCLUDING (YES)

INSTRUMENT AIR TO CNMT)

RO

54. Check PRZ level - LESS THAN OR EQUAL TO (YES)

RO 75% [60%]

55. Manually Open All Available Normal PRZ Spray Valves AND Spray At Maximum Rate (Until ANY Of The RCS Critical Depressurization Termination Criteria in Step 56 Satisfied).

RO Task #2 Critical to depressurize the RCS to minimize primary to secondary leakage prior to SG C exceeding 95% level Crew will maintain the spray valves open until one of the Evaluator Note: RCS Depressurization Termination Criteria on the following page is SATISFIED Harris 2020 NRC Exam Scenario 1 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 7 Page 69 of 83

'C' Steam Generator Tube Rupture of 250 gpm Event

Description:

(EOP-E-3)

Time Position Applicants Actions or Behavior

56. Check RCS Depressurization Termination Criteria (NO)

- SATISFIED RO

56. RNO: Continue to monitor termination criteria.

SRO

• WHEN criteria satisfied, THEN GO TO Step 57.

RO 57. Shut spray valve used for depressurization:

SRO 58. Go to Step 65.

RO 65. RCS subcooling - GREATER THAN 10°F - C (YES)

66. Level In At Least One Intact SG - GREATER (YES)

BOP THAN 25% [40%]

SRO 67. Go to Step 69.

RO 69. RCS pressure - STABLE OR RISING (YES)

RO 70. PRZ level - GREATER THAN 10% [30%] (YES)

Harris 2020 NRC Exam Scenario 1 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 7 Page 70 of 83

'C' Steam Generator Tube Rupture of 250 gpm Event

Description:

(EOP-E-3)

Time Position Applicants Actions or Behavior RO 71. Stop All But One CSIP.

72. Check CSIP Suction - ALIGNED TO RWST (YES)

RO

73. Open Normal Miniflow Isolation Valves:

RO

74. Shut BIT outlet valves:

RO Terminate the scenario after BIT outlet valves 1SI-3 and 1SI-4 are SHUT.

Announce Crew Update - End of Evaluation - I have the Lead Evaluator:

shift.

Have crew remain in the Simulator without discussing the exam. Examiners will formulate any follow-up questions.

Simulator Operator: When directed by Lead Evaluator go to FREEZE Harris 2020 NRC Exam Scenario 1 Rev FINAL

Appendix D Form ES-D-2 E-0 Attachment 3 Harris 2020 NRC Exam Scenario 1 Rev FINAL

Appendix D Form ES-D-2 E-0 Attachment 3 Harris 2020 NRC Exam Scenario 1 Rev FINAL

Appendix D Form ES-D-2 E-0 Attachment 3 Harris 2020 NRC Exam Scenario 1 Rev FINAL

Appendix D Form ES-D-2 E-0 Attachment 3 Harris 2020 NRC Exam Scenario 1 Rev FINAL

Appendix D Form ES-D-2 E-0 Attachment 3 Harris 2020 NRC Exam Scenario 1 Rev FINAL

Appendix D Form ES-D-2 E-0 Attachment 3 Harris 2020 NRC Exam Scenario 1 Rev FINAL

Appendix D Form ES-D-2 E-0 Attachment 3 Harris 2020 NRC Exam Scenario 1 Rev FINAL

Appendix D Form ES-D-2 AOP-038 Attachment 2 Harris 2020 NRC Exam Scenario 1 Rev FINAL

Appendix D Form ES-D-2 AOP-038 Attachment 2 Harris 2020 NRC Exam Scenario 1 Rev FINAL

Appendix D Form ES-D-2 OMM-004 Attachment 5 Harris 2020 NRC Exam Scenario 1 Rev FINAL

Appendix D Form ES-D-2 OMM-004 Attachment 5 Harris 2020 NRC Exam Scenario 1 Rev FINAL

Appendix D Form ES-D-2 OMM-004 Attachment 5 Harris 2020 NRC Exam Scenario 1 Rev FINAL

Appendix D Form ES-D-2 OMM-004 Attachment 5 Harris 2020 NRC Exam Scenario 1 Rev FINAL

2020 NRC Exam Scenario 1 Turnover Plant Status

• Normal shutdown is in progress with TCS Load Control at 1 GVPC units / min in accordance with GP-006, Normal Plant Shutdown, due to LCO expiring on B MDAFW pump.

• Reactor power ~ 88% power. On hold through shift turnover. GP-006 Section 6.2, Step 10 is being coordinated by the FSRO, raise TCS Load Control to 4 GVPC units/ min and continue the downpower @ 4 MW/min. The SRO will conduct a reactivity brief, prior to the crew entering the simulator for evaluation

• Current rod position is CBD @ 201 steps

• An RCS Boron sample taken 30 minutes ago was 980 ppm

• Middle of life conditions

• A Train equipment is in service

• Normal Dayshift

• Status Board is updated

• Additional Protected items A ESW Pump, A CCW Pump, A SFP Hx, RWST, due to Response to Industry Best Practices Equipment Out of Service:

• B MDAFW Pump, placed under clearance 68 hours7.87037e-4 days <br />0.0189 hours <br />1.124339e-4 weeks <br />2.5874e-5 months <br /> ago for pump seal repairs.

Not expected to be returned to service in 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />. T.S. 3.7.1.2 action a (72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> LCO). "A" MDAFW Pump, MS-70 and 72, "B" ESW Pump, "B" RHR Pump, "B" CCW Pump and 'A' Train PICs: 1, 3, 9, 13, and 17 are protected.

• 1SI-3, Boron Injection Tank Outlet Valve has been under clearance the last 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for breaker repairs. The repairs are close to completion and the valve is expected to be returned to service within the next hour. Tech Spec 3.6.3 LCO Action b and Tech Specs 3.5.2 Action a applies. OWP-SI-01 has been completed.

• B DEH Pump is under clearance for motor repairs. The pump has been unavailable for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. Repairs are expected to be completed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

A DEH pump is protected in accordance with AD-OP-ALL-0210, Section 5.5, Conditional Single Point Vulnerabilities Reactivity Plan/Brief:

• Use attached Reactivity Plan to take unit off line at 4 MW/Min.

Risk Assessment:

• YELLOW 2020 NRC Exam Simulator Scenario 1 Turnover Rev FINAL

2020 NRC Exam Simulator Scenario 1 Turnover Rev FINAL Appendix D Scenario Outline Form ES-D-1 HARRIS 2020 NRC SCENARIO 2 Facility: Harris Nuclear Plant Scenario No.: 2 Op Test No.: 05000400/2020301 Examiners: Operators: SRO:

RO:

BOP:

Initial Conditions: IC-5 BOL, 53% power

• A-SA Boric Acid Transfer Pump is under clearance for breaker repairs

• 1CS-9, Letdown Isolation Valve is under clearance for solenoid replacement

• A Gland Steam Condenser Exhauster Fan is under clearance due to high vibrations on the motor bearing Turnover: The plant is at 53% power, beginning of core life. GP-005 step 134.e, comparison of diverse indications of power after exceeding 50% power is complete.

• Manually start the standby DEH Pump prior to DEH pressure lowering below 1150 psig to prevent an automatic Turbine Trip/Reactor trip

• Manually maintain control of SG B level below 78% to prevent an automatic Critical Task: Reactor trip after steam generator level transmitter LT-486 fails low

• Manually trip all RCPs within 10 minutes of a Phase B isolation signal

• Shut BIT Outlet valve 1SI-4 prior to establishing flow through the charging header Event No. Malf. No. Event Type* Event Description R - RO/SRO 1 N/A Power ascension from 53% power N - BOP/SRO I - RO/SRO 2 nis08b PRNIS Channel NI-42 fails HIGH (AOP-001)

TS - SRO I - RO/SRO 3 lt:460 Pressurizer Level Transmitter for LT-460 fails low TS - SRO tur24a DEH pump shaft shear and failure of the standby pump to 4 jmsehpas C - BOP/SRO start C - BOP/SRO 5 lt:486 'B' SG Controlling Level Transmitter fails Low (AOP-010)

TS - SRO Steam line Break on 'B' SG inside Containment (EOP-E-0 6 mss01b M - ALL and EOP-E-2) zrpk643b 7 zrpk644b C - RO/SRO B Containment Spray pump fails to auto start zrpk645b sis017 8 sis018 C - BOP/SRO 1SI-4 failure to close from MCB switch

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Harris 2020 NRC Exam Scenario 2 Rev FINAL

Appendix D Scenario Outline Form ES-D-1 HARRIS 2020 NRC SCENARIO 2 SCENARIO

SUMMARY

2020 NRC EXAM SCENARIO 2 The plant is at 53% power, beginning of core life. GP-005, Power Operation (Mode 2 To Mode 1) is in progress as directed by plant management. GP-005 step 134.e, comparison of diverse indications of power after exceeding 50% power is complete and the turbine is in hold for turnover. Once turnover is complete, raise TCS Load Control to 4 GVPC units/ min and continue the power ascension @ 4 MW/min.

The following equipment is under clearance:

• Boric Acid Transfer Pump A-SA is under clearance due to breaker blown control power fuses. Has been under clearance for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. The problem with the breaker has been repaired and the clearance will be removed later this shift. Tech Spec 3.3.3.5.b Action c and 3.1.2.2 applies (3.1.2.2 is for tracking only). OWP-CS-04 has been completed.

• 1CS-9, Letdown Orifice Isolation valve, has been under clearance the last 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for solenoid replacement. The repairs are close to completion and the valve is expected to be returned to service within the next hour. The valve is currently shut with power removed.

OWP-CS-09 has been completed. Tech Specs 3.6.3 Action b applies.

Harris 2020 NRC Exam Scenario 2 Rev FINAL

Appendix D Scenario Outline Form ES-D-1 HARRIS 2020 NRC SCENARIO 2 SCENARIO

SUMMARY

2020 NRC EXAM SCENARIO 2 (continued)

The following equipment is under clearance (continued):

• 1CS-9, Letdown Orifice Isolation valve Tech Spec (continued)

• A Gland Seal Exhauster Fan is under clearance for high vibrations on the motor bearing.

The fan has been under clearance for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. Repairs are expected to be completed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Harris 2020 NRC Exam Scenario 2 Rev FINAL

Appendix D Scenario Outline Form ES-D-1 HARRIS 2020 NRC SCENARIO 2 SCENARIO

SUMMARY

2020 NRC EXAM SCENARIO 2 (Continued)

Event 1: Power ascension from 53% power (GP-005). Turnover takes place with the unit at 53%

Reactor power. The crew will be given credit for a reactivity manipulation during the power ascension.

Verifiable Action: It is expected that the SRO will conduct a reactivity brief, the OATC will dilute and monitor auto rod withdrawal per the reactivity plan. The BOP will operate the DEH Turbine controls as necessary to raise power. After power is raised 3% - 5% and the crew has demonstrated that they have control of the plant Event 2 may be inserted.

Event 2: PRNIS Channel NI-42 fails HIGH (AOP-001). NI-42 along with the Rod Control system MCB response will provide indications of the malfunction. Multiple ALB 013 annunciator window associated with the Power Range Nuclear Instruments will alarm.

Verifiable Action: The crew will enter AOP-001 and carry out the immediate actions. The OATC will perform the immediate actions of AOP-001 by verifying that <2 rods are dropped (no rods have dropped), place Rod Control in MANUAL and then verify no rod motion. Once the immediate actions are complete the BOP should place the Turbine in Hold to stabilize the plant. The SRO should continue with the implementation of AOP-001 to bypass NI-42 and restore Tavg to match Tref in order to return Rod Control to Auto.

The SRO should provide a temperature band of +/- 5°F to the OATC in accordance with OMM-001, Attachment 11, Control Bands And Administrative Limits. The SRO should refer to AD-OP-ALL-1000 Attachment 4, Emergent Issue Checklists for the failure and request assistance from the WCC.

The SRO should evaluate Tech Spec 3.3.1, Instrumentation - Reactor Trip System Instrumentation Action: 2.

Harris 2020 NRC Exam Scenario 2 Rev FINAL

Appendix D Scenario Outline Form ES-D-1 HARRIS 2020 NRC SCENARIO 2 SCENARIO

SUMMARY

2020 NRC EXAM SCENARIO 2 (Continued)

Event 2: Tech Spec evaluation continued Event 3: Pressurizer Level Transmitter for LT-460 fails low. ALB 009-4-3, Pressurizer Low Level Ltdn Secured And Htrs Off, will alarm due to LT-460 being less than 17%.

Verifiable Action: The crew will respond in accordance with APP-ALB-009 and verify all Pressurizer Heaters off and Letdown has automatically isolated. The OATC will select the 459/461 position on the MCB to restore two operable channels and reset each pressurizer heater as required. The BOP will ensure the failed channel is not the selected recorder channel.

The SRO should provide a level band of +/- 5% to the OATC in accordance with OMM-001, 1, Control Bands And Administrative Limits. The SRO should refer to AD-OP-ALL-1000 Attachment 4, Emergent Issue Checklists, for the failure and request assistance from the WCC.

Harris 2020 NRC Exam Scenario 2 Rev FINAL

Appendix D Scenario Outline Form ES-D-1 HARRIS 2020 NRC SCENARIO 2 SCENARIO

SUMMARY

2020 NRC EXAM SCENARIO 2 (Continued)

The SRO should evaluate Tech Spec 3.3.1, Instrumentation - Reactor Trip System Instrumentation Action: 6.

Harris 2020 NRC Exam Scenario 2 Rev FINAL

Appendix D Scenario Outline Form ES-D-1 HARRIS 2020 NRC SCENARIO 2 SCENARIO

SUMMARY

2020 NRC EXAM SCENARIO 2 (Continued)

Event 4: DEH pump shaft shear and failure of the standby pump to start. The running pump will continue to indicate running until DEH pressure lowers to < 1600 psig when annunciator ALB-020-4-2B, DEH Fluid Low Press, will alarm. The crew should dispatch an Aux Operator to investigate the cause and confirm the standby pump is not affected by the failure.

Verifiable Action: The BOP will respond to the failure by taking actions contained in the APP-ALB 020-4-2B and ensuring the start of the standby DEH pump (Critical Task #1). If DEH pressure lowers to < 1500 psig the standby pump should auto start but a relay failure will prevent the pump from auto starting which will require the pump to be started manually. AD-OP-ALL-1000, Conduct of Operations, (5.6.3.8) for Equipment Manipulation and Status Control may be used to start the standby DEH pump prior to 1500 psig.

The SRO should refer to AD-OP-ALL-1000 Attachment 4, Emergent Issue Checklists for the failure and request assistance from the WCC.

Event 5: 'B' SG Controlling Level Transmitter fails Low (AOP-010). ALB 014-2-1B, 5-1A, 5-4B, SG B NR LVL/SP Hi/Lo Dev, SG B FW > Stm Flow Mismatch, and Steam Gen B Low-Low Level, respectively will alarm. The crew will respond by entering AOP-010, Feedwater Malfunction and taking manual control of B Main Feedwater Regulating Valve to reduce Feedwater flow and stabilize level.

Verifiable Action: Taking manual control of B Main Feedwater Regulating Valve to reduce Feedwater flow and stabilize level (Critical Task #2). With the controller in manual and the plant stabilized, the crew will implement OWP-RP-06 to remove the failed channel from service.

The SRO should provide a level band of 52% to 62% to the BOP in accordance with AOP-010 and OMM-001, Attachment 11, Control Bands And Administrative Limits. The SRO should refer to AD-OP-ALL-1000 Attachment 4, Emergent Issue Checklists, for the failure and request assistance from the WCC.

The SRO should evaluate Tech Spec 3.3.1, Instrumentation - Reactor Trip System Instrumentation and Tech Spec 3.3.2, Instrumentation - Engineered Safety Features Actuation System Instrumentation Action: 6 and 19 apply respectively.

Harris 2020 NRC Exam Scenario 2 Rev FINAL

Appendix D Scenario Outline Form ES-D-1 HARRIS 2020 NRC SCENARIO 2 SCENARIO

SUMMARY

2020 NRC EXAM SCENARIO 2 (Continued)

Event 5: Tech Spec evaluation continued Harris 2020 NRC Exam Scenario 2 Rev FINAL

Appendix D Scenario Outline Form ES-D-1 HARRIS 2020 NRC SCENARIO 2 SCENARIO

SUMMARY

2020 NRC EXAM SCENARIO 2 (Continued)

Event 5: Tech Spec evaluation continued Harris 2020 NRC Exam Scenario 2 Rev FINAL

Appendix D Scenario Outline Form ES-D-1 HARRIS 2020 NRC SCENARIO 2 SCENARIO

SUMMARY

2020 NRC EXAM SCENARIO 2 (Continued)

Event 6: Steam line Break on 'B' SG inside Containment (EOP-E-0 and EOP-E-2). The major event is a Steam line break. The RCS Loop B will degrade into a break inside containment requiring the crew to implement the continuous actions for AOP-042 with change in Reactor Power greater than 5% due to a steam leak and trip the Reactor and shut Main Steam Isolation Valves and MSIV Bypass Valves. Major changes in Pressurizer Level and Charging flow will occur.

Verifiable Action: The OATC will manually trip the Reactor in accordance with AOP-042, then shut Main Steam Isolation Valves and MSIV Bypass Valves. Due to the break size the crew may actuate Safety Injection and continue with EOP-E-0. The crew will then transition from EOP-E-0 and go to EOP-E-2, Faulted Steam Generator Isolation. While the crew is performing actions of EOP-E-2 the Containment pressure will continue to rise beyond 10 psig which will actuate a Phase B isolation signal. This will require ALL RCPs to be secured.

All RCPs will need to be manually tripped within 10 minutes of a Phase B isolation signal.

(Critical Task #3)

Event 7: B Containment Spray pump fails to auto start. B CT pump should auto start when Containment pressure is > 10 psig but does not.

Verifiable Action: The operator will first attempt to actuate Containment Spray using the MCB actuation switches but the actuation still does not occur requiring manual starting of the B CT pump and alignment of the B Train CT valves AD-OP-ALL-1000, Conduct of Operations, (5.6.3.8) for Equipment Manipulation and Status Control.

Event 8: 1SI-4 failure to close from MCB switch. While implementing EOP-E-2 the crew will be directed to reset SI and shut BIT outlet valves then establish a normal Charging lineup. When the crew attempts to shut 1SI-4 from the MCB the valve will not close.

Verifiable Action: The crew should identify this failure and direct an Aux Operator to locate and shut the 1SI-4 locally in accordance with the EOP-E-2 RNO step. Not shutting 1SI-4 prior to establishing a normal Charging lineup will cause simultaneous flow through the Charging and SI lines and cause a CSIP run out condition indicated by oscillating discharge pressure. (Critical Task #4).

The scenario termination is met in EOP-ES-1.1 when Safety Injection has been terminated and the crew restores letdown to service. With PZR level lowering and RCS Hot Leg Temperatures stable or lowering the RCS pressure challenge will be removed.

Harris 2020 NRC Exam Scenario 2 Rev FINAL

Appendix D Scenario Outline Form ES-D-1 HARRIS 2020 NRC SCENARIO 2 CRITICAL TASK JUSTIFICATION:

1. Manually start the standby DEH Pump prior to DEH pressure lowering below 1150 psig to prevent an automatic or manual Turbine Trip/Reactor trip An unnecessary automatic or manual Reactor Trip for this event will create a critical task. See note below.

2. Manually maintain control of SG B level below 78% to prevent an automatic or manual Turbine Trip/Reactor trip after steam generator level transmitter LT-486 fails low An unnecessary automatic or manual Reactor Trip for this event will create a critical task. See note below.

3. Manually trip all RCPs within 10 minutes of a Phase B isolation signal Securing RCPs during a large steam break inside Containment is procedurally required when Containment pressure has exceeded the High 3 setpoint of 10 psig.

Exceeding this pressure causes a Phase B actuation which will isolate CCW flow to the RCP motor coolers. Operation of RCPs for greater than 10 minutes without CCW cooling to the motor oil coolers may result in RCP bearing damage.

4. Shut BIT Outlet valve 1SI-4 prior to establishing flow through the charging header.

Isolation of Safety Injection is required to allow the operator to stabilize RCS plant conditions. Eventually the Pressurizer will fill with water rendering pressurizer control ineffective. Consequently, in order to decrease RCS pressure to conserve makeup water, Safety Injection flow must be decreased. Because Safety Injection flow cannot be throttled, once the criteria to reduce Safety Injection flow is met Safety Injection is terminated by isolating Safety Injection flow, reducing to one CSIP in operation and realigning the CSIP discharge to the normal charging header. Shutting the BIT outlet valves is the first step in realigning normal charging to the RCS. Not shutting 1SI-4 prior to establishing a normal Charging lineup will cause simultaneous flow through the Charging and SI lines and cause a CSIP run out condition indicated by oscillating discharge pressure.

Note: Causing an unnecessary plant trip or ESF actuation (automatic or manual) may constitute a CT failure. Actions taken by the applicant(s) will be validated using the methodology for critical tasks in Appendix D to NUREG-1021.

Harris 2020 NRC Exam Scenario 2 Rev FINAL

Appendix D Scenario Outline Form ES-D-1 HARRIS 2020 NRC SCENARIO 2 Simulator Setup Reset to IC-142 password NRC3sros Go to RUN Silence and Acknowledge annunciators GO TO FREEZE and inform the lead examiner the Simulator is ready. DO NOT GO TO RUN until directed by the lead examiner.

Set ERFIS screens for normal full power conditions (The examiner has provided to the candidate with initial conditions and the initiating cues prior to placing the simulator in RUN.)

SPECIAL INSTRUCTIONS Provide a Reactivity Plan to candidates for shutting down the plant Provide a copy of the following procedures:

• GP-005, Power Operations, (Mode 2 To Mode 1) marked up through section 6.2 step 134 Press START on Counter Scaler Post conditions for status board from IC-5 Reactor Power 53%

Control Bank D at 156 steps RCS boron 1725 ppm Turnover: The plant is at 53% power, beginning of core life. GP-005 step 134.e on hold for turnover. Once turnover is complete, raise TCS Load Control to 4 GVPC units/ min and continue the power ascension @ 4 MW/min.

Equipment Under Clearance:

• Boric Acid Transfer Pump A-SA is under clearance due to breaker blown control power fuses. Has been under clearance for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. The problem with the breaker has been repaired and the clearance will be removed later this shift. Tech Spec 3.3.3.5.b Action c and 3.1.2.2 applies (3.1.2.2 is for tracking only). OWP-CS-04 has been completed.

• 1CS-9, Letdown Orifice Isolation valve, has been under clearance the last 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for solenoid replacement. The repairs are close to completion and the valve is expected to be returned to service within the next hour. The valve is currently shut with power removed.

OWP-CS-09 has been completed. Tech Specs 3.6.3 Action b applies.

• A Gland Seal Exhauster Fan is under clearance for high vibrations on the motor bearing.

The fan has been under clearance for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. Repairs are expected to be completed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Harris 2020 NRC Exam Scenario 2 Rev FINAL

Appendix D Scenario Outline Form ES-D-1 HARRIS 2020 NRC SCENARIO 2 Simulator Setup (continued)

Align equipment for repairs:

Place CIT on A-SA Boric Acid Transfer pump MCB Switch Place protected train placards IAW OMM-001 Attachment 5 Protected Train placards on B-SB BA Transfer pump Place CIT on A Gland Steam Condenser Exhaust Fan MCB switch Place CIT on 1CS-9 MCB switch Place filled out copies of OWPs into the OWP book - ensure they are removed at end of day

• OWP-CS-04 and place in MCR OWP book for A BA Transfer pump

• OWP-CS-09 and place in MCR OWP book for 1CS-9 clearance Hang restricted access signs on MCR entry swing gates Harris 2020 NRC Exam Scenario 2 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 1 Page 14 of 81 Event

Description:

Power Ascension Time Position Applicants Actions or Behavior The crew has been directed to re-commence a power ascension from 53% to the unit is at 100%. The power ascension is on hold for turnover. The SRO is expected to conduct a reactivity brief prior to commencing the power ascension. This brief may be conducted outside the simulator prior to starting the scenario.

Lead Evaluator:

When the crew has completed their board walk down and are ready to take the shift inform the Simulator Operator to place the Simulator in Run. When the Simulator is in run announce:

CREW UPDATE - (SROs Name) Your crew has the shift.

END OF UPDATE When directed by the Lead Evaluator, ensure that the Simulator Operator:

annunciator horns are on and place the Simulator in RUN.

The crew may elect to begin dilution prior to raising Evaluator Note:

turbine load.

OATC OP-107.01, Section 5.4

1. DETERMINE the volume of makeup water to be added.

OATC (Current OPT-1536 data may be used.)

SRO Directs dilution FIS-114 may be set for one gallon less than desired. A pressure transient caused by 1CS-151 shutting results in Procedure Note:

FIS-114 normally indicating one gallon more than actual flow but two gallons more would be unexpected.

Harris 2020 NRC Exam Scenario 2 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 1 Page 15 of 81 Event

Description:

Power Ascension Time Position Applicants Actions or Behavior If the translucent covers associated with the Boric Acid and Total Makeup Batch counters FIS-113 and FIS-114, Procedure Caution:

located on the MCB, are not closed, the system will not automatically stop at the preset value.

2. SET FIS-114, TOTAL MAKEUP WTR BATCH COUNTER, OATC to obtain the desired quantity.

3. ENSURE the RMW CONTROL switch has been placed in OATC the STOP position.

4. ENSURE the RMW CONTROL switch green light is lit.

5. IF the current potentiometer setpoint of controller 1CS-151, FK-114 RWMU FLOW, needs to be changed to OATC obtain makeup flow, THEN PERFORM the following:

(N/A)

a. RECORD the current potentiometer setpoint of controller 1CS-151, FK-114 RWMU FLOW, in Section 5.4.3.

b. SET controller 1CS-151, FK-114 RWMU FLOW, for the desired flow rate.

6. PLACE control switch RMW MODE SELECTOR to the ALT OATC DIL position.

• Alternate Dilution may be manually stopped at any Procedure Note: time by turning the control switch RMW CONTROL to STOP.

Harris 2020 NRC Exam Scenario 2 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 1 Page 16 of 81 Event

Description:

Power Ascension Time Position Applicants Actions or Behavior

7. START the makeup system as follows:

a. TURN control switch RMW CONTROL to START momentarily.

b. ENSURE the RED indicator light is LIT.

OATC

c. IF expected system response is not obtained, THEN TURN control switch RMW CONTROL to STOP.

8. ENSURE dilution automatically terminates when the desired quantity has been added.

9. IF controller 1CS-151, FK-114 RWMU FLOW, OATC potentiometer was changed in Step 5.4.2.5, THEN PERFORM the following: (N/A)

a. REPOSITION controller FK-114 to the position recorded in Section 5.4.3.

b. INDEPENDENTLY VERIFY FK-114 potentiometer position of Step 5.4.2.9.a is correct.

10. Monitor Tavg and rod control for proper operation.

11. Establish VCT pressure between 20-30 psig.

12. Turn control switch RMW MODE SELECTOR to AUTO.

13. START the makeup system as follows:

OATC a. TURN control switch RMW CONTROL to START momentarily.

b. ENSURE the RED indicator light is LIT.

c. IF expected system response is not obtained, THEN TURN control switch RMW CONTROL to STOP.

(Ref. 4.0.31)

There is no procedural guidance directing when the Evaluator Note: dilution to raise power is required. The crew may elect to perform the raise prior to placing the Turbine in GO.

DIRECTS BOP to start power ascension at 4 MW/Min. May SRO direct initiation of a dilution before the power ascension begins.

Harris 2020 NRC Exam Scenario 2 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 1 Page 17 of 81 Event

Description:

Power Ascension Time Position Applicants Actions or Behavior The following steps have been completed to achieve the current power level. The crew should validate status of the Evaluator Note: turbine load ascension in accordance with GP-005 section 6.2 step 108 and 110 before re-initiating the turbine load ascension.

Requests PEER check prior to manipulations of TCS Load BOP Control screen 108.On the TCS Load Control screen, Load Control section, perform the following:

a. Select Ramp Rate Selection, Select button

b. Select the desired ramp rate determined in Step 16.a OR Oper Entry (4 GVPC Units/minute)

BOP

c. IF Oper Entry is selected, THEN enter the desired ramp rate determined in Step 16.a in the Ramp Rate Entry window and depress Enter.

• ENTER the desired rate. (4 GVPC Units/minute)

• DEPRESS the ENTER push-button.

If Oper Entry is selected with the Turbine in GO, the value currently in the Ramp Rate Entry Window will become the Procedure Note:

rate in effect. It may be desirable to place the turbine in HOLD to avoid undesirable rates.

110.WHEN ready to continue raising turbine load, THEN BOP perform the following on TCS Load Control screen, Load Control section:

a. IF 960 GVPC Units was NOT entered in the Target Entry window in Step 109.b, THEN enter 960 GVPC Units in the Target Entry window and depress Enter.

(960 GVPC Units).

b. Select the Go button BOP Ensure Generator load is rising Harris 2020 NRC Exam Scenario 2 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 1 Page 18 of 81 Event

Description:

Power Ascension Time Position Applicants Actions or Behavior Once the crew demonstrates a satisfactory load ascension cue Simulator Operator to insert Trigger 2 Evaluator Note:

Event 2: PRNIS Channel NI-42 fails HIGH (AOP-001)

Harris 2020 NRC Exam Scenario 2 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 2 Page 19 of 81 Event

Description:

PRNIS Channel NI-42 fails HIGH (AOP-001)

Time Position Applicants Actions or Behavior On cue from Lead Evaluator actuate Trigger 2 Simulator Operator:

PRNIS Channel NI-42 fails HIGH (AOP-001)

• Uncontrolled inward rod motion

• ALB-013-4-1, POWER RANGE HIGH NEUTRON FLUX HIGH SP ALERT

• ALB-013-4-2, POWER RANGE HIGH NEUTRON FLUX HIGH ALERT Indications Available

• ALB-013-4-5, POWER RANGE CHANNEL DEVIATION

• ALB-013-5-1, OVERPOWER ROD STOP

• ALB-013-8-5, COMPUTER ALARM ROD DEV/SEQ NIS PWR RANGE TILTS OATC RESPONDS to uncontrolled rod motion.

AOP-001 Malfunction of Rod Control and Indication System ENTERS and directs actions of AOP-001 SRO Conducts a Crew Update Makes PA announcement for AOP entry OATC PERFORMS immediate actions.

Immediate 1. CHECK that LESS THAN TWO control rods are Action OATC (YES) dropped.

Immediate Action OATC 2. POSITION Rod Bank Selector Switch to MAN.

Immediate Action OATC 3. CHECK Control Bank motion STOPPED. (YES)

READS immediate actions and proceeds to Section 3.2.

SRO Directs BOP to place Turbine to HOLD if in GO.

Harris 2020 NRC Exam Scenario 2 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 2 Page 20 of 81 Event

Description:

PRNIS Channel NI-42 fails HIGH (AOP-001)

Time Position Applicants Actions or Behavior BOP Places Turbine to HOLD if in GO.

1. CHECK that instrument channel failure has NOT OCCURRED by observing the following:

• RCS Tavg (NO)

OATC

• RCS Tref (NO)

• Power Range NI channels (YES)

• Turbine first stage pressure (NO)

1. PERFORM the following:

• IF a power supply is lost, THEN GO TO AOP- (NO) 024, Loss of Uninterruptible Power Supply.

OATC

• IF an individual instrument failed, THEN (YES)

MAINTAIN manual rod control until corrective action is complete.

(YES)

• IF a Power Range NI Channel failed, THEN BYPASS the failed channel using OWP-RP.

Proceeds to the Detector Current Comparator Drawer and BOP places NI-42 Rod Stop Bypass switch to BYPASS

• Reports completion of task to the SRO.

Failure of RCS Median TAVE will cause an improper response of the PRESSURIZER AUTOMATIC LEVEL Procedure Note:

CONTROL and AUTOMATIC STEAM DUMP CONTROL systems.

• IF RCS MEDIAN Tavg is failed THEN PERFORM the following: (NO) o ENSURE Charging FK-122.1 charging flow OATC 1CS-231 is in manual and CONTROL (N/A) charging to maintain pressurizer level.

o ENSURE steam dumps are in Steam (N/A)

Pressure Mode using OP-126, section 5.3.

Harris 2020 NRC Exam Scenario 2 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 2 Page 21 of 81 Event

Description:

PRNIS Channel NI-42 fails HIGH (AOP-001)

Time Position Applicants Actions or Behavior

2. MANUALLY OPERATE affected control bank to restore the following:

• EQUILIBRIUM power and temperature conditions OATC

• RODS above the insertion limits of Tech Spec 3.1.3.6 and PLP-106, Technical Specification Equipment List Program and Core Operating Limits Report.

• Withdraws Control Bank D to restore Tave with Tref.

• Directs RO to maintain TAVG within 5°F of Tref per OMM-001 attachment 11.

SRO Evaluator Note: The following will be done when Tave is restored.

3. VERIFY proper operation of the following:

• CVCS demineralizers (YES)

OATC

• BTRS (N/A)

• REACTOR Makeup Control System (YES)

4. CHECK that this section was entered due to control SRO (NO) banks MOVING OUT.

6. CHECK that NEITHER of the following OCCURRED:

SRO (NO)

• Unexplained RCS Boration (NO)

• Unplanned RCS dilution Harris 2020 NRC Exam Scenario 2 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 2 Page 22 of 81 Event

Description:

PRNIS Channel NI-42 fails HIGH (AOP-001)

Time Position Applicants Actions or Behavior Failure of RCS Median TAVE will cause an improper response of the PRESSURIZER AUTOMATIC LEVEL Procedure Note:

CONTROL and AUTOMATIC STEAM DUMP CONTROL systems.

7. CHECK that spurious rod motion is due to (NO) malfunction of the Automatic Rod Control System.

SRO NO - RNO GO TO Step 9.

SRO 9. EXIT this procedure.

SRO Exits AOP-001 OWP-SRO Refer to OWP-RP-24 to remove channel from service.

RP-24

• Direct operator and I&C to perform OWP-RP-24

• Completes an Emergent Issue Checklists for the failure SRO of NI-42.

• Contacts WCC for assistance (WR, LCOTR and Maintenance support)

Acknowledge request and reports from SRO.

Simulator IF asked to report to MCR to perform OWP-RP-24 state that Communicator:

you will report as soon as possible.

It is not required to implement the OWP prior to continuing Simulator Operator:

with the scenario.

Any Tech Spec evaluation may be completed with a Evaluator Note:

follow-up question after the scenario.

Harris 2020 NRC Exam Scenario 2 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 2 Page 23 of 81 Event

Description:

PRNIS Channel NI-42 fails HIGH (AOP-001)

Time Position Applicants Actions or Behavior Enters Instrumentation TS 3.3.1 Functional Unit 2, and 3 ACTION 2 - With the number of OPERABLE channels one less than the Total Number of Channels.

STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:

a. The inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

b. The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing of other channels per Specification 4.3.1.1. and

c. Either, THERMAL POWER is restricted to less than or equal to 75% of RATED THERMAL POWER and the Power Range Neutron Flux Trip Setpoint is SRO reduced to less than or equal to 85% of RATED THERMAL POWER within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; or,. the QUADRANT POWER TILT RATIO is monitored at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> per Specification 4.2.4.2 Reference the below T.S. but it will not apply for this conditions because 3 instruments is the Minimum Number required 3.3.1 Functional Unit 19 b, c, and d.

ACTION 7 - With less than the Minimum Number of Channels OPERABLE, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> determine by observation of the associated permissive annunciator window(s) that the interlock is in its required state for the existing plant condition, or apply Specification 3.0.3.

When Tavg is restored and AOP-001 exited, cue Simulator Operator to insert Trigger 3 Evaluators Note:

Event 3: Pressurizer Level Transmitter for LT-460 fails low Harris 2020 NRC Exam Scenario 2 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 3 Page 24 of 81 Event

Description:

Pressurizer Level Transmitter for LT-460 fails low Time Position Applicants Actions or Behavior On cue from the Lead Evaluator actuate Trigger 3 Simulator Operator:

Pressurizer Level Transmitter for LT-460 fails low

• ALB-009-4-3, PRESSURIZER LOW LEVEL LTDN SECURED AND HTRS OFF Indications Available:

• LI-460, Pressurizer Level Indication

• FI-150.1, Letdown Flow Indication Responds to ALB-009-4-3 or indication of a failed Pressurizer RO Level Channel on LI-460.

APP-SRO Enters APP-ALB-009-4-3 ALB-009 Operator may use AD-OP-ALL-1000 guidance to take manual Evaluator Note: control of charging to avoid a trip or transient prior to the SRO direction.

1. CONFIRM alarm using:

a. Pressurizer level LI-459A1, LI-460, LI-461.1 (LI-460 RO low)

b. Letdown flow FI-150.1

2. VERIFY Automatic Functions:

RO a. All pressurizer heaters off

b. Letdown isolated

• Directs RO to maintain controlling band +/- 5% of reference level per OMM-001 attachment 11.

SRO Harris 2020 NRC Exam Scenario 2 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 3 Page 25 of 81 Event

Description:

Pressurizer Level Transmitter for LT-460 fails low Time Position Applicants Actions or Behavior

3. PERFORM Corrective Actions:

a. IF PRZ level is low, THEN VERIFY letdown is (YES) isolated AND heaters are off.

b. IF RCS leakage is indicated, THEN GO TO AOP- (NO) 016, Excessive Primary Plant Leakage.

c. IF alarm is due to malfunction of level control (NO) system, THEN MANUALLY RESTORE normal level. (LT-459 is controlling channel for PZR level)

d. IF the alarm is due to a failed level instrument (YES)

RO (1) USING the Pressurizer Level Controller Selector switch, THEN SELECT a position which places the two operable channels into service. (Select channels 459/461)

(2) VERIFY the failed channel is not selected, at the MCB recorder panel.

(3) RESET the control heaters by placing the control switch to OFF and then back to ON.

(4) IF maintenance is to be performed, THEN REFER TO OWP-RP, Reactor Protection.

RO SELECT 459/461 on Pressurizer Level Controller Selector OWP-SRO Refer to OWP-RP-03 to remove channel from service.

RP-03

• Direct operator and I&C to perform OWP-RP-03

• Completes an Emergent Issue Checklists for the failure SRO of LT-460.

• Contacts WCC for assistance (WR, LCOTR and Maintenance support)

Acknowledge request and reports from SRO.

Simulator IF asked to report to MCR to perform OWP-RP-03 state that Communicator:

you will report as soon as possible.

It is not required to implement the OWP prior to continuing Simulator Operator:

with the scenario.

Harris 2020 NRC Exam Scenario 2 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 3 Page 26 of 81 Event

Description:

Pressurizer Level Transmitter for LT-460 fails low Time Position Applicants Actions or Behavior Any Tech Spec evaluation may be completed with a Evaluator Note:

follow-up question after the scenario.

Enters Instrumentation TS 3.3.1 Functional Unit 11 ACTION 6 - With the number of OPERABLE channels one less than the Total Number of Channels.

STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:

SRO

a. The inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

b. The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing of other channels per Specification 4.3.1.1.

• Completes an Emergent Issue Checklists for the failure of LI-460.

SRO

• Contacts WCC for assistance (WR, LCOTR and Maintenance support)

Simulator Acknowledge request.

Communicator Once the crew has taken manual control of Charging FCV-122 and selects an alternate controlling Pressurizer channel normal letdown flow may be restored.

IF desired to observe the restoration of normal letdown the actions have been listed on pages 27-31.

Evaluators Note: IF desired to have normal letdown remain isolated continue to page 32 and cue Simulator Operator to insert Trigger 4 Event 4: DEH pump shaft shear and failure of the standby pump to start Harris 2020 NRC Exam Scenario 2 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 3 Page 27 of 81 Restore letdown IAW OP-107, Chemical and Volume Control Event

Description:

System Time Position Applicants Actions or Behavior OP-107 OP-107, Section 5.4 Verifies Initial Conditions:

1. Charging flow has been established per Section 5.3. (YES)

2. Pressurizer level is greater than 17%. (YES)

RO 3. The following valves are shut:

(YES) o 1CS-7, 45 GPM Letdown Orifice A o 1CS-8, 60 GPM Letdown Orifice B o 1CS-9, 60 GPM Letdown Orifice C If Charging flow was stopped or greatly reduced prior to letdown being secured, there is a possibility that the Letdown Procedure Caution: line contains voids due to insufficient cooling. This is a precursor to water hammer, and should be evaluated prior to initiating letdown flow.

1. VERIFY 1CC-337, TK-144 LTDN TEMPERATURE, controller is:

• In AUTO AND RO

• Set for 110 to 120F (4.0 to 4.7 on potentiometer) normal operation OR

• Set for 90 to 120F (2.67 to 4.7 on potentiometer) if operating per Section 8.11 PK-145.1 LTDN PRESSURE, 1CS-38, may have to be Procedure Note:

adjusted to control at lower pressures.

2. VERIFY 1CS-38 Controller, PK-145.1 LTDN PRESSURE:

RO

• in MAN

• output set at 50%

3. VERIFY open the following Letdown Isolation Valves:

• 1CS-2, LETDOWN ISOLATION LCV-459 Harris 2020 NRC Exam Scenario 2 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 3 Page 28 of 81 Restore letdown IAW OP-107, Chemical and Volume Control Event

Description:

System Time Position Applicants Actions or Behavior

• 1CS-1, LETDOWN ISOLATION LCV-460 RO 4. VERIFY open 1CS-11, LETDOWN ISOLATION.

The following table gives the minimum charging flow required to keep the regenerative heat exchanger temperature below the high temperature alarm when letdown is established:

Procedure Note:

If Pressurizer level is above the programmed level setpoint, charging flow should be adjusted to a point above the minimum required to prevent regenerative heat exchanger high temperature alarm but low enough to reduce pressurizer level.

5. ADJUST controller 1CS-231, FK-122.1 CHARGING FLOW, as required to:

RO

• Maintain normal pressurizer level program.

• Keep regenerative heat exchanger temperature below the high temperature alarm when the desired letdown orifice is placed in service.

If CVCS Demins have cooled from normal operating temperature, an increased reactivity affect may be observed.

Consideration may be given to increasing CVCS Demins to Procedure Note: operating temperature by flushing them to the RHT prior to restoring letdown. TIS-250, Recycle evaporator Feed Demineralizer Temperature Switch, can be used to determine temperature during flushing to the RHT.

Harris 2020 NRC Exam Scenario 2 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 3 Page 29 of 81 Restore letdown IAW OP-107, Chemical and Volume Control Event

Description:

System Time Position Applicants Actions or Behavior

6. IF flushing CVCS Demins to the RHT is desired for increasing temperature, THEN PERFORM the following:

RO a. NOTIFY Radwaste Control Room that letdown (N/A) flow will be diverted to the RHT.

b. PLACE 1CS-120, LETDOWN TO VCT/HOLDUP TANK LCV-115A to the RHT position.

Changes in Letdown flowrate will affect the displayed value for Procedure Note: RM-3502A (Channel 2303) due to the detector's proximity to the LTDN line.

7. OPEN an Orifice Isolation Valve (1CS-7, 1CS-8, 1CS-9) for the orifice to be placed in service.

RO 8. ADJUST 1CS-38 position by adjusting PK-145.1 output as necessary to control LP LTDN Pressure (PI-145.1) at 340 to 360 psig, to prevent lifting the LP Letdown Relief.

9. WHEN Letdown pressure has stabilized at 340 to 360 psig on PI-145.1, LP LTDN PRESS, THEN PERFORM the following:

RO a. ADJUST PK-145.1 LTDN PRESSURE setpoint to 58%.

b. PLACE the controller in AUTO.

10. VERIFY PK-145.1 LTDN PRESSURE Controller maintains Letdown pressure stable at 340 to 360 psig.

11. IF Step 5.4.2.6 was performed AND CVCS Demin temperature is at normal operating temperature, THEN PERFORM the following:

RO a. PLACE 1CS-120, LETDOWN TO VCT/HOLDUP (N/A)

TANK LCV-115A to the AUTO position.

b. NOTIFY Radwaste Control Room that diversion to the RHT has been terminated.

Harris 2020 NRC Exam Scenario 2 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 3 Page 30 of 81 Restore letdown IAW OP-107, Chemical and Volume Control Event

Description:

System Time Position Applicants Actions or Behavior Changes in Letdown flowrate will affect the displayed value for Procedure Note: RM-3502A (Channel 2303) due to the detector's proximity to the LTDN line.

12. OPEN additional orifice isolation valves (1CS-7, 1CS-8, 1CS-9) as required.

RO 13. ADJUST charging flow as necessary to:

• Prevent high temperature alarm (per table above)

• Maintain pressurizer programmed level.

Placing LK-459F in AUTO may take several minutes due to Evaluator Note:

matching PRZ level to reference level.

14. PLACE PRZ level controller, LK-459F, in AUTO, as follows:

a. PLACE PRZ level controller, LK-459F, in MAN to cancel any integrated signal.

b. Record FI-112A.1, Charging flow.

c. Determine PRZ level controller , LK-459F setpoint by using the table below:

RO

d. ADJUST PRZ level controller, LK-459F, to the calculated setpoint.

e. Place PRZ level controller, LK-459F, in AUTO Harris 2020 NRC Exam Scenario 2 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 3 Page 31 of 81 Restore letdown IAW OP-107, Chemical and Volume Control Event

Description:

System Time Position Applicants Actions or Behavior

15. WHEN the following occurs:

• Program pressurizer level is matching the current pressurizer level AND RO

• Letdown and seal return are balanced with seal injection flow and charging flow.

THEN place controller 1CS-231, FK-122.1 CHARGING FLOW, in AUTO.

16. COMPLETE Section 5.4.3. (Position Verification)

After the actions to restore Normal Letdown are complete, cue Simulator Operator to insert Trigger 4 Lead Evaluator:

Event 4: DEH pump shaft shear and failure of the standby pump to start Harris 2020 NRC Exam Scenario 2 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 4 Page 32 of 81 Event

Description:

DEH pump shaft shear and failure of the standby pump to start Time Position Applicants Actions or Behavior On cue from the Lead Evaluator actuate Trigger 4 Simulator Operator: DEH pump shaft shear and failure of the standby pump to start Due to the slow nature of the EHC system depressurizing (approximately 5-6 minutes) and only one MCB indication Evaluator Note:

for pressure the crew may not notice a pressure reduction until the annunciator for EH fluid low pressure alarms Available

• ALB-020-4-2B, EH FLUID LOW PRESS Indications:

• PI-4221 lowering trend Responds to ALB-20-4-2B or indication of degrading EHC BOP pressure on PI-4221 ALB-020 BOP Enters APP-ALB-020-4-2B BOP 1. CONFIRM alarm using

a. PI-4221, DEH Fluid Pressure indication

b. PI-4220A and PI-4220B, Local DEH Pump discharge pressure indicators BOP 2. VERIFY Automatic Functions:

a. Standby DEH Pump starts at 1500 psig, as (NO) sensed by PS-01TA-4223V The BOP may immediately start the standby pump or wait until after reading the APP and the report from the AO. IF Evaluator Note:

pressure is allowed to continue to lower when pressure reaches 1150 psig the Main Turbine will trip.

Harris 2020 NRC Exam Scenario 2 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 4 Page 33 of 81 Event

Description:

DEH pump shaft shear and failure of the standby pump to start Time Position Applicants Actions or Behavior Starts EHC Pump B and observes pressure returning to normal on PI-4221.

Critical BOP Critical to start the standby DEH Pump prior to DEH pressure Task #1 lowering below 1150 psig to prevent an automatic Turbine Trip/Reactor trip.

(ALB-018 window 3-4, Turbine Trip Auto Stop Oil Trip)

BOP 3. PERFORM Corrective Actions:

a. IF the Reactor is tripped, THEN GO TO EOP- (NO)

E-0.

b. START the standby DEH Pump.

o Manually starts standby DEH Pump (NO)

c. IF EH fluid pressure drops to 1500 psig, THEN (NO)

INITIATE a rapid plant shutdown using AOP-038, Rapid Downpower, while continuing with this procedure.

d. DISPATCH an operator to perform the following:

(1) MONITOR DEH Pump and PCV operation.

(2) VERIFY OPEN the following:

(a) 1EH-1, A EH Pump Suction Vlv BOP (b) 1EH-8, B EH Pump Suction Vlv (c) 1EH-31, Main Hdr Press Switch Isol Vlv (NO)

(3) INVESTIGATE system for leaks.

(4) IF a leak is found, THEN ISOLATE the leak AND IMMEDIATELY NOTIFY Control Room.

Dispatches AO to investigate failure of EHC Pump A.

When dispatched to investigate, report the A EHC Pump Simulator shaft is sheared and not producing any discharge Communicator:

pressure.

• Completes an Emergent Issue Checklists for the failure of DEH Pump A.

SRO

• Contacts WCC for assistance (WR, and Maintenance support)

Harris 2020 NRC Exam Scenario 2 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 4 Page 34 of 81 Event

Description:

DEH pump shaft shear and failure of the standby pump to start Time Position Applicants Actions or Behavior After the crew has restored DEH header pressure, cue Simulator Operator to insert Trigger 5 Lead Evaluator:

Event 5: 'B' SG Controlling Level Transmitter fails Low (AOP-010)

Harris 2020 NRC Exam Scenario 2 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 5 Page 35 of 81 Event

Description:

SG 'B' Controlling Level Transmitter fails Low (AOP-010)

Time Position Applicants Actions or Behavior On cue from the Lead Evaluator actuate Trigger 5 Simulator Operator:

SG 'B' Controlling Level Transmitter fails Low (AOP-010)

• ALB-014-2-1B, SG B NR LVL/SP HI/LO DEV

• ALB-014-5-1A, SG B FW > STM FLOW MISMATCH Indications Available:

• ALB-014-5-4B, STEAM GEN B LOW-LOW LVL

• SG B levels rising BOP RESPONDS to alarms and ENTERS AOP-010 AOP-010 Feedwater Malfunctions ENTERS and directs actions of AOP-010 SRO Conducts a Crew Update Makes PA announcement for AOP entry Procedure Note: Steps 1 through 4 are immediate actions.

1. CHECK Feedwater Regulator valves operating properly.

(NO)

RNO

1. PERFORM the following:

• PLACE affected Feedwater Regulator valve(s) in MANUAL.

Places SG B Feedwater Reg valve in MANUAL Critical

• MAINTAIN Steam Generator level(s) between Task # 2 BOP 52 and 62%.

Immediate Action Checks SG level and operates manual controller to maintain level between 52%-62%.

Critical Task: Maintain control of SG B level below 78% to prevent an automatic Turbine Trip/Reactor trip after the controlling level transmitter LT-486 fails low.

• IF Steam Generator level(s) cannot be controlled, THEN TRIP the Reactor AND GO TO EOP-E-0. (Should be controlled)

Harris 2020 NRC Exam Scenario 2 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 5 Page 36 of 81 Event

Description:

SG 'B' Controlling Level Transmitter fails Low (AOP-010)

Time Position Applicants Actions or Behavior

2. CHECK ANY Main Feedwater Pump TRIPPED (NO)

Immediate Action BOP RNO

2. GO TO STEP 6

6. MAINTAIN ALL of the following:

• At least ONE Main Feedwater Pump RUNNING BOP

• Main Feedwater flow to ALL Steam Generators

• ALL Steam Generator levels greater than 30%

Maintains all of the above

7. CHECK Feedwater Regulator Valves operating properly in AUTO: (NO not B)

• Response to SG levels (NO)

• Valve position indication

• Response to feed flow/steam flow mismatch RNO

7. PERFORM the following:

BOP a. IF automatic SG water level control can be (NO) restored by selecting out a failed instrument, THEN USE OP-134.01, Feedwater System, Section 8.10 to swap Steam Flow/Feed Flow Control and Recorder Channels and restore level control to automatic.

b. REFER to Tech Spec 3.3.1 AND IMPLEMENT OWP-RP or OWP-ESF where appropriate.

c. IF needed, THEN CONTROL feed flow to SGs using Main Feed Reg Valve Bypass FCVs. (NO)

• Directs BOP to maintain controlling band of 52% to 62%

per OMM-001 attachment 11.

SRO Inability to monitor one or more Safety System Parameters concurrent with a turbine runback of greater than 25%, requires Procedure Note:

a change of event classification per the HNP Emergency Plan.

[C.2, C.3].

Harris 2020 NRC Exam Scenario 2 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 5 Page 37 of 81 Event

Description:

SG 'B' Controlling Level Transmitter fails Low (AOP-010)

Time Position Applicants Actions or Behavior

8. CHECK turbine runs back less than 25% turbine BOP (YES) load A feedwater train consists of a Condensate Pump, Condensate Procedure Note:

Booster Pump and Main Feedwater Pump.

9. GO TO the applicable section:

SRO EVENT: All Condensate/Feedwater flow malfunctions (other than pump trips) Section 3.1 Page 10

1. CHECK the following Recirc and Dump Valves operating properly in MODU:

• Main Feedwater Pumps (YES)

• Condensate Booster Pumps (YES)

BOP

• Condensate Pumps (YES)

• 1CE-293, Condensate Recirc (YES)

• 1CE-142, Condensate Dump To CST Isolation (YES)

Valve (SLB-4/7-1)

BOP 2. CHECK the Condensate and Feedwater System INTACT.

Pumps should be stopped in the order of higher to lower pressure. (To stop a Condensate Pump, stop a Main Procedure Note:

Feedwater Pump followed by a Condensate Booster Pump and then the Condensate Pump.)

BOP 3. CHECK pumps for NORMAL OPERATION. (YES)

4. NOTIFY Load Dispatcher of ANY load limitations.

SRO (No load limitations so Dispatcher will not be called)

5. CHECK Reactor thermal power changed by less SRO (YES) than 15% in any one hour period.

Harris 2020 NRC Exam Scenario 2 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 5 Page 38 of 81 Event

Description:

SG 'B' Controlling Level Transmitter fails Low (AOP-010)

Time Position Applicants Actions or Behavior SRO EXIT this procedure.

OWP-SRO Refer to OWP-RP-06 to remove channel from service.

RP-06 Contacts WCC for support, requests WR and LCOTR.

SRO Contacts I&C to have channel removed from service.

Simulator Respond to crew requests.

Communicator:

Any Tech Spec evaluation may be completed with a Evaluator Note:

follow-up question after the scenario.

Harris 2020 NRC Exam Scenario 2 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 5 Page 39 of 81 Event

Description:

SG 'B' Controlling Level Transmitter fails Low (AOP-010)

Time Position Applicants Actions or Behavior Enters Instrumentation TS 3.3.1 Functional Unit 13 and 14 ACTION 6 - With the number of OPERABLE channels one less than the Total Number of Channels.

STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:

a. The inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

b. The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing of other channels per Specification 4.3.1.1.

SRO 3.3.2 Functional Unit 5 and 6 ACTION 19 - With the number of OPERABLE channels one less than the Total Number of Channels, operation may proceed provided the following conditions are satisfied :

a. The inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and

b. The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing of other channels per Specification 4.3.2.1.

Channel does NOT have to be removed from service using the OWP to continue the scenario. Once after SG level is under control and the TS has been identified, cue Evaluator Note: Simulator Operator to insert Trigger 6 Event 6: Steam line Break on 'B' SG inside Containment (EOP-E-0 and EOP-E-2)

Harris 2020 NRC Exam Scenario 2 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 6 Page 40 of 81 Event

Description:

Steam line Break on B SG inside Containment (EOP-E-0 and EOP-E-2)

Time Position Applicants Actions or Behavior On cue from the Lead Evaluator actuate Trigger 6 Simulator Operator: Steam line Break on B SG inside Containment (EOP-E-0 and EOP-E-2)

The crew should identify the leak. The crew will enter E-0 and perform the immediate actions. The SRO may also direct a manual Steam Line Isolation. The crew should diagnose that a LOCA is NOT in progress and transition from E-0 to E-2, Faulted Steam Generator Isolation.

• When SG B pressure is < 100 psi of A and C SG (with MSLI) an AFW isolation signal will close the B MD and TD AFW valves.

• When Containment pressure > 3 psig the crew should Evaluator Note: identify Adverse Containment conditions are required to be implemented.

• When 1SI-4 is closed from the MCB it will fail to close requiring the RAB Aux Operator to locally close the valve

• When Containment pressure exceeds 10 psig B CT Pump should start but will NOT autostart. It must be manually started and aligned for spray.

• ALB-028-5-1 CONTAINMENT AIR HIGH VACUUM will clear (if in due to earlier ESW Pump start)

• ALB-028-8-5 COMPUTER ALARM VENTILATION SYSTEM

• Rising pressure in Containment Indications Available

• Rising temperature in Containment

• Rising SG steam flow

• Tavg lowers

• PRZ level and pressure lower

• Power rises The crew may go to AOP-042. They will not have time to make progress before requiring a trip.

Evaluator Note:

Depending on how timing the crew may or may not actuate a Manual Reactor trip based on conditions that will exceed an ESF actuation setpoint Harris 2020 NRC Exam Scenario 2 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 6 Page 41 of 81 Event

Description:

Steam line Break on B SG inside Containment (EOP-E-0)

Time Position Applicants Actions or Behavior (Time permitting - an auto Reactor Trip may occur prior to RO announcement)

Informs SRO then actuates a Manual Reactor Trip Directs manual Reactor Trip and Ensure Safety Injection SRO activation EOP-E-0 Reactor Trip Or Safety Injection Enters EOP-E-0 SRO Makes plant PA announcement Conducts a Crew Update

1. Ensure Reactor Trip.

(YES)

Immediate Action RO

2. Check Turbine is Tripped - All throttle valves shut (YES)

Immediate Action BOP Harris 2020 NRC Exam Scenario 2 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 6 Page 42 of 81 Event

Description:

Steam line Break on B SG inside Containment (EOP-E-0)

Time Position Applicants Actions or Behavior

3. Perform The Following:

Immediate a. AC emergency buses AT LEAST ONE (YES)

Action BOP ENERGIZED

b. AC emergency buses - BOTH energized (YES)

4. Safety Injection ACTUATED (BOTH TRAINS) (YES)

Immediate Action RO

5. Perform The Following:

a. Review Foldout page and assign foldout.

RCP Trip criteria SRO Alternate Miniflow Open/Shut criteria RHR restart criteria Ruptured SG AFW Isolation criteria AFW supply switchover criteria Harris 2020 NRC Exam Scenario 2 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 6 Page 43 of 81 Event

Description:

Steam line Break on B SG inside Containment (EOP-E-0)

Time Position Applicants Actions or Behavior E-0 Foldout Evaluator Aide:

SRO b. Evaluate EAL Matrix.

Identifies Containment Adverse Conditions CREW Containment Pressure > 3 psig

6. Ensure CSIPs - ALL RUNNING (YES)

RO A and B running

7. Ensure RHR Pumps - ALL RUNNING (YES)

RO A and B running RO 8. Safety Injection flow > 200 gpm (YES)

Harris 2020 NRC Exam Scenario 2 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 6 Page 44 of 81 Event

Description:

Steam line Break on B SG inside Containment (EOP-E-0)

Time Position Applicants Actions or Behavior

9. RCS pressure LESS than 230 PSIG SRO (NO)

RNO

9. GO to Step 12

12. Main Steam Line Isolation - ACTUATED (YES)

BOP BOP 13. Ensure All MSIVs AND Bypass Valves - SHUT (YES)

14. Any SG pressure - 100 PSIG LOWER THAN (YES)

BOP PRESSURE IN TWO OTHER SGs

15. Ensure MDAFW AND TDAFW Isolation Valves AND Flow Control Valves To Affected SG - (YES)

SHUT Both MDAFW and TDAFW isolation valve and FCV to the B SG BOP

• 1AF-93 (SHUT)

(SHUT)

• 1AF-143 (SHUT)

• FCV-2071 B (1AF-130)

(SHUT)

• FCV-2051B (1AF-51)

Harris 2020 NRC Exam Scenario 2 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 7 Page 45 of 81 Failure of B Train Containment Spray Pump to actuate Event

Description:

(EOP-E-0)

Time Position Applicants Actions or Behavior

16. Check CNMT Pressure - HAS REMAINED LESS THAN 10 PSIG (YES/NO time dependent when YES)

RNO BOP

16. Perform the following:

(NO) a) Ensure Containment Spray - ACTUATED Identifies that the B Containment Spray pump has not started and attempts to actuate Containment Spray using the MCB Containment Spray switches (2 per train) - Pump does not start Manually starts B Containment Spray pump and aligns spray valves Opens 1CT-11 and 1CT-88 Harris 2020 NRC Exam Scenario 2 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 6 Page 46 of 81 Event

Description:

Steam line Break on B SG inside Containment (EOP-E-0)

Time Position Applicants Actions or Behavior

16. Check CNMT Pressure - HAS REMAINED LESS THAN 10 PSIG (YES/NO time dependent when YES)

Start time: Time ALB-001-5-1, Containment Isolation Phase B, received at ______________

RNO Critical 16. Perform the following:

Task #3 RO b) Stop ALL RCPs Locates MCB switches and STOPS ALL 3 RCPs Time ALL RCPs secured: ______________

Total time: _____________

Critical to have all RCPs secured in < 10 Minutes

17. Ensure AFW flow - AT LEAST 200 KPPH (YES)

BOP ESTABLISHED

18. Sequencer Load Block 9 (Manual Loading (YES)

BOP Permissive) ACTUATED (BOTH TRAINS)

BOP 19. Energize AC buses 1A1 AND 1B1 Evaluator Note: E-0, Attachment 3 is located on page 67.

The RO will perform all board actions until the BOP completes Attachment 3. The BOP is permitted to properly align plant equipment IAW E-0 Attachment 3 Evaluator Note: without SRO approval.

The Scenario Guide still identifies tasks by board position because the time frame for completion of Attachment 3 is not predictable.

Harris 2020 NRC Exam Scenario 2 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 6 Page 47 of 81 Event

Description:

Steam line Break on B SG inside Containment (EOP-E-0)

Time Position Applicants Actions or Behavior

20. Ensure Alignment Of Components From Actuation Of BOP ESFAS Signals Using Attachment 3, "Safeguards Actuation Verification", While Continuing With This Procedure.

Directs AO to place 1A and 1B Air Compressor in the local BOP control mode per E-0 Attachment 3 step 22 Acknowledge the request to place 1A and 1B Air Simulator Compressor in the local control mode per Communicator E-0 Attachment 3 step 22 When directed to place the 1A and 1B Air Compressor in Simulator Operator the local control mode: Run APP\air\acs_to_local When the APP for 1A and 1B Air Compressor has Simulator completed running call the MCR and inform them that the Communicator air compressors are running in local control.

Directs AO to Unlock AND Turn ON The Breakers For The BOP CSIP Suction AND Discharge CrossConnect Valves per E-0 Attachment 3 step 23 (or from step 11 - refer to Attachment 2)

Acknowledge the request to Unlock AND Turn ON The Simulator Breakers For The CSIP Suction AND Discharge Cross Communicator Connect Valves When directed to Unlock AND Turn ON The Breakers for Simulator Operator the CSIP Suction AND Discharge CrossConnect Valves:

Run APP\cvc\E-0 Att 2 CSIP suct & disch valve power.txt.

When the APP for CSIP Suction AND Discharge Cross Simulator Connect Valves has completed running call the MCR and Communicator inform them that CSIP Suction AND Discharge Cross Connect Valves are energized.

RCPs are secured therefore WR CL temperatures should be used when checking RCS temperature. RCS temp trend Examiners Note:

will be < 557°F and dropping - control FF, maintain total FF > 200 KPPH until SG level > 40% (all MSIVs are shut)

Harris 2020 NRC Exam Scenario 2 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 6 Page 48 of 81 Event

Description:

Steam line Break on B SG inside Containment (EOP-E-0)

Time Position Applicants Actions or Behavior

21. Stabilize AND Maintain Temperature Between 555°F AND RO 559°F Using Table 1.

RO Harris 2020 NRC Exam Scenario 2 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 6 Page 49 of 81 Event

Description:

Steam line Break on B SG inside Containment (EOP-E-2)

Time Position Applicants Actions or Behavior

22. PRZ PORVs - SHUT (YES)

RO 23. PRZ Spray Valves - SHUT (RCPs are secured) (YES)

24. PRZ PORV Block Valves - AT LEAST ONE OPEN (YES)

25. Any SG pressure - DROPPING IN AN UNCONTROLLED MANNER OR COMPLETELY (YES)

SRO DEPRESSURIZED (B SG)

26. GO TO E-2, "FAULTED STEAM GENERATOR ISOLATION", Step 1.

EOP-E-2 Faulted Steam Generator Isolation Enters EOP-E-2 Conducts a Crew Update

• At least one SG must be maintained available for RCS cooldown.

Procedure Caution:

• Any faulted SG OR secondary break should remain isolated during subsequent recovery actions unless needed for RCS cooldown.

SRO 1. Initiate Monitoring Of Critical Safety Function Status Trees.

2. Verify All MSIVs - SHUT (YES)

BOP

3. Verify All MSIV bypass valves - SHUT (YES)

4. Check Any SG pressure - STABLE OR RISING (YES)

BOP (NOT FAULTED) (A and C SG)

5. Any SG pressure - DROPPING IN AN UNCONTROLLED MANNER (YES)

BOP OR COMPLETELY DEPRESSURIZED (B SG)

Harris 2020 NRC Exam Scenario 2 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 6 Page 50 of 81 Event

Description:

Steam line Break on B SG inside Containment (EOP-E-2)

Time Position Applicants Actions or Behavior IF the TDAFW pump is the only available source of feed flow, Procedure Caution: THEN maintain steam supply to the TDAFW pump from one SG.

6. Isolate Faulted SG(s) (Identified In Step 5):

• Verify faulted SG(s) PORV - SHUT (YES)

BOP

• Verify main FW isolation valves - SHUT (YES)

(Automatically)

• Ensure MDAFW AND TDAFW pump isolation valves to faulted SG(s) - SHUT

• 1AF-93 (SHUT)

BOP

• 1AF-143 (SHUT)

(YES / NO time dependent - may have identified and isolated these valves in E-0)

• Shut faulted SG(s) steam supply valve to TDAFW pump - SHUT (SHUT)

BOP Shuts 1MS-70

• Ensure main steam drain isolation(s) before (YES)

MSIVs - SHUT:

BOP Harris 2020 NRC Exam Scenario 2 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 6 Page 51 of 81 Event

Description:

Steam line Break on B SG inside Containment (EOP-E-2)

Time Position Applicants Actions or Behavior

• Ensure SG blowdown isolation valves - SHUT BOP (YES)

(YES)

(YES)

• Ensure main steam analyzer isolation valves -

(YES)

BOP SHUT Check CST Level - GREATER THAN (YES) 10%

A SG may be suspected to be ruptured if it fails to dry out Procedure Note: following isolation of feed flow. Local checks for radiation can be used to confirm primary-to-secondary leakage.

8. Any SG - ABNORMAL RADIATION OR UNCONTROLLED LEVEL RISE (NO)

CREW RNO Go to Step 10 Harris 2020 NRC Exam Scenario 2 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 6 Page 52 of 81 Event

Description:

Steam line Break on B SG inside Containment (EOP-E-2)

Time Position Applicants Actions or Behavior

10. Check If SI Has Been Terminated:

a. Check for all of the following:

o Check BIT outlet valves - SHUT OR ISOLATED RO 1SI-3 (OPEN)

(NO) 1SI-4 (OPEN)

(NO)

RNO Go to step 13

13. Check SI Termination Criteria:

BOP a. Check Subcooling - > 40°F (YES)

b. Level in at least one SG > 40% (YES)

c. RCS pressure - STABLE OR RISING (YES)

RO d. PRZ level - > 30% (YES / NO - time dependent action)

PRZ level > 30%

IF YES then crew will continue with E-2 below Evaluator Note:

IF NO then crew will transition to E the actions for E-1 follow E-2 (included later in guide)

E-2 RO 14. Reset SI Continues

15. Manually Realign Safeguards Equipment Following A Loss Crew Of Offsite Power. (There is no loss of power - N/A)

16. Resets Phase A AND Phase B Isolation Signals.

RO (both were actuated)

Harris 2020 NRC Exam Scenario 2 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 6 Page 53 of 81 Event

Description:

Steam line Break on B SG inside Containment (EOP-E-2)

Time Position Applicants Actions or Behavior

17. Open Instrument Air AND Nitrogen Valves to Containment:

RO Locates and OPENS both valves

18. Stop all but ONE CSIP (STOPS A / B CSIP)

RO

19. RCS pressure - STABLE OR RISING (YES)

20. Check CSIP suction - ALIGNED TO RWST (YES)

RO

21. Open Normal Miniflow Isolation Valves:

RO Locates controls and OPENS each valve Harris 2020 NRC Exam Scenario 2 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 8 Page 54 of 81 Event

Description:

Failure of BIT outlet isolation valve 1SI-4 to close (EOP-E-2)

Time Position Applicants Actions or Behavior Event 8 - Failure of 1SI-4 to close

22. Shut BIT Outlet Valves:

Shuts 1SI-3 from MCB switch Attempts to shut 1SI-4 will not SHUT from MCB switch Critical RO Task #4 Dispatches RAB Aux Operator to locally shut 1SI-4 (may also request that the breaker for the valve OPEN)

Critical Task to shut BIT Outlet valve 1SI-4 prior to establishing flow through the charging header or CSIP run out conditions will occur as indicated by oscillating discharge pressure.

IF this valve has not been previously shut then:

Acknowledge request to locally shut 1SI-4 (A-230-FX32-Simulator W3-S2) AND if requested acknowledge request to OPEN Communicator: breaker prior to locally valve operation.

Report back approximately 1 minute after Simulator Operator completes actions below that 1SI-4 is SHUT.

Perform the following actions from Sim Diagram SIS02 to operate 1SI-4:

Simulator Operator - (IF requested) OPEN control power rf sis016 Engage handwheel rf sis017 Shut valve modify rf sis018

23. Verify Cold Leg AND Hot Leg Injection Valves -

SHUT (YES)

RO Harris 2020 NRC Exam Scenario 2 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 6 Page 55 of 81 Event

Description:

Steam line Break on B SG inside Containment (EOP-E-2)

Time Position Applicants Actions or Behavior Procedure Note: High head SI flow should be isolated before continuing.

26. Establish Charging Lineup:

a. Shut charging flow control valve:

(SHUT)

RO

b. Open charging line isolation valves:

(OPEN)

(OPEN)

27. Monitor RCS Hot Leg Temperature:

a. Check RCS hot leg temperature - STABLE (YES / NO RO

- time dependent - probably rising)

YES / NO - BOP action next step

b. IF YES - Manually dump steam AND control feed flow BOP to maintain RCS temperature stable.

a.1) IF NO - If temperature rising, THEN manually dump BOP steam from intact SG PORVs at maximum rate to stabilize temperature.

RCS temperature must be stabilized to allow evaluation of PRZ Procedure Note:

level trend.

a.2) IF NO - WHEN temperature stabilizes, THEN manually BOP dump steam AND control feed flow to maintain RCS temperature stable.

Charging flow should NOT exceed 150 GPM to prevent Procedure Caution:

damage to the regenerative heat exchanger.

Harris 2020 NRC Exam Scenario 2 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 6 Page 56 of 81 Event

Description:

Steam line Break on B SG inside Containment (EOP-E-1)

Time Position Applicants Actions or Behavior

28. Control Charging Flow To Maintain PRZ Level:

a. Control charging using charging flow control valve:

RO

b. Maintain charging flow less than 150 GPM

c. PRZ level - CAN BE MAINTAINED STABLE (YES)

RO OR RISING SRO 29. GO TO ES-1.1, "SI TERMINATION", step 1 IF the crew transitioned to EOP-E-1 based on PRZ level

< 30% then continue on next page.

Evaluator Note:

If PRZ level is > 30% then continue with EOP- ES-1.1, SI Termination step 1 (see page 60 in this guide)

EOP-E-1 Loss of Reactor or Secondary Coolant Procedure Note: Foldout applies Assigns Foldout items to RO and or BOP RO: RCP Trip criteria, RHR Restart criteria, Alternate Miniflow SRO Open/Shut criteria, Cold Leg Recirculation switchover criteria BOP: AFW supply switchover criteria, Secondary integrity criteria, E-3 transition criteria Harris 2020 NRC Exam Scenario 2 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 6 Page 57 of 81 Event

Description:

Steam line Break on B SG inside Containment (EOP-E-1)

Time Position Applicants Actions or Behavior Evaluator Aide: E-1 Foldout CREW 1. Initiate Monitoring Of Critical Safety Function Status Trees.

2. Maintain RCP Seal Injection Flow Between 8 GPM and RO 13 GPM.

Harris 2020 NRC Exam Scenario 2 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 6 Page 58 of 81 Event

Description:

Steam line Break on B SG inside Containment (EOP-E-1)

Time Position Applicants Actions or Behavior

3. Check Intact SG Levels:

a. Any level - GREATER THAN 40% (YES)

BOP

b. Control Feed Flow to maintain all intact levels between 40% - 50%

c. Any level - RISING IN AN UNCONTROLLED (NO)

BOP MANNER RO 4. Check PRZ PORV AND Block Valves:

a. Verify AC buses 1A1 AND 1B1 - ENERGIZED (YES)

RO b. Check PRZ PORVs - SHUT (YES)

f. Check block valves - AT LEAST ONE OPEN (YES)

5. Check SI Termination Criteria: (YES)

RO

a. RCS subcooling - >40°F

b. Level in at least one intact SG > 40% (YES)

BOP Total feed flow to intact SGs > 200 KPPH (YES)

d. PRZ level > 30% (YES / NO time dependent)

e. YES - GO TO ES-1.1, SI Termination, Step 1 (later in RO guide)

NO - Continue with E-1 actions below Harris 2020 NRC Exam Scenario 2 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 6 Page 59 of 81 Event

Description:

Steam line Break on B SG inside Containment (EOP-E-1)

Time Position Applicants Actions or Behavior

6. Check CNMT Spray Status:

a. Check any CNMT spray pump - RUNNING (YES)

E-1 Consult plant operations staff to determine if RO Continues CNMT spray should be placed in standby.

CNMT spray - TO BE PLACED IN STANDBY (When directed by plant operations staff)

9. Check Source Range Detector Status: (YES)

a. Intermediate range flux - LESS THAN 5x10-11 AMPS (YES)

RO

b. Verify source range detectors - ENERGIZED

c. Transfer nuclear recorder to source range scale.

10. Check RHR Pump Status:

a. Check RHR pump suction - ALIGNED TO RWST RO (YES)

(YES)

b. RCS Pressure - GREATER THAN 230 PSIG (YES)

RO c. RCS pressure - STABLE OR RISING (YES)

d. Stop RHR pumps (STOPS both RHR pumps)

Harris 2020 NRC Exam Scenario 2 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 6 Page 60 of 81 Event

Description:

Steam line Break on 'B' SG inside Containment (EOP-ES-1.1)

Time Position Applicants Actions or Behavior Check RCS And SG Pressures: (time dependent)

Check for both of the following:

All SG Pressures - STABLE OR RISING (YES / NO)

RO RCS pressure - STABLE OR DROPPING (YES / NO)

IF NO - the crew will return to step 1 and loop back to through the procedure. When they reach step 5 to check PRZ level they will have adequate level and transition to ES-1.1, SI Termination.

SI Termination is entered from either E-2 step 29 or E-1 Evaluator Note:

Step 5.e EOP-ES-1.1 SI Termination Procedure Note: Foldout Applies Assigns foldout action items to RO and or BOP

• Cold leg recirculation switchover criteria SRO

• RHR restart criteria

• Secondary integrity criteria

• AFW switchover criteria Harris 2020 NRC Exam Scenario 2 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 6 Page 61 of 81 Event

Description:

Steam line Break on 'B' SG inside Containment (EOP-ES-1.1)

Time Position Applicants Actions or Behavior Evaluator Aide: ES-1.1 Foldout SRO 1. Initiate Monitoring Of Critical Safety Function Status Trees.

2. Check If SI Has Been Terminated:

RO a. Check for all of the following:

• Check BIT outlet valves - SHUT OR ISOLATED

• 1SI-3 (YES / NO - shut in E-2 step 22 OR will be shut in ES-1.1 step 9.c - coming up)

• 1SI-4 (YES / NO - shut in E-2 step 22 OR will be shut in ES-1.1 step 9.c - coming up)

RO IF answer is NO then perform actions on following pages for NO response to reset SI If YES then do the following step and the actions then follow steps on page 66 of this guide after NO response ends.

• Check cold leg AND hot leg injection valves - SHUT (YES)

RO o 1SI-52 (YES) o 1SI-86 o 1SI-107 (YES)

Harris 2020 NRC Exam Scenario 2 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 6 Page 62 of 81 Event

Description:

Steam line Break on 'B' SG inside Containment (EOP-ES-1.1)

Time Position Applicants Actions or Behavior

3. Reset SI (DONE)

4. Manually realign Safeguards Equipment Following A Loss of Offsite Power (NO action required)\

5. Reset Phase A and Phase B Isolation Signals

6. Open IA and Nitrogen Valves to CNMT: (DONE)

(DONE)

7. Stop all but ONE CSIP (DONE)

8. Check RCS Pressure - STABLE OR RISING NO (YES)

RO 9. Isolate High Head SI Flow:

response

a. Check CSIP suction - aligned to RWST

b. Open normal miniflow isolation valves:

c. Shut BIT Outlet Valves:

Shuts 1SI-3 from MCB switch Attempts to shut 1SI-4 will not SHUT from MCB Critical switch Task #4 RO NO response Dispatches RAB Aux Operator to locally shut 1SI-4 (may also request that the breaker for the valve OPEN)

Critical Task to shut BIT Outlet valve 1SI-4 prior to establishing flow through the charging header or CSIP run out conditions will occur as indicated by oscillating discharge pressure.

Harris 2020 NRC Exam Scenario 2 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 6 Page 63 of 81 Event

Description:

Steam line Break on 'B' SG inside Containment (EOP-ES-1.1)

Time Position Applicants Actions or Behavior IF this valve has not been previously shut then:

Acknowledge request to locally shut 1SI-4 Simulator (A-230-FX32-W3-S2) AND if requested acknowledge Communicator: request to OPEN breaker prior to locally valve operation.

Report back approximately 1 minute after Simulator Operator completes actions below that 1SI-4 is SHUT.

Perform the following actions from Sim Diagram SIS02 to operate 1SI-4:

Simulator Operator - (IF requested) OPEN control power rf sis016 Engage handwheel rf sis017 Shut valve rf sis018

d. Verify cold leg AND hot leg injection valves - SHUT (YES)

NO RO response Procedure Caution: High head SI flow should be isolated before continuing

11. Establish Charging Lineup:

NO a. Shut charging flow control valve:

(SHUTS) response

• ends RO

b. Open charging line isolation valves:

after this (OPEN) step (OPEN)

Harris 2020 NRC Exam Scenario 2 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 6 Page 64 of 81 Event

Description:

Steam line Break on 'B' SG inside Containment (EOP-ES-1.1)

Time Position Applicants Actions or Behavior Charging flow should NOT exceed 150 GPM to prevent Procedure Caution:

damage to the regenerative heat exchanger.

12. Control Charging Flow To Maintain PRZ Level:

a. Control charging using charging flow control valve:

RO

b. Maintain charging flow < 150 gpm

c. PRZ level - CAN BE MAINTAINED STABLE (YES)

OR RISING

13. Check If RHR Pumps Should Be Stopped:

a. Check RHR pumps - ANY RUNNING WITH SUCTION ALIGNED TO RWST (YES)

RO

b. Stop RHR pumps (locates MCB stop switches and STOPs both RHR pumps)

• Simultaneous flow through the charging and SI lines may cause CSIP runout (as indicated by oscillating Procedure Caution: discharge pressure).

• Charging flow should NOT exceed 150 GPM to prevent damage to the regenerative heat exchanger.

14. Check SI Reinitiation Criteria:

a. RCS subcooling - GREATER THAN 40°F (YES)

RO b. PRZ level - GREATER THAN 30%

(YES)

c. PRZ level - Can Be Maintained GREATER (YES)

THAN 30%

Harris 2020 NRC Exam Scenario 2 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 6 Page 65 of 81 Event

Description:

Steam line Break on 'B' SG inside Containment (EOP-ES-1.1)

Time Position Applicants Actions or Behavior Additional foldout item, "SI REINITIATION CRITERIA" applies.

Procedure Note:

Evaluator Aide: ES-1.1 Foldout SI REINITIATION CRITERIA SRO Assigns foldout for SI Reinitiation criteria

15. Establish Steam Generator Pressure Control Mode:

a. Check if steam dump to condenser AVAILABLE: (NO)

BOP

a. Use intact SG PORV for steam dumping in subsequent steps.

RCS temperature must be stabilized to allow evaluation of PRZ Procedure Note:

level trend.

16. Monitor RCS Hot Leg Temperature:

RO

a. Check RCS hot leg temperature - STABLE (YES)

Harris 2020 NRC Exam Scenario 2 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 6 Page 66 of 81 Event

Description:

Steam line Break on 'B' SG inside Containment (EOP-ES-1.1)

Time Position Applicants Actions or Behavior Excessive RCS activity can cause adverse radiological Procedure Caution:

conditions when letdown is placed in service.

Pressure controller PK-145.1 is normally set to maintain 350 Procedure Note: PSIG (58%). If RCS pressure is low, the setpoint may have to be reduced to obtain proper letdown flow.

17. Check If Letdown Can Be Placed In Service:

RO a. Check PRZ Level - GREATER THAN 40% (YES)

b. Establish Letdown.

After letdown is established Pressurizer level can be lowered Examiners Note: and Pressurizer pressure should no longer be a problem.

END OF SCENARIO Terminate the scenario when RCS hot leg temperature stable or stabilizing under the crews control and letdown established.

Lead Evaluator: Announce Crew Update - End of Evaluation - I have the shift.

Have crew remain in the Simulator without discussing the exam. Examiners will formulate any follow-up questions.

Simulator Operator: When directed by Lead Evaluator go to FREEZE Harris 2020 NRC Exam Scenario 2 Rev FINAL

Appendix D Form ES-D-2 E-0 Attachment 3 Harris 2020 NRC Exam Scenario 2 Rev FINAL

Appendix D Form ES-D-2 E-0 Attachment 3 Harris 2020 NRC Exam Scenario 2 Rev FINAL

Appendix D Form ES-D-2 E-0 Attachment 3 Harris 2020 NRC Exam Scenario 2 Rev FINAL

Appendix D Form ES-D-2 E-0 Attachment 3 Harris 2020 NRC Exam Scenario 2 Rev FINAL

Appendix D Form ES-D-2 E-0 Attachment 3 Harris 2020 NRC Exam Scenario 2 Rev FINAL

Appendix D Form ES-D-2 E-0 Attachment 3 Harris 2020 NRC Exam Scenario 2 Rev FINAL

Appendix D Form ES-D-2 E-0 Attachment 3 Harris 2020 NRC Exam Scenario 2 Rev FINAL

Appendix D Form ES-D-2 AOP-042 Harris 2020 NRC Exam Scenario 2 Rev FINAL

Appendix D Form ES-D-2 AOP-042 Harris 2020 NRC Exam Scenario 2 Rev FINAL

Appendix D Form ES-D-2 AOP-042 Harris 2020 NRC Exam Scenario 2 Rev FINAL

Appendix D Form ES-D-2 AOP-042 Harris 2020 NRC Exam Scenario 2 Rev FINAL

Appendix D Form ES-D-2 AOP-042 Harris 2020 NRC Exam Scenario 2 Rev FINAL

Appendix D Form ES-D-2 AOP-042 Harris 2020 NRC Exam Scenario 2 Rev FINAL

Appendix D Form ES-D-2 AOP-042 Harris 2020 NRC Exam Scenario 2 Rev FINAL

Appendix D Form ES-D-2 AOP-042 Harris 2020 NRC Exam Scenario 2 Rev FINAL

2020 NRC Exam Scenario 2 Turnover Plant Status

• Normal startup is in progress with TCS Load Control at 1 GVPC units / min in accordance with GP-005, Power Operation (Mode 2 To Mode 1) , Section 6.2, Step 134.e

• Reactor power ~ 53% power startup on hold through shift turnover. Once complete, raise TCS Load Control to 4 GVPC units/ min and continue the power ascension @ 4 MW/min

• Current rod position is CBD @ 162 steps

• An RCS Boron sample taken 30 minutes ago was 1725 ppm

• Beginning of life conditions

• A Train equipment is in service

• Normal Dayshift

• Status Board is updated

• Additional Protected items A ESW Pump, A CCW Pump, A SFP Hx, RWST, for Response to Industry Best Practices Equipment Out of Service:

• A-SA Boric Acid Transfer Pump is under clearance due to breaker blown control power fuses. Has been under clearance for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. The problem with the breaker has been repaired and the clearance will be removed later this shift.

Tech Spec 3.3.3.5.b Action c and 3.1.2.2 applies (3.1.2.2 is for tracking only).

OWP-CS-04 has been completed.

• 1CS-9, Letdown Orifice Isolation Valve is under clearance for solenoid replacement. Tech Spec 3.6.3 LCO Action b applies. OWP-CS-09 has been completed.

• A Gland Seal Exhauster Fan is under clearance for high vibrations on the motor bearing. The fan has been under clearance for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. Repairs are expected to be completed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Reactivity Plan/Brief:

• Use attached Reactivity Plan to continue bringing the unit on-line at 4 MW/Min.

Risk Assessment:

• YELLOW 2020 NRC Exam Simulator Scenario 2 Turnover Rev FINAL

2020 NRC Exam Simulator Scenario 2 Turnover Rev FINAL 2020 NRC Exam Simulator Scenario 2 Turnover Rev FINAL Appendix D Scenario Outline Form ES-D-1 HARRIS 2020 NRC SCENARIO 3 Facility: Harris Nuclear Plant Scenario No.: 3 Op Test No.: 05000400/2020301 Examiners: Operators: SRO:

RO:

BOP:

Initial Conditions: IC-27, MOL, 3% power

• B NSW Pump is under clearance for breaker repairs Turnover: The plant is at 3% power, middle of core life. Startup on HOLD for briefing GP-005 Rev 107 Step 87

• Manually start AFW flow to maintain control of SG level above 25% to prevent an automatic Reactor trip after trip of the last running Main Feed Pump

• Manually start at least one high head ECCS pump to prevent RVLIS Dynamic Critical Task: Range Level from lowering below 33%

• During a Small Break LOCA secure all RCPs with SI flow > 200 gpm and RCS pressure < 1400 psig to prevent RVLIS Dynamic Range Level from lowering below 33%

Event No. Malf. No. Event Type* Event Description xd2i085 C - BOP/SRO Control Room Air Handler AH-15 trip requiring standby Air 1 xd2o085w TS - SRO Handler startup - (APP-030) xn30d06 tt:144 I - RO/SRO Letdown Temperature Controller fails LOW/Diversion Valve 2

jtb143b fails to bypass demineralizers 3 cnd04a C - BOP/SRO Main Condenser Evacuation Pump trips - (AOP-012)

C - RO/SRO 4 rcs10 Reactor Vessel Flange Leak - (AOP-016)

TS - SRO cfw16a Running MFW Pump trips - (AOP-010) xb1i155 C - BOP/SRO 5 Standby MFW Pump fails to start zr211158 TS - SRO Both MDAFW Pump AUTO start failure zr211113 RCP B rising vibration (AOP-018). Vibrations require a 6 rcs09b C - RO/SRO manual Reactor trip (E-0) , then secure B RCP and PRZ spray valve.

M - ALL Failure of the Reactor Trip breakers to open auto or manual 7 rps01b

- (EOP-FR-S.1) 8 rcs01a M - ALL Small Break LOCA - (EOP-E-1)

Failure of B Sequencer Load Block 1 to actuate during the 9 dsg04a C - RO/SRO Safety Injection which fails to start B CSIP Failure of Safety Injection Isolation valves on 'A' Train CSIP 10 zrpk601a C - BOP/SRO normal mini flow 1CS-214 fails to close automatically

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Harris 2020 NRC Exam Scenario 3 Rev FINAL

Appendix D Scenario Outline Form ES-D-1 HARRIS 2020 NRC SCENARIO 3 SCENARIO

SUMMARY

2020 NRC EXAM SCENARIO 3 The crew will assume the watch while the JITT Trained Startup crew is attending a briefing by Reactor Engineering. The plant was in Mode 1 with Turbine valve testing complete when secondary chemistry parameters degraded and Reactor power was lowered to < 5%. The plant startup is on hold in MODE 2. The candidates are to maintain current plant conditions with Reactor Power ~ 3%.

The following equipment is under clearance:

• B NSW Pump is under clearance for motor repairs. The pump has been unavailable for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. Repairs are expected to be completed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Event 1: Control Room Air Handler AH-15A-SA trips. Annunciator ALB-030-6-4, Control Room HVAC Normal Supply Fans AH-15A-SA Low Flow - O/L will alarm. The HVAC dampers will automatically reposition and all Control Room Ventilation will secure.

Verifiable Action: The BOP will respond in accordance with the alarm procedure for ALB-030-6-4. The BOP should identify that the standby fan has failed to automatically start and report the failure to the SRO. The SRO should direct the BOP to manually start the standby fan using OP-173, Control Room Area HVAC Systems.

The SRO should evaluate Tech Spec 3.7.6, Control Room Emergency Filtration system and determine action a.1 applies.

• With one Control Room Emergency Filtration System inoperable, restore the inoperable system to OPERABLE status within 7 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

The SRO should prepare AD-OP-ALL-1000 Attachment 4, Emergent Issue Checklists for the failure and request assistance from the WCC.

Harris 2020 NRC Exam Scenario 3 Rev FINAL

Appendix D Scenario Outline Form ES-D-1 HARRIS 2020 NRC SCENARIO 3 SCENARIO

SUMMARY

2020 NRC EXAM SCENARIO 3 (Continued)

Event 2: Letdown Temperature Controller fails - LD/Diversion Valve fails to bypass demineralizers. This failure will cause temperature controller TK-144 output to decrease to zero. Without cooling to the letdown heat exchanger, temperatures observed on TI-143 will rise.

At 135°F annunciator ALB-007-3-2, Demin Flow Diversion High Temp will alarm.

Verifiable Action: The OATC will respond in accordance with the alarm procedure for ALB 007-3-2. The OATC should identify that the divert valve to the VCT has failed to respond and report the failure to the SRO. The OATC should manually bypass the CVCS Demineralizers with 1CS-50 (TCV-143), and then take manual control of TK-144 to restore letdown temperature to normal.

The SRO should provide a temperature band between 110°F to 120°F to the OATC in accordance with AD-OP-ALL-1000, Conduct of Operations, (5.5.6) for operation Control Bands.

(Temperature band guidance can be found in OP-107, Chemical Volume And Control). The CVCS Demineralizers should remain bypassed pending an evaluation for continued resin use.

The SRO should prepare AD-OP-ALL-1000 Attachment 4, Emergent Issue Checklists for the failure and request assistance from the WCC.

Event 3: Main Condenser Evacuation Pump A trips. - ALB -021-4-1, Condenser Vacuum Pump A Trip, will alarm and the breaker for the MCES Pump A will indicate open on the MCB.

Main condenser Vacuum will degrade slowly.

Verifiable Action: The BOP will respond in accordance with the alarm procedure for ALB 021-4-1 and identify that the A MCES Pump has tripped based on MCB indication. The BOP will report the failure to the SRO and manually start the B MCES Pump. The SRO should review AOP-012, Partial Loss of Condenser Vacuum, and work through the procedure to determine if any additional actions are required.

The SRO should refer to AD-OP-ALL-1000 Attachment 4, Emergent Issue Checklists for the failure and request assistance from the WCC.

Event 4: Reactor Vessel Flange leak of ~ 15 gpm. The crew should notice Pressurizer level slowly lowering and a rise in charging flow. Annunciator ALB-010-5-5, Reactor vessel flange leakoff high temp will alarm when MCB temperature indicator TI-401 reaches 140°F.

Verifiable Action: The OATC will respond in accordance with the alarm procedure for ALB 010-3-2. The OATC should identify that the rising temperature on TI-401 and report the failure to the SRO. The OATC should shut 1RC-46 in accordance with the alarm response. manually actions for Reactor Vessel leakage directs shutting 1RC-46, Head Flange Seal Leakoff Line Isolation.

The closure of this valve will stop leakage from the inner Reactor head seal. AOP-016, Excessive Primary Plant Leakage may also be entered by the crew to address the flange leakage but the leakage will be stopped when addressed with the APP actions.

The SRO should evaluate Tech Spec 3.4.6.2, Reactor Coolant System - Operational Leakage and determine action b applies for condition d (briefly until 1RC-46 is shut):

Harris 2020 NRC Exam Scenario 3 Rev FINAL

Appendix D Scenario Outline Form ES-D-1 HARRIS 2020 NRC SCENARIO 3 SCENARIO

SUMMARY

2020 NRC EXAM SCENARIO 3 (Continued)

Event 4: Tech Spec evaluation continued T.S. 3.4.6.2: Reactor Coolant System operational leakage shall be limited to:

d. 10 gpm IDENTIFIED LEAKAGE from the Reactor Coolant System (Modes 1, 2, 3, and 4)

Action:

b. With any Reactor Coolant System operational leakage greater than anyone of the above limits, excluding primary-to-secondary leakage, PRESSURE BOUNDARY LEAKAGE and leakage from Reactor Coolant System Pressure Isolation Valves, reduce the leakage rate to within limits within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

The SRO should refer to AD-OP-ALL-1000 Attachment 4, Emergent Issue Checklists for the failure and request assistance from the WCC for entry into Containment to complete the APP-ALB-010 actions.

Event 5: A MFP trips with B MFP failure to start and initiate AFW in accordance with AOP-010, Feedwater Malfunctions - A MFP trip, with the B MFW pump failing to auto start may be inserted once Pressurizer level and RCS Leakoff temperature have stabilized. Both MDAFW pumps fail to auto start but can be started in the MCR.

Verifiable Action: The BOP will respond in accordance with the alarm procedure for ALB 016-1-4. The BOP should identify that the A MFP has tripped and the B MFP failed to start based on Feedwater discharge pressure and plant response and report the failure to the SRO and verbalize the immediate actions of AOP-010. The SRO should enter AOP-010, Feedwater Malfunctions, and work through the procedure to initiate AFW flow to maintain Steam Generator Level between 52 and 62%(Critical Task #1). The BOP may place the A MFP and B MFP control switches in the stop position for the tripped MFP in accordance with APP-ALB-016-1-4.

The crew will implement OWP-ESF-07 to install jumpers to place the inputs from the A and B MFPs to start the MDAFW Pumps and auto open of the MDAFW FCVs, in the trip condition.

The SRO should refer to AD-OP-ALL-1000 Attachment 4, Emergent Issue Checklists, for the failure and request assistance from the WCC.

The SRO should evaluate Tech Spec 3.3.2, Instrumentation - Engineered Safety Features Actuation System Instrumentation Action: 15 applies.

Harris 2020 NRC Exam Scenario 3 Rev FINAL

Appendix D Scenario Outline Form ES-D-1 HARRIS 2020 NRC SCENARIO 3 SCENARIO

SUMMARY

2020 NRC EXAM SCENARIO 3 (Continued)

Event 5: Tech Spec evaluation continued Harris 2020 NRC Exam Scenario 3 Rev FINAL

Appendix D Scenario Outline Form ES-D-1 HARRIS 2020 NRC SCENARIO 3 SCENARIO

SUMMARY

2020 NRC EXAM SCENARIO 3 (Continued)

Event 6: B RCP high vibration. During this event the B RCP vibrations will begin to rise over 3 minutes and peak at 28 mils shaft. Note: the shaft vibration instrumentation reads up to 30 mils. The crew will respond to the B RCP malfunction by either identify rising vibrations or when ALB-010-2-5, RCP-B Trouble alarms.

Verifiable Action: The OATC will respond in accordance with the alarm procedure for ALB 010-2-5 and report this to the alarm to the SRO. The BOP should see the A RCP vibration probe readings are rising and report the failure to the SRO. The SRO should enter AOP-018, Reactor Coolant Pump Abnormal Conditions and the OATC should perform the immediate actions of checking any CSIP running. Vibrations will continue to rise and exceed AOP-018 RCP trip criteria of 20 mils shaft. The OATC will perform a manual Reactor trip and at which time the Reactor will fail to trip (ATWS) and the will have to implement EOP-FR-S.1.

The SRO should evaluate Tech Spec 3.4.1.1, Reactor Coolant Loops and Coolant Circulation Startup and Power Operation, and determine this action is applicable prior to opening the Reactor Trip Breakers. This may be discussed after the scenario based on the sequence of this event.

Once the immediate actions of EOP-FR-S.1 are completed the crew will transition to EOP-E-0 and secure the A RCP and associated PRZ spray valve after EOP-E-0 immediate actions are completed.

Event 7: Major - ATWS Reactor Trip breakers fail to open auto or manual. The crew should recognize that the Reactor has failed to trip and enter FR-S.1, Response to Nuclear Power Generation/ATWS. The Reactor Trip breakers will be opened locally one minute after a field operator has been dispatched to perform those actions. Once the crew has inserted negative reactivity via rod insertion (Auto or manual) or initiated the emergency Boration and have verified that the Reactor is tripped in FR-S.1, they should exit FR-S.1 and return to EOP-E-0.

Harris 2020 NRC Exam Scenario 3 Rev FINAL

Appendix D Scenario Outline Form ES-D-1 HARRIS 2020 NRC SCENARIO 3 SCENARIO

SUMMARY

2020 NRC EXAM SCENARIO 3 (Continued)

Event 7: Continued Verifiable Action: The OATC will respond in accordance with EOP-FR-S.1 immediate actions and attempt to trip the Reactor via the second MCB Rector Trip switch. The BOP will respond in accordance with EOP-FR-S.1 immediate actions trip the Turbine from the MCB via the Turbine Trip switch. Once the immediate actions of EOP-FR-S.1 are complete the SRO should make a plant announcement for an available operator to come to the MCR for directions to locally trip the Reactor.

The next event Small Break LOCA will ramp in over the 4 minutes from the time the Reactor Trip breakers open allowing the crew to then transition from EOP E-0 to ES-0.1, Reactor Trip Response.

Event 8: Major - Small Break LOCA caused by a Loop 1 Cold Leg break resulting in either a Manual OR Automatic SI initiation. The crew should recognize a changing plant conditions with Pressurizer level and RCS pressure lowing. If the crew responds quickly to the event they may manually actuate a Safety Injection based on ES-0.1 foldout criteria of not being able to maintain Pressurizer level > 5% or RCS subcooling < 10°F. If they do not respond quickly an Automatic Safety Injection will occur. The crew will then transition from ES-0.1 back to E-0, Reactor Trip or Safety Injection. After returning to EOP-E-0 and with SI actuated the crew will identify the A CSIP has tripped and the B CSIP has failed to start from the Sequencer and pressure in the Containment will continue to rise due to the LOCA. The degrading conditions in Containment will cause the crew to transition from EOP-E-0 to EOP-E-1, Loss of Reactor or Secondary Coolant.

Verifiable Action: Once the crew starts the B CSIP (Critical Task #2). The Foldout Criteria for securing RCPs will be met and secure the RCPs (Critical Task #3). The OATC will report this condition to the SRO. The SRO should continue in EOP-E-0, and direct the OATC to implement the procedure foldout to ensure all RCPs are stopped.

Event 9: During the Safety Injection activation the B Load Sequencer will skip the B CSIP load block.

Verifiable Action: The OATC will report this condition to the SRO. The SRO should continue in EOP-E-0, and work through the procedure to ensure the OATC starts the B CSIP in accordance with step 6. Provided the sequencer has reached Load Block 9 (Manual Loading Permissive) the OATC may start B CSIP when the automatic function failure is observed in accordance with AD-OP-ALL-1000, Conduct of Operations, (5.6.3.8) for Equipment Manipulation and Status Control after notifying the SRO.

Harris 2020 NRC Exam Scenario 3 Rev FINAL

Appendix D Scenario Outline Form ES-D-1 HARRIS 2020 NRC SCENARIO 3 SCENARIO

SUMMARY

2020 NRC EXAM SCENARIO 3 (Continued)

Event 10: Failure of Safety Injection Isolation valves on 'A' Train CSIP normal mini flow 1CS-214 fails to close automatically.

Verifiable Action: The BOP or the OATC will report this condition to the SRO. The SRO should continue in EOP-E-0, and work through the procedure to ensure the BOP or the OATC shuts 1CS-214 in accordance with EOP-E-0, Attachment 1. The BOP or the OATC may shut 1CS-214 when the automatic function failure is observed in accordance with AD-OP-ALL-1000, Conduct of Operations, (5.6.3.8) for Equipment Manipulation and Status Control after notifying the SRO.

The crew will continue in EOP-0 into EOP-E-1, Loss of Reactor Or Secondary Coolant until the transition to EOP-ES-1.2, Post-LOCA Cooldown and Depressurization, is made. During the implementation of EOP-ES-1.2 a transition to EOP-FR-P.1, Response To Imminent Pressurized Thermal Shock may be required based on Cold Leg temperature of the broke RCS loop dropping below 240°F. The crew will return back to EOP-ES-1.2 where the scenario termination is met after the first SG pressure reduction has been completed.

Harris 2020 NRC Exam Scenario 3 Rev FINAL

Appendix D Scenario Outline Form ES-D-1 HARRIS 2020 NRC SCENARIO 3 CRITICAL TASK JUSTIFICATION:

1. Manually start AFW flow to maintain control of SG level above 25% to prevent an automatic or manual Reactor trip after trip of the last running Main Feed Pump An unnecessary automatic or manual Reactor Trip for this event will create critical task.

See note below.

2. Manually start at least one high head ECCS pump to prevent RVLIS Dynamic Range Level from lowering below 33%

In this scenario the A CSIP has tripped and the B CSIP has did not automatically start from sequencer actuation. The operator must manually start the B CSIP which was in standby. Plant parameter grading criteria for the task is starting the B CSIP to prevent RVLIS Dynamic Range Level from lowering below 33% which constitutes a significant core uncover with 2 Reactor Coolant Pumps in operation.

3. During a Small Break LOCA secure all RCPs with SI flow > 200 gpm and RCS pressure

< 1400 psig to prevent RVLIS Dynamic Range Level from lowering below 33%

In this scenario EOP-E-0 foldout will apply following the completion of the immediate actions. The RCP trip criteria is BOTH of the following: SI flow > 200 gpm and RCS pressure < 1400 psig. These plant parameters are to be monitored continuously and when those conditions are met the operator must secure the operating RCPs. Plant parameter grading criteria for the task is tripping RCPs if SI flow > 200 gpm to prevent RVLIS Dynamic Range Level from lowering below 33% which constitutes a significant core uncover with 2 Reactor Coolant Pumps in operation.

Note: Causing an unnecessary plant trip or ESF actuation (automatic or manual) may constitute a CT failure. Actions taken by the applicant(s) will be validated using the methodology for critical tasks in Appendix D to NUREG-1021.

Harris 2020 NRC Exam Scenario 3 Rev FINAL

Appendix D Scenario Outline Form ES-D-1 HARRIS 2020 NRC SCENARIO 3 Simulator Setup Reset to IC-143 password NRC3sros Go to RUN Silence and Acknowledge annunciators GO TO FREEZE and inform the lead examiner the Simulator is ready. DO NOT GO TO RUN until directed by the lead examiner.

Set ERFIS screens for normal full power conditions (The examiner has provided to the candidate with initial conditions and the initiating cues prior to placing the simulator in RUN.)

SPECIAL INSTRUCTIONS Provide a Reactivity Plan to candidates for shutting down the plant Provide a copy of the following procedures:

• GP-005, Power Operation (Mode 2 To Mode 1) marked up through section 6.0 step 87 Press START on Counter Scaler Post conditions for status board from IC-27 Reactor Power 3%

Control Bank D at 102 steps RCS boron 1453 ppm Turnover: The plant is at 3% power, middle of core life. The crew will assume the watch while the JITT Trained Startup crew is attending a briefing by Reactor Engineering. The plant was in Mode 1 with Turbine valve testing complete when secondary chemistry parameters degraded and Reactor power was lowered to < 5%. The plant startup is on hold in MODE 2. The candidates are to maintain current plant conditions with Reactor Power ~ 3%.

Equipment Under Clearance:

• B NSW Pump is under clearance for breaker repairs.

Align equipment for repairs:

Place protected train placards IAW OMM-001 Attachment 5 Protected Train placards on 'A' NSW pump Place a CIT on the switch for B NSW Pump.

Hang restricted access signs on MCR entry swing gates Set CRT screen 3 to "QP STARTUP" Harris 2020 NRC Exam Scenario 3 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 1 Page 11 of 73 Control Room Air Handler AH-15 trips, standby fails to Auto Event

Description:

Start Time Position Applicants Actions or Behavior The crew has been directed to hold power at 3% while the oncoming crew conducts a turnover briefing.

When the crew has completed their board walk down and Lead Evaluator: are ready to take the shift inform the Simulator Operator to place the Simulator in Run. When the Simulator is in run announce:

CREW UPDATE - (SROs Name) Your crew has the shift.

END OF UPDATE When directed by the Lead Evaluator, ensure that the Simulator Operator:

annunciator horns are on and place the Simulator in RUN.

On cue from the Lead Evaluator actuate Trigger 1 Simulator Operator: Control Room Air Handler AH-15 trips, standby fails to Auto Start

• ALB-030-6-4, Control Room HVAC Normal Supply Fans Indications AH-15 Low Flow - O/L Available:

• Control Room ventilation damper re-alignment

• White Overload light lit on AH-15 MCB switch ALB-030 BOP RESPONDS to alarm on APP-ALB-030-6-4

1. CONFIRM alarm using:

• Fan status indication at MCB for AH-15 (1A-SA and 1B-SB)

• Damper position indication on MCB for CZ-D2SB, CZ-25, BOP and CZ-26

• ALB-030-6-3, Cont Room Normal Supply AH-15 Filter High P

2. VERIFY Automatic Functions:

BOP

• Fans trip on overload Harris 2020 NRC Exam Scenario 3 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 1 Page 12 of 73 Control Room Air Handler AH-15 trips, standby fails to Auto Event

Description:

Start Time Position Applicants Actions or Behavior BOP 3. PERFORM Corrective Actions:

a. CHECK AH-15 fans status indication on MCB.

b. IF fan is tripped, THEN PERFORM the following:

(YES)

(1) START the standby fan using OP-173, Control Room Area HVAC System.

Directs BOP to start Control Room ventilation alignment in SRO accordance with OP-173 (2) IF white fan trouble light is LIT, THEN DISPATCH an operator to check overload relays on 1A36-SA-5A or 1B36-SB-3A.

(3) DISPATCH an operator to check for tripped BOP breaker on 1A36-SA-5A or 1B36-SB-3A.

c. CHECK damper alignment on MCB for CZ-D1SA-1, CZ-D2SB-1, CZ-25 and CZ-26.

d. IF ALB-030-6-3 is ALARMING, THEN REFER TO ALB-030-6-3. (NO)

When contacted to investigate fan failure report back in 2 Simulator minutes that breaker 1A-36-SA Cubical 5A is tripped on Communicator:

overload and no problems are noted locally at the fan unit.

(Any Tech Spec evaluation can be conducted with a follow Evaluator Note:

up question after the scenario).

Enters Instrumentation TS 3.7.6 ACTION a.1 - With one Control Room Emergency SRO Filtration System inoperable, restore the inoperable system to OPERABLE status within 7 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

Completes an Emergent Issue Checklist and contacts WCC for SRO assistance. (WR, LCOTR, and Maintenance support)

Harris 2020 NRC Exam Scenario 3 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 1 Page 13 of 73 Control Room Air Handler AH-15 trips, standby fails to Auto Event

Description:

Start Time Position Applicants Actions or Behavior Simulator Acknowledge requests for assistance.

Communicator:

Once the crew completes start of the standby Air Handler and Tech Specs have been evaluated, cue Simulator Lead Evaluator: Operator to insert Trigger 2 Event 2: Letdown Temperature Control Failure Harris 2020 NRC Exam Scenario 3 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 2 Page 14 of 73 Event

Description:

Letdown Temperature Control Failure Time Position Applicants Actions or Behavior On cue from the Lead Evaluator actuate Trigger 2 Simulator Operator:

Letdown Temperature Control Failure

• ALB-007-3-2, DEMIN FLOW DIVERSION HIGH TEMP Indications Available

• TK-144 output lowers to 0

• TI-143 temperature rising ALB-007 RO RESPONDS to alarm on APP-ALB-007-3-2 RO 1. CONFIRM alarm using TI-143, LP Letdown Temperature.

RO 2. VERIFY Automatic Functions:

a. 1CS-50, Letdown to VCT/Demin, diverts flow to the VCT, bypassing the BTRS and Purification (NO)

Demineralizers (Manually positions 1CS-50, Letdown to VCT/Demin, to divert flow to the VCT)

RO 3. PERFORM Corrective Actions:

a. VERIFY that 1CS-50 diverts flow to the VCT, (YES) bypassing the BTRS and Purification

b. PERFORM the following as needed to lower letdown temperature:

(1) VERIFY proper charging flow is established. (YES)

(2) LOWER letdown flow. (N/A)

(3) IF CCW flow to the Letdown Heat Exchanger (YES) appears low, THEN:

a) TAKE manual control of TK-144.

b) OPEN 1CC-337, to raise CCW flow.

Directs RO to maintain a TK-144 outlet temperature controlling SRO band of 110°F to 120°F per OP-107.

c. IF letdown temperature can NOT be lowered, THEN (NO)

REFER TO OP-107, Chemical and Volume Control System, AND PERFORM the following:

(1) REMOVE letdown from service. (NO)

(2) IF desired, THEN PLACE Excess Letdown in (N/A) service.

Harris 2020 NRC Exam Scenario 3 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 2 Page 15 of 73 Event

Description:

Letdown Temperature Control Failure Time Position Applicants Actions or Behavior

d. NOTIFY RP that due to high temperatures closure of 1CS-50 has bypassed the demineralizers. Surveillance is SRO necessary to identify areas in the plant that could have experienced changes to radiological conditions.

Completes an Emergent Issue Checklist and contacts WCC for SRO assistance. (WR, and Maintenance support)

Simulator If contacted as WCC, System Engineer or Chemistry:

Communicator: Direct the control room to maintain flow bypassing the demineralizers until a resin damage assessment is completed.

When letdown temperature is under control, cue Simulator Operator to insert Trigger 3 Lead Evaluator:

Event 3: Main Condenser Evacuation Pump A trip Harris 2020 NRC Exam Scenario 3 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 3 Page 16 of 73 Event

Description:

Main Condenser Evacuation Pump A trip Time Position Applicants Actions or Behavior On cue from the Lead Evaluator actuate Trigger 3 Simulator Operator:

Main Condenser Evacuation Pump A trip Responding to the annunciator will direct the operator to start the standby MCES Pump if vacuum is degrading.

Evaluator Note: With the plant at low power a degrading vacuum condition may not occur, however the MCES Pump trip will meet the conditions to enter AOP-012.

• ALB-021-4-1, CONDENSER VACUUM PUMP A TRIP Indications Available

• MCES A Pump MCB switch green light lit ALB-021 BOP RESPONDS to alarm on APP-ALB-021-4-1 BOP 1. CONFIRM alarm using:

a. Condenser Vacuum Pump status

b. Condenser vacuum indication BOP 2. VERIFY Automatic Functions:

a. Standby Vacuum Pump auto-starts on rising (NO) condenser pressure only if running Vacuum Pump has not tripped.

(Manually starts MCES B Pump from MCB)

BOP 3. PERFORM Corrective Actions:

a. IF Condenser vacuum is degrading, THEN GO TO (N/A)

AOP-012, Partial Loss of Condenser Vacuum.

b. CHECK Vacuum Pump breaker indication (MCB).

c. IF necessary, THEN START the standby Vacuum Pump. (YES)

d. DISPATCH an Operator to check operation of seal water make-up to Vacuum Pump.

Simulator When contacted to investigate pump trip report back in 2 Communicator: minutes that breaker 1D3 Cubical 3D is tripped on overload and no problems are noted locally at the Vacuum Pump.

Harris 2020 NRC Exam Scenario 3 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 3 Page 17 of 73 Event

Description:

Main Condenser Evacuation Pump A trip Time Position Applicants Actions or Behavior Completes an Emergent Issue Checklist and contacts WCC for SRO assistance. (WR, and Maintenance support)

Simulator Acknowledge requests for assistance.

Communicator:

Once the crew completes start of the standby MCES B Pump, cue Simulator Operator to insert Trigger 4 Lead Evaluator:

Event 4: Reactor Vessel Flange leak of ~ 15 gpm The following write up is if AOP-012 is used for the Evaluator Note:

response to the trip of the MCES Pump Trip.

Identifies entry conditions to AOP-012, Partial Loss Of CREW Condenser Vacuum are met AOP-012 Partial Loss Of Condenser Vacuum ENTERS and directs actions of AOP-012, SRO Conducts a Crew Update Makes PA announcement for AOP entry Procedure Note: This procedure contains no immediate actions.

BOP 1. CHECK Turbine - IN Operation (YES)

2. CHECK Condenser pressure in both Zones LESS BOP (YES)

THAN 8.86 inches Hg absolute.

Siemens recommends limiting operation in the Condenser Procedure Note: Vacuum Exclusion Zone to 5 minutes per occurrence with a lifetime limit of 300 minutes.

Harris 2020 NRC Exam Scenario 3 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 3 Page 18 of 73 Event

Description:

Main Condenser Evacuation Pump A trip Time Position Applicants Actions or Behavior BOP 3.a PERFORM the following: (NO)

SRO 3.a RNO: GO TO Step 3.b.

3.b REDUCE Turbine load as necessary to maintain (N/A)

SRO Condenser vacuum using ONE of the following:

4. CONTINUE Turbine load reduction until directed (N/A) otherwise by CRS based on the following:

SRO

• Cause of vacuum loss identified and corrected

• Vacuum stable or improving

• Plant conditions require Reactor or Turbine trip

5. CHECK ALL available Condenser Vacuum Pumps - (NO)

BOP OPERATING.

5. RNO: START the Standby Condenser Vacuum Pump.

BOP (Manually starts MCES B Pump from MCB)

6. DISPATCH Operator(s) to locally perform actions of BOP Attachment 1, Local Actions for a Loss of Condenser Vacuum.

Simulator Acknowledge requests for assistance.

Communicator:

7. ENSURE the following valves - SHUT:

BOP

• 1CE-447, Condenser Vac Breaker (YES)

• 1CE-475, Condenser Vac Breaker (YES)

8. CONTACT Radwaste Control Room to determine if recent BOP equipment operations using auxiliary steam or condensate may have caused loss of vacuum.

Harris 2020 NRC Exam Scenario 3 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 3 Page 19 of 73 Event

Description:

Main Condenser Evacuation Pump A trip Time Position Applicants Actions or Behavior Simulator Acknowledge requests and report that NO recent changes Communicator: to auxiliary steam or condensate equipment operations.

BOP 9. CHECK Circulating Water Pumps - ANY TRIPPED. (NO)

SRO 9. RNO: GO TO Step 11.

If a Circulating Water Pump has tripped, it is not considered Procedure Note: available until the cause of the trip has been identified and corrected.

11. CHECK ALL available Circulating Water Pumps - (YES)

BOP RUNNING.

When all Circulating Water Pumps are tripped, failure to shut MSIVs and MSIV Bypass Valves and opening condenser Procedure Caution:

vacuum breakers may result in turbine rupture discs relieving due to elevated pressure and temperature.

12. CHECK ANY Circulating Water Pumps - (YES)

BOP RUNNING.

13. CHECK at least ONE Condensate Booster Pump - (YES)

BOP RUNNING.

14. CHECK BOTH of the following conditions EXIST:

(indicates complete failure of a Circulating Water BOP System expansion joint) [A.1]

a. CHECK ALB-021-8-5 in ALARM due to Condenser (NO)

Pit High Level.

SRO 14. RNO: GO TO Step 16.

16. CHECK major unisolable leak in Circulating Water (NO)

SRO System - EXISTS.

Harris 2020 NRC Exam Scenario 3 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 3 Page 20 of 73 Event

Description:

Main Condenser Evacuation Pump A trip Time Position Applicants Actions or Behavior SRO 16. RNO: GO TO Step 19.

19. CHECK for isolable leak between Condenser (NO)

SRO Waterbox isolation valves - EXISTS.

SRO 19. RNO: GO TO Step 22.

22. CHECK Circulating Water temperatures using the (YES)

SRO following ERFIS Computer Points - STABLE OR IMPROVING:

SRO 23. CHECK plant shutdown - INITIATED. (NO)

SRO 23. RNO: GO TO Step 28.

28. CHECK cause of loss vacuum - IDENTIFIED AND (YES)

SRO CORRECTED.

29. RESTORE Turbine load as desired per GP-005, Power SRO Operation.

SRO 30. EXIT this procedure.

Once the crew completes start of the standby MCES B Pump, cue Simulator Operator to insert Trigger 4 Lead Evaluator:

Event 4: Reactor Vessel Flange leak of ~ 15 gpm Harris 2020 NRC Exam Scenario 3 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 4 Page 21 of 73 Event

Description:

Reactor Vessel Flange leak of ~ 15 gpm Time Position Applicants Actions or Behavior On cue from the Lead Evaluator actuate Trigger 4 Simulator Operator:

Reactor Vessel Flange leak of ~ 15 gpm

• ALB-10-5-5, REACTOR VESSEL FLANGE LEAKOFF Indications HIGH TEMP Available:

• TI-401, Reactor Vessel Flange Leakoff Temp rising Responding to the annunciator will direct the operator to shut 1RC-46, Head Flange Seal leakoff Line Isolation to Evaluator Note:

stop leakage from the inner Reactor head seal. With the condition clear the crew may not enter AOP-016.

ALB-010 RO Responds to alarm and evaluates APP-ALB-010-5-5

1. CONFIRM alarm using:

a. TI-401 Reports TI-401 reading or trending high.

2. VERIFY Automatic Functions: None

3. PERFORM Corrective Actions:

a. CHECK containment temperature trend for high containment temperature resulting from a nearby steam/RCS leak (NONE)

b. Shut 1RC-46, Head Flange Seal Leakoff Line Isolation to stop leakage from inner Reactor head seal Monitors TI-401 indications and identifies temperature is lowering

c. COORDINATE Containment entry per AP-545, AND DISPATCH an Operator to containment to position the following valves:

(1) SHUT 1RC-34, Head Flange Seal Inner Leakoff Isolation.

(2) OPEN 1RC-33, Head Flange Seal Outer Leakoff Isolation.

RO Informs SRO Reactor Vessel Flange leakage is isolated Harris 2020 NRC Exam Scenario 3 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 4 Page 22 of 73 Event

Description:

Reactor Vessel Flange leak of ~ 15 gpm Time Position Applicants Actions or Behavior

• Completes an Emergent Issue Checklists for the failure of the Rx Vessel Flange.

SRO

• Contacts WCC to coordinate Containment entry per AP-545 (WR, LCOTR and Maintenance support).

Simulator Acknowledge requests for assistance.

Communicator:

Any Tech Spec evaluation can be conducted with a follow up question after the scenario. Leakrate may not be easily Evaluator Note:

determinable due to changing RCS Temperature and may require Engineering assistance Evaluates Reactor Coolant System TS 3.4.6.2 Reactor Coolant System operational leakage shall be limited to:

d. 10 gpm IDENTIFIED LEAKAGE from the Reactor Coolant System.

ACTION b. - With any Reactor Coolant System operational leakage greater than anyone of the above SRO limits, excluding primary-to-secondary leakage, PRESSURE BOUNDARY LEAKAGE and leakage from Reactor Coolant System Pressure Isolation Valves, reduce the leakage rate to within limits within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

The following write up is if AOP-016 is used for the Evaluator Note:

response to the Reactor Vessel Flange Leak.

Identifies entry conditions to AOP-016, Excessive Primary CREW Plant Leakage are met AOP-016 Excessive Primary Plant Leakage Harris 2020 NRC Exam Scenario 3 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 4 Page 23 of 73 Event

Description:

Reactor Vessel Flange leak of ~ 15 gpm Time Position Applicants Actions or Behavior ENTERS and directs actions of AOP-016, SRO Conducts a Crew Update Makes PA announcement for AOP entry Procedure Note: This procedure contains no immediate actions.

OATC 1. CHECK RHR in operation (NO)

SRO 1. RNO: GO TO Step 3.

3. REFER TO PEP-110, Emergency Classification And SRO Protective Action Recommendations, AND ENTER the EAL Matrix.

4. CHECK RCS leakage within VCT makeup capability (YES)

OATC May report that the leak is exceeding Tech Spec SG leakage.

If CSIP suction is re-aligned to the RWST, negative reactivity Procedure Note:

addition should be anticipated.

OATC 5. MAINTAIN VCT level GREATER THAN 5% (YES)

SRO 6. GO TO Step 10.

10. CHECK valid CNMT Ventilation Isolation monitors (REM-3561A, B, C and D) ALARM CLEAR (YES)

11. CHECK RM 3502A, RCS Leak Detection Radiation OATC Monitor, ALARM CLEAR (YES)

12. CHECK ALL valid Area Radiation Monitors ALARM CLEAR (YES)

13. CHECK valid Stack Monitors ALARM CLEAR (YES)

Harris 2020 NRC Exam Scenario 3 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 4 Page 24 of 73 Event

Description:

Reactor Vessel Flange leak of ~ 15 gpm Time Position Applicants Actions or Behavior

14. DETERMINE if unnecessary personnel should be SRO evacuated from affected areas, as follows:

14.a. CHECK that a valid RMS Secondary Monitor (NO)

HIGH ALARM SRO 14.a RNO: GO TO Step 14.d.

14.d CHECK that an RCS leak outside Containment, (NO) other than SG tube leakage, has caused a valid RMS alarm.

SRO 14.d RNO: GO TO Step 15.

BOP 15. DIRECT Chemistry to stop any primary sampling activities.

Simulator Acknowledge request to stop primary sampling activities.

Communicator:

• The following qualitative flow balance is to quickly determine if RCS leakage exceeds Tech Spec limits, EAL classification thresholds, or RCS makeup capability.

Procedure Note:

• RCS influent and effluent flow rates are compared and PRZ level rate of change is used to determine the RCS flow balance.

16. PERFORM a qualitative RCS flow balance, as follows:

a. ESTIMATE leak rate considering the following parameters:

• PRZ level rate of change (~55 gal/% at 653°F)

• Charging flow OATC

• Total seal injection flow

• Letdown flow

• Total seal return flow Reports estimate to SRO of ~ 15 gpm (Band of 10 to 25 gpm)

Harris 2020 NRC Exam Scenario 3 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 4 Page 25 of 73 Event

Description:

Reactor Vessel Flange leak of ~ 15 gpm Time Position Applicants Actions or Behavior

b. OPERATE the following letdown orifice valves as necessary to maintain charging flow on scale:

• 1CS-7, 45 gpm Letdown Orifice A

• 1CS-8, 60 gpm Letdown Orifice B

• 1CS-9, 60 gpm Letdown Orifice C (No changes required)

Performance of surveillance tests to determine if leakage Procedure Note: exceeds Tech Spec limits, or to more accurately quantify leakage is up to CRS discretion.

17. Determines that more accurate quantification is not needed SRO due to excessive leakage indications present.

Any Tech Spec evaluation can be conducted as a follow up Evaluator Note:

question after the scenario.

SRO 18. EVALUATE RCS leakage (refer to Tech Spec 3.4.6.2).

Reviews Reactor Coolant System TS 3.4.6.2 Reactor Coolant System operational leakage shall be limited to:

d. 10 gpm IDENTIFIED LEAKAGE from the Reactor Coolant System.

ACTION b. - With any Reactor Coolant System operational leakage greater than any one of the above limits, excluding primary-to-secondary leakage, PRESSURE BOUNDARY LEAKAGE and leakage from Reactor Coolant System Pressure Isolation Valves, reduce the leakage rate to within limits within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

19. DETERMINE leak location from one or more of the following:

SRO MCB indications and Valid Radiation Monitors

• From RV Flange Harris 2020 NRC Exam Scenario 3 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 4 Page 26 of 73 Event

Description:

Reactor Vessel Flange leak of ~ 15 gpm Time Position Applicants Actions or Behavior

20. NOTIFY Health Physics of the following:

a. Leak location:

• Source inside or outside CNMT BOP

• To closed system, SG or to atmosphere

b. Applicable radiation levels.

NOTIFY HP of Reactor Vessel Flange leakage Simulator Acknowledge RCs leakage is coming from Reactor Vessel Communicator: Flange.

21. WHEN leakage location has been determined, THEN SRO PERFORM the applicable

Attachment:

Leakage From RV Flange Attachment 6 page 28 Transitions to Attachment 6:

SRO 1. Consult with Operation Management to determine leak isolation and recovery actions Radiation Control personnel must identify radiological Procedure Note: conditions or provide coverage and issue a special RWP prior to CNMT entry.

2. IF CNMT entry is made to isolate the leak, THEN VERIFY valves manipulated for leak isolation are documented per the SRO following:

• OMM-001, Operations Administrative Requirements

• OPS-NGGC-1303, Verification Practices Completes an Emergent Issue Checklists for the failure of the Rx Vessel Flange.

SRO Contacts WCC to coordinate Containment entry per AP-545 (WR, LCOTR and Maintenance support).

SRO 3. Exit this procedure.

Harris 2020 NRC Exam Scenario 3 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 4 Page 27 of 73 Event

Description:

Reactor Vessel Flange leak of ~ 15 gpm Time Position Applicants Actions or Behavior After Rx Vessel leakage has stabilized, cue Simulator Operator to insert Trigger 5 Evaluator Note:

Event 5: A MFP trips with B MFP failure to start AOP-010).

Harris 2020 NRC Exam Scenario 3 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 5 Page 28 of 73 MFP A trips with MFP B failure to start Event

Description:

(AOP-010)

Time Position Applicants Actions or Behavior On cue from the Lead Evaluator insert Trigger 5 Simulator Operator:

MFP A trips with B MFP failure to start (AOP-010)

• ALB-016-1-4, FW PUMP A/B O/C TRIP -GND OR BKR Indications Available: FAIL TO CLOSE

• Multiple FW flow alarms BOP RESPONDS to alarms and ENTERS AOP-010 AOP-010 Feedwater Malfunctions ENTERS and directs actions of AOP-010 SRO Conducts a Crew Update Makes PA announcement for AOP entry Procedure Note: Steps 1 through 4 are immediate actions.

Immediate 1. CHECK Feedwater Regulator valves operating Action BOP (YES) properly.

Immediate Action BOP 2. CHECK ANY Main Feedwater Pump TRIPPED (YES)

Immediate Action BOP 3. CHECK initial Reactor power less than 90%. (YES)

Immediate Action BOP 4. CHECK initial Reactor power less than 80%. (YES)

Turbine runback will automatically terminate at approximately 50% power.

Procedure Note: Turbine runbacks are identified as follows:

• ALB-20/2-2, TURBINE RUNBACK OPERATIVE in alarm

• TCS Runback in Urgent Priority alarm BOP 5. CHECK initial Reactor power less than 60%. (YES)

Harris 2020 NRC Exam Scenario 3 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 5 Page 29 of 73 MFP A trips with MFP B failure to start Event

Description:

(AOP-010)

Time Position Applicants Actions or Behavior

6. MAINTAIN ALL of the following:

• At least ONE Main Feedwater Pump RUNNING (NO)

BOP

• Main Feedwater flow to ALL Steam Generators (YES)

• ALL Steam Generator levels greater than 30% (YES)

SRO 6. RNO: PERFORM the following:

a. IF ANY SG level drops to 30% THEN TRIP the Reactor AND GO TO EOP-E-0.Places SG B (NO)

Feedwater Reg valve in MANUAL

b. IF Above POAH AND Reactor power is LESS THAN 10%, THEN: (YES)

Critical (1) INITIATE AFW flow to maintain Steam Task # 1 BOP Generator levels between 52 and 62%.

Critical Task: Manually start AFW flow to maintain control of SG level above 25% to prevent an automatic Reactor trip after trip of the last running Main Feed Pump.

Procedure Note: Mode change occurs at 5% Reactor power.

SRO (2) REDUCE power as necessary to maintain SG level.

c. IF below POAH, THEN: (NO)

7. CHECK Feedwater Regulator Valves operating properly in AUTO: (YES)

BOP

• Response to SG levels

• Valve position indication

• Response to feed flow/steam flow mismatch Inability to monitor one or more Safety System Parameters concurrent with a turbine runback of greater than 25%, requires Procedure Note:

a change of event classification per the HNP Emergency Plan.

[C.2, C.3]

Harris 2020 NRC Exam Scenario 3 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 5 Page 30 of 73 MFP A trips with MFP B failure to start Event

Description:

(AOP-010)

Time Position Applicants Actions or Behavior

8. CHECK turbine runs back less than 25% turbine BOP YES load A feedwater train consists of a Condensate Pump, Condensate Procedure Note:

Booster Pump and Main Feedwater Pump.

9. GO TO the applicable section:

SRO EVENT: Loss of Running Pumps Section 3.2 Page 14

• A feedwater train consists of a Condensate Pump, Condensate Booster Pump and Main Feedwater Pump.

• Target load for loss of a running pump is as follows:

o One Heater Drain Pump with both FW Trains operating:

Less than 100% Power o No Heater Drain Pumps with both FW Trains operating:

90% turbine load.

Procedure Note:

o Single Main Feedwater Pump running with both Condensate Pumps and both Condensate Booster Pumps operating: 7.0 mpph Total FW Flow.

o Single Feedwater Train with both Heater Drain Pumps operating: 7.0 mpph Total FW Flow.

o Single Feedwater Train operating: 5.5 mpph Total FW Flow.

1. MAINTAIN ALL of the following:

• At least ONE Main Feedwater Pump RUNNING (NO)

BOP

• Main Feedwater flow to ALL Steam Generators (YES)

• ALL Steam Generator levels greater than 30% (YES)

SRO 1. RNO: PERFORM the following:

Harris 2020 NRC Exam Scenario 3 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 5 Page 31 of 73 MFP A trips with MFP B failure to start Event

Description:

(AOP-010)

Time Position Applicants Actions or Behavior

a. IF ANY SG level drops to 30% THEN TRIP the Reactor AND GO TO EOP-E-0.Places SG B (NO)

Feedwater Reg valve in MANUAL

b. IF Above POAH AND Reactor power is LESS THAN 10%, THEN: (YES)

Critical (1) INITIATE AFW flow to maintain Steam Task # 1 BOP Generator levels between 52 and 62%.

Critical Task: Manually start AFW flow to maintain control of SG level above 25% to prevent an automatic Reactor trip after trip of the last running Main Feed Pump Procedure Note: Mode change occurs at 5% Reactor power.

SRO (2) REDUCE power as necessary to maintain SG level.

c. IF below POAH, THEN: (NO)

2. CHECK control rods INSERTING to reduce Tavg - Tref RO mismatch.

(Rod Control is in Manual at this time)

3. CHECK Main Steam pressure less than PORV BOP (YES) controller setpoint. (nominally 1106 psig).

Improper operation of the Steam Dumps while in manual Procedure Caution: control can lead to excessive SG swell or overcooling of the RCS.

BOP 4. CHECK proper Steam Dump Valve operation. (YES)

5. CHECK SG levels TRENDING to between 52% and BOP (YES) 62%.

Harris 2020 NRC Exam Scenario 3 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 5 Page 32 of 73 MFP A trips with MFP B failure to start Event

Description:

(AOP-010)

Time Position Applicants Actions or Behavior RO 6. CHECK PZR PORVs SHUT. (YES)

RO 7. CHECK PZR pressure TRENDING to 2235 psig. (YES)

RO 8. CHECK PZR Level TRENDING to reference level. (YES)

9. ALIGN Main Feedwater Pump control switches, as applicable:

Pumps

• Tripped Pump - STOP (spring-return to AUTO)

BOP

• Auto-started Pump - START (spring-return to AUTO)

Pump Recirc Valves

• Tripped Pump - SHUT

• Auto-started Pump - MODU BOP 10. CHECK BOTH Heater Drain Pumps TRIPPED. (YES)

11. CHECK the following high-high level alarms BOP (YES)

CLEAR:

A feedwater train consists of a Condensate Pump, Condensate Procedure Note:

Booster Pump and Main Feedwater Pump.

12. CHECK load less than or equal to target based on final condition. (YES)

BOP Harris 2020 NRC Exam Scenario 3 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 5 Page 33 of 73 MFP A trips with MFP B failure to start Event

Description:

(AOP-010)

Time Position Applicants Actions or Behavior

13. DISPATCH an operator to check the following seated, observing tailpipes:

BOP

• MSR Relief Valves

• SG Safety Valves Acknowledge communications After 2-3 minutes report back that nothing is abnormal with the tailpipes and no leaks were found Simulator Communicator: IF contacted by MCR to investigate the causes of the A and later the B MFW pump trip report that both breakers have tripped on overcurrent. There are no signs of damage at the pumps.

14. CHECK Hotwell level trending to between 71% and BOP (YES) 76%.

15. RESET Loss of Load interlocks C7A and C7B, as follows:

BOP (Steam Dumps are in Steam Pressure Mode at this time)

16. NOTIFY Load Dispatcher of ANY load limitations.

SRO (Generator is not connected to the Grid at this time)

17. CHECK Reactor thermal power changed by less (YES) than 15% in any one hour period. [C.1]

SRO

18. Within 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> of load rejection, CHECK control rods above insertion limits. (YES)

SRO EXIT this procedure.

OWP- Refer to OWP-ESF-07 to install jumpers to place required SRO ESF-07 channels in the tripped condition.

Contacts WCC for support, requests WR and LCOTR.

SRO Contacts I&C to have channel removed from service.

Harris 2020 NRC Exam Scenario 3 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 5 Page 34 of 73 MFP A trips with MFP B failure to start Event

Description:

(AOP-010)

Time Position Applicants Actions or Behavior IF WCC is contacted then report that Electrical Simulator Maintenance is investigating the problems with the Communicator: breakers and any repairs will be made as quickly as possible.

Any Tech Spec evaluation may be completed with a Evaluator Note:

follow-up question after the scenario.

Enters Instrumentation TS 3.3.2 Functional Unit 6.f ACTION 15 - With the number of OPERABLE SRO channels one less than the Total Number of Channels, operation may proceed until performance of the next required CHANNEL OPERATIONAL TEST provided the inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

Once the plant has stabilized, cue Simulator Operator to insert Trigger 6 Lead Evaluator:

Event 6: RCP B rising vibration (AOP-018)

Harris 2020 NRC Exam Scenario 3 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 6 Page 35 of 73 Event

Description:

RCP B rising vibration (AOP-018)

Time Position Applicants Actions or Behavior On cue from the Lead Evaluator actuate Trigger 6 Simulator Operator:

RCP B rising vibration (AOP-018)

• ALB-010-2-5, RCP-B TROUBLE Available Indications

• RCP B vibration monitors rising and red high vibration lights lit RO RESPONDS to alarms and ENTERS AOP-018 AOP-018 Reactor Coolant Pump Abnormal Conditions Immediate Action RO 1. CHECK any CSIP running. (YES)

ENTERS and directs actions of AOP-018, SRO Conducts a Crew Update Makes PA announcement for AOP entry

2. REFER TO PEP-110, Emergency Classification And SRO Protective Action Recommendations, AND ENTER the EAL Matrix.

Minimum allowable flow for a CSIP is 60 gpm which is provided by normal miniflow during normal operation and alternate Procedure Note:

miniflow during safety injection. Maintaining CSIP flow greater than or equal to 60 gpm also satisfies this requirement.

3. EVALUATE plant conditions AND GO TO the appropriate section:

MALFUNCTION: High Reactor Coolant Pump Vibration, Section 3.2 Page 8 The following question may be YES at this time but the limit will be exceeded quickly. This is a continuous action Evaluator Note:

step and implemented when the limit is exceeded. The guide is therefore written as if the limit is exceeded.

Harris 2020 NRC Exam Scenario 3 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 6 Page 36 of 73 Event

Description:

RCP B rising vibration (AOP-018)

Time Position Applicants Actions or Behavior

1. CHECK ALL RCPs operating within the limits of (NO)

Attachment 1 (Page 22).

RO SRO 1. RNO: GO TO STEP 3 RO 3. CHECK the Reactor is TRIPPED. (NO)

The SRO should conduct a Crew Update and review AOP-018 Section 3.2 steps 4 through 7 and direct these Evaluator Note:

actions to be performed after the E-0 immediate actions are ensured complete.

3. RNO: TRIP the Reactor AND GO TO EOP-E-0. (Perform SRO Steps 4 through 7 as time permits.)

Upon entering EOP-E-0, Rx WILL NOT trip from RPS or Evaluator Note:

MCB switches EOP-E-0 REACTOR TRIP OR SAFETY INJECTION SRO 1. Directs manual Reactor Trip

1. RNO Initiates a MANUAL Reactor trip. from center section of RO the Main Control Board (switch is failed).

1.a RNO Attempts to initiate a MANUAL Reactor Trip from left RO section of the Main Control Board (switch is failed).

Harris 2020 NRC Exam Scenario 3 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 6 Page 37 of 73 Event

Description:

RCP B rising vibration (AOP-018)

Time Position Applicants Actions or Behavior Both manual reactor trip switches must be actuated before Procedure Note:

initiating a manual turbine trip.

1.a RNO IF the reactor will not trip after using both MCB SRO manual trip switches, THEN go to FR-S.1, "RESPONSE TO NUCLEAR POWER GENERATION/ATWS", Step 1.

Harris 2020 NRC Exam Scenario 3 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 7 Page 38 of 73 Failure of the Reactor Trip breakers to open auto or manual Event

Description:

(EOP-FR-S.1)

Time Position Applicants Actions or Behavior During the ATWS - the crew makes a PA announcement for Simulator an operator to contact or report to the MCR for Communicator: instructions to locally trip the Reactor. CALL the MCR as the TB AO and get the instructions.

After the TB AO has received instructions to locally trip the Reactor, wait 1 minute then run TRG-15. Trigger 15 will Simulator Operator: delete the ATWS malfunction (RPS01B) and trip the Reactor locally. After running TRG-15 call MCR and report that the Rx trip breakers were locally opened.

EOP-FR-S.1 is the first transition step from EOP-E-0 and contains immediate action step required to be performed Evaluator Note:

from memory. Because of this the SRO may proceed directly to EOP-FR-S.1.

EOP- FR-S.1 Response to Nuclear Power Generation / ATWS To maximize core cooling, RCPs should NOT be tripped with reactor power GREATER THAN 5%. (Normal support Procedure Caution: conditions for running RCPs are NOT required for these circumstances. The RCP TRIP CRITERIA for small break LOCA conditions is NOT applicable to this procedure.)

Procedure Note: Steps 1 through 2 are immediate action steps.

1. Ensure Reactor Trip:

a. Reactor Trip AND Bypass BKRs - OPEN (NO)

Immediate Action RO (NO)

b. Rod bottom lights (Zero Steps) - LIT (NO)

c. Neutron flux - DROPPING

1. RNO actions:

IF the reactor will NOT trip (automatically AND after using both RO manual trip switches), THEN verify negative reactivity inserted by any of the following while continuing with this procedure:

1) Manually insert control rods

2) Ensure control rods inserting in automatic Harris 2020 NRC Exam Scenario 3 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 7 Page 39 of 73 Failure of the Reactor Trip breakers to open auto or manual Event

Description:

(EOP-FR-S.1)

Time Position Applicants Actions or Behavior Immediate 2. Check Turbine Trip:

Action BOP (NO)

d. All turbine throttle valves - SHUT

2. RNO actions:

BOP Manually Trip Main Turbine from MCB When the Main Turbine is tripped RCS pressure will rapidly raise and one or more Pressurizer PORVs will lift.

With RCS break flow occurring, the RCS pressure will Evaluator Note:

steadily drop. SG pressure will also rapidly rise and cause all SG PORVs to OPEN and most of the SG safety valves to lift.

3. Ensure All AFW Pumps - RUNNING BOP (Starts ALL available AFW pumps)

4. Direct an operator to report to the main control room to SRO receive instructions for local actions (Local Actions to trip the reactor or turbine are directed in step 9).

SRO 5. Inform SM to Evaluate EAL Matrix (Refer to PEP-110).

Harris 2020 NRC Exam Scenario 3 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 7 Page 40 of 73 Failure of the Reactor Trip breakers to open auto or manual Event

Description:

(EOP-FR-S.1)

Time Position Applicants Actions or Behavior Actuation of the sequencer inhibits operation of the boric acid pumps. (If the sequencer runs on Program A, the pumps can Procedure Note: be started manually after LB-9. Otherwise, the sequencer must be reset to restore operation of the pumps)

SI flow accomplishes emergency boration.

After the reactor is tripped, RCS pressure will rapidly lower to the Auto SI setpoint (1850 psig). The crew may/may not have time to manually actuate SI; as such, there is no Evaluator Note: problem with the crew NOT performing a manual SI.

After the reactor is tripped, the A CSIP will trip on an electrical fault, and the Safeguards Sequencer will fail to start the B CSIP.

6. Initiate Emergency Boration of RCS:

a. Check SI flow - GREATER THAN 200 GPM. (NO) 6.a RNO: Go to Step 6.c

c. Emergency borate from the BAT:

1) Start a boric acid pump.

2) Perform any of the following (listed in order of preference):

RO e. Open Emergency Boric Acid Addition valve:

1CS-278

f. Open normal boration valves:

FCV-113A FCV-113B

3) Ensure boric acid flow to CSIP suction - AT LEAST 30 GPM

4) Ensure CSIP flow to RCS - AT LEAST 30 GPM RO d. Check PRZ Pressure - LESS THAN 2335 PSIG. (YES)

SRO e. Go to Step 8.

Harris 2020 NRC Exam Scenario 3 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 7 Page 41 of 73 Failure of the Reactor Trip breakers to open auto or manual Event

Description:

(EOP-FR-S.1)

Time Position Applicants Actions or Behavior

8. Isolate CNMT Ventilation:

a. Stop the following fans: (If running)

• AH-82A NORMAL PURGE SUPPLY FAN BOP

• AH-82B NORMAL PURGE SUPPLY FAN

• E-5A CNMT PRE-ENTRY PURGE EXHAUST FAN

• E-5B CNMT PRE-ENTRY PURGE EXHAUST FAN

b. Ensure the valves and dampers listed in the table BOP (YES)

- SHUT.

The following actions will be complete IF local AO actions Evaluator Note: have been completed; IF NOT the RNO steps will be directed by the Crew.

9. Check Trip Status:

RO

a. Check Reactor - TRIPPED (NO) 9.a RNO actions:

Direct and AO to perform the following local actions:

Locally trip the reactor using any of the following (listed in order of preference):

SRO 1) Locally trip both reactor trip breakers:

2) Locally trip both reactor trip bypass breakers:

3) Locally trip both rod drive MG set generator output breakers:

4) Locally trip both rod drive MG set motor breakers:

Harris 2020 NRC Exam Scenario 3 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 7 Page 42 of 73 Event

Description:

Failure of the Reactor Trip breakers to open auto or manual (EOP-FR-S.1)

Time Position Applicants Actions or Behavior BOP b. Check turbine - TRIPPED (YES)

The following actions will be performed once ATWS condition is clear (1 minute after the crew directs the Local AO actions).

After the reactor is tripped, the A CSIP will trip on an Evaluator Note: electrical fault, IF ATWS condition is not clear the REACTOR SUBCRITICALITY CRITERIA FOLDOUT will apply and the Crew will continue with EOP-FR-S.1 until the foldout criteria is satisfied.

10. Check Reactor Subcritical:

a. Check for both of the following:

RO

• Power range channels - LESS THAN 5% (YES)

• Intermediate range startup rate channels - (YES)

NEGATIVE SRO b. Observe CAUTION prior to Step 25 and go to Step 25.

Boration should continue to obtain adequate shutdown margin Procedure Caution:

during subsequent recovery actions.

SRO 25. Initiate Monitoring of Critical Safety Function Status Trees.

SRO 26. Return to Procedure And Step In Effect.

SRO Returns to procedure in effect (EOP-E-0, Step 1)

Evaluator Note: The SRO should return to EOP-E-0, Step 1 Harris 2020 NRC Exam Scenario 3 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 8 Page 43 of 73 Small Break LOCA Event

Description:

(EOP-E-0)

Time Position Applicants Actions or Behavior SRO Transitions to EOP-E-0, Step 1 EOP-E-0 Reactor Trip Or Safety Injection Enters EOP-E-0 SRO Holds crew update RO/BOP Re-performs E-0 Immediate Actions.

1. Ensure Reactor Trip:

Immediate (YES)

Actions RO (YES)

(YES)

2. Check Turbine Trip - ALL THROTTLE VALVES SHUT (YES)

Immediate (YES)

Actions BOP (YES)

(YES)

3. Perform The Following:

Immediate

• AC Emergency Buses - AT LEAST ONE (YES)

Actions BOP ENERGIZED (YES)

• AC Emergency Buses - BOTH ENERGIZED Harris 2020 NRC Exam Scenario 3 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 8 Page 44 of 73 Small Break LOCA Event

Description:

(EOP-E-0)

Time Position Applicants Actions or Behavior After the reactor is tripped, RCS pressure will rapidly lower, to the Auto SI setpoint (1850 psig). The crew may/may not have time to manually actuate SI; as such, there is no problem with the crew NOT performing a Evaluator Note: manual SI.

After the reactor is tripped, the A CSIP will trip on an electrical fault, and the Safeguards Sequencer will fail to start the B CSIP.

4. Safety Injection - ACTUCATED (BOTH TRAINS)

(YES)

Immediate Actions RO Steps 1 through 4 are immediate action steps Procedure Note:

Foldout applies. (Immediate actions should be completed prior implementing Foldout Page items.)

Following completion of the EOP-E-0 immediate actions Evaluator Note: the RO should complete AOP-018, section 3.2 Step 4-7 as directed by the SRO prior to the ATWS Event.

AOP-018 Reactor Coolant Pump Abnormal Conditions Directs RO/BOP to secure the RCP B and continue with SRO AOP-018 steps 4-7

4. STOPS RCP B RO/BOP 6. RNO places PK-444D.1 to manual then shuts valve with demand at 0%

Harris 2020 NRC Exam Scenario 3 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 9 Page 45 of 73 Failure of B Sequencer Load Block 1 to actuate during the Safety Injection Event

Description:

which fails to start B CSIP (EOP-E-0)

Time Position Applicants Actions or Behavior SRO Reviews Foldout page Evaluator Note:

5.a Assigns Foldout items:

Alternate Miniflow Open/Shut Criteria, RHR Restart Criteria, AFW Supply Switchover Criteria SRO 5.b Directs Shift Manager to Evaluate EAL Matrix (Refer to PEP-110)

RO 6. Ensure CSIPs - ALL RUNNING (NO)

Checks Safeguards Sequencer has reached Load Block 9 Critical (Manual Load Permissive)

Task # 2 RO Starts B CSIP (Critical to manually start B CSIP to prevent RVLIS Dynamic Range Level from lowering below 33%.)

Harris 2020 NRC Exam Scenario 3 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 8 Page 46 of 73 Small Break LOCA Event

Description:

(EOP-E-0) Continued Time Position Applicants Actions or Behavior The following actions should be taken in accordance with EOP-E-0 Foldout criteria during the scenario:

• When RCP trip criteria is met per Foldout the crew should have the B CSIP running, identify the Evaluator Note:

condition and then trip all running RCPs

• Ensure Alternate Miniflow Isolation Valves CLOSE or CLOSE the Miniflow Block Valves when RCS Pressure lowers to less than 1800 PSIG.

RO 7. Ensure RHR pumps - ALL RUNNING (YES)

RO 8. Safety Injection flow - GREATER THAN 200 GPM (YES)

Identifies Foldout RCP Trip Criteria is MET SI flow > 200 GPM RCS pressure < 1400 psig Critical Task # 3 RO Informs SRO that RCP trip criteria is met Secures ALL RCPs (Critical to secure all RCPs with SI flow > 200 gpm and RCS pressure < 1400 psig to prevent RVLIS Dynamic Range Level from lowering below 33%.)

RO 9. RCS pressure - LESS THAN 230 PSIG (NO)

SRO 9. RNO: GO TO Step 12.

BOP 12. MAIN Steam isolation - ACTUATED. (NO)

12. RNO: Check Main Steam Line Isolation - (NO)

REQUIRED Perform the following:

SRO

• IF Main Steam Isolation is NOT required, THEN go to Step 16.

Harris 2020 NRC Exam Scenario 3 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 8 Page 47 of 73 Small Break LOCA Event

Description:

(EOP-E-0) Continued Time Position Applicants Actions or Behavior

16. CHECK CNMT Pressure - HAS REMAINED LESS (YES)

RO THAN 10 PSIG

17. Ensure AFW flow - AT LEAST 200 KPPH (YES)

RO/BOP ESTABLISHED

18. Sequencer Load Block 9 (Manual Loading BOP (YES)

Permissive) - ACTUATED (BOTH TRAINS)

BOP 19. Energize AC buses 1A1 AND 1B1 The RO will perform all board actions until the BOP completes Attachment 3. The BOP is permitted to properly align plant equipment in accordance with EOP-E-0, Attachment 3 without SRO approval.

Evaluator Note: The Scenario Guide still identifies tasks by board position because the time frame for completion of Attachment 3 is not predictable.

EOP-E-0, Attachment 3, Safeguards Actuation Verification has been included as Attachment 3 (Pg 67 of

73) at the end of this scenario.

20. Ensure Alignment of Components From Actuation of BOP ESFAS Signals Using Attachment 3, Safeguards Actuation Verification, While Continuing with this Procedure.

Harris 2020 NRC Exam Scenario 3 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 10 Page 48 of 73 Failure of Safety Injection Isolation valves on 'A' Train CSIP Event

Description:

normal mini flow 1CS-214 fails to close automatically Time Position Applicants Actions or Behavior Attachment 3 Step 5. Ensure SI Valves - PROPERLY ALIGNED (Refer to Attachment 1.)

BOP Event 10 Identifies that 1CS-214, CSIP normal miniflow valve is not SHUT and manually shuts valve to align the system correctly.

Attachment 1 (Pg 66 of 73) at the end of this scenario.

Directs AO to place 1A and 1B Air Compressor in the local BOP control mode per E-0 Attachment 3 step 22 Acknowledge the request to place 1A and 1B Air Simulator Compressor in the local control mode per Communicator E-0 Attachment 3 step 22 When directed to place the 1A and 1B Air Compressor in Simulator Operator the local control mode: Run APP\air\acs_to_local When the APP for 1A and 1B Air Compressor has Simulator completed running call the MCR and inform them that the Communicator air compressors are running in local control.

Directs AO to Unlock AND Turn ON The Breakers For The BOP CSIP Suction AND Discharge CrossConnect Valves per E-0 Attachment 3 step 23 (or from step 11 - refer to Attachment 2)

Acknowledge the request to Unlock AND Turn ON The Simulator Breakers For The CSIP Suction AND Discharge Cross Communicator Connect Valves When directed to Unlock AND Turn ON The Breakers for Simulator Operator the CSIP Suction AND Discharge CrossConnect Valves:

Run APP\cvc\E-0 Att 2 CSIP suct & disch valve power.txt.

When the APP for CSIP Suction AND Discharge Cross Simulator Connect Valves has completed running call the MCR and Communicator inform them that CSIP Suction AND Discharge Cross Connect Valves are energized.

Harris 2020 NRC Exam Scenario 3 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 9 Page 49 of 73 Small Break LOCA Event

Description:

(EOP-E-0) Continued Time Position Applicants Actions or Behavior

21. Stabilize And Maintain Temperature Between 555°F To 559°F Using Table 1.

BOP/RO Identifies RCS cooldown continues and shuts MSIVs CREW NOTE: MSIVs may have been shut from MSLI

22. PRZ PORVs - SHUT (YES)

RO 23. PRZ Spray Valves - SHUT (RCPs are secured) (YES)

24. PRZ PORV Block Valves - AT LEAST ONE OPEN (YES)

25. Any SG pressure - DROPPING IN AN (NO)

SRO UNCONTROLLED MANNER OR COMPLETELY DEPRESSURIZED SRO 25. RNO: GO TO Step 27.

27. Any SG - ABNORMAL RADIATION (NO)

SRO OR UNCONTROLLED LEVEL RISE Harris 2020 NRC Exam Scenario 3 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 9 Page 50 of 73 Small Break LOCA Event

Description:

(EOP-E-1)

Time Position Applicants Actions or Behavior SRO 27. RNO: GO TO Step 30.

SRO 30. CNMT pressure - NORMAL (NO)

30. RNO: GO TO E-1, "LOSS OF REACTOR OR SRO SECONDARY COOLANT", Step 1.

SRO Transitions to EOP-E-0, Step 1 EOP-E-1 Loss Of Reactor Or Secondary Coolant Enters EOP-E-1 SRO Holds crew update Procedure Note Foldout applies.

SRO Review Foldout page Harris 2020 NRC Exam Scenario 3 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 9 Page 51 of 73 Small Break LOCA Event

Description:

(EOP-E-1)

Time Position Applicants Actions or Behavior Evaluator Note:

SRO Assigns Foldout items:

SRO 1. Initiate Monitoring Of Critical Safety Function Status Trees.

The crew should review foldout criteria.

Evaluator Note: The crew identify and use Adverse Values identified in brackets in the EOP procedures [ ] when Containment Pressure exceeds 3 PSIG

2. Maintain RCP Seal Injection flow between 8 GPM AND RO 13 GPM.

Harris 2020 NRC Exam Scenario 3 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 9 Page 52 of 73 Small Break LOCA Event

Description:

(EOP-E-1)

Time Position Applicants Actions or Behavior

3. Check Intact SG Levels:

a. Any level - GREATER THAN 25% [40%]. (YES)

(Dependent on timing - same results)

BOP b. Control feed flow to maintain all intact levels between 25% AND 50% [40% AND 50%].

c. Any level - RISING IN AN UNCONTROLLED (NO)

MANNER.

SRO 3.c RNO: GO TO Step 4.

4. Check PZR PORV block valves:

a. Ensure AC buses 1A1 AND 1B1 - Energized (YES)

RO b. Check PORVs Shut (YES)

c. Go to Step 4.f.

(YES)

f. Check block valves - AT LEAST ONE OPEN.

5. Check SI Termination Criteria:

(YES/

a. RCS subcooling - GREATER THAN NO)

RO o 10°F [40°F] - C o 20°F [50°F] - M (Dependent on timing - same results)

IF Subcooling > 10°F then the check is performed, Evaluator Note:

otherwise the following is N/A

b. Check secondary heat sink by observing any of the following:

BOP o Level in at least one intact SG - >25% [40%] (YES) o Total feed flow to intact SGs - > 200 KPPH (YES)

c. RCS pressure - Stable Or Rising (YES/

RO d. PRZ level - GREATER THAN 10% [30%]

NO)

(Dependent on timing - same results)

Harris 2020 NRC Exam Scenario 3 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 9 Page 53 of 73 Small Break LOCA Event

Description:

(EOP-E-1)

Time Position Applicants Actions or Behavior

e. WHEN the SI termination criteria are met, THEN GO TO SRO EOP-ES-1.1, SI TERMINATION, Step 1. (not met initially)

6. Check CNMT Spray Status:

RO (NO)

a. Check any CNMT Spray Pump - RUNNING.

6.a RNO: Perform the following:

SRO IF CNMT spray pumps were NOT stopped by operator action, THEN go to Step 9.

9. Check Source Range Detector Status:

a. Intermediate range flux - LESS THAN 5x10-11 (YES)

RO AMPS

b. Ensure source range detectors - ENERGIZED

c. Transfer nuclear recorder to source range scale

10. Check RHR Pump status:

a. Check RHR pump suction - ALIGNED TO RWST (YES)

b. RCS Pressure greater than 230 PSIG (YES)

c. RCS pressure - STABLE OR RISING (YES)

RO o YES - Stop RHR pumps

b. RCS Pressure greater than 230 PSIG o NO - leave RHR pumps on. (NO)

(Dependent on timing)

The evaluation/trend of RCS pressure in the next several steps is dependent on how long it took the crew to reach Evaluators Note:

these steps (Decay Heat/Break Flow/ECCS flow). Pressure should be stable or lowering at this point.

11. Check RCS And SG Pressures:

a. Check for both of the following:

(YES)

• All SG Pressures - STABLE OR RISING.

(YES)

• RCS pressure - STABLE OR DROPPING.

Harris 2020 NRC Exam Scenario 3 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 9 Page 54 of 73 Small Break LOCA Event

Description:

(EOP-E-1)

Time Position Applicants Actions or Behavior If the evaluation/trend of RCS pressure in the previous Evaluators Note: step was rising the SRO will return to EOP-E-1, Step 1 (Pg 51 of 73) and wait for the plant to stabilize.

12. Establish CCW Flow To The RHR Heat Exchangers:

a. Ensure both CCW Pumps running

b. Open the following valves: (CCW Return From RHR HX) (YES)

RO o 1CC-147 Train A o 1CC-167 Train B (locates MCB switch and opens valves listed)

RO c. Ensure CCW flow to the RHR Heat Exchangers (YES)

d. Perform one of the following to establish two independent CCW systems:

o Shut train A CCW non-essential supply AND return valves:

• 1CC-99 RO

• 1CC-128 OR o Shut train B CCW non-essential supply AND return valves:

• 1CC-113

• 1CC-127 (locates MCB switch and shuts one Train of valves listed)

13. Check EDG status:

a. Check AC emergency buses 1A-SA AND 1B-SB -

BOP/RO ENERGIZED BY OFFSITE POWER (YES) o Check Bus voltages (Normal) o Check breakers 105 and 125 closed SRO b. GO TO Step 13.e.

Harris 2020 NRC Exam Scenario 3 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 9 Page 55 of 73 Small Break LOCA Event

Description:

(EOP-E-1)

Time Position Applicants Actions or Behavior BOP/RO e. Check any EDG - running unloaded (YES)

f. Reset SI RO (takes both SI reset switches to RESET and observes status light change from SI active to SI reset)

g. Manually realign safeguards equipment following a loss of offsite power.

SRO (Refer to E-0, "REACTOR TRIP OR SAFETY INJECTION",

Attachment 6.)

h. Shutdown any unloaded EDGs using OP-155, Diesel BOP Generator Emergency Power System, Section 7.0

14. Initiate Evaluation of Plant Status:

a. RHR system - CAPABLE OF COLD LEG RECIRCULATION (Refer to Attachment 2) (YES)

SRO

b. Check Auxiliary AND Radwaste Processing Building radiation - NORMAL (YES)

c. Go to Step 15.

Harris 2020 NRC Exam Scenario 3 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 9 Page 56 of 73 Small Break LOCA Event

Description:

(EOP-E-1)

Time Position Applicants Actions or Behavior Evaluator Note:

Harris 2020 NRC Exam Scenario 3 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 9 Page 57 of 73 Small Break LOCA Event

Description:

(EOP-ES-1.2)

Time Position Applicants Actions or Behavior

15. Check RCS Status

a. Check for both of the following:

RO o RCS pressure - LESS THAN 230 PSIG (NO) o Any RHR HX header flow - GREATER THAN (NO) 1000 GPM

15. RNO:GO TO Go to ES-1.2, "POST LOCA COOLDOWN SRO AND DEPRESSURIZATION", Step 1 SRO Transitions to EOP-ES-1.2, Step 1 At some point during the implementation of EOP-ES-1.2 the break will clear and the Safety Injection flow filling the RCS with cold RWST water will cause a reduction in RCS pressure and temperature.

The critical safety function status tree for RCS integrity Evaluator Note: will begin to toggle from Green to Yellow to Orange to Red.

Eventually RCS Integrity will remain RED and the crew will transition to EOP-FR-P.1.

The scenario guide is written for the transition that occurred based on the plant response during validation.

When this transition occurs will vary based on the pace of implantation by the crew.

EOP-ES-1.2 Post LOCA Cooldown and Depressurization Enters EOP-ES-1.2 SRO Holds crew update Procedure Note Foldout applies.

SRO Review Foldout page Harris 2020 NRC Exam Scenario 3 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 9 Page 58 of 73 Small Break LOCA Event

Description:

(EOP-ES-1.2)

Time Position Applicants Actions or Behavior Evaluator Note:

SRO Assigns Foldout items:

RO 1. Reset SI (already performed)

2. Manually realign safeguards equipment following a loss of SRO offsite power.

Harris 2020 NRC Exam Scenario 3 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 9 Page 59 of 73 Small Break LOCA Event

Description:

(EOP-ES-1.2)

Time Position Applicants Actions or Behavior (Refer to E-0, "REACTOR TRIP OR SAFETY INJECTION",

Attachment 6.)

3. Reset Phase A and Phase B Isolation signals

• Reset Phase A (if actuated)

RO (locates MCB Phase A switch and resets Phase A)

• Reset Phase B (if actuated)

(Phase B not actuated)

4. Open Instrument Air and Nitrogen valves to CNMT RO

• 1IA-819

• 1SI-287 (locates MCB switches and opens valve)

5. Monitor AC Buses:

a. Check AC emergency buses 1A-SA AND 1B-BOP/RO SB - ENERGIZED BY OFFSITE POWER (YES) o Check Bus voltages (Normal) o Check breakers 105 and 125 closed SRO b. GO TO Step 5.e.

The scenario guide is written for the transition to EOP-FR-Evaluator Note: P.1 at this point in the scenario based on the plant response during validation. When this transition occurs will vary based on the pace of implantation by the crew.

EOP-FR-P.1 Response to Imminent Pressurized Thermal Shock Enters EOP-FR-P.1 SRO Holds crew update Procedure Note Foldout applies.

Harris 2020 NRC Exam Scenario 3 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 9 Page 60 of 73 Small Break LOCA Event

Description:

(EOP-FR-P.1)

Time Position Applicants Actions or Behavior SRO Review Foldout page Evaluator Note:

1. Check RCS Pressure:

a. Check for both of the following:

• RCS pressure - LESS THAN 230 PSIG (NO)

RO

• Any RHR HX header flow - > 1000 GPM (NO)

RO restarts RHR pumps when RCS pressure < RHR shutoff head - EOP-ES-1.2 foldout action item SRO 1.a RNO: GO TO Step 2.

2. Check RCS Cold Leg Temperature Trend:

RO a. Check RCS Cold Leg Temperatures - STABLE (NO)

OR RISING SRO 2. RNO: Observe NOTE prior to Step 3 and GO TO Step 3.

Procedure Note: A faulted SG is any SG that is depressurizing in an uncontrolled manner or is completely depressurized.

Harris 2020 NRC Exam Scenario 3 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 9 Page 61 of 73 Small Break LOCA Event

Description:

(EOP-FR-P.1)

Time Position Applicants Actions or Behavior

3. Stop RCS Cooldown:

a. Ensure SG PORVs - SHUT (YES)

b. Ensure condenser steam dump valves - SHUT (YES)

c. Check RHR system - IN SHUTDOWN COOLING (NO)

BOP MODE 3.c. RNO: Go to Step 3.e.

e. Any non-faulted SG level - > 25% [40%] (YES)

f. Control feed flow to non-faulted SG(s) to stop RCS cooldown.

IF the TDAFW pump is the only available source of feed flow, Procedure Caution: THEN maintain steam supply to the TDAFW pump from one SG.

BOP 4. Minimize RCS Cooldown From Faulted SG(s):

a. Check any SG - FAULTED (NO)

SRO 4.a. RNO: GO TO Step 5.

5. Check PRZ PORV Block Valves:

RO a. Ensure power to block valves - AVAILABLE (YES)

b. Check block valves - AT LEAST ONE OPEN (YES)

Procedure Note: IF PRZ PORV opens on high pressure, Step 6 should be repeated after pressure drops to less than PORV setpoint.

6. Check PRZ PORVs:

RO a. Check all of the following:

1) Check LTOPS control switches - IN NORMAL (NO)

(NOT BLOCKED)

SRO 6.a. RNO: GO TO Step 6.d.

RO d. Check PRZ pressure - < 2335 psig (YES)

e. Ensure PRZ PORVs - SHUT (YES)

Harris 2020 NRC Exam Scenario 3 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 9 Page 62 of 73 Small Break LOCA Event

Description:

(EOP-FR-P.1)

Time Position Applicants Actions or Behavior RO 7. Check SI Flow - > 200 gpm (YES)

8. Check SI Termination Criteria:

SRO a. Check for both of the following:

1) RCS subcooling - > 60°F [90°F] - C (NO) 8.a. RNO: Observe CAUTION prior to Step 9 and go to Step 9.

Following a complete loss of normal seal cooling, the affected Procedure Caution: RCP(s) should NOT be started prior to a status evaluation performed by the Plant Operations Staff or responsible engineer.

9. Check If An RCP Should Be Started:

SRO a. RCS subcooling - GREATER THAN 10°F

[40°F] - C (NO) 9.a. RNO: Observe CAUTION prior to Step 33 and go to Step 33.

Following an excessive cooldown, reactor vessel stress must Procedure Caution: be relieved to enhance and maintain vessel integrity. Do NOT perform any actions that raise pressure OR cause an RCS cooldown until the soak is complete.

Even if a soak period is required, steam may be released from Procedure Note: intact SGs with pressure higher than the saturation pressure for lowest cold leg temperature.

33. Determine RCS Soak Requirements:

a. RCS cooldown rate - > 100°F in any 60 min period (YES)

b. Perform one hour RCS soak:

• Maintain RCS temperature stable.

SRO

• Maintain RCS pressure stable.

• Perform actions of other procedures that do NOT cause an RCS cooldown OR raise pressure.

Harris 2020 NRC Exam Scenario 3 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 9 Page 63 of 73 Small Break LOCA Event

Description:

(EOP-ES-1.2)

Time Position Applicants Actions or Behavior

34. Establish Subsequent Cooldown:

a. RCS subcooling monitor - AVAILABLE (YES)

SRO b. Maintain RCS subcooling between 10°F and 190°F [40°F and 160°F].

c. Maintain RCS cooldown rate less than 50°F in any sixty minute period.

SRO 35. Return to Procedure And Step In Effect.

EOP-ES-1.2 Returns to EOP-ES-1.2 Step 5.e SRO Holds crew update SRO b. GO TO Step 5.e.

e. Check all non-emergency AC buses -

BOP/RO (YES)

ENERGIZED PRZ heaters should NOT be energized until PRZ water level Procedure Caution: indicates greater than minimum recommended by plant operations staff to ensure heaters are covered.

6. Secure PRZ Heaters:

RO

• Place backup heaters in the OFF position

• Ensure control heaters - OFF

• Consult plant operations staff for a recommended minimum indicated PRZ water level that will ensure heaters are SRO covered.

(Refer to ERG Executive Volume, Generic Issue:

Evaluations by the Plant Engineering Staff.)

Harris 2020 NRC Exam Scenario 3 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 9 Page 64 of 73 Small Break LOCA Event

Description:

(EOP-ES-1.2)

Time Position Applicants Actions or Behavior

7. Check if RHR Pumps should be stopped:

a. Check RHR pump suction - ANY RUNNING WITH SUCTION ALIGNED TO RWST

b. Check RCS Pressure: (YES)

• RCS Pressure greater than 230 PSIG RO (YES)

• RCS Pressure STABLE OR RISING (YES)

c. Stop RHR pumps

• RCS Pressure STABLE OR RISING (NO) o NO - leave RHR pumps on and go to Step 8.

(Dependent on timing)

8. Check Intact SG Levels:

a. Any level - GREATER THAN 25% [40%] (YES)

BOP

b. Control feed flow to maintain all intact levels between 25% and 50% [40% and 50%].

After the low steam pressure SI signal is blocked, main Procedure Note: steamline isolation will occur if the high steam pressure rate setpoint is exceeded.

9. Check PRZ Pressure:

a. Pressure - less than 2000 PSIG (YES)

RO b. Block low steam pressure SI (Locates Low Steam Line Pressure SI MCB block switch and places switch to block - verifies block on status lights)

Even if the lowest RCS cold leg temperature has dropped by 100°F in the last 60 minutes, steam may be released from Procedure Note:

intact SGs with pressure higher than the saturation pressure for lowest cold leg temperature.

10. Initiate RCS Cooldown To Cold Shutdown:

a. Maintain Cooldown rate in RCS cold legs - <100F/HR SRO (SRO should maintain requirements of EOP-FR-P.1

<50F/HR until the 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> soak is complete.)

Harris 2020 NRC Exam Scenario 3 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 9 Page 65 of 73 Small Break LOCA Event

Description:

(EOP-ES-1.2)

Time Position Applicants Actions or Behavior

b. Check RHR system - OPERATING IN RO (NO)

SHUTDOWN COOLING MODE SRO 10.b RNO: GO TO Step 10.f

f. Check all of the following to determine if steam can be dumped to condenser:

o Check any intact SG MSIV - OPEN (NO)

BOP (NO) o Condenser Available (C-9)- LIT (BPLB 3-3)

(YES) o Steam Dump Control - AVAILABLE The may recouple RCS with SGs which will require SG PORVs to be opened and SG pressure reduced. The SRO should maintain requirements of EOP-FR-P.1 until the 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> soak is complete.

Evaluator Note: o Maintain RCS temperature stable.

o Maintain RCS pressure stable.

o Perform actions of other procedures that do NOT cause an RCS cooldown OR raise pressure.

10.f. RNO: Dump steam from intact SGs using any of the following (listed in order of preference):

BOP 1) SG PORVs

2) Locally operate SG PORVs

3) TDAFW pump Terminate the scenario when the crew discusses their plan for cooldown of the RCS.

Announce Crew Update - End of Evaluation - I have the Lead Evaluator:

shift.

Have crew remain in the Simulator without discussing the exam. Examiners will formulate any follow-up questions.

Simulator Operator: When directed by Lead Evaluator go to FREEZE Harris 2020 NRC Exam Scenario 3 Rev FINAL

Appendix D Form ES-D-2 E-0 Attachment 1 Harris 2020 NRC Exam Scenario 3 Rev FINAL

Appendix D Form ES-D-2 E-0 Attachment 3 Harris 2020 NRC Exam Scenario 3 Rev FINAL

Appendix D Form ES-D-2 E-0 Attachment 3 Harris 2020 NRC Exam Scenario 3 Rev FINAL

Appendix D Form ES-D-2 E-0 Attachment 3 Harris 2020 NRC Exam Scenario 3 Rev FINAL

Appendix D Form ES-D-2 E-0 Attachment 3 Harris 2020 NRC Exam Scenario 3 Rev FINAL

Appendix D Form ES-D-2 E-0 Attachment 3 Harris 2020 NRC Exam Scenario 3 Rev FINAL

Appendix D Form ES-D-2 E-0 Attachment 3 Harris 2020 NRC Exam Scenario 3 Rev FINAL

Appendix D Form ES-D-2 E-0 Attachment 3 Harris 2020 NRC Exam Scenario 3 Rev FINAL

Plant Status

• A Reactor S/U has been completed 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after a Reactor trip

• GP-005 was being performed by the previous shift

• The plant was in Mode 1

• GP-005 Turbine valve testing complete

• At that time secondary chemistry parameters degraded and Reactor power was lowered to < 5%

• Conditions are as follows:

o The plant is in Mode 2 at 3% power o Mode 1 MEL is complete o Turbine speed is 1700 rpm o A Train equipment is in service o A Train Main Feedwater Pump and Both Condensate and Condensate Booster pumps are in service o FRV bypass valves are controlling S/G levels o Rod position is CBD at 102 steps o RCS Boron is 1472 ppm o MOL conditions o Normal Dayshift o Status Board is updated

• Your crew directions are to hold present plant condition

• You will then be relieved by the JITT Trained Startup crew Equipment Out of Service:

• B NSW Pump is under clearance for motor repairs. The pump has been unavailable for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

Repairs are expected to be completed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. A NSW Pump is protected Reactivity Plan/Brief:

• Use the current OPT-1536, Routine Reactivity Data Calculation, maintain current reactor power. The previous reactivity addition was a 20 gallon boration 15 minutes earlier Risk Assessment:

• GREEN 2020 NRC Exam Simulator Scenario 3 Turnover Rev FINAL

Appendix D Scenario Outline Form ES-D-1 HARRIS 2020 NRC SCENARIO 4 Facility: Harris Nuclear Plant Scenario No.: 4 Op Test No.: 05000400/2020301 Examiners: Operators: SRO:

RO:

BOP:

Initial Conditions: IC-19 MOL, 100% power

• 1CS-9, Letdown Isolation Valve is under clearance for solenoid replacement

• B MDAFW Pump is under clearance for pump packing repairs

• B DEH Pump Out of Service Turnover: The plant is at 100% power, middle of core life. GP-006 step 4

• Manually maintain control of SG A level above 25% to prevent an automatic Reactor trip after steam pressure transmitter PT-475 fails low Critical Task:

• Manually maintain control of PRZ Pressure above 1960 psig to prevent an automatic Reactor trip after the pressure transmitter PT-444 fails high

• Initiate RCS Bleed and Feed for Successful High-Head SI Pump Injection prevent RVLIS Full Range Level from lowering below 39%.

Event No. Malf. No. Event Type* Event Description R - RO/SRO 1 N/A Power reduction from 100% power N - BOP/SRO C - RO/SRO Normal Service Water Pump A sheared shaft (AOP-022) 2 sws07a TS - SRO I - RO/SRO 3 prs06a Pressurizer PORV 445A Leakage (AOP-016)

TS - SRO 4 gen15 C - BOP/SRO Generator Voltage Regulator Failure I - BOP/SRO Feed pressure transmitter failure low on A SG PT-475 (AOP-5 pt:475 TS - SRO 010)

C - RO/SRO 6 pt:444 PT-444 Fails HIGH (AOP-019)

TS - SRO eps01 Loss of Offsite Power with a Feed line break inside CNMT 7 cfw01c M - ALL cfw20a (EOP-E-0) mss05a mss05b Main Steamline Isolation fails, 'B' CCW pump fails to Auto 8 mss05c C - BOP/SRO start dsg04b 9 cfw01a M - ALL 'A' MDAFW pump trips after the Reactor trips (EOP-FR-H.1) 10 prs03e C - RO/SRO Pressurizer PORV 445B fails to open

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Harris 2020 NRC Exam Scenario 4 Rev FINAL

Appendix D Scenario Outline Form ES-D-1 HARRIS 2020 NRC SCENARIO 4 SCENARIO

SUMMARY

2020 NRC EXAM SCENARIO 4 The plant is at 100% power, middle of core life. Due to the B MDAFW pump LCO expiring, a normal shutdown in accordance with GP-006, Normal Plant Shutdown From Power Operation To Hot Standby (Mode 1 To Mode 3) is in progress as directed by plant management. Continue the shutdown @ 4 MW/min with TCS Load Control at 4 GVPC units/ min The following equipment is under clearance:

• MDAFW Pump B-SB is under clearance for pump packing repairs. The pump has been inoperable for 66 hours7.638889e-4 days <br />0.0183 hours <br />1.09127e-4 weeks <br />2.5113e-5 months <br /> and cannot be restored to operable status. Tech Spec 3.7.1.2 Action a and Tech Spec 3.3.3.5.b Action c applies.

Harris 2020 NRC Exam Scenario 4 Rev FINAL

Appendix D Scenario Outline Form ES-D-1 HARRIS 2020 NRC SCENARIO 4 SCENARIO

SUMMARY

2020 NRC EXAM SCENARIO 4 continued The following equipment is under clearance (continued):

• B DEH Pump is under clearance for motor repairs. The pump has been unavailable for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. Repairs are expected to be completed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

• 1CS-9, Letdown Orifice Isolation valve, has been under clearance the last 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for solenoid replacement. The repairs are close to completion and the valve is expected to be returned to service within the next hour. The valve is currently shut with power removed.

OWP-CS-09 has been completed. Tech Specs 3.6.3 Action b applies.

Harris 2020 NRC Exam Scenario 4 Rev FINAL

Appendix D Scenario Outline Form ES-D-1 HARRIS 2020 NRC SCENARIO 4 SCENARIO

SUMMARY

2020 NRC EXAM SCENARIO 4 (Continued)

Event 1: Plant Shutdown (GP-006). Turnover takes place with the unit at 100% Reactor power.

The crew will be given credit for a reactivity manipulation during the down power.

Verifiable Action: It is expected that the SRO will conduct a reactivity brief, the RO will borate and monitor auto rod insertion per the reactivity plan. The BOP will operate the DEH Turbine controls as necessary to lower power. After power is reduced 3% - 5% and the crew has demonstrated that they have control of the plant during a shutdown Event 2 will be inserted.

Event 2: Normal Service Water Pump A sheared shaft (AOP-022). This failure will result in multiple NSW alarms on ALB 002 and the crew should enter AOP-022. While NSW system pressure is low the ESW system will automatically start and isolate into the A and B train headers. With lower temperature ESW water providing cooling into Containment the potential exists for a low pressure condition to occur. This will be indicated by ALB 028-5-1, Containment Air High Vacuum.

Verifiable Action: The crew will enter AOP-022 and carry out the immediate actions. The RO will perform the immediate actions of AOP-022 by verifying that the ESW pump automatically starts and the running CSIP does not operate greater than 1 minute without cooling water. The BOP will verbalize that no EDG is running to complete the immediate actions. Once the immediate actions are complete the BOP should place the Turbine in Hold to stabilize the plant and the crew should use the AOP to start up the standby NSW pump and verify proper system operation.

The SRO should evaluate Tech Spec 3.6.1.4, Containment Systems - Internal Pressure Action.

The SRO should refer to AD-OP-ALL-1000 Attachment 4, Emergent Issue Checklists for the failure and request assistance from the WCC.

Event 3: Pressurizer PORV 445A Leakage (AOP-016). This failure will cause PRZ PORV 445A to leak, resulting in rising PRT pressure and level. PORV Line Temp indicator TI-463 will rise as observed on the MCB and the crew will respond in accordance with ALB 009-8-2, Pressurizer Relief Discharge High Temp. The crew may utilize AOP-016, Excessive Primary Plant Leakage, to determine which PORV is leaking.

Harris 2020 NRC Exam Scenario 4 Rev FINAL

Appendix D Scenario Outline Form ES-D-1 HARRIS 2020 NRC SCENARIO 4 SCENARIO

SUMMARY

2020 NRC EXAM SCENARIO 4 (Continued)

Verifiable Action: The crew may respond in accordance with the alarm response procedure APP-ALB-009 or by entering AOP-016, which has NO immediate actions. The RO will place the block valve (1RC-117) for the affected PRZ PORV (1RC-118) in the shut position and monitor the PRT parameters to confirm isolation of the PORV.

The SRO should evaluate Tech Spec 3.4.4, Reactor Coolant System - Relief Valves Action a.

The SRO should refer to AD-OP-ALL-1000 Attachment 4, Emergent Issue Checklists for the failure and request assistance from the WCC.

Event 4: Generator Voltage Regulator Failure. This will cause the automatic function of the voltage regulator to oscillate which will be indicated on the ERFIS computer Quick Plot VAC and the MCB indication EI-567, Megavars. As the amplitude of the oscillations grows if the crew continues to operate the AVR in Auto the system will reject to manual after 10 minutes.

Verifiable Action: Event 4: Generator Voltage Regulator Failure. This will cause the automatic function of the voltage regulator to oscillate which will be indicated on the ERFIS computer Quick Plot VAC and MCB indication EI-565 and EI-567, Generator Megawatts and Megavars respectively. As the amplitude of the oscillations grows ALB 022-9-4, Computer Alarm Gen/Exciter Systems and 4-3, Gen Volt/Freq Ratio Limiter Active Or Under-Freq, alarm requiring the BOP to take manual control of the AVR in order to restore control of Generator Megavars.

The SRO should refer to AD-OP-ALL-1000 Attachment 4, Emergent Issue Checklists for the failure and request assistance from the WCC.

Event 5: Feed pressure transmitter failure low on A SG FT-475 (AOP-010). This failure will cause ALB 014-1-2, 1-4, 4-1B, 4-2A, Loop A Hi Steam Line P Low-P1, Loop A Hi Steam Line Press Rate Alert, SG A Stm > FW Flow Mismatch, and Loop A Low Stm Line Press Alert respectively to alarm. The crew will respond by entering AOP-010, Feedwater Malfunction and taking manual control of A Main Feedwater Regulating Valve to raise Feedwater flow and stabilize level.

Harris 2020 NRC Exam Scenario 4 Rev FINAL

Appendix D Scenario Outline Form ES-D-1 HARRIS 2020 NRC SCENARIO 4 SCENARIO

SUMMARY

2020 NRC EXAM SCENARIO 4 (Continued)

Verifiable Action: The BOP will respond to the failure by taking the immediate actions of AOP-010 by manually controlling the A FRV and restoring level 57%. With the controller in manual and the plant stabilized the crew will implement OWP-ESF-02 to remove the failed channel from service (Critical Task #1).

The SRO should evaluate Tech Spec 3.3.1, Instrumentation - Reactor Trip System Instrumentation, Tech Spec 3.3.2, Instrumentation - Engineered Safety Features Actuation System Instrumentation and Tech Spec 3.3.3.6. Action: 6 and 19 apply respectively.

Harris 2020 NRC Exam Scenario 4 Rev FINAL

Appendix D Scenario Outline Form ES-D-1 HARRIS 2020 NRC SCENARIO 4 SCENARIO

SUMMARY

2020 NRC EXAM SCENARIO 4 (Continued)

Event 5: Tech Spec evaluation continued Harris 2020 NRC Exam Scenario 4 Rev FINAL

Appendix D Scenario Outline Form ES-D-1 HARRIS 2020 NRC SCENARIO 4 SCENARIO

SUMMARY

2020 NRC EXAM SCENARIO 4 (Continued)

Event 5: Tech Spec evaluation continued The SRO should provide a level band of 52% to 62% to the BOP in accordance with AOP-010 and OMM-001, Attachment 11, Control Bands And Administrative Limits. The SRO should refer to AD-OP-ALL-1000 Attachment 4, Emergent Issue Checklists for the failure and request assistance from the WCC.

Event 6: PT-444 Fails HIGH (AOP-019). This failure will cause multiple ALB 009 annunciators to alarm along with lowering RCS pressure and changes in Pressurizer Level and Charging flow.

This will require the crew to implement the immediate actions for AOP-019. Additionally ALB 010-8-5A, Cmptr Alarm Rx Coolant, will alarm if RCS pressure is allowed to lower below 2215 psig.

Verifiable Action: The crew will respond by entering AOP-019 and performing the immediate actions. Depending on the timing of the RO 1RC-114, PRZ PORV 444B SB may open be when the PORV status is evaluated during the AOP-019 immediate actions which will require the RO to place 1RC-114 in the shut position. The RO will place the Master Pressure controller in manual and reduce the output to shut the PRZ spray valves and 1RC-114, while energizing the PRZ Backup Heaters to restore pressure (Critical Task #2).

Harris 2020 NRC Exam Scenario 4 Rev FINAL

Appendix D Scenario Outline Form ES-D-1 HARRIS 2020 NRC SCENARIO 4 SCENARIO

SUMMARY

2020 NRC EXAM SCENARIO 4 (Continued)

The SRO should evaluate Tech Spec 3.2.5, Power Distribution Limits - DNB Parameters Action.

The SRO should refer to AD-OP-ALL-1000 Attachment 4, Emergent Issue Checklists for the failure and request assistance from the WCC.

Event 7: Loss of Offsite Power with a Feed line break inside CNMT (EOP-E-0). The major event is a Feed line Break inside containment. The SG A will degrade to a fault inside containment coincident with a loss of offsite power requiring the crew to implement the immediate actions of EOP-E-0 and stabilize the unit.

Verifiable Action: The crew will perform the EOP-E-0 immediate actions to ensure the Reactor is tripped, Turbine is tripped, and both AC emergency buses are energized. The crew should determine Safety Injection actuation is required based on rising containment pressure and sump level. They should monitor Safety Injection to ensure it automatically actuates at 3.0 psig in containment and continue with EOP-E-0. The BOP will stabilize RCS temperature using EOP-E-0, Table 1 and energize AC buses 1A1 and 1B1.

Event 8: Main Steam line Isolation fails, 'B' CCW pump fails to Auto start. The MSIVs will fail to close at 3.0 psig in containment and the sequencer will fail to start the B CCW pump.

Verifiable Action: The BOP will attempt to manually actuate MSLI from the MCB in accordance with EOP-E-0, which will not be successful and then manually place each switch in the shut position in accordance with AD-OP-ALL-1000, Conduct of Operations, (5.6.3.8) for Equipment Manipulation and Status Control, but this will not be successful as well. The RO will manually start the B CCW Pump once the B Sequencer reaches Load Block 9, Automatic Manual Harris 2020 NRC Exam Scenario 4 Rev FINAL

Appendix D Scenario Outline Form ES-D-1 HARRIS 2020 NRC SCENARIO 4 SCENARIO

SUMMARY

2020 NRC EXAM SCENARIO 4 (Continued)

Loading Permissive, in accordance with AD-OP-ALL-1000, Conduct of Operations, (5.6.3.8) for Equipment Manipulation and Status Control or EOP-E-0, Attachment 3, Safeguards Actuation Verification.

Event 9: 'A' MDAFW pump trips after the Reactor trips (EOP-FR-H.1). The crew should identify this failure and attempt to restore a source of Feedwater. Transition to EOP-FR-H.1 will be required at this time. The crew will continue with EOP-FR-H.1 until heat sink is restored or the requirement to initiate Bleed and Feed are met.

Verifiable Action: The RO will be required to secure any running RHR pumps in in accordance with EOP-FR-H.1 Event 10: Pressurizer PORV 445B fails to open. During the performance of EOP-FR-H.1 actions to establish Bleed and Feed PORV 445B the non-safety PRZ PORV will fail to open.

Verifiable Action: The crew should identify this failure and open the Reactor Vent valve to ensure an adequate RCS Bleed Path is established, in accordance with EOP-FR-H.1 step 30.

The scenario termination is met in EOP-FR-H.1 after RCS Bleed and Feed has been established prior to PRZ PORVs automatically opening (Critical Task #3).

Harris 2020 NRC Exam Scenario 4 Rev FINAL

Appendix D Scenario Outline Form ES-D-1 HARRIS 2020 NRC SCENARIO 4 CRITICAL TASK JUSTIFICATION:

1. Manually maintain control of SG A level above 25% to prevent an automatic or manual Reactor trip after steam pressure transmitter PT-475 fails low An unnecessary automatic or manual Reactor Trip for this event will create critical task.

See note below.

2. Manually maintain control of PRZ Pressure above 1960 psig to prevent an automatic or manual Reactor trip after the pressure transmitter PT-444 fails high An unnecessary automatic or manual Reactor Trip for this event will create critical task.

See note below.

3. Initiate RCS Bleed and Feed for Successful High-Head SI Pump Injection to prevent RVLIS Full Range Level from lowering below 39%

Failure to initiate RCS bleed and feed before the RCS saturates at a pressure above the shutoff head of the high-head ECCS pumps results in significant and sustained core uncovery. If RCS bleed is initiated so that the RCS is depressurized below the shutoff head of the high-head ECCS pumps, then core uncovery is prevented or minimized. At Harris the plant with no Reactor Coolant Pump operating RVLIS Full Range Level lowering below 39% will provide indication of significant core uncovery.

Note: Causing an unnecessary plant trip or ESF actuation (automatic or manual) may constitute a CT failure. Actions taken by the applicant(s) will be validated using the methodology for critical tasks in Appendix D to NUREG-1021.

Harris 2020 NRC Exam Scenario 4 Rev FINAL

Appendix D Scenario Outline Form ES-D-1 HARRIS 2020 NRC SCENARIO 4 Simulator Setup Reset to IC-144 password NRC3sros Go to RUN Silence and Acknowledge annunciators GO TO FREEZE and inform the lead examiner the Simulator is ready. DO NOT GO TO RUN until directed by the lead examiner.

Set ERFIS screens for normal full power conditions (The examiner has provided to the candidate with initial conditions and the initiating cues prior to placing the simulator in RUN.)

SPECIAL INSTRUCTIONS Provide a Reactivity Plan to candidates for shutting down the plant Provide a copy of the following procedures:

• GP-006, NORMAL PLANT SHUTDOWN FROM POWER OPERATION TO HOT STANDBY (MODE 1 TO MODE 3) marked up through section 6.2 step 4 Press START on Counter Scaler Post conditions for status board from IC-19 Reactor Power 100%

Control Bank D at 218 steps RCS boron 954 ppm Turnover: The plant is at 100% power, middle of core life. Due to the B MDAFW pump LCO expiring, a normal shutdown in accordance with GP-006, Normal Plant Shutdown From Power Operation To Hot Standby (Mode 1 To Mode 3) is in progress as directed by plant management.

Continue the shutdown @ 4 MW/min with TCS Load Control at 4 GVPC units/ min Equipment Under Clearance:

• MDAFW Pump B-SB is under clearance for motor high vibrations. The pump has been inoperable for 66 hours7.638889e-4 days <br />0.0183 hours <br />1.09127e-4 weeks <br />2.5113e-5 months <br /> and cannot be restored to operable status. Tech Spec 3.7.1.2 LCO Action a and Tech Spec 3.3.3.5.b Action c applies.

• B DEH Pump is under clearance for motor repairs. The pump has been unavailable for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. Repairs are expected to be completed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

• 1CS-9, Letdown Orifice Isolation valve, has been under clearance the last 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for solenoid replacement. The repairs are close to completion and the valve is expected to be returned this shift. The valve is currently shut with power removed. OWP-CS-09 has been completed. Tech Specs 3.6.3 Action b applies.

Harris 2020 NRC Exam Scenario 4 Rev FINAL

Appendix D Scenario Outline Form ES-D-1 HARRIS 2020 NRC SCENARIO 4 Simulator Setup (continued)

Align equipment for repairs:

Place CIT on 'B-SB' MDAFW pump MCB Switch Place protected train placards in accordance with OMM-001 Attachment 5 Protected Train placards on 'A-SA' MDAFW pump, 'B-SB' RHR Pump, 'B-SB' CCW Pump,

'B-SB' ESW Pump, 1MS-70 and 1MS-72 Place the B DEH Pump in PTL and then hang a CIT on MCB switch Place protected train placards in accordance with AD-OP-ALL-0210, Single Point Vulnerabilities Protected Train placards on A DEH Pump Place CIT on 1CS-9 MCB switch Place protected train placards in accordance with Response to Industry Best Practices, Expectations Protected train placards on A-SA ESW Pump, A-SA CCW Pump, and A-SA SFP Hx Place filled out copies of OWPs into the OWP book - ensure they are removed at end of day

• OWP-CS-09 and place in MCR OWP book for 1CS-9 clearance Harris 2020 NRC Exam Scenario 4 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 1 Page 14 of 71 Event

Description:

Power Reduction Time Position Applicants Actions or Behavior The crew has been directed to commence a power reduction from 100% to the unit is off line. The power reduction is on hold for turnover. The SRO is expected to conduct a reactivity brief prior to commencing the power reduction. This brief may be conducted outside the simulator prior to starting the scenario.

Lead Evaluator:

When the crew has completed their board walk down and are ready to take the shift inform the Simulator Operator to place the Simulator in Run. When the Simulator is in run announce:

CREW UPDATE - (SROs Name) Your crew has the shift.

END OF UPDATE When directed by the Lead Evaluator, ensure that the Simulator Operator:

annunciator horns are on and place the Simulator in RUN.

GP-006 GP-006, Section 6.2 When PRZ backup heaters are energized in manual, then PK-444A1 (PRZ Master Pressure Controller) (a PI controller) will integrate up to a greater than normal output, opening PRZ Spray Valves to return and maintain RCS pressure at setpoint.

The result is as follows:

Procedure Note:

• PORV PCV-444B will open at a lower than expected pressure.

• ALB-009-3-2 (Pressurizer High Press Deviation Control), will activate at a lower than expected pressure.

• Higher probability for exceeding Tech Spec DNB limit for RCS pressure.

4. Energize all available Pressurizer Backup Heaters per RO OP-100 Section 8.15.

The crew may elect to begin boration prior to lowering Evaluator Note:

turbine load.

Harris 2020 NRC Exam Scenario 4 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 1 Page 15 of 71 Event

Description:

Power Reduction Time Position Applicants Actions or Behavior RO OP-107.01, Section 5.2

1. DETERMINE the volume of boric acid to be added.

RO (Current OPT-1536 data or approved reactivity plan from Engineering may be used.)

SRO Directs boration FIS-113, BORIC ACID BATCH COUNTER, has a tenths Procedure Note:

position.

If the translucent covers associated with the Boric Acid and Total Makeup Batch counters FIS-113 and FIS-114, located on Procedure Caution:

the MCB, are not closed, the system will not automatically stop at the preset value.

2. SET FIS-113, BORIC ACID BATCH COUNTER, to obtain the desired quantity.

RO 3. ENSURE the RMW CONTROL switch has been placed in the STOP position.

4. ENSURE the RMW CONTROL switch green light is lit.

• Boric Acid flow controller must be set between 0.2 and 6 (1 and 30 gpm.).

• Performing small borations at high flow rates may result in Procedure Note: an overboration based on equipment response times.

Boration flow should be set such that the time required to reach the desired setpoint will happen after release of the control switch.

Harris 2020 NRC Exam Scenario 4 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 1 Page 16 of 71 Event

Description:

Power Reduction Time Position Applicants Actions or Behavior

5. IF the current potentiometer setpoint of controller 1CS-RO 283, FK-113 BORIC ACID FLOW, needs to be changed to obtain makeup flow, THEN: (N/A)

a. RECORD the current potentiometer setpoint of controller 1CS-283, FK-113 BORIC ACID FLOW, in Section 5.2.3.

b. SET controller 1CS-283, FK-113 BORIC ACID FLOW, for the desired flow rate.

6. PLACE control switch RMW MODE SELECTOR to the BOR RO position.

• Boration may be manually stopped at any time by turning control switch RMW CONTROL to STOP.

Procedure Note:

• During makeup operations following an alternate dilution, approximately 10 gallons of dilution should be expected due to dilution water remaining in the primary makeup lines.

7. START the makeup system as follows:

a. TURN control switch RMW CONTROL to START momentarily.

b. ENSURE the RED indicator light is LIT.

RO

c. IF expected system response is not obtained, THEN TURN control switch RMW CONTROL to STOP.

8. ENSURE boration automatically terminates when the desired quantity of boron has been added.

9. IF controller 1CS-283, FK-113 BORIC ACID FLOW, was RO changed in Step 5.2.2.5, THEN: (N/A)

a. REPOSITION controller 1CS-283, FK-113 BORIC ACID FLOW, to the position recorded in Step 5.2.2.5.a.

b. INDEPENDENTLY VERIFY controller 1CS-283, FK-113 BORIC ACID FLOW, position.

Harris 2020 NRC Exam Scenario 4 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 1 Page 17 of 71 Event

Description:

Power Reduction Time Position Applicants Actions or Behavior

10. Monitor Tavg and rod control for proper operation.

11. Establish VCT pressure between 20-30 psig.

12. Turn control switch RMW MODE SELECTOR to AUTO.

RO 13. START the makeup system as follows:

a. TURN control switch RMW CONTROL to START momentarily.

b. ENSURE the RED indicator light is LIT.

SRO GP-006, Section 6.2 continued DIRECTS BOP to start power reduction at 4 MW/Min. May SRO direct initiation of a boration before the power reduction begins.

Routine load changes must be coordinated with the Load Dispatcher to meet system load demands GVPC is the preferred method of Load Control. Megawatt Control is normally used only during GV and TV testing Procedure Note: Controls and indications in following steps are on the TCS Load Control screen If Oper Entry is selected with the Turbine in GO, the value currently in the Ramp Rate Entry Window will become the load rate in effect. It may be desirable to place the turbine in HOLD to avoid undesirable ramp rates Requests PEER check prior to manipulations of TCS Load BOP Control screen BOP 5. On TCS Load Control screen, Load Control section, perform the following:

Harris 2020 NRC Exam Scenario 4 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 1 Page 18 of 71 Event

Description:

Power Reduction Time Position Applicants Actions or Behavior

a. IF GVPC indicator is TRUE, THEN go to Step 5.c

c. Select Ramp Rate Selection, Select button

d. Select the desired ramp rate OR Oper Entry on Load Ramp Rate Selection menu

• ENTER the desired rate, NOT to exceed 5 MW/MIN, in the DEMAND display. (4 DEH Units/minute)

e. IF Oper Entry is selected, THEN enter the desired loading rate in the Ramp Rate Entry window and depress Enter.

• ENTER the desired rate, NOT to exceed 5 MW/MIN, in the DEMAND display. (4 DEH Units/minute)

• DEPRESS the ENTER push-button.

The unloading of the unit can be stopped at any time by Procedure Note: selecting the Hold button. The load reduction can be resumed by selecting the Go button There is no procedural guidance directing when the Evaluator Note: boration to lower power is required. The crew may elect to perform the boration prior to placing the Turbine in GO.

6. Reduce turbine load as follows:

a. Enter desired Target Load (120 MW if shutting down) in Target Entry window and depress Enter BOP b. Select the Go button

c. Check that Demand window indication counts down towards desired Target Load

d. Check that load ramps towards desired Target Load Once a raise/lower command button is activated, it will remain in the visually depressed state as an indication the button Procedure Note: cannot be activated again for approximately two seconds. After two seconds, command buttons automatically return to their default visual state indicating the button may be activated again Harris 2020 NRC Exam Scenario 4 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 1 Page 19 of 71 Event

Description:

Power Reduction Time Position Applicants Actions or Behavior

7. IF AT ANY TIME, a small incremental change of Target Load value (1 or 5 megawatts) is desired, THEN select any of the following buttons:

BOP

• 1 MW

• 5 MW

• 1 MW

• 5 MW BOP 8. Ensure Generator load is lowering As the crew demonstrates a satisfactory load reduction, cue Simulator Operator to insert Trigger 2 Evaluator Note:

Event 2: Normal Service Water Pump A sheared shaft (AOP-022)

Harris 2020 NRC Exam Scenario 4 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 2 Page 20 of 71 Normal Service Water Pump A sheared shaft Event

Description:

(AOP-022)

Time Position Applicants Actions or Behavior On cue from the Lead Evaluator actuate Trigger 2 Simulator Operator:

Normal Service Water Pump A sheared shaft (AOP-022)

• ALB 002-4-5, SERV WTR LEAKAGE

• ALB 002-5-5, SERV WTR HEADER A HIGH-LOW FLOW

• ALB-002-6-1, SERV WTR SUPPLY HDR A LOW PRESS Indications Available:

• ALB 002-6-6, SERV WTR HEADER B HIGH-LOW FLOW

• ALB-002-7-1, SERV WTR SUPPLY HDR B LOW PRESS

• ALB-002-7-2, SERV WTR PUMPS DISCHARGE LOW PRESS Responds to ALB-002 alarms - reports low NSW header RO pressure with pump running indication.

The ESW Pumps will auto start on low header pressure Evaluator Note:

after 20 second time delay.

AOP-022 Loss Of Service Water ENTERS and directs actions of AOP-022, SRO Conducts a Crew Update Makes PA announcement for AOP entry.

Immediate 1. CHECK ESW flow lost to ANY RUNNING CSIP - (NO)

Action RO MORE THAN 1-minute:

SRO 1. RNO: GO TO Step 2.

Immediate 2. CHECK ESW flow lost to ANY RUNNING EDG - (NO)

Action RO MORE THAN 1-minute:

SRO 2. RNO: GO TO Step 3.

Harris 2020 NRC Exam Scenario 4 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 2 Page 21 of 71 Normal Service Water Pump A sheared shaft Event

Description:

(AOP-022)

Time Position Applicants Actions or Behavior There are several points in the AOP where an AO may be dispatched to check for leaks and proper operation of Simulator equipment. Report no leaks, no breaker problems but Communicator: when dispatched to the pump, after 1 to 2 minutes report that the coupling appears to have failed and request maintenance assistance.

IF REQUESTED TO OPEN KNIFE SWITCH ON THE A NSW PUMP BREAKER: go to rf SWS100 and open the knife Simulator Operator:

switch then have Communicator report back when completed

3. GO TO the appropriate step as indicated by the (YES) parameter LOST:

SRO

• NSW Pump failure

• NSW Pump loss of flow GO TO 3.0/ Step 6 (Page 9)

SRO 6. PERFORM the following for a loss of NSW flow:

a. CHECK loss of NSW Header due to NSW Pump (YES)

FAILED or LOSS OF FLOW.

b. START standby NSW Pump as follows:

(1) ENSURE discharge valve for affected pump is CLOSING by placing affected pump control switch to STOP.

(2) START standby NSW Pump in priming mode RO by momentarily placing standby NSW Pump control switch to START.

(3) WHEN discharge valve for affected pump is fully SHUT, THEN PLACE and HOLD control switch for running pump to START to fully OPEN pump discharge valve.

c. CHECK ANY NSW Pump - RUNNING. (YES)

SRO d. GO TO Section 3.2 (page 37)

Harris 2020 NRC Exam Scenario 4 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 2 Page 22 of 71 Normal Service Water Pump A sheared shaft Event

Description:

(AOP-022)

Time Position Applicants Actions or Behavior The following alarms will annunciate due to loss of cooling in containment and subsequent start of ESW:

• ALB-028-5-1, CONTAINMENT AIR HIGH VACUUM Evaluator Note:

• ALB-028-8-5, COMPUTER ALARM VENTILATION SYSTEM The BOP should identify these alarms and identify Tech Specs 3.6.1.4, 3.6.1.1, 3.6.3, 3.6.5 and 3.9.4 to be referenced MAY go to MANUAL and shut FK-7624, Norm Purge Exh Flow, in order to raise CNMT pressure to exit T.S. 3.6.1.4 (ALB-028-5-1, 3.c and AD-OP-ALL-1000)

BOP NOTE: informs CRS prior to taking manual control for need of actions T.S. 3.6.1.4 - Restore within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> LCO or HSB within next 6 SRO hours: due to High Vac in CNMT

1. CHECK Turbine trip required by ANY of the following SRO conditions - EXIST:

• No NSW Pump can be operated (NO)

• Non-isolable leak exists in the NSW system RO

• Major isolable leak exists on the Turbine Building NSW Header AND time does not permit a controlled plant shutdown SRO 1. RNO: GO TO Step 13.

Steps 13 through 19 address leaks on NSW turbine building Procedure Note: header. Leaks on individual components supplied by the Turbine Building header are addressed by Steps 20 and 21.

Harris 2020 NRC Exam Scenario 4 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 2 Page 23 of 71 Normal Service Water Pump A sheared shaft Event

Description:

(AOP-022)

Time Position Applicants Actions or Behavior

13. CHECK for minor isolable leak on Turbine Building (NO)

CREW header - ANY EXISTING.

SRO 13. RNO: GO TO Step 20.

20. CHECK for leak in an individual component - ANY (NO)

CREW EXISTING.

SRO 20. RNO: GO TO Step 22.

CREW 22. CHECK for leak on WPB header - ANY EXISTING. (NO)

SRO 22. RNO: GO TO Step 24.

RO 24. CHECK that NSW Pump(s) - MALFUNCTIONED. (YES)

25. PERFORM the following for affected NSW Pump(s): (NO)

CREW a. PERFORM the following:

(1) CHECK NSW Pump breaker(s) -

MALFUNCTIONED.

SRO 25.a.1. RNO: GO TO Step 25.b.

Harris 2020 NRC Exam Scenario 4 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 2 Page 24 of 71 Normal Service Water Pump A sheared shaft Event

Description:

(AOP-022)

Time Position Applicants Actions or Behavior If Service Water Chamber level indication is not available, a substituted conservative value of LESS THAN 31 INCHES Procedure Note:

Cooling Tower Basin level (LI-1931) may indicate that Service Water Chamber level is low.

b. CHECK adequate pump suction inventory EXISTS:

• LI-9300.1, Service Water PMP A CHMBR LVL, (YES)

CREW GREATER THAN 51% (ERFIS LSW9300)

• LI-9302, Service Water PMP B CHMBR LVL, (YES)

GREATER THAN 51% (ERFIS LSW9302)

c. Locally ENSURE the following for the affected NSW Pump per OP-139, Service Water System:

• Proper cooling and seal water supply to NSW (YES)

CREW Pumps.

(YES)

• Proper operation of NSW strainer backwash.

d. Locally CHECK NSW Pump(s) for signs of (YES) damage (shaft shear or other obvious problems).

26. INITIATE appropriate corrective action for the loss of NSW.

• Completes an Emergent Issue Checklists and contacts SRO WCC for the failure of A NSW Pump assistance. (WR, LCOTR and Maintenance support)

Simulator Acknowledge communications Communicator:

27. CHECK Reactor thermal power changed by less (YES)

SRO than 15% in any one hour period

28. IF ESW Pump(s) were placed in service by this procedure, RO THEN NOTIFY Chemistry to sample the return to the Auxiliary Reservoir per CRC-155 Harris 2020 NRC Exam Scenario 4 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 2 Page 25 of 71 Normal Service Water Pump A sheared shaft Event

Description:

(AOP-022)

Time Position Applicants Actions or Behavior SRO 29. Exit this procedure.

With NSW restored to the Turbine and load lowering, cue Simulator Operator to insert Trigger 3 Evaluator Note:

Event 3: Pressurizer PORV 445A Leakage (AOP-016)

Harris 2020 NRC Exam Scenario 4 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 3 Page 26 of 71 Pressurizer PORV 445A Leakage Event

Description:

(AOP-016)

Time Position Applicants Actions or Behavior On cue from the Lead Evaluator actuate Trigger 3 Simulator Operator:

Pressurizer PORV 445A Leakage (AOP-016)

• ALB-009-8-2, PRESSURIZER RELIEF DISCHARGE HIGH TEMP Indications

• TI-463, PRZ PORV discharge line temperature rising Available:

• LI-470.1, Pressurizer relief tank level rising

• PI-472.1, Pressurizer relief tank pressure rising

• TI-471.1, Pressurizer relief tank temperature rising Responding to the annunciator will direct the operator to shut 1RC-117, PRZ PORV Isolation valve to stop leakage Evaluator Note:

from PRZ PORV PCV-445A. With the condition clear the crew may not enter AOP-016.

APP-RO Responds to alarm and evaluates APP-ALB-009-8-2 ALB-009 Past experience has shown that this alarm may come in due to valve stem leakoff from one of the PORV Block Valves. The Procedure Note: block valves share a common leak-off line with the PORVs.

This can be checked using ERFIS points TVL5647 and TVL5646

1. CONFIRM alarm using:

a. TI-463, PRZ PORV discharge line temperature

b. LI-470.1, Pressurizer relief tank level

b. PI-472.1, Pressurizer relief tank pressure RO

b. TI-471.1, Pressurizer relief tank temperature o Reports TI-463, LI-470.1, PI-472.1, TI-471.1 reading or trending high.

2. VERIFY Automatic Functions: None Harris 2020 NRC Exam Scenario 4 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 3 Page 27 of 71 Pressurizer PORV 445A Leakage Event

Description:

(AOP-016)

Time Position Applicants Actions or Behavior Any PORV isolations that are shut due to decreasing RCS Procedure Caution:

Pressure should NOT be reopened without further evaluation

3. PERFORM Corrective Actions:

RO Monitors TI-401 indications and identifies temperature is lowering

a. IF a PORV is open, THEN CHECK PRZ pressure RO using PI-444, PI-445.1, PI-455.1, PI-456, and (NO)

PI-457.

For minor leakage, it may be necessary to have Engineering Procedure Note:

assistance to develop proper strategies

b. IF all PORV's indicate closed and RCS pressure is (NO)

NOT normal:

c. IF all PORV's indicate closed and RCS pressure is (YES)

RO normal:

(1) THEN SHUT one PORV isolation at the time.

(2) IF PRZ PORV discharge line temperature is not affected, THEN REOPEN the isolation valve.

ERFIS Point TRC-0463 can be used to evaluate if PORV is Evaluator Note: leaking. ERFIS Quick Plot QP PRT can be used to monitor this parameter.

• Shuts PORV isolations as directed by SRO o After shutting 1RC-117, PRT Relief Line Temperature stops rising and PRT pressure RO stabilizes

• Determines/reports PRZ PORV-445A leaking.

• Informs SRO leakage from PRZ PORV PCV-445A is isolated SRO Directs RO to reopen 1RC-115 and or 1RC-113 if shut.

Harris 2020 NRC Exam Scenario 4 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 3 Page 28 of 71 Pressurizer PORV 445A Leakage Event

Description:

(AOP-016)

Time Position Applicants Actions or Behavior Any Tech Spec evaluation can be conducted with a follow Evaluator Note:

up question after the scenario.

Evaluates Reactor Coolant System TS 3.4.4 All power-operated relief valves (PORVs) and their associated block valves shall be OPERABLE.

ACTION a. - With one or more PORV(s) inoperable because of excessive seat leakage within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either SRO restore the PORV(s) to OPERABLE status or close the associated block valve(s) with power maintained to the block valve(s): otherwise be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

Completes an Emergent Issue Checklists for leakage from PRZ SRO PORV PCV-445A.

Simulator Acknowledge communications Communicator:

The following write up is if AOP-016 is used for the Evaluator Note:

response to the leakage from PRZ PORV PCV-445A.

Identifies entry conditions to AOP-016, Excessive Primary CREW Plant Leakage are met AOP-016 Excessive Primary Plant Leakage ENTERS and directs actions of AOP-016, SRO Conducts a Crew Update Makes PA announcement for AOP entry Procedure Note: This procedure contains no immediate actions.

OATC 1. CHECK RHR in operation (NO)

Harris 2020 NRC Exam Scenario 4 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 3 Page 29 of 71 Pressurizer PORV 445A Leakage Event

Description:

(AOP-016)

Time Position Applicants Actions or Behavior SRO 1. RNO: GO TO Step 3.

3. REFER TO PEP-110, Emergency Classification And SRO Protective Action Recommendations, AND ENTER the EAL Matrix.

4. CHECK RCS leakage within VCT makeup capability (YES)

RO May report that the leak is exceeding Tech Spec SG leakage.

If CSIP suction is re-aligned to the RWST, negative reactivity Procedure Note:

addition should be anticipated.

RO 5. MAINTAIN VCT level GREATER THAN 5% (YES)

SRO 6. GO TO Step 10.

10. CHECK valid CNMT Ventilation Isolation monitors (REM-3561A, B, C and D) ALARM CLEAR (YES)

11. CHECK RM 3502A, RCS Leak Detection Radiation RO Monitor, ALARM CLEAR (YES)

12. CHECK ALL valid Area Radiation Monitors ALARM CLEAR (YES)

13. CHECK valid Stack Monitors ALARM CLEAR (YES)

14. DETERMINE if unnecessary personnel should be SRO evacuated from affected areas, as follows:

14.a. CHECK that a valid RMS Secondary Monitor (NO)

HIGH ALARM SRO 14.a RNO: GO TO Step 14.d.

Harris 2020 NRC Exam Scenario 4 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 3 Page 30 of 71 Pressurizer PORV 445A Leakage Event

Description:

(AOP-016)

Time Position Applicants Actions or Behavior 14.d CHECK that an RCS leak outside Containment, (NO) other than SG tube leakage, has caused a valid RMS alarm.

SRO 14.d RNO: GO TO Step 15.

BOP 15. DIRECT Chemistry to stop any primary sampling activities.

Simulator Acknowledge request to stop primary sampling activities.

Communicator:

• The following qualitative flow balance is to quickly determine if RCS leakage exceeds Tech Spec limits, EAL classification thresholds, or RCS makeup capability.

Procedure Note:

• RCS influent and effluent flow rates are compared and PRZ level rate of change is used to determine the RCS flow balance.

16. PERFORM a qualitative RCS flow balance, as follows:

a. ESTIMATE leak rate considering the following parameters:

• PRZ level rate of change (~55 gal/% at 653°F)

• Charging flow OATC

• Total seal injection flow

• Letdown flow

• Total seal return flow Reports estimate to SRO of < 10 gpm (Due to the small amount of leakage No credit will be taken for this leak rate determination)

b. OPERATE the following letdown orifice valves as necessary to maintain charging flow on scale:

• 1CS-7, 45 gpm Letdown Orifice A

• 1CS-8, 60 gpm Letdown Orifice B

• 1CS-9, 60 gpm Letdown Orifice C (No changes required)

Harris 2020 NRC Exam Scenario 4 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 3 Page 31 of 71 Pressurizer PORV 445A Leakage Event

Description:

(AOP-016)

Time Position Applicants Actions or Behavior Performance of surveillance tests to determine if leakage Procedure Note: exceeds Tech Spec limits, or to more accurately quantify leakage is up to CRS discretion.

17. Determines that more accurate quantification is not needed SRO due to excessive leakage indications present.

Any Tech Spec evaluation can be conducted as a follow up Evaluator Note:

question after the scenario.

18. EVALUATE RCS leakage (refer to Tech Spec 3.4.6.2).

SRO (N/A < 10 gpm based on changes in plant parameters)

19. DETERMINE leak location from one or more of the following:

SRO MCB indications and Valid Radiation Monitors

• From PRZ PORV PCV-445A

20. NOTIFY Health Physics of the following:

a. Leak location:

• Source inside or outside CNMT BOP

• To closed system, SG or to atmosphere

b. Applicable radiation levels.

NOTIFY HP of leakage from PRZ PORV PCV-445A Simulator Acknowledge RCS leakage is coming from PRZ PORV Communicator: PCV-445A.

21. WHEN leakage location has been determined, THEN SRO PERFORM the applicable

Attachment:

Leakage From Pressurizer PORV Attachment 5 page 27 Harris 2020 NRC Exam Scenario 4 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 3 Page 32 of 71 Pressurizer PORV 445A Leakage Event

Description:

(AOP-016)

Time Position Applicants Actions or Behavior SRO Transitions to Attachment 5:

1. CHECK the PRZ PORVs SHUT. (YES)

RO

2. CHECK that the leaking PORV has been identified. (NO)

2. RNO: PERFORM ONE of the following based on severity of SRO leak:

a. SHUT AND REOPEN ONE PORV Block Valve at a (YES) time to identify the affected PORV.

b. IF leakage is significant AND RCS pressure is (NO)

RO normal, THEN:

(1) SHUT ALL PORV Block Valves.

(2) REOPEN ONE PORV Block Valve at a time to identify the affected PORV.

Any Tech Spec evaluation can be conducted with a follow Evaluator Note:

up question after the scenario.

SRO 3. REFER TO Tech Spec 3.4.4.

Evaluates Reactor Coolant System TS 3.4.4 All power-operated relief valves (PORVs) and their associated block valves shall be OPERABLE.

ACTION a. - With one or more PORV(s) inoperable because of excessive seat leakage within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either restore the PORV(s) to OPERABLE status or close the associated block valve(s) with power maintained to the block valve(s): otherwise be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

4. VERIFY valves manipulated for leak isolation are documented per the following:

SRO

• OMM-001, Operations Administrative Requirements

• OPS-NGGC-1303, Verification Practices Harris 2020 NRC Exam Scenario 4 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 3 Page 33 of 71 Pressurizer PORV 445A Leakage Event

Description:

(AOP-016)

Time Position Applicants Actions or Behavior SRO 5. Exit this procedure.

Completes an Emergent Issue Checklists for leakage from PRZ PORV PCV-445A.

SRO Contacts WCC for assistance. (WR, LCOTR and Maintenance support).

Simulator Acknowledge communications Communicator:

After Pressurizer PORV 445A Leakage has stabilized, cue Simulator Operator to insert Trigger 4 Evaluator Note:

Event 4: Generator Voltage Regulator Failure.

Harris 2020 NRC Exam Scenario 4 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 4 Page 34 of 71 Event

Description:

Generator Voltage Regulator Failure Time Position Applicants Actions or Behavior On cue from the Lead Evaluator actuate Trigger 4 Simulator Operator:

Generator Voltage Regulator Failure

• ERFIS Quick Plot QP VAC

• EI-565, Generator Megawatts

• EI-567, Megavars Indications Available:

• ALB 022-9-4, COMPUTER ALARM GEN/EXCITER SYSTEMS

• ALB 022-4-3, GEN VOLT/FREQ RATIO LIMITER ACTIVE OR UNDER-FREQ ALB-022-9-4 is a computer alarm.

ALB-022-4-3 and 6-3 provide direction to place the Voltage Regulator in manual for corrective actions.

Evaluator Note: ALB-022-4-3 response provided as this is the first alarmed received during the transient.

The crew may refer to AOP-006, Turbine Generator Trouble but no actions will result.

ALB-022 BOP RESPONDS to alarm on APP-ALB-022-4-3 Operator may use AD-OP-ALL-1000 guidance to take Evaluator Note: manual control of voltage regulator to avoid a trip or transient prior to receiving ALB-022-4-3.

1. CONFIRM alarm using:

a. At MCB:

(1) EI-525, Generator Frequency.

BOP (2) EI-520, Generator Phase Volts. (YES-Reports voltage regulation problem)

(3) EI-540, Gen Exciter Field Volts.

(4) EI-541, Gen Exciter Field Current.

Harris 2020 NRC Exam Scenario 4 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 4 Page 35 of 71 Event

Description:

Generator Voltage Regulator Failure Time Position Applicants Actions or Behavior

2. VERIFY Automatic Functions:

a. VOLTAGE Regulator Limiter decreases Generator BOP excitation

b. IF Voltage Limiter is unable to control excitation increase, a Generator Lockout occurs BOP 3. PERFORM Corrective Actions:

a. CHECK for the following at MCB:

(1) EI-525, Generator Frequency, stable at 60 Hz. (YES)

(2) EI-520, Generator Phase Volts, stable at 22 KV. (NO)

(3) EI-540, Exciter Field Voltage stable. (NO)

(4) EI-541, Exciter Field Current stable.

(YES)

An automatic transfer to MANUAL voltage control is indicated by Procedure Note: CS-1538, Operation Mode switch, white light being lit. The CS-1538, Operation Mode switch, amber light will be off.

b. OPERATE CS-1539, Voltage Setpoint Reference switch, to BOP restore Generator voltage to 22 KV and reduce MVARS.

c. IF CS-1539, Voltage Setpoint Reference switch, is (YES) ineffective AND an automatic voltage regulator control failure is suspected, THEN PERFORM the following to transfer and maintain voltage manually:

(1) PLACE CS-1538, Operation Mode switch, in MANUAL mode.

(2) OPERATE CS-1539, Voltage Setpoint Reference switch, to stabilize the Generator Stator Voltage at 22KV and reduce MVARS.

(3) DISPATCH operator to 286 TB switchgear room to check the Excitation Control Terminal (ECT)

(1EE-E258:137) on the ABB Automatic Voltage Regulator (AVR) cabinet for any event or alarm indications.

(a) IF any event or alarm indications are present, THEN NOTIFY Maintenance.

Simulator If dispatched to 286 Switchgear to inspect ABB Automatic Communicator: Voltage Regulator locally, wait approximately 2 minutes and report that there are no abnormal indications at the ABB Automatic Voltage Regulator.

Harris 2020 NRC Exam Scenario 4 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 4 Page 36 of 71 Event

Description:

Generator Voltage Regulator Failure Time Position Applicants Actions or Behavior Directs BOP to maintain a MVAR output controlling band of 75 SRO to 160 MVAR gross output per OP-153.01.

(4) IF AVR in Manual, THEN NOTIFY Load Dispatcher within 30 minutes of an Automatic Voltage Regulator BOP status change. (The notification shall include an explanation of the status change and an estimate of expected duration.) [R - Reference 5]

Simulator Acknowledge report from Control Room Communicator:

SRO d. REFERENCE AOP-028, Grid Instability. [R - Reference 6]

e. VERIFY Main Generator is operating per the Generator BOP Capability Curve.

Completes an Emergent Issue Checklist and contacts WCC for SRO assistance. (WR, Maintenance support)

Simulator Acknowledge requests for assistance.

Communicator:

After the Generator Voltage Regulator is stabilized, cue Simulator Operator to insert Trigger 5 Lead Evaluator:

Event 5: Feed pressure transmitter failure low on A SG PT-475 (AOP-010)

Harris 2020 NRC Exam Scenario 4 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 5 Page 37 of 71 Feed pressure transmitter failure low on A SG PT-475 Event

Description:

(AOP-010)

Time Position Applicants Actions or Behavior On cue from the Lead Evaluator insert Trigger 5 Simulator Operator: Feed pressure transmitter failure low on A SG PT-475 (AOP-010)

• ALB 014-1-2, LOOP A HI STEAM LINE P LOW-P1

• ALB 014-1-4, LOOP A HI STEAM LINE PRESS RATE Available Indications ALERT

• ALB 014-4-1A, SG A FW > STM FLOW MISMATCH

• ALB 014- 4-2A, LOOP A LOW STM LINE PRESS ALERT BOP RESPONDS to alarms and ENTERS AOP-010 AOP-010 Feedwater Malfunctions

1. CHECK Feedwater Regulator valves operating properly. (NO)

1. RNO: PERFORM the following:

a. PLACE affected Feedwater Regulator valve(s) in MANUAL.

Places SG A Feedwater Reg valve in MANUAL

b. MAINTAIN Steam Generator level(s) between Critical 52 and 62%.

Task # 1 BOP Checks SG level and operates manual controller to Immediate Action maintain level between 52%-62%

Critical Task: Maintain control of SG A level above 25% to prevent an automatic Reactor trip after the controlling level transmitter PT-475 fails low.

c. IF Steam Generator level(s) cannot be controlled, THEN TRIP the Reactor AND GO TO EOP-E-0. (Should be controlled)

Immediate Action BOP 2. CHECK ANY Main Feedwater Pump TRIPPED (NO)

SRO 2. RNO: GO TO STEP 6 Harris 2020 NRC Exam Scenario 4 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 5 Page 38 of 71 Feed pressure transmitter failure low on A SG PT-475 Event

Description:

(AOP-010)

Time Position Applicants Actions or Behavior ENTERS and directs actions of AOP-010, Conducts a Crew Update Makes PA announcement for AOP entry

• Directs BOP to maintain controlling band of 52% to 62% per OMM-001 attachment 11.

SRO

6. MAINTAIN ALL of the following:

• At least ONE Main Feedwater Pump RUNNING BOP

• Main Feedwater flow to ALL Steam Generators

• ALL Steam Generator levels greater than 30%

Maintains all of the above

7. CHECK Feedwater Regulator Valves operating properly in AUTO: (NO not A)

• Response to SG levels (NO)

• Valve position indication

• Response to feed flow/steam flow mismatch BOP 7. RNO: PERFORM the following:

a. IF automatic SG water level control can be restored by selecting out a failed instrument, THEN USE OP-134.01, Feedwater System, (YES)

Section 8.10 to swap Steam Flow/Feed Flow Control and Recorder Channels and restore level control to automatic.

OP-134.01 Feedwater Systems, Section 8.10

1. IF swapping Steam Generator A channels. THEN PERFORM the following:

a. PLACE MAIN FW A REGULATOR FK-478, 1FW-133 in MAN.

BOP

b. IF selecting Channel III, THEN PERFORM the (N/A) following:

c. IF selecting Channel IV, THEN PERFORM the following:

Harris 2020 NRC Exam Scenario 4 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 5 Page 39 of 71 Feed pressure transmitter failure low on A SG PT-475 Event

Description:

(AOP-010)

Time Position Applicants Actions or Behavior (1) PLACE the following selector switches to the position specified:

o STM GEN A FW FLOW CONTROL AND RECORDER Selector Switch to FT-476.

o STM GEN A STM FLOW CONTROL AND RECORDER Selector Switch to FT-475.

d. PERFORM the following to restore 1FW-133 to AUTO:

(1) ENSURE proper indication for steam flow and feed flow on the S/G 1A LEVEL, STEAM FLOW & FEEDWATER FLOW BOP recorder, UR-478.

(2) ENSURE associated SG level (LT-476) is trending towards 57%.

(3) PLACE MAIN FW A REGULATOR FK-478, 1FW-133 to AUTO.

AOP-010 Feedwater Malfunctions, Section 3.0 7.b. REFER to Tech Spec 3.3.1 AND IMPLEMENT OWP-RP or OWP-ESF where appropriate.

BOP

c. IF needed, THEN CONTROL feed flow to SGs using Main Feed Reg Valve Bypass FCVs (NO)

Inability to monitor one or more Safety System Parameters concurrent with a turbine runback of greater than 25%, requires Procedure Note:

a change of event classification per the HNP Emergency Plan.

[C.2, C.3].

8. CHECK turbine runs back less than 25% turbine BOP (YES) load A feedwater train consists of a Condensate Pump, Condensate Procedure Note:

Booster Pump and Main Feedwater Pump.

9. GO TO the applicable section:

SRO EVENT: All Condensate/Feedwater flow malfunctions (other than pump trips) Section 3.1 Page 10 Harris 2020 NRC Exam Scenario 4 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 5 Page 40 of 71 Feed pressure transmitter failure low on A SG PT-475 Event

Description:

(AOP-010)

Time Position Applicants Actions or Behavior

1. CHECK the following Recirc and Dump Valves operating properly in MODU:

• Main Feedwater Pumps (YES)

• Condensate Booster Pumps BOP (YES)

• Condensate Pumps (YES)

• 1CE-293, Condensate Recirc (YES)

• 1CE-142, Condensate Dump To CST Isolation (YES)

Valve (SLB-4/7-1)

BOP 2. CHECK the Condensate and Feedwater System INTACT.

Pumps should be stopped in the order of higher to lower pressure. (To stop a Condensate Pump, stop a Main Procedure Note:

Feedwater Pump followed by a Condensate Booster Pump and then the Condensate Pump.)

BOP 3. CHECK pumps for NORMAL OPERATION (YES)

4. NOTIFY Load Dispatcher of ANY load limitations.

SRO (No load limitations so Dispatcher will not be called)

5. CHECK Reactor thermal power changed by less SRO (YES) than 15% in any one hour period.

SRO 6. EXIT this procedure.

OWP-SRO Refer to OWP-ESF-02 to remove channel from service.

ESF-02 Contacts WCC for support, requests WR and LCOTR.

SRO Contacts I&C to have channel removed from service.

Simulator Respond to crew requests.

Communicator:

Harris 2020 NRC Exam Scenario 4 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 5 Page 41 of 71 Feed pressure transmitter failure low on A SG PT-475 Event

Description:

(AOP-010)

Time Position Applicants Actions or Behavior Any Tech Spec evaluation may be completed with a Evaluator Note:

follow-up question after the scenario.

Enters Instrumentation TS 3.3.1 Functional Unit 14 ACTION 6 - With the number of OPERABLE channels one less than the Total Number of Channels.

STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:

a. The inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

b. The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing of other channels per Specification 4.3.1.1.

SRO 3.3.2 Functional Unit 1.e ACTION 19 - With the number of OPERABLE channels one less than the Total Number of Channels, operation may proceed provided the following conditions are satisfied :

a. The inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and

b. The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing of other channels per Specification 4.3.2.1.

Channel does NOT have to be removed from service using the OWP to continue the scenario. Once SG level is under control and the TS has been identified, cue Simulator Evaluator Note: Operator to insert Trigger 6 Event 6: PT-444 Fails HIGH (AOP-019).

Harris 2020 NRC Exam Scenario 4 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 6 Page 42 of 71 Event

Description:

PT-444 Fails HIGH (AOP-019)

Time Position Applicants Actions or Behavior On cue from the Lead Evaluator actuate Trigger 6 Simulator Operator:

PT-444 Fails HIGH (AOP-019)

• ALB-009-3-2 PRESSURIZER HIGH PRESS DEVIATION CONTROL

• ALB-009-5-1 PRESSURIZER HIGH-LOW PRESS Indications Available:

• ALB-009-8-1 PRESSURIZER RELIEF TANK HIGH-LOW LEVEL PRESS OR TEMP

• ALB-009-8-2 PRESSURIZER RELIEF DISCHARGE HIGH TEMP Identifies entry conditions to AOP-019, Malfunction Of RCS CREW Pressure Control are met AOP-019 Malfunction Of RCS Pressure Control Immediate Action RO 1. CHECK that a bubble exists in the PRZ. (YES)

Depending on timing of the RO response, 1RC-114 may be in the proper position (shut) and no action will be required.

Evaluator Note:

Reducing the Master Pressure controller output in subsequent steps will ensure the valve remains shut.

2. VERIFY ALL PRZ PORVs AND associated block (NO) valves properly positioned for current PRZ pressure and plant conditions.

Immediate (SHUTS 1RC-114)

Action RO (N/A)

2. RNO IF ANY PRZ PORV will NOT shut when required, THEN SHUT its associated block valve

3. CHECK BOTH PRZ Spray Valves properly (NO)

RO positioned for current PRZ pressure and plant conditions.

Harris 2020 NRC Exam Scenario 4 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 6 Page 43 of 71 Event

Description:

PT-444 Fails HIGH (AOP-019)

Time Position Applicants Actions or Behavior

3. RNO CONTROL PRZ spray valves using ONE of the following methods (listed in order of preference):

a. AFFECTED Spray Valve controller in MANUAL (if only one is obviously malfunctioning)

OR Critical b. PK-444A, Master Pressure Controller Task # 2 (Manually Controls PK-444A to restore pressure)

Immediate Action OR

c. Both individual spray valve controllers Critical Task: Maintain control of PRZ Pressure above 1960 psig to prevent an automatic Reactor trip after the pressure transmitter PT-444 fails high.

ENTERS and directs actions of AOP-019, SRO Conducts a Crew Update Makes PA announcement for AOP entry

• Directs RO to maintain PRZ Pressure controlling band of 2210 to 2260 PSIG per OMM-001 attachment 11.

SRO

4. GO TO Section 3.1, Pressure Control Malfunctions While SRO Operating With a Pressurizer Bubble.

Loss of RCS pressure control may require initiation of the Procedure Note:

SHNPP Emergency Plan.

1. REFER TO PEP-110, Emergency Classification And SRO Protective Action Recommendations, AND ENTER the EAL Matrix.

Harris 2020 NRC Exam Scenario 4 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 6 Page 44 of 71 Event

Description:

PT-444 Fails HIGH (AOP-019)

Time Position Applicants Actions or Behavior

2. MONITOR PRZ pressure by observing other reliable RO indication.

SRO 3. CHECK plant in MODE 1 OR 2. (YES)

ERFIS Quick Plot ITREND can be used to monitor this Evaluator Note:

parameter.

RO 4. CHECK PRZ pressure CONTROLLED. (YES)

5. CHECK PRZ pressure 2335 PSIG OR LESS. (YES)

• If PT-445 is failed low, normal plant operation is not affected. However, PORVs 1RC-118 (PCV-445A SA) and Procedure Note: 1RC-116 (PCV-445B) will NOT open on high PRZ pressure when in AUTO.

• Auto actuation is NOT required for PORV operability.

6. CHECK ALL of the following PRZ PORV block valves OPEN:

(NO)

RO

• 1RC-117 (for PCV-445A SA)

• 1RC-115 (for PCV-445B) (YES)

(YES)

• 1RC-113 (for PCV-444B SB)

• Attachment 2 lists the controller outputs corresponding to Procedure Note: heater, spray, and PRZ PORV operation that are applicable during normal operation.

7. CHECK that a malfunction of one or more of the following has occurred:

• PT-444 (YES)

RO

• PK-444A (NO)

• PRZ heater(s) (NO)

• PRZ spray valve(s) or controller(s) (NO)

RO 8. CHECK PK-444A controlling properly in AUTO. (NO)

Harris 2020 NRC Exam Scenario 4 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 6 Page 45 of 71 Event

Description:

PT-444 Fails HIGH (AOP-019)

Time Position Applicants Actions or Behavior

8. RNO: PERFORM the following:

a. VERIFY PK-444A in MANUAL RO (YES)

b. ADJUST PK-444A output as necessary, to attempt to restore and maintain PRZ pressure.

RO 9. CONTROL PRZ pressure as follows:

If individual spray valve controllers are already in MAN, do Procedure Note:

NOT return to AUTO.

a. CHECK BOTH PRZ spray valve controllers in RO AUTO AND BOTH spray valves operating as (YES) desired.

Cycling a heater control switch to OFF and back to AUTO will Procedure Note: restore normal heater function if the anti-pumping circuit has disabled the heater.

RO b. CHECK ALL PRZ heaters operating as desired. (YES)

10. CHECK at least one of the following conditions present:

RO

• PRZ pressure is UNCONTROLLED (NO)

• Status of a normal spray valve or a PRZ heater bank is UNCONTROLLED SRO 10. RNO: GO TO Step 22.

22. REFER TO Tech Spec 3.2.5 AND IMPLEMENT action where appropriate.

SRO (DNB Parameters, Limit is 2185 psig - restore within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />)

23. PERFORM the following:

a. REFER TO Attachment 3, Pressure Control Malfunction SRO SymptomsBubble in Pressurizer.

b. DIRECT Maintenance to investigate and repair the PRZ Pressure Control System component malfunction Harris 2020 NRC Exam Scenario 4 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 6 Page 46 of 71 Event

Description:

PT-444 Fails HIGH (AOP-019)

Time Position Applicants Actions or Behavior Simulator Respond to crew requests.

Communicator:

Contacts WCC for support, requests WR and LCOTR.

SRO Contacts I&C to have channel removed from service.

After the TS have been identified and the plant has stabilized, cue Simulator Operator to insert Trigger 7 Examiner Note:

Event 7: Loss of Offsite Power with a Feed line break inside CNMT (EOP-E-0).

Harris 2020 NRC Exam Scenario 4 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 7 Page 47 of 71 Loss of Offsite Power with a Feed line break inside CNMT Event

Description:

(EOP-E-0)

Time Position Applicants Actions or Behavior A Loss of Offsite power will occur coincident with a Feedline Break inside Containment from the A SG. The loss of power to the RCPs will result in an automatic trip of the Reactor and the Feedline Break will result in an auto actuation of SI requiring entry into EOP-E-0. The crew will Evaluator Note: initiate a MSL Isolation. The crew should diagnose that a LOCA is NOT in progress. The TDAFW pump will trip immediately after starting and four (4) minutes after the reactor trips the A MDAFW Pump will trip requiring the crew to transition to EOP-FR-H.1, Response To Loss Of Secondary Heat Sink.

On cue from the Lead Evaluator actuate Trigger 7 Simulator Operator: Loss of Offsite Power with a Feed line break inside CNMT (EOP-E-0)

• Multiple alarms due to a Reactor trip

• Containment press/temp and humidity rising Indications Available:

• Containment Sump level rising

• Momentary loss of MCR lighting Identifies re-entry conditions to EOP-E-0, Reactor Trip Or CREW Safety Injection are met EOP-E-0 Reactor Trip Or Safety Injection Enters EOP-E-0 SRO Holds crew update RO/BOP Performs E-0 Immediate Actions.

Harris 2020 NRC Exam Scenario 4 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 7 Page 48 of 71 Loss of Offsite Power with a Feed line break inside CNMT Event

Description:

(EOP-E-0)

Time Position Applicants Actions or Behavior

1. Ensure Reactor Trip:

Immediate (YES)

Actions RO (YES)

(YES)

2. Check Turbine Trip - ALL THROTTLE VALVES SHUT (YES)

Immediate (YES)

Actions BOP (YES)

(YES)

3. Perform The Following:

Immediate a. AC Emergency Buses - AT LEAST ONE (YES)

Actions BOP ENERGIZED (YES)

b. AC Emergency Buses - BOTH ENERGIZED

4. Safety Injection - ACTUCATED (BOTH TRAINS)

(YES)

Immediate Actions RO The Main Feedwater Pumps will lose power when Off-site power is lost. The TD AFW Pump will trip once the turbine Evaluator Note: comes up to speed. The crew should identify the trip by the following annunciator:

ALB-017-7-3, Aux Feedwater Pump Turbine Trip Harris 2020 NRC Exam Scenario 4 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 7 Page 49 of 71 Loss of Offsite Power with a Feed line break inside CNMT Event

Description:

(EOP-E-0)

Time Position Applicants Actions or Behavior IF contacted to investigate the cause of the TDAFW pump trip report the mechanical overspeed leakage is damaged and will not reset. No other sign of damage at the pump.

Simulator WHEN / IF WCC is contacted report that Mechanical Communicator: Maintenance is investigating the damage and that repairs will be made as quickly as possible.

IF asked about the B MD AFW pump status report that it is still waiting on parts to complete emergent repairs.

Steps 1 through 4 are immediate action steps Procedure Note:

Foldout applies. (Immediate actions should be completed prior implementing Foldout Page items.)

SRO 5.a. Reviews Foldout page Evaluator Note:

Harris 2020 NRC Exam Scenario 4 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 7 Page 50 of 71 Loss of Offsite Power with a Feed line break inside CNMT Event

Description:

(EOP-E-0)

Time Position Applicants Actions or Behavior Assigns Foldout items:

Alternate Miniflow Open/Shut Criteria, RHR Restart Criteria, AFW Supply Switchover Criteria SRO 5.b. Directs Shift Manager to Evaluate EAL Matrix (Refer to PEP-110)

RO 6. Ensure CSIPs - ALL RUNNING (YES)

RO 7. Ensure RHR pumps - ALL RUNNING (YES)

RO 8. Safety Injection flow - GREATER THAN 200 GPM (YES)

RO 9. RCS pressure - LESS THAN 230 PSIG (NO)

SRO 9. RNO: GO TO Step 12.

BOP 12. MAIN Steam Line Isolation - ACTUATED. (NO)

SRO 12. RNO: Check MAIN Steam isolation - REQUIRED Harris 2020 NRC Exam Scenario 4 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 8 Page 51 of 71 Event

Description:

Main Steam line Isolation fails Time Position Applicants Actions or Behavior (YES)

Perform the following:

• IF Main Steam Isolation is required THEN perform the following:

BOP Event 8 (1) Manually actuate Main Steam Line Isolation.

(2) Go to Step 13.

Identifies that the MSLI did not automatically actuate and attempts to manually from the MCB.

(Manually actuation of MSLI from MCB switch fails)

13. Ensure All MSIVs AND Bypass Valves - SHUT (NO)

Event 8 BOP Identifies that the MSIVs are not shut and attempts to manually shut by placing MCB in Shut.

(MSIVs fail to close from the MCB)

14. Any SG pressure - 100 PSIG LOWER THAN (NO)

BOP PRESSURE IN TWO OTHER SGs SRO 14. RNO: GO TO Step 16.

16. CHECK CNMT Pressure - HAS REMAINED LESS (NO)

RO THAN 10 PSIG SRO 16. RNO: Perform the following:

a. Ensure CNMT spray - ACTUATED (YES)

BOP (YES)

b. Stop all RCPs Harris 2020 NRC Exam Scenario 4 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 7 Page 52 of 71 Loss of Offsite Power with a Feed line break inside CNMT Event

Description:

(EOP-E-0) Continued Time Position Applicants Actions or Behavior Depending on the pace of the crew the four minute timer for the trip of the A MDAFW Pump may have elapsed.

Evaluation of AFW flow is a continuous action step and once the time has elapsed and the pump trips the crew should return to this step (EOP-E-0, Step 17).

Evaluator Note: The following steps assume the A MDAFW Pump has tripped and will transition the crew to EOP-FR-H.1.

The crew should identify the trip by the following annunciator:

ALB-017-5-4, Aux Feedwater Pump A Trip or Close Ckt Trouble IF contacted to investigate the cause of the A MDAFW pump trip report the breaker is tripped on overcurrent. No Simulator signs of damage at the pumps.

Communicator: WHEN / IF WCC is contacted report that Electrical Maintenance is investigating the breaker and that repairs will be made as quickly as possible.

17. Ensure AFW flow - AT LEAST 200 KPPH BOP (NO)

ESTABLISHED SRO 17. RNO: Perform the following:

a. IF any SG level greater than 25% [40%], THEN go (NO) to Step 18.

b. IF no SG level greater than 25% [40%], THEN perform the following: (NO)

BOP (1) Manually start AFW pumps (2) Ensure AFW valves - PROPERLY ALIGNED (Manually alignment of the AFW system is not successful)

SRO c. IF at least 200 KPPH can NOT be established THEN perform the following: (NO)

Harris 2020 NRC Exam Scenario 4 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 8 Page 53 of 71 Event

Description:

B CCW Pump fails to auto start on SI Time Position Applicants Actions or Behavior The RO will perform all board actions until the BOP completes Attachment 3. The BOP is permitted to properly align plant equipment in accordance with Attachment 3 without SRO approval. The Scenario Guide still identifies Evaluator Note: tasks by board position because the time frame for completion of Attachment 3 is not predictable.

To follow BOP actions E-0 Attachment 3 is located in the back of this guide.

(1) Ensure alignment of components from actuation of ESFAS Signals Attachment 3, "Safeguards BOP Actuation Verification", while continuing with implementation of EOPs.

Attachment 3 Step 3. Ensure Two CCW Pumps - RUNNING Event 8 BOP Identifies that the B CCW Pump is NOT running and manually starts pump.

Directs TB AO to place 1A and 1B Air Compressor in the local BOP control mode per E-0 Attachment 3 step 22 Acknowledge the request to place 1A and 1B Air Simulator Compressor in the local control mode per Communicator E-0 Attachment 3 step 22 When directed to place the 1A and 1B Air Compressor in Simulator Operator the local control mode: Run APP\air\acs_to_local When the APP for 1A and 1B Air Compressor has Simulator completed running call the MCR and inform them that the Communicator air compressors are running in local control.

Directs AO to Unlock AND Turn ON The Breakers For The BOP CSIP Suction AND Discharge CrossConnect Valves per E-0 Attachment 3 step 23 (or from step 11 - refer to Attachment 2)

Harris 2020 NRC Exam Scenario 4 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 8 Page 54 of 71 Event

Description:

B CCW Pump fails to auto start on SI Time Position Applicants Actions or Behavior Acknowledge the request to Unlock AND Turn ON The Simulator Breakers For The CSIP Suction AND Discharge Cross Communicator Connect Valves When directed to Unlock AND Turn ON The Breakers for Simulator Operator the CSIP Suction AND Discharge CrossConnect Valves:

Run APP\cvc\E-0 Att 2 CSIP suct & disch valve power.txt.

When the APP for CSIP Suction AND Discharge Cross Simulator Connect Valves has completed running call the MCR and Communicator inform them that CSIP Suction AND Discharge Cross Connect Valves are energized.

Harris 2020 NRC Exam Scenario 4 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 9 Page 55 of 71 Event

Description:

'A' MDAFW pump trips after the Reactor trips (EOP-FR-H.1)

Time Position Applicants Actions or Behavior (2) Go to FR-H.1, "RESPONSE TO LOSS OF SRO SECONDARY HEAT SINK", Step 1.

EOP-FR-EOP-FR-H.1, Response To Loss Of Secondary Heat Sink H.1

• This procedure should NOT be performed if total feed flow capability of 200 KPPH is available and total feed flow has been reduced due to operator action as directed by the EOPs. (The following EOPs direct feed flow to be reduced below 200 KPPH:

ECA-2.1, "UNCONTROLLED DEPRESSURIZATION OF ALL STEAM GENERATORS" FR-S.1, "RESPONSE TO NUCLEAR POWER GENERATION/ATWS" Procedure Caution: FR-P.1, "RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK" FR-P.2, "RESPONSE TO ANTICIPATED PRESSURIZED THERMAL SHOCK" FR-Z.1, "RESPONSE TO HIGH CONTAINMENT PRESSURE")

• Feed flow should NOT be established to any faulted SG while a non-faulted SG is available.

SRO 1. Perform The Following:

(3) Initiate Monitoring Of Critical Safety Function Status Trees (4) Directs Shift Manager to Evaluate EAL Matrix SRO 2. Check Secondary Heat Sink Requirements:

Harris 2020 NRC Exam Scenario 4 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 9 Page 56 of 71 Event

Description:

'A' MDAFW pump trips after the Reactor trips (EOP-FR-H.1)

Time Position Applicants Actions or Behavior

a. RCS pressure - GREATER THAN ANY NON-FAULTED SG PRESSURE (YES)

RO

b. RCS temperature - GREATER THAN 350°F

[330°F] (YES)

c. Stop any running RHR pumps.

SRO 3. Check If Bleed And Feed Is Required:

a. SG wide range levels - ANY TWO LESS THAN (NO) 15% [30%]

SRO 3.a. RNO: Observe NOTE prior to Step 4 and go to Step 4.

Procedure Note: Foldout applies.

Assigns Foldout items:

RCS Bleed and Feed Initiation Criteria, Cold Leg Recirculation Switchover Criteria, AFW Supply Switchover Criteria and RHR SRO Restart Criteria

4. Check SG Blowdown And SG Sample Isolation Valves:

a. Check SG blowdown AND SG sample isolation valves in table - SHUT (YES)

BOP SRO 5. ESTABLISH AFW Flow to at least ONE SG:

Harris 2020 NRC Exam Scenario 4 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 9 Page 57 of 71 Event

Description:

'A' MDAFW pump trips after the Reactor trips (EOP-FR-H.1)

Time Position Applicants Actions or Behavior

a. OBSERVE MCB indications to determine cause of AFW failure:

o CST level (NO) o MDAFW pump power supplies (YES)

BOP (YES) o TDAFW pump steam supply valves (NO) o TDAFW pump speed controller (NO) o TDAFW pump control power (NO) o AFW valve alignment

b. TRY to restore AFW flow at the MCB.

(Refer to EOP-FR-H.1 Attachment 1 for guidance of rate of feed flow.)

(Refer to OP-137, Auxiliary Feedwater System, for guidance regarding AFW pump operations, precautions and limitations and valve operation.)

CREW Contacts AOs to investigate failures During the remainder of the scenario any communications for a request to restore MFW or AFW Simulator Communicator: Maintenance is looking at the situation and will make repairs as soon as they can.

When ANY pump is available the WCC will contact the MCR.

SRO 6. Check If AFW Flow Established:

a. Total feed flow to SGs - GREATER THAN 200 (NO)

KPPH SRO 6.a. RNO: Go to Step 6.c.

SRO 6.c. Check AFW flow - ESTABLISHED TO ANY SG (NO)

SRO 6.c. RNO: Perform the following:

Harris 2020 NRC Exam Scenario 4 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 9 Page 58 of 71 Event

Description:

'A' MDAFW pump trips after the Reactor trips (EOP-FR-H.1)

Time Position Applicants Actions or Behavior

1) Continue attempts to restore AFW flow at the MCB.

2) TRY to restore AFW flow locally.

(Refer to OP-137, Auxiliary Feedwater System, for guidance regarding AFW pump operations, precautions and limitations and valve operation.)

3) Observe NOTE prior to Step 7 and continue with Step 7.

After stopping all RCPs and placing steam dump in the steam pressure mode, RCS pressure and temperature will rise as Procedure Note:

natural circulation is established. A large loop T prior to PRZ PORV opening confirms natural circulation.

SRO 7. Stop Heat Input From RCP Operations:

a. Stop All RCPs. (YES)

b. Check steam dump to condenser - AVAILABLE: (NO) 7.b RNO: Use intact SG(s) PORV for steam dumping in SRO subsequent steps.

• Go to Step 8.

RO 8. CHECK SI - ACTUATED (YES)

SRO 9. Perform The Following To Verify Proper Sequencer And Component Operations While Continuing With This Procedure:

a. Sequencer Load Block 9 (Manual Loading RO Permissive) - ACTUATED (BOTH TRAINS) (YES)

b. Energize AC buses 1A1 AND 1B1

c. Ensure Automatic Actions From SI Actuation While Continuing With This Procedure.

SRO

• (Refer to E-0, "REACTOR TRIP OR SAFETY INJECTION", Attachment 3.)

Harris 2020 NRC Exam Scenario 4 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 9 Page 59 of 71 Event

Description:

'A' MDAFW pump trips after the Reactor trips (EOP-FR-H.1)

Time Position Applicants Actions or Behavior SI reset can NOT occur until sixty seconds after SI signal Procedure Caution:

actuation.

RO d. Reset SI

e. Manually Realign Safeguards Equipment Following A Loss Of Offsite Power.

SRO

• (Refer to E-0, "REACTOR TRIP OR SAFETY INJECTION", Attachment 6.)

f. Reset Phase A

g. Open Instrument Air AND Nitrogen Valves To CNMT:

RO SRO 10. Establish Main FW Flow To At Least One SG:

a. Check condensate system - IN SERVICE (NO) 10.a. RNO: Place condensate system in service.

SRO (Refer to OP-134, "CONDENSATE SYSTEM", Section 5.0.)

• IF condensate system can NOT be placed in (NO) service, THEN go to Step 16.

If contacted by the by the crew for a time for the return of Simulator Offsite Power acknowledge the request and report that Communicator: Offsite Power to the Harris should be restored within 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

The EDMP should NOT be used unless other sources are Procedure Note:

unavailable.

Harris 2020 NRC Exam Scenario 4 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 9 Page 60 of 71 Event

Description:

'A' MDAFW pump trips after the Reactor trips (EOP-FR-H.1)

Time Position Applicants Actions or Behavior Due to the MSIVs failing to shut as part of the scenario design the crew may elect to dispatch an operator to Evaluator Note: perform the local actions of EOP-E-2 to isolate instrument air to the RAB 261 elevation and vent the system to fail the MSIVs shut.

Simulator Acknowledge request for EOP-E-2 local action but do not Communicator: perform any actions.

SRO 16. Prepare To Depressurize Two SGs:

a. Identify 2 SGs to be fed. (YES)

b. Shut the following valves for the SG that is NOT to be fed.

BOP o MSIVs (NO) o MSIV bypass valves (YES) o SG main steam drain isolations before MSIV: (YES)

SRO 16.b RNO: Shut the following valves for the SGs to be fed.

o MSIVs (NO) o MSIV bypass valves (YES) o SG main steam drain isolations before MSIV: (YES)

SRO c. Align EDMP to SGs as follows:

1) Direct local installation of connections/hoses using ISG-HS, BOP "HEAT SINK", Attachment 5 Steps 3 through 7.

Contacts AOs to perform ISG-HS task Simulator Acknowledge request Communicator:

SRO 2) Check local installation - COMPLETE (NO)

Harris 2020 NRC Exam Scenario 4 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 9 Page 61 of 71 Event

Description:

'A' MDAFW pump trips after the Reactor trips (EOP-FR-H.1)

Time Position Applicants Actions or Behavior 16.c.2) RNO: WHEN local installation of connection/hoses is complete, THEN go to Step 16.c.3.

b. Continue with Step 19.

SRO 19. Check For Loss Of Secondary Heat Sink:

a. SG wide range levels - ANY TWO LESS THAN (NO) 15% [30%]

19.a. RNO: Return to Step 1.

The SRO will loop back to the beginning of the procedure and evaluate the status of infield actions and foldout Evaluator Note: criteria until the RCS Bleed and Feed Initiation Criteria is met at which time the crew will continue EOP-FR-H.1 returning to step 20.

Perform Steps 20 through 30 without delay to establish RCS Procedure Caution:

heat removal by RCS bleed and feed.

RO 20. Actuate Safety Injection.

SRO 21. Ensure RCS Feed Path:

a. SI flow - GREATER THAN 200 GPM (YES)

b. Check CSIPs - BOTH RUNNING (YES)

Critical c. Observe NOTE prior to Step 23 and go to Step 23.

RO Critical to initiate RCS Bleed and Feed for Successful Task #3 High-Head SI Pump Injection before RCS temperature rises above 730°F and RVLIS Full Range Level lowers below 39%

SI reset can NOT occur until sixty seconds after SI signal Procedure Note:

actuation.

RO 23. Reset SI Harris 2020 NRC Exam Scenario 4 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 9 Page 62 of 71 Event

Description:

'A' MDAFW pump trips after the Reactor trips (EOP-FR-H.1)

Time Position Applicants Actions or Behavior

24. Manually Realign Safeguards Equipment Following A Loss Of Offsite Power.

SRO (Refer to E-0, "REACTOR TRIP OR SAFETY INJECTION",

Attachment 6.)

SRO 25. Reset Phase A AND Phase B Isolation:

a. Reset Phase A (if actuated) (YES)

RO

b. Reset Phase B (if actuated) (YES)

SRO 26. Check Sequencers - RESET (BOTH TRAINS) (NO)

26. RNO: For any Sequencer that is NOT reset, perform the following:

Manual actuation of Load Block 9 cannot occur for 150 Procedure Note:

SECONDS after sequencer operation.

a. Check Sequencer Load Block 9 (Manual Loading BOP (YES)

Permissive) - ACTUATED

27. Energize AC buses 1A1 AND 1B1 (YES)

28. Open Instrument Air AND Nitrogen Valves To (YES)

CNMT:

RO Harris 2020 NRC Exam Scenario 4 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 10 Page 63 of 71 Event

Description:

Pressurizer PORV 445B fails to open Time Position Applicants Actions or Behavior SRO 29. Establish RCS Bleed Path:

a. Establish ALL RCS bleed paths listed in table by performing the following:

1) Ensure PRZ PORV Block (YES)

2) Open all PRZ PORVs (safety and non-safety (NO) regardless of operability status).

RO (PRZ PORV 445B (1RC-116) fails to open)

SRO 30. Ensure Adequate RCS Bleed Path:

c. PRZ PORVs - ALL OPEN (NO)

(PRZ PORV 445B (1RC-116) fails to open)

RO

d. PRZ PORV block valves - ALL OPEN (YES)

30. RNO: Open all RCS vent valves to commence venting:

(YES)

• 1RC-900 (YES)

• 1RC-901 (YES)

• 1RC-902 (YES)

(YES)

Critical

• 1RC-903 (YES)

Task #3

• 1RC-904 (YES)

• 1RC-905 Critical to initiate RCS Bleed and Feed for Successful High-Head SI Pump Injection before RCS temperature rises above 730°F and RVLIS Full Range Level lowers below 39%

Harris 2020 NRC Exam Scenario 4 Rev FINAL

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 4 Event # 7 Page 64 of 71

'A' MDAFW pump trips after the Reactor trips Event

Description:

(EOP-FR-H.1) Continued Time Position Applicants Actions or Behavior

31. Ensure Automatic Actions From SI Actuation While Continuing With This Procedure.

SRO (Refer to E-0, "REACTOR TRIP OR SAFETY INJECTION",

Attachment 3.)

SRO 32. Maintain RCS Heat Removal:

• Maintain SI flow.

• Maintain RCS bleed paths.

Terminate the scenario after RCS Heat Removal has been established.

Announce Crew Update - End of Evaluation - I have the Lead Evaluator:

shift.

Have crew remain in the Simulator without discussing the exam. Examiners will formulate any follow-up questions.

Simulator Operator: When directed by Lead Evaluator go to FREEZE Harris 2020 NRC Exam Scenario 4 Rev FINAL

Appendix D Form ES-D-2 E-0 Attachment 3 Harris 2020 NRC Exam Scenario 4 Rev FINAL

Appendix D Form ES-D-2 E-0 Attachment 3 Harris 2020 NRC Exam Scenario 4 Rev FINAL

Appendix D Form ES-D-2 E-0 Attachment 3 Harris 2020 NRC Exam Scenario 4 Rev FINAL

Appendix D Form ES-D-2 E-0 Attachment 3 Harris 2020 NRC Exam Scenario 4 Rev FINAL

Appendix D Form ES-D-2 E-0 Attachment 3 Harris 2020 NRC Exam Scenario 4 Rev FINAL

Appendix D Form ES-D-2 E-0 Attachment 3 Harris 2020 NRC Exam Scenario 4 Rev FINAL

Appendix D Form ES-D-2 E-0 Attachment 3 Harris 2020 NRC Exam Scenario 4 Rev FINAL

2020 NRC Exam Scenario 4 Turnover Plant Status

• Commence a shutdown at 4 MW / min with TCS Load Control at 4 GVPC units/

min in accordance with GP-006, Normal Plant Shutdown, due to LCO expiring on B MDAFW pump

• Reactor power ~ 100% power

• GP-006 Section 6.2, Step 4, continue the shutdown @ 4 MW/min with TCS Load Control at 4 GVPC units/ min

• Current rod position is CBD @ 218 steps

• An RCS Boron sample taken 30 minutes ago was 954 ppm

• Middle of life conditions

• A Train equipment is in service

• Normal Dayshift

• Status Board is updated

• Additional Protected items A ESW Pump, A CCW Pump, A SFP Hx, RWST, for Response to Industry Best Practices Equipment Out of Service:

• B MDAFW Pump, placed under clearance 62 hours7.175926e-4 days <br />0.0172 hours <br />1.025132e-4 weeks <br />2.3591e-5 months <br /> ago for pump seal repairs.

Not expected to be returned to service in 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />. T.S. 3.7.1.2 action a (72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> LCO). "A" MDAFW Pump, MS-70 and 72, "B" ESW Pump, "B" RHR Pump, "B" CCW Pump and 'A' Train PICs: 1, 3, 9, 13, and 17 are protected.

• 1CS-9, Letdown Orifice Isolation Valve is under clearance for solenoid replacement. Tech Spec 3.6.3 LCO Action b applies. OWP-CS-09 has been completed.

• B DEH Pump is under clearance for motor repairs. The pump has been unavailable for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. Repairs are expected to be completed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

A DEH pump is protected in accordance with AD-OP-ALL-0210, Section 5.3, Conditional Single Point Vulnerabilities Reactivity Plan/Brief:

• Use attached Reactivity Plan to take unit off line at 4 MW/Min.

Risk Assessment:

• YELLOW 2020 NRC Exam Simulator Scenario 4 Turnover Rev FINAL

2020 NRC Exam Simulator Scenario 4 Turnover Rev FINAL Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Harris Nuclear Plant Task No.: 004055H101 Task

Title:

BTRS End of Life Dilution Operation JPM No.: 2020 NRC Exam (OP-108) Simulator JPM a K/A

Reference:

004 A4.07 RO 3.9 SRO 3.7 ALTERNATE PATH - YES Examinee: ________________________ NRC Examiner: _________________

Facility Evaluator: ________________________ Date: ________

Method of testing:

Simulated Performance: Actual Performance: X Classroom Simulator X Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

• The plant is operating at 100% power End of Life.

• RCS temperature is ~0.3°F low.

• The BTRS system has been filled and vented

• EST-394, ASME System Pressure Test For The CVCS - C/D Thermal Regeneration Demineralizers is not required Initial Conditions:

• EST-702, Moderator Temperature Coefficient - EOL is complete

• BTRS is aligned OP-108, Boron Thermal Regeneration System per Attachments 1 and 2

• Chemistry has recommended placing the BTRS Demineralizer B resin bed in service.

• All other parameters are normal.

• The CRS has directed you to rinse in BTRS Demineralizer B resin bed for 10 minutes for a chemistry sample using End of Life Dilution Operation per OP-108, Section 8.9.

Initiating Cue:

• The initial conditions for the aligning the system are complete.

• The RAB AO is standing by to support placing BTRS in service.

• OP-108, Section 8.9.2 step 1 and Attachment 3 are complete.

To reduce student prep time, consider supplying student with a Evaluator Note: copy of the procedure and pre-briefing student prior to entry into the Simulator.

2020 HNP NRC Exam Simulator JPM a Rev FINAL

Appendix C Job Performance Measure Form ES-C-1 Worksheet Task Standard: Properly align B BTRS Demineralizer for operation in accordance with OP-108 and Verify open the BTRS bypass, 1CS-98 and verify shut the BTRS inlet, 1CS-570 due to malfunction of the BTRS system.

Required Materials: None General

References:

OP-108, Boron Thermal Regeneration System, Rev. 25 Handout: OP-108, Rev. 25, pages 1- 7, Prerequisites, P&Ls OP-108, Rev. 25, pages 43 - 47, Section, 8.9, End of Life Dilution Operation, with the Initial Conditions signed off if desired Time Critical Task: No Validation Time: 10 minutes PERFORMANCE CRITICAL STEP JUSTIFICATION STEP Step 5 Critical to open inlet valve to demin to establish correct lineup.

Step 7 Critical to open outlet valve to demin to establish correct lineup.

Step 9 Critical to open air to BTRS inlet valve to establish correct lineup.

Step 10 Critical to open BTRS outlet valve to establish correct lineup.

Step 11 Critical to place BTRS inlet valve in Auto to establish correct lineup.

Step 12 Critical to place BTRS bypass valve in Auto to establish correct lineup.

Step 16 Critical to have in correct position to flush the new resin bed prior to initiating dilution flow.

Step 18 Critical to place BTRS switch in the DIL position to initiate dilution flow.

Step 20 Critical to make adjustment in order to initiate dilution flow.

Step 22 Critical to identify that the BTRS has malfunctioned and bypass the BTRS system to prevent a unexpected dilution event and initiate a request for repairs to be made.

2020 HNP NRC Exam Simulator JPM a Rev FINAL

Appendix C Job Performance Measure Form ES-C-1 Worksheet 2020 NRC Exam - SIMULATOR SETUP Simulator Operator

• Reset to IC-145

• Password NRC3sros

• Go to run

• Silence and Acknowledge annunciators GO TO FREEZE and inform the lead examiner the Simulator is ready. DO NOT GO TO RUN until directed by the lead examiner. (The examiner has provided to the candidate with initial conditions and the initiating cues prior to placing the simulator in RUN.)

To recreate the IC setup for this JPM:

• Initial Simulator IC was IC-20

• Shut 1CS-638 and 1CS-647 to remove the A Demin from service and place BTRS in Standby in accordance with OP-108, Section 8.9.2, step 23.a - d

• Borate the RCS to get approximately - 0.3°F mismatch between Tave and Tref

• Remove the jumper from TB B1494 by lifting the leads using the malfunction below.

o imf cvc154 (n 00:00:00 00:00:00) LIFTED

• Remove air to 1CS-570 by inserting the malfunction below.

o irf xazi141 (n 00:00:00 00:00:00) FAIL_ASIS

• Silence Acknowledge and Reset Annunciators

• Freeze and Snap these conditions to your exam IC 2020 HNP NRC Exam Simulator JPM a Rev FINAL

Appendix C Page 4 of 14 Form ES-C-1 PERFORMANCE INFORMATION Simulator Operator: When directed by the Lead Examiner go to Run.

START TIME:

OP-108, Section 8.9.1, Initial Conditions Performance Step: 1 Initial Conditions

1. BTRS aligned per Attachments 1 and 2.

2. ASME Section XI Pressure Testing Program Manager (Engineering) has been notified to perform EST-394, if needed.

3. BTRS filled and vented per Section 8.10.

Standard: Reviews initial cue and determines the initial conditions for starting the system are complete Comment:

OP-108, Section 8.9.2 Procedure Steps, Step 1 Performance Step: 2 VERIFY Part 1 of Attachment 3 complete.

Standard: Reviews Attachment 3 and determines I&C has installed the required jumpers in Term Box B1494.

Comment:

OP-108, Section 8.9.2 NOTE prior to step 2 Performance Step: 3 NOTE: For End of Life Dilution Operation as many as three beds may be used, one at a time.

Standard: Operator reads and placekeeps note Comment:

- Denotes Critical Steps 2020 HNP NRC Exam Simulator JPM a Rev FINAL

Appendix C Page 5 of 14 Form ES-C-1 PERFORMANCE INFORMATION OP-108, Section 8.9.2 Step 2 Performance Step: 4 CONTACT Chemistry, and determine BTRS demin bed to be used for dilution.

Standard: Reviews initial cue and determines the BTRS demin bed to be placed in service is the BTRS Demineralizer B resin bed.

Comment:

If the candidate contacts Chemistry confirm the BTRS demin Evaluator Cue:

bed to be used is the BTRS Demineralizer B resin bed.

OP-108, Section 8.9.2 Step 3 Performance Step: 5 OPEN inlet isolation valve for demin bed to be used.

• 1CS-638 BTRS Demineralizer A Isolation

• 1CS-628 BTRS Demineralizer B Isolation

• 1CS-618 BTRS Demineralizer C Isolation

• 1CS-608 BTRS Demineralizer D Isolation Standard: Locates MCB switch for 1CS-628 and places switch to open:

• 1CS-628 BTRS Demineralizer B Isolation - OPEN Comment:

- Denotes Critical Steps 2020 HNP NRC Exam Simulator JPM a Rev FINAL

Appendix C Page 6 of 14 Form ES-C-1 PERFORMANCE INFORMATION OP-108, Section 8.9.2 Step 4 Performance Step: 6 VERIFY SHUT inlet isolation valves for demin beds that will NOT be used.

• 1CS-638 BTRS Demineralizer A Isolation

• 1CS-628 BTRS Demineralizer B Isolation

• 1CS-618 BTRS Demineralizer C Isolation

• 1CS-608 BTRS Demineralizer D Isolation Standard: Locates MCB switch for 1CS-638 and places switch to shut:

Locates MCB switches for BTRS demin inlet isolation valves and verifies shut (switch position and green light)

• 1CS-638 BTRS Demineralizer A Isolation

• 1CS-618 BTRS Demineralizer C Isolation

• 1CS-608 BTRS Demineralizer D Isolation Comment:

OP-108, Section 8.9.2 Step 5 Performance Step: 7 OPEN outlet isolation valve for demin bed to be used.

• 1CS-647 1A Demin Lower Isolation Valve

• 1CS-637 1B Demin Lower Isolation Valve

• 1CS-627 1C Demin Lower Isolation Valve

• 1CS-617 1D Demin Lower Isolation Valve Standard: Contacts the RAB AO to open:

• 1CS-637 1B Demin Lower Isolation Valve Comment:

Use Sim Drawing CVC\btr01 and OPEN 1CS-637 when open Simulator Operator then:

Communication:

Report 1CS-637, 1B Demin Lower Isolation Valve is OPEN

- Denotes Critical Steps 2020 HNP NRC Exam Simulator JPM a Rev FINAL

Appendix C Page 7 of 14 Form ES-C-1 PERFORMANCE INFORMATION OP-108, Section 8.9.2 Step 6 Performance Step: 8 VERIFY SHUT outlet isolation valves for demin beds that will NOT be used.

• 1CS-647 1A Demin Lower Isolation Valve

• 1CS-637 1B Demin Lower Isolation Valve

• 1CS-627 1C Demin Lower Isolation Valve

• 1CS-617 1D Demin Lower Isolation Valve Standard: Contacts the RAB AO to verify shut:

• 1CS-647 1A Demin Lower Isolation Valve

• 1CS-627 1C Demin Lower Isolation Valve

• 1CS-617 1D Demin Lower Isolation Valve Comment:

Wait 1 minute and report 1CS-647 1A Demin Lower Isolation Valve Simulator Operator 1CS-627 1C Demin Lower Isolation Valve Communication:

1CS-617 1D Demin Lower Isolation Valve Are all shut.

OP-108, Section 8.9.2 Step 7 Performance Step: 9 OPEN 1IA-1221-I2 IA Isol Valve to 1CS-570, BTRS INLET.

Standard: Contacts the RAB AO to open:

• 1IA-1221-I2 IA Isol Valve to 1CS-570, BTRS INLET Comment:

Delete remote function xazi141 and report Simulator Operator Communication:

1IA-1221-I2 IA Isol Valve to 1CS-570, BTRS INLET is Open

- Denotes Critical Steps 2020 HNP NRC Exam Simulator JPM a Rev FINAL

Appendix C Page 8 of 14 Form ES-C-1 PERFORMANCE INFORMATION OP-108, Section 8.9.2 Step 8 Performance Step: 10 OPEN 1CS-669 BTRS Outlet Isolation Valve.

Standard: Contacts the RAB AO to open:

• OPEN 1CS-669 BTRS Outlet Isolation Valve.

Comment:

Simulator Operator Wait 1 minute and report Communication: 1CS-669 BTRS Outlet Isolation Valve is Open OP-108, Section 8.9.2 Step 9 Performance Step: 11 POSITION the control switch for 1CS-570, BTRS INLET to AUTO.

Standard: Locates the MCB control switch for 1CS-570 and verifies it is in the AUTO position.

Comment:

OP-108, Section 8.9.2 Step 10 Performance Step: 12 POSITION the control switch for 1CS-98, BTRS BYPASS to AUTO.

Standard: Locates the MCB control switch for 1CS-98 and verifies it is in the AUTO position.

Comment:

- Denotes Critical Steps 2020 HNP NRC Exam Simulator JPM a Rev FINAL

Appendix C Page 9 of 14 Form ES-C-1 PERFORMANCE INFORMATION OP-108, Section 8.9.2 Step 11 Performance Step: 13 VERIFY HC-387, BTRS DEMIN BYPASS 1CS-606, has a 100%

demand signal.

Standard: Locates the MCB control switch for HC-387, BTRS DEMIB BYPASS 1CS-606 and verifies the horizontal demand meter output signal is at 100% demand.

Comment:

OP-108, Section 8.9.2 NOTES prior to Step 12 Performance Step: 14 NOTE: Flowing borated water through the bed and into the RHT for extended periods of time will exhaust the bed prematurely. This can be minimized by limiting the time letdown is diverted to that necessary for Chemistry to obtain a sample and securing flow through the system until the results are obtained.

NOTE: Blockage in BTRS while 1CS-120 is aligned to RHT during flushes will be seen as flow to the VCT. 1CS-47, LD Hx Relief Vlv, relieves to the VCT. This has previously been misdiagnosed as a 1CS-120 issue.

Standard: Operator reads and placekeeps notes Comment:

OP-108, Section 8.9.2 CAUTION prior to Step 12 Performance Step: 15 CAUTION: Failure to divert letdown to the holdup tank when a new resin bed is being placed in service could result in a change in RCS chemistry.

Standard: Operator reads and placekeeps caution Comment:

- Denotes Critical Steps 2020 HNP NRC Exam Simulator JPM a Rev FINAL

Appendix C Page 10 of 14 Form ES-C-1 PERFORMANCE INFORMATION OP-108, Section 8.9.2 Step 12 Performance Step: 16 IF any, one (1) of the following is true:

• BTRS has been shut down for greater than 30 days, OR

• A new BTRS resin bed has been placed in service, OR

• Fill and vent has been performed, THEN PLACE 1CS-120, LETDOWN TO VCT/HOLD UP TANK LCV-115A, to the RHT position.

Standard: Reviews initiating cues and determines that the condition a new BTRS resin bed has been placed in service is true and places 1CS-120, LETDOWN TO VCT/HOLD UP TANK LCV-115A, to the RHT position.

Comment:

OP-108, Section 8.9.2 Step 13 Performance Step: 17 IF flow was diverted to the RHT is Step 8.9.2.12, THEN NOTIFY the RMS Tech that flushing operations are in progress and will lower VCT level. This will increase radiation levels in the room.

Standard: Contacts the RMS Tech and notifies them of the flushing operations per the note.

Comment:

Simulator Operator Acknowledges flushing operations are in progress.

Communication:

If an Auto makeup of the Reactor Water Makeup system Evaluator Cue: occurs cue the candidate that the another operator will monitor the Auto makeup for proper operation.

- Denotes Critical Steps 2020 HNP NRC Exam Simulator JPM a Rev FINAL

Appendix C Page 11 of 14 Form ES-C-1 PERFORMANCE INFORMATION OP-108, Section 8.9.2 Step 14 Performance Step: 18 PERFORM the following steps:

• POSITION the BTRS FUNCTION SELECTOR switch to DIL position.

• VERIFY that the white DIL light is NOT LIT.

Standard: Locates the control switch for the BTRS FUNCTION SELECTOR, and verifies the switch in the DIL position and verifies the white DIL light is not lit.

Comment:

OP-108, Section 8.9.2 NOTE prior to Step 15 Performance Step: 19 NOTE: HC-387 operates the opposite of what may be expected. To move the output from right to left (100%

to 0%), HC-387 must be rotated to the right (clockwise). Operating Experience shows the white DIL light comes on at about 70% output of HC-387 and goes off at about 100% output.

Standard: Operator reads and placekeeps note Comment:

OP-108, Section 8.9.2 Step 15 Performance Step: 20 PERFORM the following steps:

• POSITION HC-387, BTRS DEMIN BYPASS 1CS-606, at a less than 100% demand signal.

• VERIFY that the WHITE DIL light illuminates.

Standard: Locates the control switch for HC-387, BTRS DEMIN BYPASS 1CS-606, reduces the demand signal to less than 100% and determines the WHITE DIL light does NOT illuminates.

Comment:

- Denotes Critical Steps 2020 HNP NRC Exam Simulator JPM a Rev FINAL

Appendix C Page 12 of 14 Form ES-C-1 PERFORMANCE INFORMATION OP-108, Section 8.9.2 NOTE prior to Step 16 Performance Step: 21 NOTE: If the White DIL light is not illuminated, an improper BTRS valve lineup may be the cause, and a loss of letdown flow may occur.

Standard: Operator reads and placekeeps note Comment:

OP-108, Section 8.9.2 Step 17 - Alternate Path Begins Here Performance Step: 22 IF the DIL light does not illuminate, PERFORM the following steps:

• VERIFY OPEN 1CS-98, BTRS BYPASS.

• VERIFY SHUT 1CS-570, BTRS INLET.

• INITIATE a work request to have the BTRS repaired.

Standard:

• Locates the control switch for 1CS-98, BTRS BYPASS and takes control switch to OPEN.

• Locates the control switch for 1CS-570, BTRS INLET and takes control switch to SHUT.

• Notifies the CRS to initiate a work request to repair the BTRS system Comment:

When the CRS is notified that a work request needs to be Evaluator Cue: initiated to repair the BTRS system. Evaluation on this JPM is complete.

Direct Simulator Operator to place the Simulator in Freeze.

Simulator Operator: When directed by the Lead Examiner then go to Freeze.

STOP TIME:

- Denotes Critical Steps 2020 HNP NRC Exam Simulator JPM a Rev FINAL

Appendix C Page 13 of 14 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2020 HNP NRC Exam Simulator JPM a BTRS End of Life Dilution Operation In accordance with OP-108, Boron Thermal Regeneration System Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiners Signature: Date:

2020 HNP NRC Exam Simulator JPM a Rev FINAL

Appendix C Page 14 of 14 Form ES-C-1 JPM CUE SHEET

• The plant is operating at 100% power End of Life

• RCS temperature is ~0.3°F low

• The BTRS system has been filled and vented

• EST-394, ASME System Pressure Test For The CVCS - C/D Thermal Regeneration Demineralizers is not required Initial Conditions:

• EST-702, Moderator Temperature Coefficient - EOL is complete

• BTRS is aligned OP-108, Boron Thermal Regeneration System per Attachments 1 and 2

• Chemistry has recommended placing the BTRS Demineralizer B resin bed in service

• All other parameters are normal

• The CRS has directed you to rinse in BTRS Demineralizer B resin bed for 10 minutes for a chemistry sample using End of Life Dilution Operation per OP-108, Section 8.9 Initiating Cue:

• The initial conditions for the aligning the system are complete

• The RAB AO is standing by to support placing BTRS in service

• OP-108, Section 8.9.2 step 1 and Attachment 3 are complete 2020 HNP NRC Exam Simulator JPM a Rev FINAL

Appendix C Page 1 of 14 Form ES-C-1 Worksheet Facility: Harris Nuclear Plant Task No.: 004016H101 Task

Title:

Place Excess Letdown In Service JPM No.: 2020 HNP NRC Exam Simulator JPM b K/A

Reference:

004 A4.06 3.6 RO 3.1 SRO ALTERNATE PATH - NO Examinee: ________________________ NRC Examiner: _________________

Facility Evaluator: ________________________ Date: ________

Method of testing:

Simulated Performance: Actual Performance: X Classroom Simulator X Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

• The unit is operating at 100% power MOL

• Normal letdown needs to be secured for maintenance due to a Initial Conditions:

problem with PCV-145

• PCV-145 is in manual

• You are the OATC and have been directed by the CRS to establish Excess Letdown to the VCT per OP-107, Section 8.2.

Initiating Cue:

• Excess letdown has not been in service during this refueling cycle The candidates should be briefed outside of the Simulator prior to performing this JPM. Provide them with a copy of the procedure and inform them that ALL initial conditions are satisfied.

Evaluator Note:

This will allow them to review the Precautions and Limitations associated with OP-107 and have time for a task preview of the steps to accomplish establishing Excess Letdown. Expect that the candidates will take about 10-15 minutes to complete this review.

2020 HNP NRC Exam Simulator JPM b Rev FINAL

Appendix C Page 2 of 14 Form ES-C-1 Worksheet Task Standard: Excess letdown is established with proper flow and temperature Required Materials: None General

References:

OP-107, Rev. 117 Handout: OP-107, Rev. 117, pages 1 - 17, Prerequisites, P&Ls OP-107, Rev. 117, pages 46 - 52, Section 8.2, Excess Letdown Heat Exchanger Operation Time Critical Task: No Validation Time: 15 minutes PERFORMANCE CRITICAL STEP JUSTIFICATION STEP Step 12 Excess Letdown flow cannot be established if 1CS-466, EXCESS LETDOWN TO VCT/RCDT, is NOT positioned to the RCDT.

Step 13 Excess Letdown flow cannot be established if 1CS-461, EXCESS LETDOWN valve is NOT opened.

Step 14 Excess Letdown flow cannot be established if 1CS-460, EXCESS LETDOWN valve is NOT opened Exceeding procedural parameters limits for outlet temperatures or Step 17 pressure could damage the Excess Letdown Heat Exchanger OR the relief line flow path to the RCDT.

Exceeding procedural parameters limits for outlet temperatures or Step 19 pressure could damage the Excess Letdown Heat Exchanger and for this flow path the excess pressure would go to the RCDT.

Exceeding procedural parameters limits for outlet temperatures or Step 22 pressure could damage the Excess Letdown Heat Exchanger and for this flow path the high pressure will lift the Letdown relief which discharges to the PRT.

2020 HNP NRC Exam Simulator JPM b Rev FINAL

Appendix C Page 3 of 14 Form ES-C-1 Worksheet 2020 NRC Exam JPM b - SIMULATOR SETUP Simulator Operator

• Reset to IC-151

• Password NRC3sros

• Place RED Off Normal placard on PCV-145

• Go to RUN

• Silence and Acknowledge annunciators GO TO FREEZE and inform the lead examiner the Simulator is ready. DO NOT GO TO RUN until directed by the lead examiner. (The examiner has provided to the candidate with initial conditions and the initiating cues prior to placing the simulator in RUN.)

To recreate the IC setup for this JPM:

• Initial Simulator IC was IC-19

• Initialize to IC-19, go to RUN

• Place PCV-145 in manual

• Silence Acknowledge and Reset Annunciators

• FREEZE and Snap these conditions to your exam IC 2020 HNP NRC Exam Simulator JPM b Rev FINAL

Appendix C Page 4 of 14 Form ES-C-1 PERFORMANCE INFORMATION Simulator Operator: When directed by the Lead Examiner go to Run.

START TIME:

Performance Step: 1 OBTAIN PROCEDURE Standard: Obtains OP-107 and reviews P & Ls and Section 8.2 for Excess Letdown Heat Exchanger Operation. Reviews and verifies initial conditions are satisfied.

Evaluator Cue: Initial conditions have been established Comment:

OP-107, Section 8.2.2, Note prior to step 1 Performance Step: 2 NOTE: Normally Excess Letdown will go to the VCT. However, if plant conditions warrant, the RCDT may be selected.

When the Excess Letdown line has been flushed, the VCT position can then be re-selected.

NOTE: If Excess Letdown is to remain in service for sufficient time for dilution or boration to be necessary then VCT level should be lowered to accommodate the expected level increase before placing Excess Letdown in service NOTE: Placing Excess Letdown in service will result in increased dose rates in the Seal Water Heat Exchanger Room.

Standard: Operator reads and placekeeps notes Comment:

- Denotes Critical Steps 2020 HNP NRC Exam Simulator JPM b Rev FINAL

Appendix C Page 5 of 14 Form ES-C-1 PERFORMANCE INFORMATION OP-107, Section 8.2.2, Caution prior to step 1 Performance Step: 3 Caution: Excess Letdown operation during times of BTRS operation may result in damage to the RCP seals (due to increased contaminants and higher pH water). This should not prevent any AOP or EOP actions. The Responsible Engineer for RCP or CVCS may provide additional guidance if needed.

Standard: Operator reads and placekeeps caution Comment:

OP-107, Section 8.2.2, Step 1 Performance Step: 4 INFORM Radwaste Control Room to monitor Seal Water Filter P while Excess Letdown is in service.

Standard: Contacts RW Control Room operator to monitor Seal Water Filter P while Excess Letdown is in service Acknowledge request to monitor Seal Water Filter P while Simulator Operator:

Excess Letdown is in service Comment:

OP-107, Section 8.2.2, Step 2.a Performance Step: 5 PLACE the excess letdown heat exchanger in operation as follows:

VERIFY 1CC-188, CCW TO EXCESS LETDOWN HEAT EXCHANGER, is open.

Standard: Locates MCB switch for 1CC-188, CCW TO EXCESS LETDOWN HEAT EXCHANGER, verifies it is open Comment:

- Denotes Critical Steps 2020 HNP NRC Exam Simulator JPM b Rev FINAL

Appendix C Page 6 of 14 Form ES-C-1 PERFORMANCE INFORMATION OP-107, Section 8.2.2, Step 2.b Performance Step: 6 VERIFY 1CC-202 SB, CCW FM EXCESS LTDN & RCDT HEAT EXCHANGERS, is open.

Standard: Locates MCB switch for 1CC-202 SB, CCW FM EXCESS LTDN

& RCDT HEAT EXCHANGERS, verifies it is open.

Comment:

OP-107, Section 8.2.2, Step 2.c Performance Step: 7 VERIFY 1CC-176, CCW TO EXCESS LTDN & RCDT HEAT EXCHANGERS, is open.

Standard: Locates MCB switch for 1CC-176, CCW TO EXCESS LTDN &

RCDT HEAT EXCHANGERS, verifies it is open.

Comment:

OP-107, Section 8.2.2, Note prior to step 3 Performance Step: 8 NOTE: Flushing the excess letdown line to the RCDT is required if the boron concentration in the excess letdown line from the RCS isolation valves to 1CS-466 is unknown or differs from RCS concentration. The volume of this line is 74 gallons. Two volumes (148 gallons) should be adequate to prevent unexpected reactivity changes in the RCS when flow is aligned to the VCT.

Standard: Operator reads and placekeeps note Comment:

- Denotes Critical Steps 2020 HNP NRC Exam Simulator JPM b Rev FINAL

Appendix C Page 7 of 14 Form ES-C-1 PERFORMANCE INFORMATION OP-107, Section 8.2.2, Caution prior to step 3 Performance Step: 9 Caution: 1CS-464, HC-137 EXCESS LTDN FLOW is rated for 1500 psid. Anytime that 1CS-464 is exposed to greater than 1500 psid, leakby should be expected.

Standard: Operator reads and placekeeps caution Comment:

OP-107, Section 8.2.2, Step 3.a Performance Step: 10 IF excess letdown flow is to be aligned to the RCDT, THEN PERFORM the following:

NOTIFY Radwaste Control Room of expected RCDT level change.

Standard: Contacts RW Control Room and informs the operator to expect RCDT level change.

Simulator Operator: RW Operator acknowledges Comment:

OP-107, Section 8.2.2, Step 3.b Performance Step: 11 VERIFY 1CS-464, HC-137 EXCESS LTDN FLOW is shut (potentiometer to zero).

Standard: Operator verifies 1CS-464, HC-137 EXCESS LTDN FLOW is shut (potentiometer to zero).

Comment:

- Denotes Critical Steps 2020 HNP NRC Exam Simulator JPM b Rev FINAL

Appendix C Page 8 of 14 Form ES-C-1 PERFORMANCE INFORMATION OP-107, Section 8.2.2, Step 3.c Performance Step: 12 PLACE 1CS-466, EXCESS LETDOWN TO VCT/RCDT, to the RCDT position.

Standard: Operator locates MCB switch and places 1CS-466, EXCESS LETDOWN TO VCT/RCDT, to the RCDT position.

Comment:

OP-107, Section 8.2.2, Step 4 Performance Step: 13 PLACE 1CS-461, EXCESS LETDOWN to OPEN.

Standard: Operator locates MCB switch and places 1CS-461, EXCESS LETDOWN valve to OPEN.

Comment:

OP-107, Section 8.2.2, Step 5 Performance Step: 14 PLACE 1CS-460, EXCESS LETDOWN to OPEN.

Standard: Operator locates switch and places 1CS-460, EXCESS LETDOWN valve to OPEN.

Comment:

- Denotes Critical Steps 2020 HNP NRC Exam Simulator JPM b Rev FINAL

Appendix C Page 9 of 14 Form ES-C-1 PERFORMANCE INFORMATION OP-107, Section 8.2.2, Note prior to Step 6 Performance Step: 15 NOTE: Seal Water Flow should be observed on FR-154A and FR-154B when adjusting 1CS-464, HC-137 EXCESS LTDN FLOW for the following reasons:

• RCP No 1 seal leakoff flow will be affected, and

• The possibility exists of lifting the 150 psi safety on the excess letdown/No. 1 seal return line.

Standard: Operator reads and placekeeps note Comment:

OP-107, Section 8.2.2, Caution prior to Step 6 Performance Step: 16 Caution: Do NOT exceed 174°F outlet temperature as indicated on TI-139.

Caution: Do NOT exceed 150 psig as indicated on PI-138.

Standard: Operator reads and placekeeps cautions Comment:

- Denotes Critical Steps 2020 HNP NRC Exam Simulator JPM b Rev FINAL

Appendix C Page 10 of 14 Form ES-C-1 PERFORMANCE INFORMATION OP-107, Section 8.2.2, Step 6 Performance Step: 17 ADJUST 1CS-464, HC-137 EXCESS LTDN FLOW as necessary to establish excess letdown flow, and not exceed the following parameters:

• 174°F outlet temperature as indicated on TI-139

• 150 psig as indicated on PI-138 Standard: Operator adjusts 1CS-464, HC-137 EXCESS LTDN FLOW to establish excess letdown flow while not exceeding 174°F outlet temperature as indicated on TI-139 and 150 psig as indicated on PI-138 until > 148 gallons have been flushed to the RCDT.

Examiner Cue: After adjustments to 1CS-464 have been made establishing (NOTE: This should be Excess letdown to RCDT allow applicant to stabilize temperature enough time for the and pressure then cue the applicant:

candidate to determine that an adequate flush Time compression is being used; approximately 10 has been completed.) minutes have elapsed since 1CS-464 has been opened.

Comment:

OP-107, Section 8.2.2, Step 7.a Performance Step: 18 IF excess letdown flow is to be aligned to the VCT, THEN PERFORM the following:

VERIFY 1CS-464, HC-137 EXCESS LTDN FLOW is shut (potentiometer to zero).

Standard: Locates and verifies 1CS-464, HC-137 EXCESS LTDN FLOW is SHUT Comment:

- Denotes Critical Steps 2020 HNP NRC Exam Simulator JPM b Rev FINAL

Appendix C Page 11 of 14 Form ES-C-1 PERFORMANCE INFORMATION OP-107, Section 8.2.2, Step 7.b Performance Step: 19 PLACE 1CS-466, EXCESS LETDOWN TO VCT/RCDT, to the VCT position.

Standard: Locates MCB switch and places 1CS-466, EXCESS LETDOWN TO VCT/RCDT, to the VCT position.

Comment:

OP-107, Section 8.2.2, Note prior to Step 7.c Performance Step: 20 NOTE: Seal Water Flow should be observed on FR-154A and FR-154B when adjusting 1CS-464, HC-137 EXCESS LTDN FLOW for the following reasons:

• RCP No 1 seal leakoff flow will be affected, and

• The possibility exists of lifting the 150 psi safety on the excess letdown/No. 1 seal return line.

Standard: Operator reads and placekeeps note Comment:

OP-107, Section 8.2.2, Caution prior to Step 7.c Performance Step: 21 Caution: Do NOT exceed 174°F outlet temperature as indicated on TI-139.

Caution: Do NOT exceed 150 psig as indicated on PI-138.

Standard: Operator reads and placekeeps cautions Comment:

- Denotes Critical Steps 2020 HNP NRC Exam Simulator JPM b Rev FINAL

Appendix C Page 12 of 14 Form ES-C-1 PERFORMANCE INFORMATION OP-107, Section 8.2, Step 7.c Performance Step: 22 ADJUST 1CS-464, HC-137 EXCESS LTDN FLOW as necessary to establish excess letdown flow and not exceed the following parameters:

• 174°F outlet temperature as indicated on TI-139.

• 150 psig as indicated on PI-138.

Standard: Locates MCB control for 1CS-464, HC-137 EXCESS LTDN FLOW to establish flow and adjusts excess letdown flow while not exceeding 174°F outlet temperature as indicated on TI-139 or 150 psig as indicated on PI-138.

Comment:

NOTE: It may be necessary to ask the candidate if Excess Letdown has been placed in service IF they do not report to the CRS after Excess Letdown has clearly been established.

Examiner Cue: After Excess Letdown has been established and reported to the CRS then:

Announce: I have the shift, END OF JPM Contact Simulator Operator to place the Simulator in Freeze.

STOP TIME:

Simulator Operator: When directed by the Lead Examiner then go to Freeze.

- Denotes Critical Steps 2020 HNP NRC Exam Simulator JPM b Rev FINAL

Appendix C Page 13 of 14 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2020 HNP NRC Exam Simulator JPM b Establish Excess Letdown to the VCT In accordance with OP-107, Section 8.2, Excess Letdown Heat Exchanger Operation Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiners Signature: Date:

2020 HNP NRC Exam Simulator JPM b Rev FINAL

Appendix C JPM CUE SHEET Form ES-C-1

• The unit is operating at 100% power MOL

• Normal letdown needs to be secured for maintenance due to a Initial Conditions:

problem with PCV-145

• PCV-145 is in manual

• You are the OATC and have been directed by the CRS to establish Excess Letdown to the VCT per OP-107, Section 8.2.

Initiating Cue:

• Excess letdown has not been in service during this refueling cycle 2020 HNP NRC Exam Simulator JPM b Rev FINAL

Appendix C Page 1 of 11 Form ES-C-1 Worksheet Facility: Harris Nuclear Plant Task No.: 301135H601 Task

Title:

Take Corrective Action For Failure JPM No.: 2020 NRC Exam of CSIP Mini-Flow Valves to Re-Position Simulator JPM c K/A

Reference:

006 A4.07 RO 4.4 SRO 4.4 ALTERNATE PATH - YES Examinee: ________________________ NRC Examiner: _________________

Facility Evaluator: ________________________ Date: ________

Method of testing:

Simulated Performance: Actual Performance: X Classroom Simulator X Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

• The Unit was at 100% power when a technicians error resulted in a Reactor Trip and Safety Injection Initial Conditions:

• The crew is performing EOP-E-0, Reactor Trip or Safety Injection, and are at step 37

• You are the OATC Initiating Cue:

• Beginning at Step 37, you are to continue performing EOP-E-0 2020 HNP NRC Exam Simulator JPM c Rev FINAL

Appendix C Page 2 of 11 Form ES-C-1 Worksheet Task Standard: Terminate Safety injection flow and obtain adequate flow through a running CSIP after the common miniflow isolation valve fails to open in accordance with EOP-E-0.

Required Materials: E-0, Reactor Trip or Safety Injection, Rev. 15 General

References:

E-0, Reactor Trip or Safety Injection, Rev. 15 Handout: None Time Critical Task: No Validation Time: 10 minutes PERFORMANCE CRITICAL STEP JUSTIFICATION STEP Resetting SI removes the active signal to allow termination of SI (allows Step 2 component re-positioning).

Stopping one CSIP prevents unnecessary PRZ overfill to a solid Step 4 condition.

Shutting FK-122.1 prevents CSIP runout when establishing a charging Step 9 flowpath.

Step 10 Opening 1CS-235 and 1CS-238 establishes a charging flowpath.

Opening FK-122.1 to a minimum of 10% establishes minimal charging Step 11 flow prior to isolating the BIT to ensure the running CSIP is not deadheaded.

Shutting 1SI-3 and 1SI-4 isolates flow through the BIT to prevent CSIP Step 12 runout.

Step 14 Establishing a flow rate of >60 gpm is required by procedure.

PERFORMANCE ALTERNATE PATH JUSTIFICATION STEP 1CS-214 (common miniflow isolation) failing to open prevents normal miniflow for the running CSIP to be established. The candidate must Steps 7 - 14 establish minimal charging flow prior to isolating the BIT to ensure that the running CSIP is not deadheaded.

2020 HNP NRC Exam Simulator JPM c Rev FINAL

Appendix C Page 3 of 11 Form ES-C-1 Worksheet 2020 NRC Exam - SIMULATOR SETUP Simulator Operator

• Reset to IC-146

• Password NRC3sros

• Go to run

• Silence and Acknowledge annunciators

• It may be necessary to roll the Generator 86 relays at the start of this JPM or between runs. To accomplish this run the AMS file Roll Gen 86 Relays to get the 86 relays to the trip condition.

• NOTE: The ERFIS screen that normally displays Tavg needs to be switched to Turn on code ITREND for RCS temperature and pressure.

GO TO FREEZE and inform the lead examiner the Simulator is ready. DO NOT GO TO RUN until directed by the lead examiner. (The examiner has provided to the candidate with initial conditions and the initiating cues prior to placing the simulator in RUN.)

To recreate the IC setup for this JPM:

• Initial Simulator IC was IC-19

• Pre-load failure of control switch 1CS-214 o IDI XA2I162 (n 00:00:00 00:00:00) ASIS Insert:

• SIS01A (1 00:00:00 00:00:00) INADVERTENT_INIT

• SIS01B (1 00:00:00 00:00:00) INADVERTENT_INIT

• Go To RUN and initiate Trigger 1 - Inadvertent SI Train A and B

• Perform / markup E-0 through Step 37 (SI Termination Criteria).

• Set up ERFIS Plot to include RCS Pressure

• Adjust AFW flow to approx. 80 KPPH/SG

• Secure TDAFWP by closing 1MS-70 and 1MS-72

• Energize 1A1 and 1B1

• Silence Acknowledge and Reset Annunciators

• FREEZE (with PZR Level at approx. 60%) and Snap these conditions to your exam IC

• NOTE: The ERFIS screen that normally displays Tavg needs to be switched to Turn on code ITREND for RCS temperature and pressure.

2020 HNP NRC Exam Simulator JPM c Rev FINAL

Appendix C Page 4 of 11 Form ES-C-1 PERFORMANCE INFORMATION Simulator Operator: When directed by the Lead Examiner go to Run.

START TIME:

Performance Step: 1 OBTAIN PROCEDURE Standard: Obtains copy of EOP-E-0 and reviews steps that will be performed prior to initiation of step.

Comment:

E-0, Step 37 Performance Step: 2 Reset Safety Injection.

Standard: () Locates Train A and Train B SI reset MCB switch and takes respective train switch to reset position and then allows switch to return to normal position.

Verifies that SI is reset by observation of Bypass Permissive Lights

• SI Actuated light stays on until both A and B train reset is completed.

• When train A or B is reset the SI Reset Auto SI Blocked light blinks on and off

• When both train A and B are reset the SI Actuated light extinguishes and the SI Reset Auto SI Blocked Light stays ON Comment:

- Denotes Critical Steps 2020 HNP NRC Exam Simulator JPM c Rev FINAL

Appendix C Page 5 of 11 Form ES-C-1 PERFORMANCE INFORMATION E-0, Step 38 Performance Step: 3 Manually Realign Safeguards Equipment Following A Loss Of Offsite Power. (Refer to Attachment 6)

Standard: Acknowledges requirement to manually realign Safeguards Equipment following a loss of Offsite Power (Notes that no loss of power has occurred)

Comment:

E-0, Step 39 Performance Step: 4 Stop All But One CSIP.

Standard: Observes that A and B CSIP are running.

• Locates MCB switch for the CSIP control and secures ONE CSIP.

Comment:

E-0, Step 40 Performance Step: 5 RCS Pressure - STABLE OR RISING Standard: Verifies RCS pressure is rising by trends on ERFIS, OSI PI or MCB RCS pressure meters. (may report trend to CRS)

(IF reported that RCS pressure is rising: acknowledge Evaluator Cue:

report)

Comment:

- Denotes Critical Steps 2020 HNP NRC Exam Simulator JPM c Rev FINAL

Appendix C Page 6 of 11 Form ES-C-1 PERFORMANCE INFORMATION E-0, Step 41 Performance Step: 6 Open Normal Miniflow Isolation Valves:

• CSIP A: 1CS-182

• CSIP B: 1CS-196

• CSIP C: 1CS-210

• COMMON: 1CS-214 Standard: Locates MCB switch for each of the following valves and takes switch to OPEN position

• CSIP A: 1CS-182

• CSIP B: 1CS-196

• CSIP C: 1CS-210 Locates MCB switch for 1CS-214 and after attempting to open valve determines that the valve will NOT OPEN Determines RNO for step 41 is needed Comment:

E-0, Step 41 RNO - ALTERNATE PATH begins here Performance Step: 7

• If normal miniflow for running CSIP established, THEN GO TO Step 42. (NO)

• IF normal miniflow for running CSIP can NOT be established, THEN Observe NOTE prior to Step 45 AND GO TO Step 45. (YES)

Standard: Determines that RNO action is to go to step 45 and proceed with actions there.

Comment:

- Denotes Critical Steps 2020 HNP NRC Exam Simulator JPM c Rev FINAL

Appendix C Page 7 of 11 Form ES-C-1 PERFORMANCE INFORMATION E-0, Step 45 - NOTE prior to step (ALTERNATE PATH)

Performance Step: 8 NOTE: The following step contains a Safety Injection termination sequence for which CSIP normal miniflow is not available. The charging flow control valve is opened a minimal amount prior to isolating the BIT to ensure the running CSIP is not deadheaded.

Standard: Operator reads and placekeeps note Comment:

E-0, Step 45.a (ALTERNATE PATH)

Performance Step: 9 Establish Minimum Charging Flow AND Isolate BIT Flow:

Shut charging flow control valve: FK-122.1 Standard: Locates MCB control for FK-122.1, places FK-122.1 in MANUAL and reduces output to 0 (shuts valve)

Comment:

E-0, Step 45.b (ALTERNATE PATH)

Performance Step: 10 Open charging line isolation valves:

• 1CS-235

• 1CS-238 Standard: Locates MCB control switches for each valve and takes switches to OPEN

• 1CS-235 (red light on)

• 1CS-238 (red light on)

Comment:

- Denotes Critical Steps 2020 HNP NRC Exam Simulator JPM c Rev FINAL

Appendix C Page 8 of 11 Form ES-C-1 PERFORMANCE INFORMATION E-0, Step 45.c (ALTERNATE PATH)

Performance Step: 11 Set charging flow controller demand position to 30%.

Standard: Locates MCB control for 1FK-122.1 and adjusts FK-122.1 open to 30%. (critical to establish an indication of a positive increase in charging flow)

Comment:

E-0, Step 45.d (ALTERNATE PATH)

Performance Step: 12 Shut BIT outlet valves:

• 1SI-3

• 1SI-4 Standard: Locates MCB control switches for each valve and takes switches to SHUT

• 1SI-3 (green light on)

• 1SI-4 (green light on)

Comment:

- Denotes Critical Steps 2020 HNP NRC Exam Simulator JPM c Rev FINAL

Appendix C Page 9 of 11 Form ES-C-1 PERFORMANCE INFORMATION E-0, Step 45.e (ALTERNATE PATH)

Performance Step: 13 Ensure cold leg AND hot leg injection valves - SHUT

• 1SI-52

• 1SI-86

• 1SI-107 Standard: Locates MCB control for 1SI-52, 1SI-86 and 1SI-107 and verifies that all three valves are shut (green lights on)

Comment:

E-0, Step 45.f (ALTERNATE PATH)

Performance Step: 14 Establish and maintain at least 60 GPM flow through CSIP.

Total flow through the running CSIP consists of Charging Flow (FI-122A.1) in addition to the three RCP Seal Injection Evaluator Note: Flows (FI-130A, FI-127A and FI-124A).

With FK-122.1 set to ~30% flow will be >60 GPM Standard: Totals flow of Charging flow through FI-122A.1 and RCP Seal Injection flows (3) through FI-130A, FI-127A, and FI-124A. IF the total is < 60 gpm THEN Locates MCB for CSIP flow (FI-122) and adjusts Charging Flow Controller FK-122.1 until total flow maintained is 60 gpm.

Comment:

After applicant adjusts/ensures Charging Flow + Seal Injection flow is verified to be maintaining >60 gpm flow -

Evaluation on this JPM is complete.

Evaluator Cue: Announce: I have the shift. END OF JPM Contact the Simulator Operator and place the Simulator in Freeze.

STOP TIME:

Simulator Operator: When directed by the Lead Examiner then go to Freeze.

- Denotes Critical Steps 2020 HNP NRC Exam Simulator JPM c Rev FINAL

Appendix C Page 10 of 11 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2020 HNP NRC Exam Simulator JPM c Take Corrective Action For Failure of CSIP Mini-Flow Valves to Re-Position In accordance with EOP-E-0, Reactor Trip or Safety Injection Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiners Signature: Date:

2020 HNP NRC Exam Simulator JPM c Rev FINAL

Appendix C Page 11 of 11 Form ES-C-1 JPM CUE SHEET

• The Unit was at 100% power when a technicians error resulted in a Reactor Trip and Safety Injection Initial Conditions:

• The crews is performing EOP-E-0, Reactor Trip or Safety Injection and are at step 37

• You are the OATC Initiating Cue:

• Beginning at Step 37, you are to continue performing EOP-E-0 2020 HNP NRC Exam Simulator JPM c Rev FINAL

Appendix C Page 1 of 15 Form ES-C-1 Worksheet Facility: Harris Nuclear Plant Task No.: 003001H101 Task

Title:

Start a RCP with Spray Valve JPM No.: 2020 NRC Exam Failure Simulator JPM d K/A

Reference:

002 A1.01 RO 3.8 SRO 4.1 ALTERNATE PATH - YES Examinee: ________________________ NRC Examiner: _____________

Facility Evaluator: ________________________ Date: ________

Method of testing:

Simulated Performance: Actual Performance: X Classroom Simulator X Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

• You are the extra RO during a plant startup.

• GP-004, Reactor Startup is in progress and is currently on HOLD.

• The plant has been stabilized with Shutdown Banks withdrawn.

Initial Conditions:

• Two hours ago the B RCP was removed from service for maintenance.

• Maintenance has been completed and the B RCP is ready for operation.

• The previous crew has verified that all initial conditions to start the RCP are met and have initialed all steps

• The CRS has instructed you to start B RCP, in accordance with OP-100, Reactor Coolant System, Section 5.1, Reactor Coolant Initiating Cue:

Pump Start-up.

• The initial conditions have been verified.

To reduce student prep time, consider supplying student with a Evaluators Note: copy of the procedure and pre-briefing student prior to entry into the Simulator.

2020 HNP NRC Exam Simulator JPM d Rev FINAL

Appendix C Page 2 of 15 Form ES-C-1 Worksheet Task Standard: B RCP started in accordance with OP-100 and PRZ spray manually controlled in accordance with AOP-019, Malfunction of RCS Pressure Control, due to a failed open PRZ spray valve following the pump start.

Required Materials: OP-100 mark up with Attachment 3 included.

General

References:

OP-100, Reactor Coolant System, Rev. 47 and AOP-019, Malfunction of RCS Pressure Control, Rev. 25 Handout: OP-100, Rev. 47, pages 1 - 8, Prerequisites, P&Ls OP-100, Rev. 47, pages 9 - 12, Section 5.1, Reactor Coolant Pump Start-up, with the Initial Conditions signed off if desired OP-100, Rev. 47, page 94, Attachment 3, #1 Seal Performance Parameters Time Critical Task: No Validation Time: 10 minutes PERFORMANCE CRITICAL STEP JUSTIFICATION STEP System interlock requires proper oil pressure be established prior to Step 9 starting pump Administrative requirements state the System flow cannot be established until the lift oil pump breaker is closed for > 2 mins to Step 13 prevent pump damage AOP-019 requires the operator to perform the immediate actions including the RNO response to control a PRZ Spray valve (shut valve).

Step 21 Performing these actions correctly will prevent an unnecessary Safety Injection from occurring.

PERFORMANCE ALTERNATE PATH CRITICAL STEP JUSTIFICATION STEP Entry conditions are met for AOP-019, Malfunction of RCS Pressure Control when PRZ Spray valve controller PK-444D.1, PRZ Spray Loop B, 1RC-103 fails open upon starting the B RCP. AOP-019 requires the Step 16-21 operator to perform the immediate actions including the RNO response to control a PRZ Spray valve (shut valve) when that valve is NOT properly positioned for current PRZ pressure or plant conditions.

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Appendix C Page 3 of 15 Form ES-C-1 Worksheet 2020 NRC Exam - SIMULATOR SETUP Simulator Operator

• Reset to IC-147

• Password NRC3sros

• Go to RUN

• CRT displays - CRT 2: QP VCT, CRT 3: QP TAVG and CRT 4: QP SGLVL

• Set Source Range Audio Multiplier to 1000 to establish audible counts

• Silence and Acknowledge annunciators GO TO FREEZE and inform the lead examiner the Simulator is ready. DO NOT GO TO RUN until directed by the lead examiner. (The examiner has provided to the candidate with initial conditions and the initiating cues prior to placing the simulator in RUN.)

To recreate the IC setup for this JPM:

• Initial Simulator IC was IC-7, Mode 3 HSD, MOL conditions - RCS pressure 2235, RCS temp. 557°F, all rods in

• GO to run

• Secure the B RCP

• Wait approximately 5 minutes for the simulator to stabilize

• Create a conditional Trigger to open PRZ spray valve PK-444D.1 with a 45 second delay and 45 second ramp after the control switch for the B RCP is taken to start To create the conditional trigger:

- Go to malfunctions

- Find PRS14B Pressurizer Spray Valve 444D Failure (with manual control) o Open the malfunction window o Set delay to 45 seconds o Set ramp time to 45 seconds o Set initial severity to 30 (that way the meter will not go to 0 -

adjust this to whatever percent open 1RC-103 is at after securing the B RCP and the simulator is stable) o Set the malfunction to Trigger 1

- Go to triggers o Click on Trigger 1 o Click on Assign File o Choose RCP_B_START o (source file should now have RCP_B_START)

• Silence Acknowledge and Reset Annunciators

• Freeze and Snap these conditions to your exam IC 2020 HNP NRC Exam Simulator JPM d Rev FINAL

Appendix C Page 4 of 15 Form ES-C-1 PERFORMANCE INFORMATION Simulator Operator: When directed by the Lead Examiner go to Run.

The candidates should be briefed outside of the Simulator prior to performing this JPM. Provide them with a copy of the procedure (with initial conditions initialed as completed).

This will allow them to review the Precautions and Limitations associated with OP-100 and have time for a task preview of the Evaluator Note: steps to accomplish starting the RCP. Expect that the candidates will take about 20 minutes to complete this review.

During the performance of the JPM the candidate may use either MCB indication or ERFIS indications when reviewing RCP pump indications.

START TIME:

Obtain Procedure Performance Step: 1 Procedure obtained and begins the task of starting the RCP Standard: Reviews initial cue and determines the initial conditions for starting the system are complete Comment:

OP-100, Section 5.1.2, Caution prior to Step 1 Performance Step: 2 CAUTION: Only one RCP is to be started at any one time. If the motor is allowed to coast to a stop between starts, two successive starts are permitted. A third start may be made when the winding and the core have cooled by running for 20 minutes, or by standing idle for 45 minutes.

Standard: Operator reads and placekeeps caution Comment:

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Appendix C Page 5 of 15 Form ES-C-1 PERFORMANCE INFORMATION OP-100, Section 5.1.2, Step 1.a Performance Step: 3 VERIFY the following before pump start:

IF jogging RCPs per GP-001, THEN VERIFY RCS Pressure is greater than 325 psig.

Standard: Step 1.a is marked N/A Comment:

OP-100, Section 5.1.2, Step 1.b Performance Step: 4 VERIFY # 1 Seal P is greater than 200 psid.

Standard: Locates PI-156A1 and verifies that the A RCP #1 Seal P is greater than 200 psid.

Comment:

OP-100, Section 5.1.2, Note prior to Step 1.c Performance Step: 5 NOTE: VCT Outlet Temp TE-116 should be used for seal injection water temperature.

Standard: Operator reads and placekeeps note Comment:

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Appendix C Page 6 of 15 Form ES-C-1 PERFORMANCE INFORMATION OP-100, Section 5.1.2, Step 1.c Performance Step: 6 VERIFY Seal Injection flow is between 8 and 13 gpm at a temperature between 60 and 130°F.

Standard: Locates seal injection flow indication FI-156A and verifies flow between 8-13 gpm and also verifies VCT temperature indicator TI-116.1 reading between 60-130°F. The candidate my use ERFIS points rather than MCB indications.

Comment:

OP-100, Section 5.1.2, Step 1.d Performance Step: 7 VERIFY # 1 Seal Leakoff is in the normal operating range of Attachment 3.

Standard: Locates #1 Seal Leakoff flow indicator FR-154A and verifies that it meets Attachment 3 requirements (see below).

Seal Leakoff flow is also available via multiple programs on the Plant Evaluator Note: Computer (ERFIS, OSI-PI, etc). It is acceptable for the candidate to complete this step using ANY of the available indications.

Comment:

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Appendix C Page 7 of 15 Form ES-C-1 PERFORMANCE INFORMATION OP-100, Section 5.1.2, Caution prior to Step 2 Performance Step: 8 CAUTION: RCPs shall not be started with one or more of the RCS cold leg temperatures less than or equal to 325°F unless the secondary water temperature is less than 50°F above each of the RCS cold leg temperatures. This caution is only applicable to the first RCP to be started.

Standard: Operator reads and placekeeps caution

- Understands the caution is N/A.

Comment:

OP-100, Section 5.1.2, Step 2 Performance Step: 9 START the RCP Oil Lift Pump.

Standard: Locates B RCP Oil Lift Pump switch and starts the oil lift pump.

(Critical to start the RCP Oil Lift Pump)

START Time ____________

Comment:

OP-100, Section 5.1.2, Step 3 Performance Step: 10 VERIFY the amber permissive light on the lift pump control switch is lit indicating proper lift oil pressure has been achieved.

Standard: Locates amber permissive light on the B RCP Oil Lift Pump Switch and verifies it is lit.

Comment:

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Appendix C Page 8 of 15 Form ES-C-1 PERFORMANCE INFORMATION OP-100, Section 5.1.2, Step 4 Performance Step: 11 ALLOW the RCP Oil Lift Pump to run for a minimum of 2 minutes before starting an RCP.

Standard: Waits minimum of 2 minutes after starting the oil lift pump prior to starting the A RCP.

Comment:

OP-100, Section 5.1.2, Note prior to Step 5 Performance Step: 12 When an RCP is started, the RCP ammeter will go off scale high, and then decrease to the normal hot or cold running amps after 15 to 25 seconds.

Standard: Operator reads and placekeeps note Comment:

When the B RCP start switch is taken to start a timer starts and runs for 45 seconds after which 1RC-103 will ramp open over 45 seconds lowering RCS pressure and requiring the operator to enter into AOP-019.

Evaluator Note: Annunciators ALB-009-5-1, PRZ High-Low Press and ALB-009-3-3, PRZ Cont Low Press and Heaters On will alarm ~60 seconds after 1RC-103 begins to fail open.

IF no actions are taken a SI will occur ~4:30 minutes from event onset.

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Appendix C Page 9 of 15 Form ES-C-1 PERFORMANCE INFORMATION OP-100, Section 5.1.2, Step 5 Performance Step: 13 START the RCP.

Standard: Locates control switch for B RCP and starts B RCP Comment: START Time ____________ (> 2minutes since lift pump start)

The two minute minimum is not critical but ensures start permissives are met for the RCP start.

OP-100, Section 5.1.2, Step 6 Performance Step: 14 VERIFY the following normal operating parameters:

• Running amps: Hot 460 to 540 amps Cold 715 amps

• RCS flow: Greater than or equal to 98%

• # 1 Seal P Greater than 200 psid

• # 1 Seal leakoff in the normal operating range of Attachment 3

• Motor Winding temperature <300°F Standard: Locates and verifies each parameter is in the normal operating range (ERFIS or MCB indications may be used)

Comment: Note: Hot running motor amp range of 460 to 540 amps will apply.

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Appendix C Page 10 of 15 Form ES-C-1 PERFORMANCE INFORMATION The actions to secure the B RCP oil lift pump do not have Evaluators Note: to be performed since the RCS pressure reduction will take precedence over this step.

OP-100, Section 5.1.2, Note prior to Step 7 Performance Step: 15 NOTE: The oil lift pump should be run at least 1 minute after starting an RCP.

After at least 1 minute, STOP the RCP OIL LIFT PUMP.

Standard: Waits at least 1 minute then secures the B RCP oil lift pump.

Comment: Secure Time ____________ (> 1 minute since RCP start)

ALTERNATE PATH Performance Step: 16 Identifies RCS pressure lowering and Spray valve 1RC-103 failure Annunciators:

• ALB-009-5-1, PRZ High-Low Press

• ALB-009-3-3, PRZ Cont Low Press and Heaters On Standard: Identifies RCS pressure lowering Identifies PRZ Spray Loop A PCV-444D (1RC-103) red indication light and valve demand increasing (or at 100%)

Acknowledges alarms and reports conditions to CRS May review APP or directly enter AOP-019 based on current plant indications Announces AOP-019 Entry Conditions met, taking immediate actions for AOP-019.

Comment:

Evaluator Cue: CRS acknowledges report

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Appendix C Page 11 of 15 Form ES-C-1 PERFORMANCE INFORMATION Securing B RCP is an action contained in AOP-019 but this action is not performed immediately. Stopping the B RCP Evaluator Note: would be performed at step 14 in Section 3.1 of the procedure unless other trip limits on the RCP are exceeded prior to reaching this step.

AOP-019, Malfunction of RCS Pressure Control Performance Step: 17

• Steps 1 through 3 are immediate actions Standard: Performs immediate actions from memory without accessing or reading from the AOP Comment:

AOP-019, Step 1 Performance Step: 18 CHECK that a bubble exists in the PRZ. (YES)

Standard: States that a bubble exists in the PRZ Comment:

AOP-019, Step 2 Performance Step: 19 VERIFY ALL PRZ PORVs AND associated block valves properly positioned for current PRZ pressure and plant (YES) conditions.

Standard: Verifies ALL PRZ PORVs AND associated block valves properly Positioned by observing green shut lights indicated for all PRZ PORV and all red open lights on for PRZ PORV Block Valve control switches.

Comment:

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Appendix C Page 12 of 15 Form ES-C-1 PERFORMANCE INFORMATION AOP-019, Step 3 Performance Step: 20 CHECK BOTH PRZ Spray Valves properly positioned for current PRZ pressure and plant conditions.

PCV-444C PRZ Spray Loop A (1RC-107) - SHUT (YES)

PCV-444D PRZ Spray Loop B (1RC-103) - OPEN (NO)

Standard: Identifies that the PRZ Spray valves are NOT properly positioned for current plant conditions.

- Takes RNO actions Comment: 1RC-107 is shut which is its proper position.

1RC-103 should not be full open (or going full open for this condition).

AOP-019, Step 3 RNO Performance Step: 21 CONTROL PRZ Spray Valves using ONE of the following methods (listed in order of preference):

- AFFECTED Spray Valve controller in MANUAL (if only one is obviously malfunctioning)

OR

- PK-444A, Master Pressure Controller, in MANUAL OR

- BOTH individual Spray Valve controllers in MANUAL Standard: Places PCV-444D PRZ Spray Loop B controller to manual and lowers the output to zero (0).

Stops RCS pressure reduction caused from open spray valve.

Stabilizes RCS pressure.

Comment: (Critical to stop the RCS pressure reduction using one of the methods listed to prevent an unnecessary automatic SI from occurring.)

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Appendix C Page 13 of 15 Form ES-C-1 PERFORMANCE INFORMATION AOP-019, Malfunction of RCS Pressure Control Performance Step: 22 Obtain copy of AOP-019 Standard: Announces immediate actions of AOP-019 are complete and obtains a copy of AOP-019 to continue actions associated with the procedure.

Evaluator Cue: CRS acknowledges report Comment:

After the candidate has shut 1RC-103 and has obtained a copy of AOP-019: Evaluation on this JPM is complete.

Examiner Cue: Announce END OF JPM Direct Simulator Operator to place the Simulator in FREEZE.

STOP TIME:

Simulator Operator: When directed by the Lead Examiner then go to Freeze.

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Appendix C Page 14 of 15 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2020 HNP NRC Exam Simulator JPM d Start a RCP with Spray Valve Failure In accordance with OP-100, Reactor Coolant System In accordance with AOP-019, Malfunction Of RCS Pressure Control Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiners Signature: Date:

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Appendix C Form ES-C-1 JPM CUE SHEET

• You are the extra RO during a plant startup.

• GP-004, Reactor Startup is in progress and is currently on HOLD.

• The plant has been stabilized with Shutdown Banks withdrawn.

Initial Conditions:

• Two hours ago the B RCP was removed from service for maintenance.

• Maintenance has been completed and the B RCP is ready for operation.

• The previous crew has verified that all initial conditions to start the RCP are met and have initialed all steps

• The CRS has instructed you to start B RCP, in accordance with OP-100, Reactor Coolant System, Section 5.1, Reactor Coolant Initiating Cue:

Pump Start-up.

• The initial conditions have been verified.

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Appendix C Page 1 of 14 Form ES-C-1 Worksheet Facility: Harris Nuclear Plant Task No.: 022001H101 Task

Title:

Return the Containment Fan JPM No.: 2020 NRC Exam Coolers to normal following a Safety Simulator JPM e Injection actuation K/A

Reference:

022 A4.01 RO 3.6 SRO 3.6 ALTERNATE PATH - NO Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: Actual Performance: X Classroom Simulator X Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

• An automatic SI initiation occurred due to a combination of equipment failure and technician error Initial Conditions:

• SI has been terminated You have been directed to return Containment Fan Coolers to the normal alignment per ES-1.1, SI Termination, Attachment 1 step 6.a Initiating Cue:

using OP-169, Containment Cooling And Ventilation, Section 8.4. The A-SA train will be used for normal operation.

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Appendix C Page 2 of 14 Form ES-C-1 Worksheet Task Standard: The A-SA train of Containment Fan Coolers are returned to NORMAL lineup in accordance with EOP-ES-1.1 and OP-169.

Required Materials: None General

References:

EOP-ES-1.1, SI Termination, Rev 3 OP-169, Containment Cooling And Ventilation, Rev 28 Handout: EOP-ES-1.1 Attachment 1 Sheet 3 of 7 OP-169, Rev. 28, pages 1 - 6, Prerequisites, P&Ls OP-169, Rev. 28, pages 7 - 9, Section 5.1, Start Up of Containment Fan Cooler Units (Normal Cooling Mode)

OP-169, Rev. 28, pages 27 - 28, Section, 8.4, Returning System to Normal from SI Operation Time Critical Task: No Validation Time: 15 Minutes PERFORMANCE CRITICAL STEP JUSTIFICATION STEP Step 4 The fan must be stopped in order to be in the correct operating mode for the current plant condition with the emergency dampers shut.

To comply with OP-169, Precaution and Limitation #11 Step 13 After any fan cooler is started in low speed, the fan should be allowed to come up to speed for approximately 15 seconds before shifting to fast speed. This reduces the starting current required for high speed operation.

The fan must be stopped in order to change fan speed from low speed Step 15 to high speed in order to be in the correct operating mode for the current plant condition.

Step 17 The fan must be stopped in order to be in the correct operating mode for the current plant condition with the emergency dampers shut.

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Appendix C Page 3 of 14 Form ES-C-1 Worksheet 2020 NRC Exam - SIMULATOR SETUP Simulator Operator

• Reset to IC-148

• Password NRC3sros

• Go to RUN and wait ~ 10 seconds then silence and acknowledge alarms.

GO TO FREEZE and inform the lead examiner the Simulator is ready. DO NOT GO TO RUN until directed by the lead examiner. (The examiner has provided to the candidate with initial conditions and the initiating cues prior to placing the simulator in RUN.)

To recreate the IC setup for this JPM:

• Initial Simulator IC was IC-19

• Insert a Manual SI or MALF for Inadvertent SI

• Perform / markup E-0 through transition to ES-1.1

• Perform / markup ES-1.1 actions up to step 35 which is Realign Plant Systems for Normal Ops using Attachment 1 (restoration of Containment Fan Coolers is directed)

• Leave Fan Coolers in SI Mode

• Silence Acknowledge and Reset Annunciators

• FREEZE and Snap these conditions to your exam IC 2020 HNP NRC Exam Simulator JPM e Rev FINAL

Appendix C Page 4 of 14 Form ES-C-1 PERFORMANCE INFORMATION Simulator Operator: When directed by the Lead Examiner go to Run.

START TIME:

OP-169, 8.4.1 Performance Step: 1 Review applicable procedure.

Standard: Verifies Initial Conditions are met.

• SI Reset (YES)

• Instrument Air restored to dampers (YES)

Comment:

OP-169, 8.4.2, Caution prior to step 1 Performance Step: 2 CAUTION: Failure of equipment to secure in this section will result in the associated EDG being inoperable. Tech Spec 3.8.1.1 is applicable until the breaker for the affected load is opened.

Standard: Operator reads and placekeeps caution Comment:

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Appendix C Page 5 of 14 Form ES-C-1 PERFORMANCE INFORMATION OP-169, 8.4.2 Step 1 Performance Step: 3 CIRCLE the train to be used for normal operation. A-SA (B-SB)

Evaluator Cue: The CRS designates Train A for normal operation.

Standard:

• Circles the A-SA components for alignment in step 2 Comment:

OP-169, 8.4.2 Step 2 Performance Step: 4 PLACE the following control switches for the selected trains Air Handling Units to STOP:

• AH-2 A-SA (AH-1 A-SB)

• AH-2 B-SA (AH-1 B-SB)

• AH-3 A-SA (AH-4 A-SB)

• AH-3 B-SA (AH-4 B-SB)

Standard:

• Places AH-2 A-SA control switch in STOP.

• Places AH-2 B-SA control switch in STOP.

• Places AH-3 A-SA control switch in STOP.

• Places AH-3 B-SA control switch in STOP.

Comment:

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Appendix C Page 6 of 14 Form ES-C-1 PERFORMANCE INFORMATION OP-169, 8.4.2 Step 3 Performance Step: 5 CHECK the following post-accident discharge nozzle dampers SHUT on Status Light Box 5 (6) for the selected train of fans:

a. CV-D3 for AH-2 (CV-D1 for AH-1)

b. CV-D5 for AH-3 (CV-D7 for AH-4)

Standard: Verifies CV-D3 and CV-D5 indicate SHUT on Status Light Box 5.

Comment:

OP-169, 8.4.2 Step 4 Performance Step: 6 PLACE the train secured in Step 8.4.2.2 in operation per Section

5.1. Standard

Proceeds to Section 5.1.

Evaluator Cue: Provide OP-169, Section 5.1 to the candidate at this time.

Comment:

OP-169, Note prior to Section 5.1 Performance Step: 7 NOTE: Where the Operator has a choice between Train A or Train B, this procedure will list Train A number and letter identification first with Train B in parentheses.

Standard: Operator reads and placekeeps note Comment:

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Appendix C Page 7 of 14 Form ES-C-1 PERFORMANCE INFORMATION OP-169, 5.1.1, Initial Conditions Performance Step: 8 Verify Initial Conditions:

• Attachments 1 and 2 are completed.

• ESW train is in service which corresponds to the AH unit train to be started.

Standard:

• Acknowledges cue for Attachments 1 and 2.

• Verifies ESW Train A in service.

Evaluator Cue: Attachments 1 and 2 have been completed.

Comment:

OP-169, 5.1.2, Note prior to step 1 Performance Step: 9 NOTE: When changing Containment Cooling modes, or swapping Containment Fan Cooler Trains, care must be taken to prevent the following:

• Entering Technical Specification 3.6.1.4 at -1.0 inwg Containment pressure (1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> action).

• Opening the Containment Vacuum Breakers at -2.25 inwg Containment pressure.

This may be accomplished by performing the evolution slowly, monitoring CNMT pressure effects using ERFIS point PCP7611. Also, placing the Containment Normal Purge Exhaust flow controller (FK-7624) in manual and shutting CP-B9, will allow CNMT pressure to slowly rise, thus compensating for the CNMT pressure drop that will occur during each fan start.

Standard: Operator reads and placekeeps note Comment:

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Appendix C Page 8 of 14 Form ES-C-1 PERFORMANCE INFORMATION OP-169, 5.1.2, Caution prior to step 1 Performance Step: 10 CAUTION: Failure of equipment to secure in this section will result in the associated EDG being inoperable. Tech Spec 3.8.1.1 is applicable until the breaker for the affected load is opened.

Standard: Operator reads and placekeeps caution Comment:

OP-169, 5.1.2, step 1 Performance Step: 11 IF CNMT Normal Purge is in service AND IF desired for CNMT pressure control, THEN PERFORM the following:

a. PLACE FK-7624, NORM PURGE EXH FLOW, in MANUAL.

b. Using FK-7624, SHUT CP-B9, NORM CONT PURGE MODULATING VALVE (SLB-7 / 5-3).

c. IF CNMT Normal Purge needs to be restored at any time during the performance of this procedure section, THEN PERFORM the following:

(1) IF CNMT Normal Purge has NOT tripped, THEN RESTORE FK-7624 to AUTO.

(2) IF CNMT Normal Purge has tripped, THEN STARTUP CNMT Normal Purge per OP-168.

Standard:

• Checks CNMT Normal Purge secured and N/As steps 1.a, 1.b, and 1.c CNMT Normal Purge will be restored by another operator Evaluator Cue:

per ES-1.1 Attachment 1 step 12.

Comment:

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Appendix C Page 9 of 14 Form ES-C-1 PERFORMANCE INFORMATION OP-169, 5.1.2, Note prior to step 2 Performance Step: 12 NOTE: In winter months, the operating train should be secured per Section 7.1 prior to starting the idle train, to minimize the potential for entering Technical Specification 3.6.1.4 at -1.0 inwg Containment pressure (1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> action), or opening the Containment Vacuum Breakers at -2.25 inwg Containment pressure.

Standard: Operator reads and placekeeps note Comment:

OP-169, 5.1.2, step 2 Performance Step: 13 Place the control switches for both fans in each Containment cooler unit AH-2 A-SA (AH-1 B-SB) and AH-3 A-SA (AH-4 B-SB) to LO-SPD.

Standard:

• Places control switch for AH-2 A-SA in LO-SPD.

• Places control switch for AH-2 B-SA in LO-SPD.

• Places control switch for AH-3 A-SA in LO-SPD.

• Places control switch for AH-3 B-SA in LO-SPD.

Comment:

OP-169, 5.1.2, Notes prior to step 3 Performance Step: 14 NOTE: After any fan cooler is started in low speed, the fan should be allowed to come up to speed for approximately 15 seconds before shifting to fast speed. This reduces the starting current required for high speed operation.

NOTE: The following switch sequence must be performed without delay, one fan at a time, to prevent fan coast down before being started in fast speed. This sequence is functionally related (obtain a single result in close sequence or time), allowing signoff to be delayed until running in HI-SPD.

Standard: Operator reads and placekeeps notes Comment:

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Appendix C Page 10 of 14 Form ES-C-1 PERFORMANCE INFORMATION OP-169, 5.1.2, step 3 Performance Step: 15 Place the control switch for the fans started in Step 5.1.2.2, START in HI-SPD as follows:

• AH-2 A-SA (AH-1 A-SB)

(1) PLACE AH-2 A-SA (AH-1 A-SB) control switch to STOP (2) PLACE AH-2 -SA (AH-1 A-SB) control switch to HI-SPD

• AH-2 B-SA (AH-B-SB)

(1) PLACE AH-2 B-SA (AH-1 B-SB) control switch to STOP (2) PLACE AH-2 B-SA (AH-1 B-SB) control switch to HI-SPD

• AH-3 A-SA (AH-4 A-SB)

(1) PLACE AH-3 A-SA (AH-4 A-SB) control switch to STOP (2) PLACE AH-3 A-SA (AH-3 A-SB) control switch to HI-SPD

• AH-3 B-SA (AH-4 B-SB)

(1) PLACE AH-3 B-SA (AH-4 B-SB) control switch to STOP (2) PLACE AH-3 B-SA (AH-4 B-SB) control switch to HI-SPD Standard:

• Places control switch for AH-2 A-SA in STOP, then HI-SPD

• Places control switch for AH-2 B-SA in STOP, then HI-SPD

• Places control switch for AH-3 A-SA in STOP, then HI-SPD

• Places control switch for AH-3 B-SA in STOP, then HI-SPD Comment:

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Appendix C Page 11 of 14 Form ES-C-1 PERFORMANCE INFORMATION OP-169, 5.1.2, step 4, 5, and 6 Performance Step: 16

• IF FK-7624 was taken to MANUAL in Step 5.1.2.1.a, THEN RESTORE FK-7624 to AUTO.

• IF CNMT Normal Purge is not in service, AND it is desired to place CNMT Normal Purge in service, THEN STARTUP CNMT Normal Purge per OP-168.

• IF both trains of Containment Fan Cooler fans are running (such as during a train swap evolution), THEN PROCEED to Section 7.1 to secure the desired train.

Standard: Reviews steps 4, 5, and 6 and marks these steps N/A Returns to Section 8.4.2 and proceeds with step 5 Comment:

OP-169, 8.4.2, step 5 Performance Step: 17 PLACE the following control switches for the standby train to STOP:

• AH-1 A-SB (AH-2 A-SA)

• AH-1 B-SB (AH-2 B-SA)

• AH-4 A-SB (AH-3 A-SA)

• AH-4 B-SB (AH-3 B-SA)

Standard:

• Places control switch for AH-1 A-SB in STOP

• Places control switch for AH-1 B-SB in STOP

• Places control switch for AH-4 A-SB in STOP

• Places control switch for AH-4 A-SB in STOP Comment:

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Appendix C Page 12 of 14 Form ES-C-1 PERFORMANCE INFORMATION OP-169, 8.4.2, step 6 Performance Step: 18 CHECK the following post-accident discharge nozzle dampers SHUT on Status Light Box 6 (5) for the standby train of fans:

a. CV-D1 for AH-1 (CV-D3 for AH-2) (Shut)

b. CV-D7 for AH-4 (CV-D5 for AH-3) (Shut)

Standard: Checks CV-D1 for AH-1 and CV-D7 for AH-4 indicate SHUT on Status Light Box 6.

Comment:

OP-169, 8.4.2, step 7 Performance Step: 19 If containment temperature is greater than 118 F or if additional cooling is desired, refer to Section 8.1, Start-Up of Fan Cooler Units (Maximum Cooling mode).

Standard: Verifies containment temperature is less than 118 F.

(Maybe > 118° but trending DOWN at this time.)

Marks step 7 as N/A Evaluator Cue: If requested to perform section 8.1 cue the candidate that another operator will complete section 8.1.

Comment:

After containment temperature is verified at or trending to less than 118 F: Evaluation on this JPM is complete.

Evaluator Cue: Announce END OF JPM Direct Simulator Operator to place the Simulator in FREEZE.

STOP TIME:

Simulator Operator: When directed by the Lead Examiner then go to Freeze.

- Denotes Critical Steps 2020 HNP NRC Exam Simulator JPM e Rev FINAL

Appendix C Page 13 of 14 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2020 HNP NRC Exam Simulator JPM e Return the Containment Fan Coolers to normal following a Safety Injection actuation In accordance with OP-169, Containment Cooling And Ventilation In accordance with EOP-ES-1.1, SI Termination Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiners Signature: Date:

2020 HNP NRC Exam Simulator JPM e Rev FINAL

Appendix C Page 14 of 14 Form ES-C-1 JPM CUE SHEET

• An automatic SI initiation occurred due to a combination of equipment failure and technician error Initial Conditions:

• SI has been terminated You have been directed to return Containment Fan Coolers to the normal alignment per ES-1.1, SI Termination, Attachment 1 step 6.a Initiating Cue:

using OP-169, Containment Cooling And Ventilation, Section 8.4. The A-SA train will be used for normal operation.

2020 HNP NRC Exam Simulator JPM e Rev FINAL

Appendix C Page 1 of 11 Form ES-C-1 Worksheet Facility: Harris Nuclear Plant Task No.: 064005H101 Task

Title:

Shutdown EDG A-SA From MCB JPM No.: 2020 NRC Exam For Maintenance - Field Flash Stays Energized Simulator JPM f K/A

Reference:

064 A4.06 RO 3.9 SRO 3.9 ALTERNATE PATH - YES Examinee: ________________________ NRC Examiner: _________________

Facility Evaluator: ________________________ Date: ________

Method of testing:

Simulated Performance: Actual Performance: X Classroom Simulator X Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

• The Unit is operating 100% power

• The A EDG is running in parallel with the grid to support testing of the governor Initial Conditions:

• OST-1013, 1A-SA Emergency Diesel Generator Operability Test Monthly Interval Modes 1-2-3-4-5-6 is NOT in progress

• Testing of the governor is complete

• The previous shift has reduced the EDG load from 6.3 MW to 2.3 MW and 1 MVAR over the last 30 minutes per OP-155, Emergency Diesel Generator Section 7.1 Initiating Cue:

• You are the BOP. The CRS directs you to continue shutting down the A EDG using OP-155 Section 7.1.2 starting at Step 4.

The candidate should be briefed outside of the simulator prior to performing this JPM. Provide them with a copy of OP-155, pages 1 - 14, 42 - 46, 177 - 182. This will allow them to review the Evaluator NOTE:

Precautions and Limitations associated with OP-155 and have time for a task review of the steps. Expect the candidate to take about 10 - 15 minutes to complete this review.

2020 HNP NRC Exam Simulator JPM f Rev FINAL

Appendix C Page 2 of 11 Form ES-C-1 Worksheet Task Standard: A EDG unloaded and shutdown using the STOP control switch per OP-155 then EMERGENCY STOPPED following a failure of the field flash to de-energize.

Required Materials: None General

References:

OP-155, Diesel Generator Emergency Power System, Rev. 91 Handout: OP-155, Rev. 91, pages 1 - 14, Prerequisites, P&Ls OP-155, Rev. 91, pages 42 - 46, Section 7.1, Unloading and Shutdown of Emergency Diesel Generators From the MCB, signed off up to 7.1.2 Step 4.

OP-155, Rev. 91, pages 177 - 182, Attachment 7 - Emergency Diesel Generator Post Run Checklist Time Critical Task: No Validation Time: 10 minutes PERFORMANCE CRITICAL STEP JUSTIFICATION STEP Controlled load reduction to 0.5 MW prevents reverse powering the A Step 4 EDG.

Opening Breaker 106 separates the A EDG from the grid which Step 5 removes load from the EDG and allows the stack exhaust temperatures to lower limiting thermal stresses on the EDG.

Normal stopping the EDG closes the Air admission valves and positions Step 13 the EDG fuel racks to minimum slow the EDG speed.

Emergency stopping the EDG de-energizes the field flashing circuit Step 15 voltage to prevent the voltage regulator from catching fire if not de-energized.

PERFORMANCE ALTERNATE PATH JUSTIFICATION STEP Generator continues to produce voltage following normal shutdown Steps 14 & 15 requiring operator to emergency stop the EDG.

2020 HNP NRC Exam Simulator JPM f Rev FINAL

Appendix C Page 3 of 11 Form ES-C-1 Worksheet 2020 NRC Exam - SIMULATOR SETUP Simulator Operator

• Reset to IC-149

• Password NRC3sros

• Put reactivity data sheets for IC-19 and MOL on status board

• Go to run

• Silence and Acknowledge annunciators GO TO FREEZE and inform the lead examiner the Simulator is ready. DO NOT GO TO RUN until directed by the lead examiner. (The examiner has provided to the candidate with initial conditions and the initiating cues prior to placing the simulator in RUN.)

To recreate the IC setup for this JPM:

• Initial Simulator IC was IC-19

• Go To RUN

• Start and load the A EDG to approximately 2.3 MW and 1 MVAR.

• To simulate that the EDG has been stopped and field flashing is still occurring by still having voltage on meter EI-6955A and EI-5945A, create a CAEP as follows:

TRG 1 "EDG_A_Start_Switch_to_Stop" iao xd1d010m (1 00:00:05 00:00:00) 7.2 00:00:05 7.08 iao xd1d022m (1 00:00:05 00:00:00) 210 00:00:05 167 iao xd1d023m (1 00:00:05 00:00:00) 56 00:00:05 51 TRG 2 "EDG_A_Emergency_Stop_Switch_to_Stop" trg= 2 dao xd1d010m trg= 2 dao xd1d022m trg= 2 dao xd1d023m

• Silence Acknowledge and Reset Annunciators

• FREEZE and Snap these conditions to your exam IC 2020 HNP NRC Exam Simulator JPM f Rev FINAL

Appendix C Page 4 of 11 Form ES-C-1 PERFORMANCE INFORMATION Simulator Operator: When directed by the Lead Examiner go to Run.

START TIME:

OP-155 Section 7.1.2, Note prior to step 4 Performance Step: 1 NOTE: The EDG should be completely unloaded from 35% load in less than 5 minutes to minimize carbon buildup.

Standard: Operator reads and placekeeps note Comment:

OP-155 Section 7.1.2 Step 4.a Performance Step: 2 PERFORM the following:

a. ENSURE load has been less than 6.2 to 6.4 MW for at least 20 minutes Standard: Refers to Initial Conditions and determines the A EDG load has been below 6.2 MW for the last 30 Comment:

- Denotes Critical Steps 2020 HNP NRC Exam Simulator JPM f Rev FINAL

Appendix C Page 5 of 11 Form ES-C-1 PERFORMANCE INFORMATION OP-155, Section 7.1.2 Step 4.b Performance Step: 3 b. ENSURE Generator Winding Temperature is less than 135°C Standard: Contacts AO at the ECP or obtains winding temperature from ERFIS Simulator Operator: If contacted, Generator Winding Temperature is 125°C.

Comment:

Terminate the JPM if the candidate reverse powers the A Evaluator Note:

EDG OP-155, Section 7.1.2 Step 4.c Performance Step: 4 c. REDUCE load to 0.5 MW Standard: Time Started Load Reduction: ______

Locates the Governor Control and Auto Voltage Adjust control switches and adjust the control switches to reduce the A EDG load to 0.5 MW while maintaining load within the Attachment 9 -

Emergency Diesel Generator Capacity Curve limits Comment:

- Denotes Critical Steps 2020 HNP NRC Exam Simulator JPM f Rev FINAL

Appendix C Page 6 of 11 Form ES-C-1 PERFORMANCE INFORMATION OP-155, Section 7.1.2 Step 4.d Performance Step: 5 d. PLACE DIESEL GEN A-SA BREAKER 106 SA to TRIP.

Standard: Locates Diesel Gen A-SA Breaker 106 SA control switch and places the switch in the trip position in 5 minutes from resuming load reduction Comment:

OP-155, Section 7.1.2 Step 5. a Performance Step: 6 ENSURE the following:

a. DIESEL GEN A-SA BREAKER 106 SA to indicates OPEN.

Standard: Locates Diesel Gen A-SA Breaker 106 SA control switch and determines the Green light is Lit and the Red light is extinguished.

Comment:

OP-155, Section 7.1.2 Step 5.b Performance Step: 7 b. EI-6957A1 SA, A Power, indicates zero..

Standard: Locates EI-6957A1 SA, A Power indication and determines the meter is on the lower peg indicating zero.

Comment:

- Denotes Critical Steps 2020 HNP NRC Exam Simulator JPM f Rev FINAL

Appendix C Page 7 of 11 Form ES-C-1 PERFORMANCE INFORMATION OP-155, Section 7.1.2 Step 5.c Performance Step: 8 c. EI-6951A SA, A Amps, indicates zero.

Standard: Locates EI-6951A SA, A Amps indication and determines the meter is on the lower peg indicating zero.

Comment:

OP-155, Section 7.1.2 Step 6 Performance Step: 9 RECORD time DIESEL GEN A-SA BREAKER 106 SA is opened on Attachment 7.

Standard: Refers to Attachment 7 - Emergency Diesel Generator Post Run Checklist, and records the time Breaker 106 SA is open in Step 17.j.

Comment:

OP-155, Section 7.1.2 Step 7 Performance Step: 10 IF performing monthly EDG test, THEN PERFORM the following:

a. MARK the remainder of this section N/A.

b. CONTINUE EDG shutdown per OST-1013 (OST-1073).

Standard: Refers to initial conditions and determines step is not applicable and marks step 7a and 7b N/A.

Comment:

- Denotes Critical Steps 2020 HNP NRC Exam Simulator JPM f Rev FINAL

Appendix C Page 8 of 11 Form ES-C-1 PERFORMANCE INFORMATION OP-155, Note prior to Section 7.1.2 Step 8 Performance Step: 11 To determine that cylinder temperatures are less than 450°F, the stack exhaust temperature will be monitored until temperature is less than 500°F.

Standard: Operator reads and placekeeps note Comment:

OP-155, Section 7.1.2 Step 8 Performance Step: 12 At the ECP, POSITION temperature selector switch to positions 17 and 18 to monitor stack exhaust temperatures.

Standard:

• Contacts AO at the ECP and requests stack exhaust temperatures.

Stack Exhaust Temperatures are 475°F on positions 17 Simulator Operator:

and 18.

Comment:

OP-155, Section 7.1.2 Step 9 Performance Step: 13 At the MCB, WHEN stack exhaust temperatures are less than 500°F, THEN POSITION DIESEL GENERATOR A-SA CONTROL SWITCH TO STOP.

Standard: Locates Diesel Generator A-SA control switch and places the switch in the stop position Comment:

- Denotes Critical Steps 2020 HNP NRC Exam Simulator JPM f Rev FINAL

Appendix C Page 9 of 11 Form ES-C-1 PERFORMANCE INFORMATION Alternate Path begins here OP-155, Section 7.1.2 Step 10 Performance Step: 14 At the MCB, CHECK the following: (Reference 2.7.4, 2.7.7, 2.8.11)

a. EI-6955A SA, A VOLTS, voltage is decreasing.

b. EI-6954A SA, A FLD VOLTS, voltage is decreasing.

Standard: Locates EI-6955A SA, A Volts and EI-6954A SA, A FLD Volts indications and determines the meters are unchanged and the generator is still producing voltage.

Comment:

OP-155, Section 7.1.2 Step 11 (ALTERNATE PATH)

Performance Step: 15 IF voltage is NOT decreasing, THEN EMERGENCY STOP the EDG to prevent the voltage regulator from catching fire.

Standard: () Locate Diesel Generator A-SA Emergency Stop control switch and places the switch in the emergency stop position Reports to CRS that EDG A had to be Emergency Stopped due to field flashing still occurring.

Comment:

Evaluator Acknowledge any communications.

Communication:

After the A EDG has been Emergency stopped and communications are completed:

Evaluator Note:

Cue - END OF JPM - I have the shift.

Direct Simulator Operator to go to FREEZE STOP TIME:

Simulator Operator: When directed by the Lead Examiner go to FREEZE.

- Denotes Critical Steps 2020 HNP NRC Exam Simulator JPM f Rev FINAL

Appendix C Page 10 of 11 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2020 HNP NRC Exam Simulator JPM f Shutdown EDG A-SA From MCB For Maintenance - Field Flash Stays Energized In accordance with OP-155, Diesel Generator Emergency Power System Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiners Signature: Date:

2020 HNP NRC Exam Simulator JPM f Rev FINAL

Appendix C Page 11 of 11 Form ES-C-1 JPM CUE SHEET

• The Unit is operating 100% power

• The A EDG is running in parallel with the grid to support testing of the governor Initial Conditions:

• OST-1013, 1A-SA Emergency Diesel Generator Operability Test Monthly Interval Modes 1-2-3-4-5-6 is NOT in progress

• Testing of the governor is complete

• The previous shift has reduced the EDG load from 6.3 MW to 2.3 MW and 1 MVAR over the last 30 minutes per OP-155, Emergency Diesel Generator Section 7.1

• You are the BOP. The CRS directs you to continue shutting Initiating Cue:

down the A EDG using OP-155 Section 7.1.2 starting at Step 4 2020 HNP NRC Exam Simulator JPM f Rev FINAL

Appendix C Page 1 of 15 Form ES-C-1 Worksheet Facility: Harris Nuclear Plant Task No.: 015001H101 Task

Title:

Power Range NI Gain Adjustment JPM No.: 2020 NRC Exam Simulator JPM g K/A

Reference:

015 A4.02 RO 3.9 SRO 3.9 ALTERNATE PATH - NO Examinee: ________________________ NRC Examiner: ______________

Facility Evaluator: ________________________ Date: ________

Method of testing:

Simulated Performance: Actual Performance: X Classroom Simulator X Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

• The unit is at 100% equilibrium conditions.

• Following maintenance on PR Channel NI-41, all required testing has been completed and the channel is ready to be returned to service. A calorimetric has just been performed per OST-1000, Power Range Heat Balance, ERFIS Online Calculation, Daily Initial Conditions: Interval, Mode 1 (Above 15% Power). The OST requires that an NI gain adjustment be performed.

• The calculated power is 99.88%. Indicated power on PR channel NI-41 at the time of the calorimetric was at its current value.

• Rod Control is in Automatic.

You are to perform the Power Range NI Gain Adjust for PR channel Initiating Cue: NI-41 in accordance with OP-105, Excore Nuclear Instrumentation, Section 8.3 and Attachment 2.

NOTE: The Simulator Operator will be required to adjust the Pot Setting for NI-41 per the Simulator Setup instructions each time this JPM is administered.

The candidate should be briefed outside of the simulator prior to performing this JPM. Provide them with a copy of OP-105, pages 1-8, 19, 37-48. This will allow them to review the Precautions and Evaluator NOTE:

Limitations associated with OP-105 and have time for a task review of the steps. Expect the candidate to take about 10 - 15 minutes to complete this review.

2020 HNP NRC Exam Simulator JPM g Rev FINAL

Appendix C Page 2 of 15 Form ES-C-1 Worksheet Task Standard: Gain has been adjusted within limits for PR Channel N-41 in accordance with OP-105.

Required Materials: None General

References:

OP-104, Rod Control System, Rev. 45 OP-105, Excore Nuclear Instrumentation Rev. 30 Handout: OP-104, Rev. 45, pages 1- 8, Prerequisites, P&Ls OP-104, Rev. 45, page 54, and Section, 8.15, Placing Rod Control In Manual For Testing/Plant Conditions OP-105, Rev. 30, pages 1 - 7, Prerequisites, P&Ls OP-105, Rev. 30, page 19, Section, 8.3, Power Range NI Gain Adjustment OP-105, Rev. 30, pages 37 - 48, Attachment 2, Power Range NI Gain Adjustment Time Critical Task: No Validation Time: 15 minutes PERFORMANCE CRITICAL STEP JUSTIFICATION STEP Step 4 Must determine the desired indication, including sign, of N-41 to return the instrumentation to the current power level.

Must place Rod control from Automatic control to Manual control to Step 6 prevent unnecessary reactivity change from occurring due to control rod motion that would occur while adjusting NI gain on channel N-41.

Must adjust the gain pot in CW direction until indicated power is within Step 14 0.5% of value determined to meet the acceptance criteria prior to relocking the pots. Note: the procedure acceptance is within 0.2% but due to the sensitivity of the pots, acceptance for this step is +/- 0.5%

Step 17 Must determine reset the RATE TRIP signal to restore RPS logic from 1 of 3 logic to the normal 2 of 4 logic if the RATE TRIP signal is present.

2020 HNP NRC Exam Simulator JPM g Rev FINAL

Appendix C Page 3 of 15 Form ES-C-1 Worksheet 2020 NRC Exam - SIMULATOR SETUP Simulator Operator

• Reset to IC-152

• Password NRC3sros

• Put reactivity data sheets for IC-19 and MOL on status board

• Go to run

• Place Meter Rate on front of PR channel NI-41 to Fast

• Unlock gain pot on the front of PR channel NI-41 o If this is the first performance of the day, swipe the pot by rotating it several turns in each direction to clean it. The pots can become very sensitive over time.

• Slowly adjust the gain to 2.70 (verify that it indicates approximately 3 % - 4 %

below the other 3 PR channels)

• Lock gain pot

• Place Meter Rate on front of PR channel NI-41 to Slow

• Silence and Acknowledge annunciators GO TO FREEZE and inform the lead examiner the Simulator is ready. DO NOT GO TO RUN until directed by the lead examiner. (The examiner has provided to the candidate with initial conditions and the initiating cues prior to placing the simulator in RUN.)

This portion of Simulator setup is now compete and must be completed between each evaluation.

To recreate the IC setup for this JPM:

• Initial Simulator IC was IC-19

• Initialize to IC-19, go to RUN

• Place Rod Control in MAN

• Place Meter Rate on front of PR channel NI-41 to Fast

• Unlock gain pot on the front of PR channel NI-41

• If this is the first performance of the day, swipe the pot by rotating it several turns in each direction to clean it. During Validation it was noted the pots can become very sensitive over time.

• Slowly adjust the gain to 2.70 (verify that it indicates approximately 3 % - 4 % below the other 3 PR channels)

• Ensure any alarms caused by this adjustment are acknowledged

• Lock gain pot

• Place Meter Rate on front of PR channel NI-41 to Slow

• Place Rod Control in AUTO

• Silence Acknowledge and Reset Annunciators

• Freeze and Snap these conditions to your exam IC 2020 HNP NRC Exam Simulator JPM g Rev FINAL

Appendix C Page 4 of 15 Form ES-C-1 PERFORMANCE INFORMATION Simulator Operator: When directed by the Lead Examiner go to Run.

START TIME:

OP-105 Attachment 2 Notes and Caution prior to step 1 Performance Step: 1 NOTE: Calculated power shall be that power calculated by OST-1000, OST-1004 or other applicable plant procedures.

NOTE: If the indicator on the NI drawers is not available, the corresponding ERFIS point may be used. The following computer points update every two seconds, and can be used for initial adjustment:

• ANM0120 NI-41 PR CHANNEL

• ANM0121 NI-42 PR CHANNEL

• ANM0122 NI-43 PR CHANNEL

• ANM0123 NI-44 PR CHANNEL The following computer points are the one minute average of the points above, and are used in recording indicated power and making final determinations on adequacy of the adjustment:

• ANM0120M NI-41 PR CHANNEL

• ANM0121M NI-42 PR CHANNEL

• ANM0122M NI-43 PR CHANNEL

• ANM0123M NI-44 PR CHANNEL Caution: To prevent a possible non-conservative adjustment being made, no significant power decreases should be made between the time of performance of the calorimetric and the following adjustments.

Standard: Reads and place keeps notes and caution Comment:

- Denotes Critical Steps 2020 HNP NRC Exam Simulator JPM g Rev FINAL

Appendix C Page 5 of 15 Form ES-C-1 PERFORMANCE INFORMATION OP-105 Attachment 2 Step 1 Performance Step: 2 MARK portions of Attachment 2 N/A for any NI not being adjusted as follows:

IF NI-41 will not be adjusted, THEN MARK the following N/A:

IF NI-42 will not be adjusted, THEN MARK the following N/A:

IF NI-43 will not be adjusted, THEN MARK the following N/A:

IF NI-44 will not be adjusted, THEN MARK the following N/A:

Standard:

Determines NI-42, NI-43 and NI-44 will not be adjusted and marks through the applicable section with N/A.

Comment:

The candidate should be allowed to complete this step as Evaluator Note: part of the pre-job brief prior to entering the simulator for evaluation.

OP-105 Attachment 2 Step 2 Performance Step: 3 DETERMINE the difference, including sign, between the calculated power (from OST-1000 or OST-1004) and the indicated reactor power at the time data was obtained as follows:

CALC PWR - N41 IND PWR = N41 DIFFERENCE 99.88 - 96.0 = +3.88 Standard:

Calculates difference (Determined by subtracting present indicated value of N-41 from 99.88% calculated power.)

(Band 99.88 - 95.8 = 3.68 to 99.88 - 96.2 = 4.08)

Comment:

You will be asked to initial for IV during the procedure.

State that you can assume that the IV has been performed Evaluator Note: for each step performed.

The candidate is responsible to ensure each step is completed correctly

- Denotes Critical Steps 2020 HNP NRC Exam Simulator JPM g Rev FINAL

Appendix C Page 6 of 15 Form ES-C-1 PERFORMANCE INFORMATION OP-105 Attachment 2 Step 3 Performance Step: 4 DETERMINE the desired indication, including sign, of NIS as follows:

N41 PRESENT IND + N41 DIFFERENCE = N41 DESIRED IND 96.0 + (+3.88) = 99.88 Standard:

Calculates desired N-41 indication to be 99.9%

Determined by algebraically summing N-41 difference from Step 2 and N-41 present indicated value.

(Band 95.8 + 3.68 = 99.48 to 96.2 + 4.08 = 100.28)

Comment:

OP-105 Attachment 2 Step 4 Performance Step: 5 Record the as found setting of the GAIN potentiometer on the front of Power Range Drawer B Standard: Records setting as 2.70 Comment:

- Denotes Critical Steps 2020 HNP NRC Exam Simulator JPM g Rev FINAL

Appendix C Page 7 of 15 Form ES-C-1 PERFORMANCE INFORMATION OP-105 Attachment 2 Step 5 Performance Step: 6 VERIFY the ROD BANK SELECTOR switch is in MANUAL per OP-104 Section 8.15, Placing Rod Control In Manual For Testing/Plant Conditions, to prevent undesired rod movement during the adjustment.

Standard:

Obtains copy of OP-104 Section 8.15 and places Rod Bank Selector switch in Manual position.

OP-104 Section 8.15 Initial conditions: Plant conditions or testing require Rod Control to be in Manual Step 1. At the MCB, ROTATE the ROD BANK SELECTOR Switch to MAN Step 2. VERIFY Rod Speed of 48 steps per minute on SI-408 NOTE: OMM-001, Operations Administrative Requirements, suggest a trip limit of Tavg not within 10° of Tref, whether high or low, in stable plant conditions.

Step 3. MAINTAIN Tavg within 2°F of Tref.

Step 4. IF desired WHEN testing is completed or plant conditions have changed, THEN PLACE Rod Control in AUTO per Section 5.5.

Evaluator Cue: Provide OP-104, Section 8.15 to the candidate at this time.

Comment:

- Denotes Critical Steps 2020 HNP NRC Exam Simulator JPM g Rev FINAL

Appendix C Page 8 of 15 Form ES-C-1 PERFORMANCE INFORMATION OP-105 Attachment 2 Step 6 Performance Step: 7 VERIFY the Feed Reg Bypass Valve Controllers are in manual to prevent undesired valve motion during adjustment.

1FW-140, MN FW A REG BYP FK-479.1 1FW-256, MN FW B REG BYP FK-489.1 1FW-198, MN FW C REG BYP FK-499.1 Standard: Locates MCB switches for Feed Reg Bypass Valve Controllers and verifies that all 3 are in manual Comment:

OP-105, Attachment 2, N41 Adjustments (sheet 4 of 12)

Step 1 Performance Step: 8 RECORD N41 DESIRED IND from calculation performed in Step 2 on Sheet 3 in the space provided.

N41 DESIRED IND _______________

Standard:

Records desired indication from calculation performed in Step 2 on sheet 3 in the space provided N41 desired indication (99.88)

(Band 99.48 to 100.28)

Comment:

- Denotes Critical Steps 2020 HNP NRC Exam Simulator JPM g Rev FINAL

Appendix C Page 9 of 15 Form ES-C-1 PERFORMANCE INFORMATION OP-105, Attachment 2, N41 Adjustments, Caution prior to Step 2 Performance Step: 9 Caution: Adjustments should NOT be made to a Power Range channel while another channel has tripped bistables. This may cause a reactor trip due to required logic being completed.

(Reference CR 97-03027-5)

Standard: Reads and place keeps caution Comment:

OP-105, Attachment 2, N41 Adjustments, Step 2 Performance Step: 10 VERIFY that there are no PR trip bistables energized on TSLB-3 or TSLB-4, except for trip bistables that are manually blocked.

Standard: Verifies no PR trip bistables energized on TSLB-3 or TSLB-4, with exception of PR High Flux Lo Setpoint, which is manually blocked Comment:

OP-105, Attachment 2, N41 Adjustments, Note prior to Step 3 Performance Step: 11 After the GAIN adjustment, the METER RATE switch may be returned to SLOW to evaluate if the adjustment is adequate.

Standard: Reads and place keeps Note Comment:

- Denotes Critical Steps 2020 HNP NRC Exam Simulator JPM g Rev FINAL

Appendix C Page 10 of 15 Form ES-C-1 PERFORMANCE INFORMATION OP-105, Attachment 2, N41 Adjustments, Step 3 Performance Step: 12 At N41 power range drawer A, PLACE the METER RATE switch in FAST.

Standard: Places Meter Rate switch to Fast position Comment:

OP-105, Attachment 2, N41 Adjustments, Caution prior to Step 4 Performance Step: 13 Adjustment of GAIN potentiometer should be made slowly to avoid producing a RATE TRIP signal.

Standard: Reads and place keeps Caution Comment:

OP-105, Attachment 2, N41 Adjustments, Step 4 Performance Step: 14 At N41 power range drawer B, PERFORM the following:

a. UNLOCK GAIN potentiometer.

b. SLOWLY ADJUST GAIN potentiometer until the indicated power is within 0.2% of the DESIRED IND from Step 1.

Standard: Unlocks and slowly adjusts Gain pot in CW direction until indicated power is within 0.2 % of value previously determined in Step 1 (STEP 1 was 99.9, band is 99.5 to 100.2)

Comment: Due to the sensitivity of the pots, acceptance for this step is lower limit of 99.5% and upper limit of 100.2%

- Denotes Critical Steps 2020 HNP NRC Exam Simulator JPM g Rev FINAL

Appendix C Page 11 of 15 Form ES-C-1 PERFORMANCE INFORMATION OP-105, Attachment 2, N41 Adjustments, Step 5 Performance Step: 15 IF there is insufficient fine gain adjustment using the drawer B gain potentiometer, THEN PERFORM Attachment 3 AND RETURN to Step 4.b: (Otherwise, this Step is N/A)

Standard: N/As step since adequate adjustment exists Comment:

OP-105, Attachment 2, N41 Adjustments, Step 6 Performance Step: 16 LOCK GAIN potentiometer(s) in place.

Standard: Locks Gain pot on N-41 in place Comment:

OP-105, Attachment 2, N41 Adjustments, Step 7 Performance Step: 17 IF a RATE TRIP signal occurs, THEN RESET the RATE TRIP signal before going to the next channel.

(Otherwise this Step is N/A)

Standard: N/As step Rate Trip should not have occurred Comment: () This step will become critical if a RATE TRIP signal is generated during the performance of the JPM.

- Denotes Critical Steps 2020 HNP NRC Exam Simulator JPM g Rev FINAL

Appendix C Page 12 of 15 Form ES-C-1 PERFORMANCE INFORMATION OP-105, Attachment 2, N41 Adjustments, Step 8 Performance Step: 18 RECORD the as left GAIN potentiometer setting.

Standard: Records current as left GAIN potentiometer setting in space provided.

Comment:

OP-105, Attachment 2, N41 Adjustments, Step 9 Performance Step: 19 On Drawer A, PLACE the METER RATE switch in SLOW.

Standard: Takes Drawer A Meter Rate switch to SLOW Comment:

OP-105, Attachment 2, N41 Adjustments, Step 10 Performance Step: 20 RECORD the new indicated power (on drawer A)

Standard: Records the new indicated power on drawer A in space provided Comment:

- Denotes Critical Steps 2020 HNP NRC Exam Simulator JPM g Rev FINAL

Appendix C Page 13 of 15 Form ES-C-1 PERFORMANCE INFORMATION OP-105, Attachment 2, N41 Adjustments, Step 11 Performance Step: 21 VERIFY that new indicated power is within 2% of desired indication from Step 1 above.

Standard: Verifies that new indicated power is within 2% of desired indication from Step 1 above.

Comment:

OP-105, Attachment 2, Restoration Performance Step: 22 NOTE: If placing ROD BANK SELECTOR switch in AUTO use OP-104 Section 5.5, Automatic Rod Control.

Standard: Reads and place keeps Note Comment:

After completing Attachment 2 up to the Restoration of Rod Control: Evaluation on this JPM is complete.

Evaluator Cue:

END OF JPM Inform Simulator Operator to place the Simulator in Freeze.

STOP TIME:

Simulator Operator: When directed by the Lead Examiner then go to Freeze.

- Denotes Critical Steps 2020 HNP NRC Exam Simulator JPM g Rev FINAL

Appendix C Page 14 of 15 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2020 HNP NRC Exam Simulator JPM g Power range NI Gain Adjustment In accordance with OP-105, Excore Nuclear Instrumentation Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiners Signature: Date:

2020 HNP NRC Exam Simulator JPM g Rev FINAL

Appendix C Form ES-C-1 JPM CUE SHEET

• The unit is at 100% equilibrium conditions.

• Following maintenance on PR Channel N-41, all required testing has been completed and the channel is ready to be returned to service. A calorimetric has just been performed per OST-1000, Power Range Heat Balance, ERFIS Online Calculation, Daily Initial Conditions: Interval, Mode 1 (Above 15% Power).

• The calculated power is 99.88%. Indicated power on PR channel NI-41 at the time of the calorimetric was at its current value.

• Rod Control is in Automatic You are to perform the Power Range NI Gain Adjust for PR channel Initiating Cue: NI-41 in accordance with OP-105, Excore Nuclear Instrumentation, Section 8.3 and Attachment 2.

2020 HNP NRC Exam Simulator JPM g Rev FINAL

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Harris Nuclear Plant Task No.: 008010H101 Task

Title:

Align CCW to Support RHR System JPM No.: 2020 NRC Exam Operations Simulator JPM CR h K/A

Reference:

008 A4.01 RO 3.3 SRO 3.1 ALTERNATE PATH - NO Examinee: ________________________ NRC Examiner: ______________

Facility Evaluator: ________________________ Date: ________

Method of testing:

Simulated Performance: Actual Performance: X Classroom Simulator X Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

• The Unit is in Mode 4, going to Mode 5

• Preparations are underway to place both trains of RHR in service Initial Conditions:

• Both ESW Trains are in service

• CCW Pump A is running

• In accordance with OP-145, Component Cooling Water o Align CCW to support operation of both RHR trains Initiating Cue:

o Align B train of CCW to supply the non-essential header

• All Section 3.0 Prerequisites are met.

• The candidate should be briefed outside of the simulator prior to performing this JPM. Provide a copy of OP-145, Rev. 80, pages 1-11, 15-19, 48-53 and 224-225.

• Inform them that ALL initial conditions are satisfied.

Examiners Note:

• The section 8.9 initial conditions should be signed off and section 5.2 initial conditions signed off. This will allow them to review the Precautions and Limitations associated with OP-145 and have time for a task review of the steps. Expect the candidate to take about 10 - 15 minutes to complete this review.

2020 HNP NRC Exam Simulator JPM h Rev FINAL

Appendix C Job Performance Measure Form ES-C-1 Worksheet Task Standard: Two CCW Pumps running with the required CCW flow rate established through both RHR Heat Exchangers and B Train of CCW supplying the non-essential header in accordance with OP-145.

Required Materials: None General

References:

OP-145, Component Cooling Water, Rev. 80 Handout: OP-145, Rev. 80, pages 1 - 11, Prerequisites, P&Ls OP-145, Rev. 80, pages 15 - 19, Section 5.2, Starting a Second CCW Pump, with the Initial Conditions signed off if desired OP-145, Rev 80, pages 48 - 53, Section 8.9, Aligning CCW to Support RHR System Operations, with the Initial Conditions signed off if desired OP-145, Rev 80, pages 224 - 225, Attachment 18, RHR HX Outlet and RHR Pump Cooler Outlet Flows As Found / As Left Data Time Critical Task: No Validation Time: 25 minutes PERFORMANCE CRITICAL STEP JUSTIFICATION STEP Step 7 Critical because two CCW Pumps are required to support two RHR Trains and other loads.

Step 11 Critical to align flow through RHR HX A or heat exchanger will not provide cooling.

Step 15 Critical to isolate Train A from Non-Essential Header.

Step 17 Critical to isolate Train A from Non-Essential Header.

Step 26 Critical to align flow through RHR HX B.

2020 HNP NRC Exam Simulator JPM h Rev FINAL

Appendix C Job Performance Measure Form ES-C-1 Worksheet 2020 NRC Exam - SIMULATOR SETUP Simulator Operator - NOTE: The setup time for this JPM may take > 5 minutes

• Reset to IC-150

• Password NRC3sros

• Go to RUN and wait ~ 10 seconds then silence and acknowledge alarms.

GO TO FREEZE and inform the lead examiner the Simulator is ready. DO NOT GO TO RUN until directed by the lead examiner. (The examiner has provided to the candidate with initial conditions and the initiating cues prior to placing the simulator in RUN.)

To recreate the IC setup for this JPM:

• Reset to IC-16

• Place LTOPS in NORMAL and establish feed with AFW to prevent distracting alarms

• Start both ESW Pumps

• Throttle 1CC-575 irf ccw080 (n 0 0) 50 0 0

• Shut 1CC-522 irf ccw122 (n 0 0) 0 0 0

• Open 1CC-512 irf ccw083 (n 0 0) 100 0 0

• Check FI-652.1 in normal band 10,000 gpm to 11,000 gpm o Perform the following to adjust CCW flow on FI-652.1 to band of 7850 and 8500 gpm Throttle 1CC-508 irf ccw073 ( n 0 0) 4 00:00:30 41

• IF VCT makeup occurs during this set up allow the VCT to fill

• Stabilize the plant including AFW flows

• FREEZE and SNAP 2020 HNP NRC Exam Simulator JPM h Rev FINAL

Appendix C Page 4 of 18 Form ES-C-1 PERFORMANCE INFORMATION Simulator Operator: When directed by the Lead Examiner go to Run.

START TIME:

OP-145, Section 8.9.1 Initial Conditions Performance Step: 1 Implements procedure Standard:

• Reviews Sections 1.0 through 4.0.

• Proceeds to Section 8.9.

• Reviews the initial conditions for 8.9

1. RHR System operation desired for RCS cooldown (YES)

Comment:

OP-145, 8.9.2.1 Notes and Caution prior to step 1 Performance Step: 2 Note: The purpose of this section is to ensure CCW pump runout does not occur. Maximum flow through one CCW pump is 12,650 gpm. This section will ensure that one CCW pump is not supplying both essential cooling loops and the non-essential loop simultaneously.

Note: Normally it is desirable to place both RHR cooling trains in operation in Mode 4. This will require both CCW pumps to be in operation and one train of non-essential supply and return valves to be shut.

Caution: To prevent pump runout when aligning CCW flow to the RHR Hx, verify flow rate to the Non-essential header with one pump running is less than 8500 gpm, as indicated on FI-652.1 (FI-653.1) prior to opening 1CC-147 (1CC-167).

Standard: Reads and place keeps Notes and Caution Comment:

- Denotes Critical Steps 2020 HNP NRC Exam Simulator JPM h Rev FINAL

Appendix C Page 5 of 18 Form ES-C-1 PERFORMANCE INFORMATION OP-145, 8.9.2 step 1 Performance Step: 3 PERFORM the following to verify total CCW flow rate is between 7850 gpm and 8500 gpm:

• IF SFP 2&3A is in service, THEN THROTTLE SHUT 1CC-508, SFP HX 2&3A CCW Outlet Isolation Valve.

• IF SFP 2&3B is in service, THEN THROTTLE SHUT 1CC-521, SFP HX 2&3B CCW Outlet Isolation Valve.

Standard: Determines flow is within band and initials step Simulator Operator / If contacted to throttle shut 1CC-508 use Simulator Drawing Communicator: CCW07 / open window for 1CC-508 and adjust the percent open FI-652.1 MCB indication reads 8400 gpm and 8200 gpm on ERFIS Evaluator Note:

FI-652.1 Tolerance is + 200 gpm based on which indication the candidate is monitoring.

Comment:

OP-145, 8.9.2 step 2 Performance Step: 4 IF both trains of RHR cooling are to be placed in service, START the second CCW pump per Section 5.2.

Standard: Proceeds to Section 5.2 to start CCW Pump B.

Comment:

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Appendix C Page 6 of 18 Form ES-C-1 PERFORMANCE INFORMATION OP-145, 5.2.1 Performance Step: 5 Verifies Initial Conditions Standard: Notes all Initial Conditions are signed (including the prestart checks)

Contacts Aux Operator to standby for B CCW pump start Simulator Communicator: When requested: Report you are standing by.

Comment:

OP-145, 5.2.2 Notes and Caution prior to step 1 Performance Step: 6 Note:

• Starting the second pump could cause P fluctuations across REM-01CC-3501ASA (BSB) which may shut solenoid valves 1CC-23 and 1CC-40.

• Starting the second pump may cause flow oscillations which could shut 1CC-252. Re-opening of 1CC-252 should not be attempted until the second pump is secured.

• APP-ALB-005 Windows 1-3, 2-1, and 3-2 are expected alarms when starting the second CCW Pump.

Caution:

• With one CCW pump running and the standby pump capable of an automatic start, ensure a minimum flowrate of 7850 gpm exists as indicated on FI-652.1 (FI-653.1). If both CCW pumps are running OR the CCW trains are separated, a minimum of 3850 gpm per pump is required. This lower flowrate should only be allowed for short durations to accomplish pump swapping or system realignment.

Standard: Reads and place keeps notes and caution Makes PA announcement for pump start then:

At the MCB, START CCW Pump Train B-SB.

Comment:

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Appendix C Page 7 of 18 Form ES-C-1 PERFORMANCE INFORMATION OP-145, 5.2.2 step 1 Performance Step: 7 At the MCB, START CCW Pump Train B-SB (A-SA).

Standard: Selects CCW Pump B to start and releases (critical)

Verifies pump start indications (not critical)

Contacts Aux Operator to ensure good start (not critical)

IF contacted OR asked to report on B CCW pump start Simulator Communicator: Report the B CCW pump had a good start and you will continue to monitor during pump warm up to full operating conditions.

Comment:

OP-145, 5.2.2 step 2 Performance Step: 8 VERIFY flow is greater than or equal to 3850 gpm on FI-653.1 and FI- 652.1.

Standard: Verifies 3850 gpm on FI-653.1 and FI-652.1.

Comment:

OP-145, 5.2.2 step 3 Performance Step: 9 VERIFY OPEN, 1CC-23 and 1CC-40, REM 3501 A CCW Inlet Solenoid Valve and REM 3501 B CCW Inlet Solenoid Valve respectively.

Standard: Contacts Aux Operator for verification Simulator Communicator: Report: 1CC-23 and 1CC-40 are OPEN Comment:

- Denotes Critical Steps 2020 HNP NRC Exam Simulator JPM h Rev FINAL

Appendix C Page 8 of 18 Form ES-C-1 PERFORMANCE INFORMATION OP-145, 5.2.2 steps 4 and 5 Performance Step: 10 IF 1CC-23 or 1CC-40 shut as a result of starting the CCW pump, THEN INITIATE a CR.

PERFORM one of the following:

• SECURE a second CCW Pump using Section 7.1

• ALIGN CCW to support RHR cooling using Section 8.9 Standard: N/As step 4 and returns to Section 8.9 Comment:

OP-145, 8.9.2 step 3 Performance Step: 11 OPEN 1CC-147 (1CC-167), CCW FROM RHR HEAT EXCHANGER A-SA (B-SB).

Standard: Locates switch and Places 1CC-147 in OPEN (RED indication).

Comment:

OP-145, 8.9.2 Caution prior to step 4 Performance Step: 12 Caution:

With one CCW pump running and the standby pump capable of an automatic start, ensure a minimum flowrate of 7850 gpm exists as indicated on FI-652.1 (FI-653.1). If both CCW pumps are running OR the CCW trains are separated, a minimum of 3850 gpm per pump is required. This lower flowrate should only be allowed for short durations to accomplish pump swapping or system realignment. (Reference 2.6.6)

Standard: Reads and place keeps Caution Comment:

- Denotes Critical Steps 2020 HNP NRC Exam Simulator JPM h Rev FINAL

Appendix C Page 9 of 18 Form ES-C-1 PERFORMANCE INFORMATION OP-145, 8.9.2 step 4 Performance Step: 13 VERIFY RHR HX A (B) out flow is 5600 to 8150 gpm on FI-688A1 (FI-689A1).

Standard: Verifies RHR HX A out flow is 5600 to 8150 gpm on FI-688A1.

Comment:

OP-145, 8.9.2 Notes and Caution prior to step 5 Performance Step: 14 Note: Steps 8.9.2.5 and 8.9.2.6 are written to place the non-essential header on 'B' CCW. If desired to place the non-essential header on 'A' CCW, perform steps in parenthesis.

Note: If a leak occurs, and surge tank level is less than 40%

(below the divider plate), make up water for the B CCW header will be supplied by demin water. Makeup water for the A CCW header must be supplied by the Reactor Makeup Water System.

Caution: Shutting both 1CC-99 and 1CC-113 will result in the loss of the Nonessential Header.

Standard: Reads and place keeps Notes and Caution Comment:

OP-145, 8.9.2 step 5 Performance Step: 15 IF both CCW pumps are in service, CLOSE 1CC-99 (1CC-113),

CCW HEAT EXCHANGER A(B) TO NONESSENTIAL SUP.

Standard: Locates switch and Closes only 1CC-99 (GREEN indication).

Comment:

- Denotes Critical Steps 2020 HNP NRC Exam Simulator JPM h Rev FINAL

Appendix C Page 10 of 18 Form ES-C-1 PERFORMANCE INFORMATION OP-145, 8.9.2 Caution prior to step 6 Performance Step: 16 Caution: Shutting both 1CC-128 and 1CC-127 will result in the loss of the Nonessential Header.

Standard: Reads and place keeps Caution Comment:

OP-145, 8.9.2 step 6 Performance Step: 17 IF both CCW pumps are in service, CLOSE 1CC-128 (1CC-127),

CCW NONESSENTIAL RETURN TO HEADER A(B).

Standard: Locates switch and Closes 1CC-128 (GREEN indication).

Comment:

OP-145, 8.9.2 step 7.a.(1)

Performance Step: 18 VERIFY the following:

a. IF both CCW Pumps are in service, PERFORM the following, recording data on Attachment 18:

• RECORD AS FOUND (AF) RHR Hx A-SA (B-SB) CCW outlet flow from FCC0688 (FCC0689).

Standard:

• Determines current reading on MCB indicator FI-688A1

• Circles appropriate step (8.9.2.7.a(1)) in the A Train column of Attachment 18

• Documents the as found (AF) value in the Reading column of Attachment 18 Comment:

- Denotes Critical Steps 2020 HNP NRC Exam Simulator JPM h Rev FINAL

Appendix C Page 11 of 18 Form ES-C-1 PERFORMANCE INFORMATION OP-145, 8.9.2 step 7.a.(2)

Performance Step: 19 VERIFY the following:

a. IF both CCW Pumps are in service, PERFORM the following, recording data on Attachment 18:

• RECORD AS FOUND (AF) RHR Pump A (B) Cooler Outlet flow rate from FIS-646 (FIS-647).

Standard:

• Contacts local operator to determine the current reading on indicator FIS-646

• Circles appropriate step (8.9.2.7.a(2)) in the A Train column of Attachment 18

• Documents the as found (AF) value in the Reading column of Attachment 18 Simulator Communicator: Report: The as found value of FIS-646 is 8.4 gpm Comment:

OP-145, 8.9.2 step 7.a.(3)

Performance Step: 20 VERIFY the following:

a. IF both CCW Pumps are in service, PERFORM the following, recording data on Attachment 18:

• IF RHR Hx A-SA (B-SB) CCW outlet flow is NOT within 7850 - 8050 gpm, THEN PERFORM the following:

Standard:

• Determines steps 7.a (3) is N/A If asked to adjust flow then reduce the percent open of Simulator Operator: 1CC-146 on Sim drawing for CCW03 from 46 to 44 to obtain slightly lower flow rate on FI-688A1 Comment:

- Denotes Critical Steps 2020 HNP NRC Exam Simulator JPM h Rev FINAL

Appendix C Page 12 of 18 Form ES-C-1 PERFORMANCE INFORMATION OP-145, 8.9.2 step 7.a.(4)

Performance Step: 21 VERIFY the following:

a. IF both CCW Pumps are in service, PERFORM the following, recording data on Attachment 18:

• RECORD throttle position of 1CC-146 (1CC-166), in DEGREES OPEN.

Standard:

• Contacts local operator to determine the current position of 1CC-146

• Circles appropriate step (8.9.2.7.a(4)) in the A Train column of Attachment 18

• Documents the as found (AF) position in the Reading column of Attachment 18 Simulator Communicator: Report: The position of 1CC-146 is 47.5 degrees OPEN Comment:

OP-145, 8.9.2 step 7.a.(5)

Performance Step: 22 VERIFY the following:

a. IF both CCW Pumps are in service, PERFORM the following, recording data on Attachment 18:

• IF CCW cooler outlet flow rate is NOT between 7 gpm and 10 gpm as indicated on FIS-646 (FIS-647), THEN PERFORM the following substeps:

Standard:

• Determines step 7.a (5) is N/A Comment:

- Denotes Critical Steps 2020 HNP NRC Exam Simulator JPM h Rev FINAL

Appendix C Page 13 of 18 Form ES-C-1 PERFORMANCE INFORMATION OP-145, 8.9.2 step 7.a.(6)

Performance Step: 23 VERIFY the following:

a. IF both CCW Pumps are in service, PERFORM the following, recording data on Attachment 18:

• RECORD AS LEFT (AL) RHR Hx A-SA (B-SB) CCW outlet flow from FCC0688 (FCC0689).

Standard:

• Determines current reading on MCB indicator FI-688A1

• Circles appropriate step (8.9.2.7.a(6)) in the A Train column of Attachment 18

• Documents the as found (AL) value in the Reading column of Attachment 18 Comment:

OP-145, 8.9.2 step 7.a.(7)

Performance Step: 24 VERIFY the following:

a. IF both CCW Pumps are in service, PERFORM the following, recording data on Attachment 18:

• RECORD AS LEFT (AL) RHR Pump A (B) Cooler Outlet flow rate from FIS-646 (FIS-647).

Standard:

• Contacts local operator to determine the current reading on indicator FIS-646

• Circles appropriate step (8.9.2.7.a(7)) in the A Train column of Attachment 18

• Documents the as found (AL) value in the Reading column of Attachment 18 Simulator Communicator: Report: The as left value of FIS-646 is 8.4 gpm Comment:

- Denotes Critical Steps 2020 HNP NRC Exam Simulator JPM h Rev FINAL

Appendix C Page 14 of 18 Form ES-C-1 PERFORMANCE INFORMATION OP-145, 8.9.2 step 7.a.(8)

Performance Step: 23 VERIFY the following:

a. IF both CCW Pumps are in service, PERFORM the following, recording data on Attachment 18:

• PERFORM component verifications on Attachment 18.

Standard:

• Directs a second operator verify position of 1CC-146 Comment:

OP-145, 8.9.2 step 7.b Performance Step: 24 VERIFY the following:

b. IF one CCW Pump is in service, THEN PERFORM the following:

Standard:

• Determines step 7.b is N/A Comment:

OP-145, 8.9.2 Caution prior to step 8 Performance Step: 25 Caution: Do not supply CCW to both RHR Heat Exchangers simultaneously with only one CCW pump running.

Standard: Reads and place keeps note Comment:

- Denotes Critical Steps 2020 HNP NRC Exam Simulator JPM h Rev FINAL

Appendix C Page 15 of 18 Form ES-C-1 PERFORMANCE INFORMATION OP-145, 8.9.2 step 8 Performance Step: 26 IF both trains of RHR cooling are to be placed in service, OPEN 1CC-167 (1CC-147), CCW FROM RHR HEAT EXCHANGER B-SB (A-SA).

Standard: Locates switch and Opens 1CC-167 (RED indication).

Comment:

OP-145, 8.9.2 step 9 Performance Step: 27 VERIFY CCW Pump B-SB (A-SA) flow rate in the required range, as follows:

• CHECK CCW Pump B-SB (A-SA) flow rate is between 10,000 and 12,500 gpm on MCB indicator FI-653.1 (FI-652.1). IF flow rate is not between 10,000 and 12,500 gpm, THEN ADJUST the applicable valve.

Standard: Verifies flow rate is between 10,000 and 12,500 gpm on FI-653.1 and there is NO need for flow adjustment and N/As step 9.b.

Comment:

OP-145, 8.9.2 step 10 Performance Step: 28 Locally VERIFY FI-693, CCW Flow Gross Failed Fuel Detector, is between 8 and 12 gpm.

Standard: Contacts Aux Operator to verify flow on FI-693 between 8 and 12 gpm Simulator Communicator: Flow on FI-693 reads 10 gpm Comment:

- Denotes Critical Steps 2020 HNP NRC Exam Simulator JPM h Rev FINAL

Appendix C Page 16 of 18 Form ES-C-1 PERFORMANCE INFORMATION OP-145, 8.9.2 step 11 Performance Step: 29 WHEN CCW is no longer required for RHR Operation, PERFORM the following steps:

Standard: Step is N/A at this time.

Comment:

When Step 8.9.2.11 is read: Evaluation on this JPM is complete.

Evaluator Cue: Announce END OF JPM Direct Simulator Operator to place the Simulator in FREEZE.

STOP TIME:

Simulator Operator: When directed by the Lead Examiner then go to Freeze.

- Denotes Critical Steps 2020 HNP NRC Exam Simulator JPM h Rev FINAL

Appendix C Page 17 of 18 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2020 HNP NRC Exam Simulator JPM h Align CCW to Support RHR System Operations In accordance with OP-145, Component Cooling Water Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiners Signature: Date:

2020 HNP NRC Exam Simulator JPM h Rev FINAL

Appendix C Page 18 of 18 Form ES-C-1 JPM CUE SHEET

• The Unit is in Mode 4, going to Mode 5

• Preparations are underway to place both trains of RHR in service Initial Conditions:

• Both ESW Trains are in service

• CCW Pump A is running

• In accordance with OP-145, Component Cooling Water o Align CCW to support operation of both RHR trains Initiating Cue:

o Align B train of CCW to supply the non-essential header

• All Section 3.0 Prerequisites are met.

2020 HNP NRC Exam Simulator JPM h Rev FINAL

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Harris Nuclear Plant Task No.: 344074H504

Title:

Locally Start EDGs per OP-155 JPM No.: 2020 NRC Exam In-Plant JPM i K/A

Reference:

APE 068 AA1.10 RO 3.7 SRO 3.9 ALTERNATE PATH - YES Examinee: ________________________ NRC Examiner: _________________

Facility Evaluator: ________________________ Date: ________

Method of testing:

Simulated Performance: X Actual Performance:

Classroom Simulator Plant X READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

• AOP-004 has been entered due to a fire in the MCR

• A (B) Safety bus is not energized due to a SUT fault

• EDG 1A-SA (1B-SB) was in standby operation but did not automatically start

• AOP-004 has directed that the A (B) EDG be locally started Initial Conditions: and A (B) safety bus energized

• Both safety and non-safety Plant DC Distribution Systems are in operation per OP-156.01 to support EDG operation

• The manual transfer to LOCAL has been completed at MTP 1A-SA (1B-SB)

• Your position is the Outside Operator Initiating Cue:

• The CRS has directed you to locally start the A (B) EDG IAW OP-155 Section 8.14.2.

At this time provide the student with a copy of OP-155, Section 8.14, signed off up to 8.14.1, step 4 and the student Initiating Cue Evaluator: for the EDG the JPM will be performed on.

This should be the NON- protected train EDG based on discussion with Shift Manager.

2020 HNP NRC Exam In-Plant JPM i Rev FINAL

Appendix C Job Performance Measure Form ES-C-1 Worksheet Task Standard: EDG A (B) is locally started and manually reset the K1 relay to allow the associated EDG field to self flash in accordance with OP-155 Required Materials: Standard PPE Attachments 1 and 2, Pictures of K1 relay (Optional)

General

References:

OP-155 (Rev. 91)

APP-DGP-001 (Rev. 34)

Handout: OP-155, Rev. 91, pages 1 - 14, Prerequisites, P&Ls OP-155, Rev. 91, pages 88 - 94, Section 8.14, Local Manual Start with an Emergency Bus Deenergized, signed off up to 8.14.1 Step 4 if desired.

Time Critical Task: No Validation Time: 15 minutes PERFORMANCE CRITICAL STEP JUSTIFICATION STEP Depressing the STOP pushbutton will reset the starting circuit and 6 allow the EDG to be started. If this pushbutton is NOT depressed the EDG will not start and the bus will remain de-energized.

Depressing the START pushbutton will start the EDG. The EDG must 13 be operating to power the emergency bus.

18 Required to reset K1 relay to allow EDG to flash.

PERFORMANCE ALTERNATE PATH JUSTIFICATION STEP Generator field fails to automatically flash requiring operator action to 17 reset the K1 relay to allow the generator field to flash.

2020 HNP NRC Exam In-Plant JPM i Rev FINAL

Appendix C Page 3 of 24 Form ES-C-1 Performance Information BEFORE YOU START THIS JPM IN-PLANT JPM SAFETY CONSIDERATIONS:

CAUTION: EQUIPMENT MAY AUTO START OR MAY BE ENERGIZED

- SIMULATE ONLY - DO NOT OPERATE ANY ACTUAL PLANT EQUIPMENT!!!

Before entering the performance location of this JPM, ensure you AND the candidate have the proper PPE for the area you are going to go to or will travel through to get there.

Avoid contacting any plant equipment.

Follow ALARA practices in the RCA.

Do NOT remove ladders from their storage locations. Have the candidate simulate obtaining and using a ladder if one would be needed during the actual performance of this task.

NOTE: Add one minute for Take a Minute checks.

Start time begins when the candidate is briefed outside the Blue Heaven conference Room START TIME:

Proceeds to 1A-SA (1B-SB) EDG OP-155 Section 8.14.1 Notes prior to Initial Conditions Performance Step: 1 NOTE: Equipment applicable to B train is shown in parenthesis.

NOTE: If power is NOT available to 1D131-3 (1E231-3), Engine Control Panel, the ECP Temperature Indication System and ENGINE HOURS meter are de-energized.

Standard: Operator reads and placekeeps notes Comment:

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Appendix C Page 4 of 24 Form ES-C-1 Performance Information OP-155 Section 8.14.1 Initial Conditions Performance Step: 2 1. EDG 1A-SA (1B-SB) is not in operation. (YES)

2. AOP-004 has directed EDG to be started. (YES)

3. Both safety and non-safety Plant DC Distribution System in operation per OP-156.01 to support EDG operation. (YES)

4. Attachments 1, 3, 4 (1A-SA) or 2, 3, 5 (1B-SB) are complete.

(YES - the EDG was in standby and ready for an emergency start so all Attachments for these lineups have been previously completed)

Standard: Reviews Initial Conditions 1 - 4 as complete If CRS is called at the ACP about the initial conditions then Evaluator Cue:

cue that the initial conditions are satisfied.

OP-155 Section 8.14.2 Note prior to Step 1 Performance Step: 3 NOTE: Equipment applicable to B train is shown in parenthesis.

Relay 43T-DG6/SA is N/A if transferring B train relays.

Standard: Operator reads and placekeeps notes Comment:

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Appendix C Page 5 of 24 Form ES-C-1 Performance Information OP-155 Section 8.14.2 Step 1 Performance Step: 4 IF necessary, THEN, At Main Transfer Panel 1A-SA (1B-SB),

PERFORM a manual transfer to LOCAL by placing the following relays in TRANSF:

Relay Position 43T-DG1SA/1082 (43T-DG1SB/1085) TRANSF 43T-DG2SA/1082 (43T-DG2SB/1085) TRANSF 43T-DG3SA/1082 (43T-DG3SB/1085) TRANSF 43T-DG4SA/1082 (43T-DG4SB/1085) TRANSF 43T-DG5SA/1082 (43T-DG5SB/1085) TRANSF 43T-DG6SA/1082 TRANSF Standard: Initials step 1 completed (Provided in the JPM initial conditions)

IF asked or if they are going to perform step 1 then CUE:

Evaluator Cue: The Main Transfer Panel 1A-SA (1B-SB) relays have been placed in LOCAL by another operator.

Comment:

OP-155 Section 8.14.2 Step 2 Performance Step: 5 ENSURE the following:

a. NO non-emergency trips are active.

b. At GCP, ENSURE the UNIT-PARALLEL switch in PARALLEL.

Standard: Operator verifies on the EDG control panel that there are NO non-emergency trips active and the UNIT-PARALLEL switch is in the PARALLEL position Evaluator Cue: (when checked) The non-emergency trip windows are clear Comment:

- Denotes Critical Steps 2020 HNP NRC Exam In-Plant JPM i Rev FINAL

Appendix C Page 6 of 24 Form ES-C-1 Performance Information OP-155 Section 8.14.2 Step 3 Performance Step: 6 IF the FAILED TO START annunciator is in, THEN DEPRESS the STOP pushbutton (critical step is to depress the STOP pushbutton; not the resetting of the annunciator)

Standard: Operator checks annunciator window G-6 clear Evaluator Cue: Annunciator window G-6 Failed to Start is lit Standard: Operator depresses RED STOP pushbutton Evaluator Cue: Annunciator window G-6 is slow flashing Standard: Operator depresses the alarm functions reset pushbutton Evaluator Cue: Annunciator window G-6 is clear Comment:

OP-155 Section 8.14.2 Step 4 Performance Step: 7 At ECP, ENSURE the following OPERATIONAL MODE indicator lights are LIT:

a. A CONTROL CIRCUIT

b. B CONTROL CIRCUIT Standard: Operator checks control circuit lights lit (when checked)

Evaluator Cue: The control circuit light for A Control Circuit is lit The control circuit light for B Control Circuit is lit Comment:

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Appendix C Page 7 of 24 Form ES-C-1 Performance Information OP-155 Section 8.14.2 Step 5 Performance Step: 8 PERFORM a general inspection of the EDG, looking for any obvious reasons that the EDG failed to start Standard: Operator performs inspection Allow the candidate 1 or 2 minutes to describe the actions for performing the inspection then cue them there are no Evaluator Cue:

obvious signs of damage and all indications associated with this EDG are as you see them now.

Comment:

OP-155 Section 8.14.2 Step 6 Performance Step: 9 ENSURE the Fuel Limit Cylinder has retracted Standard: Operator Verifies the Fuel Limit Cylinder has retracted NOTE: The examinee may want to climb on the EDG to verify where the Fuel Limit Cylinder is and inspect the current position. Direct them to use a flashlight and describe how they would verify the Fuel Limit Cylinder has retracted. (SAFETY FIRST)

On the left side of the mechanical governor is where the Fuel Limit Cylinder is located. On the engine side Evaluator Cue:

of the cylinder a rod extends and will contact a bolted on flat stock piece attached to the fuel rack rod. The fuel limit cylinder rod extends and contacts this piece to prevent full fuel rack motion. Looking at the back of the cylinder you can see if the rod that protrudes out of it is retracted or extended.

Cue: The Fuel Limit Cylinder (rod) has retracted Comment:

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Appendix C Page 8 of 24 Form ES-C-1 Performance Information OP-155 Section 8.14.2, Note before step 7 NOTE: If starting air receiver pressures are low, but still above Performance Step: 10 100 psig, isolating one of the receivers prior to attempting to start the EDG will maximize the potential number of start attempts Standard: Operator reads and placekeeps notes Comment:

OP-155 Section 8.14.2 step 7 Performance Step: 11 ENSURE at least one starting air receiver is greater than 100 psig Standard: Operator verifies at least one starting air receiver is greater than 100 psig Evaluator Cue: Pressures are what you see - (current values)

Comment:

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Appendix C Page 9 of 24 Form ES-C-1 Performance Information OP-155 Section 8.14.2, Notes before step 8 NOTE: If the STOP pushbutton was depressed in Step 8.14.2.3, the control circuitry must reset before another start can be attempted. This takes approximately three minutes.

Performance Step: 12 NOTE: The EDG most likely will start in a fast start mode due to the undervoltage. Depending on what failure(s) occurred, however, the EDG may start in the slow start mode.

Standard: Operator reads and placekeeps notes Evaluator Cue: If asked inform the candidate 5 minutes has elapsed Comment:

OP-155 Section 8.14.2 step 8 Performance Step: 13 DEPRESS EDG 1A-SA (1B-SB) PUSH TO START pushbutton Standard: Operator depresses (BLACK) EDG 1A-SA (1B-SB) PUSH TO START pushbutton 1A-SA (1B-SB) EDG has started Evaluator Cue: (when checked) The Diesel Engine RPMs are rising and have now stabilized at 450 RPM Comment:

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Appendix C Page 10 of 24 Form ES-C-1 Performance Information OP-155 Section 8.14.2, Caution before step 9 CAUTION: EDG field flashing will occur at 360 to 380 RPM for a normal slow start. EDG field flashing will occur at 190 to 210 RPM for an emergency start. If EDG fails to start field flashing Performance Step: 14 will remain energized resulting in possible fire in GCP control section. Depressing the EDG 1A-SA (1B-SB) STOP pushbutton will de-energize field flashing circuit.

Standard: Operator reads and placekeeps caution Operator may verify proper start of diesel. If operator requests or goes to observe these indication, provide the following information as requested:

Evaluator Cue:

• DG LOCAL CONTROL PANEL AC VOLTMETER - 0 VAC

• DG GEN FIELD AMMETER - 0 Amps

• DG frequency is 0 Hz

• DG FIELD DC VOLTAGE - 0 volts Comment:

OP-155 Section 8.14.2 step 9 Performance Step: 15 IF the FAILED TO START annunciator is received, THEN DEPRESS the STOP pushbutton Standard: Operator checks annunciator and does not depress STOP Evaluator Cue: (when checked) Annunciator G-6 Failed To Start is clear Comment:

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Appendix C Page 11 of 24 Form ES-C-1 Performance Information OP-155 Section 8.14.2 notes before step 10 Performance Step: 16 NOTE: If EDG starts but the generator fails to flash:

• The EDG will be operating at 470 rpm with zero field volts.

• The K1 relay must be reset to enable any future field flashing.

• If EDG is left running, the EDG should self flash within 10 seconds, if the K1 relay is reset.

NOTE: Satisfactory field flash conditions are indicated by:

• Generator AC voltage between 6500 and 7200 volts

• Engine speed between 445 and 455 rpm

• Field DC voltage indicates a higher voltage Standard: Operator reads and placekeeps notes IF checking parameters cue these when asked:

Evaluator Note:

• DG LOCAL CONTROL PANEL AC VOLTMETER - 0 VAC

• Engine speed is 450 RPM

• DG 1A-SA FIELD DC VOLTAGE - 0 volts Comment:

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Appendix C Page 12 of 24 Form ES-C-1 Performance Information OP-155 Section 8.14.2 step 10 - ALTERNATE PATH begins Performance Step: 17 IF EDG starts but the generator fails to flash, THEN PERFORM the following Standard: Operator identifies the generator failed to flash and implements step 8.14.2.10.

From the indications provided to the examinee, they should Evaluator Note:

be able to identify that the field has NOT flashed.

Comment:

The Attachment 1 pictures will be used once the location of the GCP has been demonstrated. Att. 1 should be shown Evaluator Note:

first. When the operator points out the K1 relay, Att. 2 may be used for close up review of the relay.

OP-155 Section 8.14.2 step 10.a (ALTERNATE PATH)

Performance Step: 18 In GCP behind left section door three feet above floor, RESET the K1 relay by pushing the reset switch in the direction of the arrow on the K1 Relay reset coil.

Standard: Operator locates and resets relay K1 in the GCP (left section).

Operator should determine the generator field has flashed.

(When reset) The K1 relay is reset.

IF checking parameters, provide when asked:

Evaluator Note:

• DG LOCAL CONTROL PANEL AC VOLTMETER - 6900 VAC

• Engine speed is 450 RPM

• DG 1A-SA FIELD DC VOLTAGE - 45 volts Comment:

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Appendix C Page 13 of 24 Form ES-C-1 Performance Information OP-155 Section 8.14.2 step 10.b (ALTERNATE PATH)

Performance Step: 19 ENSURE disconnect DS-DP-1A1-SA-13 (DS-DP-1B1-SB-13),

Gen 1A-SA (1B-SB) Control Panel, in ON and power is present to panel.

Standard: Operator locates and verifies disconnect DS-DP-1A1-SA-13 (DS-DP-1B1-SB-13) is ON. Operator should also note that steps 8.14.2.10.c through 10.e are now N/A.

When checked, disconnect DS-DP-1A1-SA-13 Evaluator Note:

(DS-DP-1B1-SB-13) is in the ON position.

Comment:

OP-155 Section 8.14.2 step 11 Performance Step: 20 ENSURE the following:

a. CS-1983SA (CS-2003SB), A (B) EDG Auxiliary Lube Oil Pump, in AUTO

b. CS-1984SA (CS-2004SB), A (B) EDG Lube Oil Keep Warm Pump, in AUTO.

Standard: Operator verifies AUXILIARY LUBE OIL PUMP control switch in AUTO Evaluator Cue: AUXILIARY LUBE OIL PUMP switch is in AUTO Standard: Operator verifies LUBE OIL KEEP WARM PUMP control switch in AUTO.

Evaluator Cue: LUBE OIL KEEP WARM PUMP control switch in AUTO Comment:

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Appendix C Page 14 of 24 Form ES-C-1 Performance Information OP-155 Section 8.14.2 step 12 Performance Step: 21 At ECP, ENSURE the following:

a. Engine is running at 445 to 455 RPM.

b. JACKET WATER PRESS rises to 10 to 20 psig.

c. SHUTDOWN SYSTEM ACTIVE light lit.

d. READY TO LOAD light lit.

Standard: Operator verifies Engine is running at 445 to 455 RPM Evaluator Cue: Engine RPM is 450 Standard: Operator verifies JACKET WATER PRESS increases to 10 to 20 psig Evaluator Cue: JACKET WATER PRESS is 16 psig Standard: Operator verifies SHUTDOWN SYSTEM ACTIVE light lit Evaluator Cue: SHUTDOWN SYSTEM ACTIVE (Red) light is lit Standard: Operator verifies READY TO LOAD light lit Evaluator Cue: READY TO LOAD (Blue) light is lit Comment:

STOP TIME:

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Appendix C Page 15 of 24 Form ES-C-1 Performance Information KEY 1A K1 Relay TOP

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Appendix C Page 16 of 24 Form ES-C-1 Performance Information KEY 2A

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Appendix C Page 17 of 24 Form ES-C-1 Performance Information KEY 1B K1 Relay TOP

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Appendix C Page 18 of 24 Form ES-C-1 Performance Information KEY 2B

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Appendix C Page 19 of 24 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2020 HNP NRC Exam In-Plant JPM j Locally Start A-SA or B-SB EDG per OP-155 Examinees Name:

Date Performed:

Facility Evaluator:

Time to Complete:

Question Documentation Question:

Response

Result: PASS FAIL Examiners Signature: Date:

2020 HNP NRC Exam In-Plant JPM i Rev FINAL

Appendix C Page 20 of 24 Form ES-C-1 Attachment Attachment 1A TOP 2020 HNP NRC Exam In-Plant JPM i Rev FINAL

Appendix C Page 21 of 24 Form ES-C-1 Attachment Attachment 2A 2020 HNP NRC Exam In-Plant JPM i Rev FINAL

Appendix C Page 22 of 24 Form ES-C-1 Attachment Attachment 1B TOP 2020 HNP NRC Exam In-Plant JPM i Rev FINAL

Appendix C Page 23 of 24 Form ES-C-1 Attachment Attachment 2B 2020 HNP NRC Exam In-Plant JPM i Rev FINAL

Appendix C Form ES-C-1 JPM CUE SHEET BEFORE YOU START THIS JPM IN-PLANT JPM SAFETY CONSIDERATIONS:

CAUTION: EQUIPMENT MAY AUTO START OR MAYBE ENERGIZED

- SIMULATE ONLY - DO NOT OPERATE ANY ACTUAL PLANT EQUIPMENT!!!

Before entering the performance location of this JPM, ensure you AND the examiner have the proper PPE for the area you are going to go to or will travel through to get there.

Avoid contacting any plant equipment.

Follow ALARA practices in the RCA.

Do NOT remove ladders from their storage locations. Simulate obtaining and using a ladder if one would be needed during the actual performance of this task.

• AOP-004 has been entered due to a fire in the MCR

• A (B) Safety bus is not energized due to a SUT fault

• EDG 1A-SA (1B-SB) was in standby operation but did not automatically start

• AOP-004 has directed that the A (B) EDG be locally started Initial Conditions:

and A (B) safety bus energized

• Both safety and non-safety Plant DC Distribution Systems are in operation per OP-156.01 to support EDG operation

• The manual transfer to LOCAL has been completed at MTP 1A-SA (1B-SB)

• Your position is the Outside Operator Initiating Cue:

• The CRS has directed you to locally start the A (B) EDG IAW OP-155 Section 8.14.2.

2020 HNP NRC Exam In-Plant JPM i Rev FINAL

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Harris Nuclear Plant Task No.: 121001H404 Task

Title:

Place the ASI System in Standby JPM No.: 2020 NRC Exam Alignment (OP-185) In-Plant JPM j K/A

Reference:

AA2.67 RO 2.9 SRO 3.1 ALTERNATE PATH - NO Examinee: ________________________ NRC Examiner: _________________

Facility Evaluator: ________________________ Date: ________

Method of testing:

Simulated Performance: X Actual Performance:

Classroom Simulator Plant X READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

• A Normal Plant Heatup is in progress in accordance with GP-002, Normal Plant Heatup From Cold Solid To Hot Subcritical Mode 5 To Mode 3.

Initial Conditions:

• Current RCS temperature is 335°F

• The A CSIP is in service and providing 9 gpm to all 3 RCP Seals.

• The MCR has directed you to perform OP-185, Alternate Seal Injection, Section 5.1, Automatic Standby Alignment Prior to MODE 3.

Initiating Cue:

• Initial Conditions have been met

• You are to perform section 5.1.2.

For this task assume you have a set of AO RAB rounds keys.

At this time provide the student with a copy of OP-185, Evaluator:

Section 5.1, Marked up through Initial Conditions NOTE: Expect that the entry and exit from the RCA will add time to complete this JPM.

2020 HNP NRC Exam In-Plant JPM j Rev FINAL

Appendix C Job Performance Measure Form ES-C-1 Worksheet Task Standard: Place the ASI System in Standby Alignment in accordance with OP-185 Required Materials: Standard PPE Photos of 1CS-828 and 1CS-827 (Attachment 1A and 1B)

General

References:

OP-185, Alternate Seal Injection, Rev. 12 Handout: OP-185, Rev. 12, pages 1 - 4, Prerequisites, P&Ls OP-185, Rev. 12, pages 5 - 8, Section 5.1, Automatic Standby Alignment Prior to MODE 3, signed off up to 5.1.1 Step 7 if desired.

Time Critical Task: No Validation Time: 15 minutes PERFORMANCE CRITICAL STEP JUSTIFICATION STEP Step 3 Required to ensure proper Alternate Seal Injection Standby Alignment Prior to entering Mode 3.

Step 4 Required to ensure proper Alternate Seal Injection Standby Alignment Prior to entering Mode 3.

Step 7 Must locate CS-210.1 switch and place CS-210.1, ASI PUMP, in the AUTO position in order for the ASI pump to work when required.

Step 8 Must locate CS-210.2, SQUIB VALVE 1ASI-21 BYPASS, switch and place the switch to NORMAL for the squib valve to work when required.

Step 9 Must locate CS-210.3, SQUIB VALVE 1ASI-22 BYPASS, switch and place the switch to NORMAL for the squib valve to work when required.

Step 10 Must locate and PLACE breaker PP-1D232-6, Feed to ASI System Control Panel, in the ON. position in order for the ASI pump to work when required.

Step 11 Must locate and PLACE breaker 1D23-1B, Alternate Seal Injection Pump in the ON. position in order for the ASI pump to work when required.

2020 HNP NRC Exam In-Plant JPM j Rev FINAL

Appendix C Page 3 of 15 Form ES-C-1 PERFORMANCE INFORMATION BEFORE YOU START THIS JPM IN-PLANT JPM SAFETY CONSIDERATIONS:

CAUTION: EQUIPMENT MAY AUTO START OR MAY BE ENERGIZED

- SIMULATE ONLY - DO NOT OPERATE ANY ACTUAL PLANT EQUIPMENT!!!

Before entering the performance location of this JPM, ensure you AND the candidate have the proper PPE for the area you are going to go to or will travel through to get there.

Avoid contacting any plant equipment.

Follow ALARA practices in the RCA.

Do NOT remove ladders from their storage locations. Have the candidate simulate obtaining and using a ladder if one would be needed during the actual performance of this task.

NOTE: Add one minute for Take a Minute checks.

Start time begins when the candidate is briefed outside the Waste Process Building 276 Elevation conference Room START TIME:

OP-185, 5.1.2 Note prior to step 1 Performance Step: 1 The valves in step 5.1.2.2 and 5.1.2.3 are located in the CVCS Filter Valve Gallery.

Standard: Operator reads and placekeeps notes Comment:

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Appendix C Page 4 of 15 Form ES-C-1 PERFORMANCE INFORMATION OP-185, 5.1.2.1 Performance Step: 2 IF aligning ASI for OPT-1532 testing, THEN:

a. MARK Steps 5.1.2.2, 5.1.2.3, 5.1.2.10 and 5.1.2.11 N/A.

b. CONTINUE with Step 5.1.2.4.

Standard: Determines steps 5.1.2.2, 5.1.2.3, 5.1.2.10 and 5.1.2.11 are applicable and marks Step 5.1.2.1 N/A Comment:

OP-185, 5.1.2.2 Performance Step: 3 Lock Open 1CS-828, ASI Supply Header Upstream Isolation Vlv.

The location of 1CS-828 may be difficult to see when following the candidate into the CVCS filter valve gallery since the area to stand in is small. Have the candidate show you where the valve is located on the valve map outside the CVCS filter gallery before entering the area.

Evaluator Note:

• There may have be a change in dose conditions from when this JPM was validated. DO NOT ENTER THE AREA TO IDENTIFY THE VALVES IF YOU WILL RECEIVE A DOSE OF

>1milliRem during the performance of this JPM. Instead use the valve map and Attachment 1A to allow the candidate to describe what would be done.

Standard: Locates 1CS-828, ASI Supply Header Upstream Isolation valve (or on the valve map outside the CVCS filter valve gallery)

(#51 on the map).

Provide feedback that 1CS-828 as found position is locked Evaluator Cue:

open.

Comment:

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Appendix C Page 5 of 15 Form ES-C-1 PERFORMANCE INFORMATION OP-185, 5.1.2.3 Performance Step: 4 Lock Open 1CS-827, ASI Supply Header Downstream Isolation Vlv.

The location of 1CS-827 may be difficult to see when following the candidate into the CVCS filter valve gallery since the area to stand in is small. Have the candidate show you where the valve is located on the valve map outside the CVCS filter gallery before entering the area.

Evaluator Note:

• There may have be a change in dose conditions from when this JPM was validated. DO NOT ENTER THE AREA TO IDENTIFY THE VALVES IF YOU WILL RECEIVE A DOSE OF

>1milliRem during the performance of this JPM. Instead use the valve map and Attachment 1B to allow the candidate to describe what would be done.

Standard: Locates 1CS-827, ASI Supply Header Downstream Isolation valve (or on the valve map outside the CVCS filter valve gallery)

(#50 on the map).

Provide feedback that 1CS-827 as found position is locked Evaluator Cue:

open.

Comment:

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Appendix C Page 6 of 15 Form ES-C-1 PERFORMANCE INFORMATION OP-185, 5.1.2.4 Provide feedback as each component is checked that the Evaluator Cue:

associated light indication is OFF.

Performance Step: 5 CHECK the ASI System Control Panel for the following:

Standard: Locates each indication in step 4 and checks that all lights are off.

Comment:

OP-185 section 5.1.2 Note prior to step 5 Performance Step: 6 The actions in Step 5.1.2.5 will clear ALB-8-2-3, ASI SYSTEM TROUBLE, if no other inputs to the ALB are active.

Standard: Operator reads and placekeeps notes Comment:

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Appendix C Page 7 of 15 Form ES-C-1 PERFORMANCE INFORMATION OP-185 section 5.1.2.5.a Performance Step: 7 At the ASI System Control Panel, PERFORM the following:

a. PLACE CS-210.1, ASI PUMP, in AUTO.

Evaluator Cue: The initial switch position of CS-210.1 is OFF Standard: Locates CS-210.1 and places CS-210.1, ASI PUMP, in the AUTO position.

NOTE: Both lights are OUT and both lights will STILL BE OUT when CS-210.1 is placed in AUTO Evaluator Cue: Once the switch is turned provide feedback:

CS-210.1 is now in AUTO Comment:

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Appendix C Page 8 of 15 Form ES-C-1 PERFORMANCE INFORMATION OP-185 section 5.1.2.5.b (Begin Critical Steps)

Performance Step: 8 Place CS-210.2, SQUIB VALVE 1ASI-21 BYPASS, in NORMAL Evaluator Cue: The initial switch position of CS-210.2 is in BYPASS Standard: Identifies that this step is a critical step. Locates CS-210.2 and determine that switch is in the bypass position. Repositions switch to NORMAL NOTE: Both lights are OUT and both lights will STILL BE OUT when CS-210.2 is placed in NORMAL Evaluator Cue:

Once the switch is turned:

CS-210.2 is now in NORMAL.

Comment:

OP-185 section 5.1.2.5.c Performance Step: 9 Place CS-210.3, SQUIB VALVE 1ASI-22 BYPASS, in NORMAL Evaluator Cue: The initial switch position of CS-210.3 is in BYPASS Standard: Locates CS-210.3 and determine that switch is in the bypass position. Repositions switch to NORMAL NOTE: Both lights are OUT and both lights will STILL BE OUT when CS-210.3 is placed in NORMAL Evaluator Cue:

Once the switch is turned:

CS-210.3 is now in NORMAL.

Comment:

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Appendix C Page 9 of 15 Form ES-C-1 PERFORMANCE INFORMATION OP-185 section 5.1.2.6 Performance Step: 10 PLACE breaker PP-1D232-6, Feed to ASI System Control Panel, to ON.

PP-1D232-6, Feed to ASI System Control breaker Panel Evaluator Cue:

is OFF Standard: Locates PP-1D232-6 and determines that the breaker is OFF.

Places breaker to the ON position.

Once the breaker is manipulated:

The breaker is now ON NOTE: Candidate may go back to the panel after the breaker is ON to check light conditions. IF they do and they want a Evaluator Cue: response for the light indications then cue:

24VDC control power available (white light ON) 120VAC control power available (white light ON)

ALL 4 Green lights on Firing Circuit Available (green ON)

Comment:

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Appendix C Page 10 of 15 Form ES-C-1 PERFORMANCE INFORMATION OP-185 section 5.1.2.7 Performance Step: 11 PLACE breaker 1D23-1B, Alternate Seal Injection Pump, to ON.

1D23-1B, Alternate Seal Injection Pump breaker is OFF Evaluator Cue:

IF ASKED: (both red and green lights should be OFF)

Standard: Locates breaker 1D23-1B, Alternate Seal Injection Pump is OFF and once the breaker is manipulated provide feedback that breaker is now ON.

Once the breaker is manipulated:

The breaker is now ON.

Evaluator Cue:

IF ASKED: green light is LIT on breaker AND above the Auto switch 210.1 on the panel Comment:

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Appendix C Page 11 of 15 Form ES-C-1 PERFORMANCE INFORMATION End Critical Steps OP-185 section 5.1.2.8 Performance Step: 12 Check the ASI system control Panel for the following:

As each indicator is read, provide feedback that each light is Evaluator Cue:

properly lit as determined from the table in this step.

Standard: Locates each indication listed in step 8 and verifies that the lights are indicating properly.

Once Student reads step 5.1.2.9, Announce Evaluator Cue:

End of JPM.

Comment:

STOP TIME:

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Appendix C Page 12 of 15 Form ES-C-1 PERFORMANCE INFORMATION Attachment 1A

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Appendix C Page 13 of 15 Form ES-C-1 PERFORMANCE INFORMATION Attachment 1B

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Appendix C Page 14 of 15 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2020 HNP NRC Exam In-Plant JPM j Place the ASI System in Standby Alignment In accordance with OP-185 Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiners Signature: Date:

2020 HNP NRC Exam In-Plant JPM j Rev FINAL

Appendix C Form ES-C-1 JPM CUE SHEET BEFORE YOU START THIS JPM IN-PLANT JPM SAFETY CONSIDERATIONS:

CAUTION: EQUIPMENT MAY AUTO START OR MAYBE ENERGIZED

- SIMULATE ONLY - DO NOT OPERATE ANY ACTUAL PLANT EQUIPMENT!!!

Before entering the performance location of this JPM, ensure you AND the examiner have the proper PPE for the area you are going to go to or will travel through to get there.

Avoid contacting any plant equipment.

Follow ALARA practices in the RCA.

Do NOT remove ladders from their storage locations. Simulate obtaining and using a ladder if one would be needed during the actual performance of this task.

• A Normal Plant Heatup is in progress in accordance with GP-002, Normal Plant Heatup From Cold Solid To Hot Subcritical Mode 5 To Mode 3.

Initial Conditions:

• Current RCS temperature is 335°F

• The A CSIP is in service and providing 9 gpm to all 3 RCP Seals.

• The MCR has directed you to perform OP-185, Alternate Seal Injection, Section 5.1, Automatic Standby Alignment Prior to MODE 3.

Initiating Cue:

• Initial Conditions have been met

• You are to perform section 5.1.2.

For this task assume you have a set of AO RAB rounds keys.

2020 HNP NRC Exam In-Plant JPM j Rev FINAL

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Harris Nuclear Plant Task No.: 301013H401 Task

Title:

Isolate the ECCS Accumulators JPM No.: 2020 NRC Exam After a Control Room Evacuation In-Plant JPM k (AOP-004)

K/A

Reference:

APE 068 AG2.1.30 RO 3.9 SRO 3.4 ALTERNATE PATH - NO Examinee: ________________________ NRC Examiner: _________________

Facility Evaluator: ________________________ Date: ________

Method of testing:

Simulated Performance: X Actual Performance:

Classroom Simulator Plant X READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

• The control room has been evacuated due to a fire.

• A cooldown is in progress in accordance with AOP-004, REMOTE Initial Conditions:

SHUTDOWN.

• RCS Pressure is 975 PSIG by PI-402.2.

You are the TB AO and have been assigned to perform AOP-004, Initiating Cue:

Section 3.1, Step 30 - Isolate SI Accumulators.

2020 HNP NRC Exam JPM CR k Rev),1$/

Appendix C Job Performance Measure Form ES-C-1 Worksheet Task Standard: All accumulators isolated and MOVs de-energized in accordance with AOP-004.

Required Materials:

• Standard PPE

• Attachments 1, 2, 3, 4 and 5, ATP Pictures of 1SI-246, 1SI-247, 1SI-248 (Optional)

• Provide the evaluator with a key for ATP Cabinet (Key #33).

• Opening the ATP door actuates an alarm in the control room.

• To minimize Control room distractions Attachments 1-5 should be used.

• Discuss with CRS the option of allowing applicants to reset local alarm caused by opening ATP Cabinet door on Sequencer Panel if Attachments 1-5 are not used.

General

References:

AOP-004, Remote Shutdown, Rev 70 Handout: AOP-004, Rev. 70, page 37, Section 3.1, Step 30 (Pg. 37)

Time Critical Task: No Validation Time: 20 minutes PERFORMANCE CRITICAL STEP JUSTIFICATION STEP Step 2 Required action to reenergizes valve motor to allow valve operation Step 3 Required action to reenergizes valve motor to allow valve operation Repositioning of this valve is required to isolated accumulator water flow Step 4 path and possible inadvertent injection of nitrogen into the RCS Repositioning of this valve is required to isolated accumulator water flow Step 5 path and possible inadvertent injection of nitrogen into the RCS 2020 HNP NRC Exam JPM CR k Rev),1$/

Appendix C Page 3 of 21 Form ES-C-1 PERFORMANCE INFORMATION BEFORE YOU START THIS JPM IN-PLANT JPM SAFETY CONSIDERATIONS:

CAUTION: EQUIPMENT MAY AUTO START OR MAY BE ENERGIZED

- SIMULATE ONLY - DO NOT OPERATE ANY ACTUAL PLANT EQUIPMENT!!!

Before entering the performance location of this JPM, ensure you AND the candidate have the proper PPE for the area you are going to go to or will travel through to get there.

Avoid contacting any plant equipment.

Follow ALARA practices in the RCA.

Do NOT remove ladders from their storage locations. Have the candidate simulate obtaining and using a ladder if one would be needed during the actual performance of this task.

NOTE: Add one minute for Take a Minute checks.

Start time begins when the candidate is briefed outside the Blue Heaven conference Room START TIME:

AOP-004 Performance Step: 1 Obtain locked valve and ATP Cabinet keys.

Standard: Discusses how to obtain keys (ACP Room Key Locker).

The Evaluator can elect to have the applicant locate the ACP Evaluator Note: Room Key Locker or to discuss the key acquisition. The key to the ACP Key Locker is in a break glass case.

• Provide Handout of AOP-004, Section 3.1, Step 30.

• Acknowledge discussion and tell applicant to assume Evaluator Cue: that they have the locked valve key.

• Provide ATP Cabinet key if Attachment 1-5 will NOT be utilized.

Comment:

- Denotes Critical Steps 2020 HNP NRC Exam JPM CR k Rev),1$/

Appendix C Page 4 of 21 Form ES-C-1 PERFORMANCE INFORMATION AOP-004, Section 3.1, Step 30.a Performance Step: 2 WHEN RCS pressure is 900 to 1000 psig, as indicated on PI-402.2, THEN ISOLATE SI accumulators:

286 RAB / RO with locked valve key

a. UNLOCK AND TURN ON accumulator discharge valve breakers:

• Accumulator A: 1A21-SA-5C (both breakers)

• Accumulator C: 1A21-SA-3D (both breakers)

Standard:

• Locates 1A21-SA-5C, identifies UNLOCKS then places breaker in ON position for both breakers for Accumulator A

• Locates 1A21-SA-3D, identifies UNLOCKS then places breaker in ON position for both breakers for Accumulator C Provide feedback on breaker position:

Valve indicating lights indicate the valves are OPEN, i.e.

Evaluator Cue: Red light ON, Green light OFF.

Voltage Vision lights indicate valve is energized, i.e.

Red lights ON Comment: The locked valve key is on the key ring which is a turnover item for the TB AO watch station. Critical to unlock valve breaker in order to provide power to MOV for operation.

- Denotes Critical Steps 2020 HNP NRC Exam JPM CR k Rev),1$/

Appendix C Page 5 of 21 Form ES-C-1 PERFORMANCE INFORMATION AOP-004, Section 3.1, Step 30.a Performance Step: 3 WHEN RCS pressure is 900 to 1000 psig, as indicated on PI-402.2, THEN ISOLATE SI accumulators:

286 RAB / RO with locked valve key

a. UNLOCK AND TURN ON accumulator discharge valve breakers:

• Accumulator B: 1B21-SB-5C (both breakers)

Standard:

• Locates 1B21-SB-5C, identifies UNLOCKS then places breaker in ON position for both breakers for Accumulator B Provide feedback on breaker position.

Valve indicating lights indicate the valves are OPEN, i.e.

Evaluator Cue: Red light ON, Green light OFF.

Voltage Vision lights indicate valve is energized, i.e.

Red lights ON Comment: The locked valve key is on the key ring which is a turnover item for the TB AO watch station. Critical to unlock valve breaker in order to provide power to MOV for operation.

- Denotes Critical Steps 2020 HNP NRC Exam JPM CR k Rev),1$/

Appendix C Page 6 of 21 Form ES-C-1 PERFORMANCE INFORMATION Opening the ATP door actuates an alarm in the control room.

The Attachment pictures will be used once the location of the ATP has been demonstrated. Att. 1 should be shown Evaluator Note: first.

When the operator points out 1SI-246, Att. 2 may be used for close up review of the control switch.

When the operator points out 1SI-248, Att. 3 may be used for close up review of the control switch.

AOP-004, Section 3.1, Step 30.b Performance Step: 4 SHUT SI accumulator discharge valves at the Auxiliary Transfer Panels listed:

Cable Vault A / RO with ATP cabinet key

• 1SI-246, Accumulator A Discharge (at ATP A)

Cable Vault A / RO with ATP cabinet key

• 1SI-248, Accumulator C Discharge (at ATP A)

Standard:

• Locates and opens ATP A and identifies control switch for 1SI-246 then places switch in SHUT position

• Locates and opens ATP A and identifies control switch for 1SI-248 then places switch in SHUT position Provide feedback on switch position.

Evaluator Cue: Valve indication lights change status at this time, i.e.

Green light ON, Red light OFF Comment: Critical to close discharge valves to prevent inadvertent discharge during cooldown.

- Denotes Critical Steps 2020 HNP NRC Exam JPM CR k Rev),1$/

Appendix C Page 7 of 21 Form ES-C-1 PERFORMANCE INFORMATION Opening the ATP door actuates an alarm in the control room.

The Attachment pictures will be used once the location of Evaluator Note: the ATP has been demonstrated. Att. 4 should be shown first.

When the operator points out 1SI-247, Att. 5 may be used for close up review of the control switch.

AOP-004, Section 3.1, Step 30.b Performance Step: 5 SHUT SI accumulator discharge valves at the Auxiliary Transfer Panels listed:

Cable Vault B / RO with ATP cabinet key

• 1SI-247, Accumulator B Discharge (at ATP B)

Standard:

• Locates and opens ATP B and identifies control switch for 1SI-247 then places switch in SHUT position Provide feedback on switch position.

Evaluator Cue: Valve indication lights change status at this time, i.e.

Green light ON, Red light OFF Comment: Critical to close discharge valves to prevent inadvertent discharge during cooldown.

The Evaluator can elect to have the candidate discuss Evaluator Note: the remaining steps since it involves returning to equipment already located and re-opening the breakers that were previously closed.

- Denotes Critical Steps 2020 HNP NRC Exam JPM CR k Rev),1$/

Appendix C Page 8 of 21 Form ES-C-1 PERFORMANCE INFORMATION AOP-004, Section 3.1, Step 30.c Performance Step: 6 286 RAB / RO with locked valve key TURN OFF AND LOCK accumulator discharge valve breakers:

• Accumulator A: 1A21-SA-5C (both breakers)

• Accumulator C: 1A21-SA-3D (both breakers)

Standard:

• Returns to 1A21-SA-5C, identifies OFF then LOCK position for both breakers for Accumulator A.

• Returns to 1A21-SA-3D, identifies OFF then LOCK position for both breakers for Accumulator C.

Provide feedback on breaker position.

Voltage Vision lights indicate valve is de-energized, i.e.

Evaluator Cue: Red lights OFF Valve indicating lights indicate the valves are SHUT, i.e.

Green light ON, Red light OFF Comment:

- Denotes Critical Steps 2020 HNP NRC Exam JPM CR k Rev),1$/

Appendix C Page 9 of 21 Form ES-C-1 PERFORMANCE INFORMATION AOP-004, Section 3.1, Step 30.c Performance Step: 7 286 RAB / RO with locked valve key TURN OFF AND LOCK accumulator discharge valve breakers:

• Accumulator B: 1B21-SB-5C (both breakers)

Standard: Returns to 1B21-SB-5C, identifies OFF then LOCK position for both breakers for Accumulator B.

Evaluator Cue: Provide feedback on breaker position.

Voltage Vision lights indicate valve is de-energized, i.e.

Red lights OFF Valve indicating lights indicate the valves are SHUT, i.e.

Green light ON, Red light OFF Comment:

When all SI Accumulator Discharge Valves are de-energized:

Terminating Cue:

Evaluation on this JPM is complete.

STOP TIME:

- Denotes Critical Steps 2020 HNP NRC Exam JPM CR k Rev),1$/

Appendix C Page 10 of 21 Form ES-C-1 PERFORMANCE INFORMATION KEY 1SI-246 1SI-248

- Denotes Critical Steps 2020 HNP NRC Exam JPM CR k Rev),1$/

Appendix C Page 11 of 21 Form ES-C-1 PERFORMANCE INFORMATION KEY

- Denotes Critical Steps 2020 HNP NRC Exam JPM CR k Rev FINAL

Appendix C Page 12 of 21 Form ES-C-1 PERFORMANCE INFORMATION KEY

- Denotes Critical Steps 2020 HNP NRC Exam JPM CR k Rev FINAL

Appendix C Page 13 of 21 Form ES-C-1 PERFORMANCE INFORMATION KEY 1SI-247

- Denotes Critical Steps 2020 HNP NRC Exam JPM CR k Rev FINAL

Appendix C Page 14 of 21 Form ES-C-1 PERFORMANCE INFORMATION KEY

- Denotes Critical Steps 2020 HNP NRC Exam JPM CR k Rev FINAL

Appendix C Page 15 of 21 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2020 NRC Exam IP JPM k Isolate the ECCS Accumulators After a Control Room Evacuation In accordance with AOP-004 Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiners Signature: Date:

2020 HNP NRC Exam JPM CR k Rev FINAL

Appendix C Page 16 of 21 Form ES-C-1 ATTACHMENT Attachment 1 2020 HNP NRC Exam JPM CR k Rev FINAL

Appendix C Page 17 of 21 Form ES-C-1 ATTACHMENT Attachment 2 2020 HNP NRC Exam JPM CR k Rev FINAL

Appendix C Page 18 of 21 Form ES-C-1 ATTACHMENT Attachment 3 2020 HNP NRC Exam JPM CR k Rev FINAL

Appendix C Page 19 of 21 Form ES-C-1 ATTACHMENT Attachment 4 2020 HNP NRC Exam JPM CR k Rev FINAL

Appendix C Page 20 of 21 Form ES-C-1 ATTACHMENT Attachment 5 2020 HNP NRC Exam JPM CR k Rev FINAL

Appendix C Form ES-C-1 JPM CUE SHEET BEFORE YOU START THIS JPM IN-PLANT JPM SAFETY CONSIDERATIONS:

CAUTION: EQUIPMENT MAY AUTO START OR MAYBE ENERGIZED

- SIMULATE ONLY - DO NOT OPERATE ANY ACTUAL PLANT EQUIPMENT!!!

Before entering the performance location of this JPM, ensure you AND the examiner have the proper PPE for the area you are going to go to or will travel through to get there.

Avoid contacting any plant equipment.

Follow ALARA practices in the RCA.

Do NOT remove ladders from their storage locations. Simulate obtaining and using a ladder if one would be needed during the actual performance of this task.

• The control room has been evacuated due to a fire.

• A cooldown is in progress in accordance with AOP-004, Initial Conditions:

REMOTE SHUTDOWN.

• RCS Pressure is 975 PSIG by PI-402.2.

You are the TB AO and have been assigned to perform AOP-004, Initiating Cue:

Section 3.1, Step 30 - Isolate SI Accumulators.

2020 HNP NRC Exam JPM CR k Rev FINAL

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Harris Nuclear Plant Task No.: 018003H101 Task

Title:

Determine AFD with AFD Monitor JPM No.: 2020 NRC Exam INOP Admin JPM RO A1-1 K/A

Reference:

G 2.1.25 RO 3.9 SRO 4.2 ALTERNATE PATH - NO Examinee: _________________________ NRC Examiner: _________________

Facility Evaluator: _________________________ Date: _________________

Method of testing:

Simulated Performance: Actual Performance: X Classroom X Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate, discuss, or perform and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

• The plant was at 90% power, with a load reduction in progress Initial Conditions:

• The load reduction has been stopped to evaluate AFD following oscillations at 0900 With the information provided complete Attachment 5 of OST-1021, Daily Surveillance Requirements to determine Axial Flux Difference.

After completing OST-1021, Attachment 5 evaluate the results and circle the response below.

Initiating Cue:

IF any 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or less Technical Specifications apply list the associated LCO action(s) and the required completion time(s).

Base any action completion times from the time of 0900.

When complete return your results to the evaluator.

2020 NRC Admin Exam RO A1-1 Rev FINAL

Appendix C Job Performance Measure Form ES-C-1 Worksheet Task Standard: All calculations within +/- 1% of actual.

Correct less than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Tech Spec and LCO action times are identified.

Required Materials: Calculator General

References:

OST-1021, Daily Surveillance Requirements, Rev. 114 OP-163, ERFIS, Rev. 42 Rod Control Manual, Unit One Reactor Operating Data, Rev. 8 Technical Specifications, Rev 185 Handouts: OP-163, Rev. 42, pages 1 - 8, Prerequisites, P&Ls OP-163, Rev. 42, pages 14 - 15, Section 6.2, (Continuous Use) - Axial Flux Differential (AFD) Monitor Rod Control Manual, Section 2.1, Axial Flux Difference Limits, Rev. 0 Technical Specification 3.2.1, Power Distribution Limits - Axial Flux Difference OR 2020 NRC Exam Frozen Procedures Folder OST-1021, Rev. 114, pages 44-46, Attachment 5, Axial Flux Difference Log JPM Cue Sheets Pages 16 - 20 Time Critical Task: No Validation Time: 10 minutes PERFORMANCE CRITICAL STEP JUSTIFICATION STEP Step 7 If the wrong values are selected then the results will NOT be correct Step 10 If the wrong Limit is determined a required Tech Spec LCO action could be exceeded Step 11 If the wrong Limit is determined a required Tech Spec LCO action could be exceeded Step 12 If operation outside of the acceptable region is allowed to continue fuel damage may result.

Step 13 If the wrong Tech Spec Action is selected an LCO action could be exceeded 2020 NRC Admin Exam RO A1-1 Rev FINAL

Appendix C Page 3 of 23 Form ES-C-1 PERFORMANCE INFORMATION Start Time: __________.

OP-163 Performance Step: 1 OBTAIN PROCEDURE (provided in frozen procedure)

Standard: Obtains OP-163 and refers to Section 6.2.

Comment:

OP-163, Section 6.2.2, Step 1.a Performance Step: 2 REVIEW the automatic or On Demand report print-out to verify the following:

• The print-out monitored values are consistent with MCB indications.

Standard:

Locates JPM Cue sheet with attached On Demand and Shift Summary Report Comment:

OP-163, Section 6.2.2, NOTE prior to Step 1.b Performance Step: 3 NOTE: There may be rounding off differences between the automatic printout and the latest AFD curve generated by TE-NF-PWR-0809, Target AFD Calculation.

Standard: Operator reads and placekeeps notes Comment:

- Denotes a Critical Step 2020 NRC Admin Exam RO A1-1 Rev FINAL

Appendix C Page 4 of 23 Form ES-C-1 PERFORMANCE INFORMATION OP-163, Section 6.2.2, Step 1.b Performance Step: 4 REVIEW the automatic or On Demand report print-out to verify the following:

• The printout Operating Band Low and Operating Band High values match the latest Axial Flux Difference Limits As A Function of Rated Thermal Power curve as shown in the ROD Manual.

Standard: Locates Reactor Operating Data Manual and reviews Section 2.1, AFD Limits and determines the current limits are

-12.0% to + 8.0% at 100% Reactor Power

-26.0% to + 20.0% at 50% Reactor Power Comment:

OP-163, Section 6.2.2, Step 2 Performance Step: 5 CHANNEL CHECK the following AFD ERFIS points against MCB indication:

• URE1540 CURRENT CHAN 1 AXIAL FLUX DIFF

• URE1541 CURRENT CHAN 2 AXIAL FLUX DIFF

• URE1542 CURRENT CHAN 3 AXIAL FLUX DIFF

• URE1543 CURRENT CHAN 4 AXIAL FLUX DIFF Standard:

Locates JPM Cue sheet with attached MCB Indication images and compares to information from Shift Summary Report Comment:

- Denotes a Critical Step 2020 NRC Admin Exam RO A1-1 Rev FINAL

Appendix C Page 5 of 23 Form ES-C-1 PERFORMANCE INFORMATION OP-163, Section 6.2.2, NOTE prior to Step 3 Performance Step: 6 NOTE: Only one (1) channel having an unacceptable quality does not make the AFD Monitor inoperable.

Standard: Operator reads and placekeeps notes Comment:

OP-163, Section 6.2.2, Step 3 Performance Step: 7 VERIFY the following AFD ERFIS points are restored to processing with acceptable quality codes as defined in Precaution & Limitation Step 4.0.4:

• URE1540 CURRENT CHAN 1 AXIAL FLUX DIFF

• URE1541 CURRENT CHAN 2 AXIAL FLUX DIFF

• URE1542 CURRENT CHAN 3 AXIAL FLUX DIFF

• URE1543 CURRENT CHAN 4 AXIAL FLUX DIFF

• ANM0120M PWR RNG CHANNEL N41 Q4 1-MIN AVG

• ANM0121M PWR RNG CHANNEL N42 Q2 1-MIN AVG

• ANM0122M PWR RNG CHANNEL N43 Q1 1-MIN AVG

• ANM0123M PWR RNG CHANNEL N44 Q3 1-MIN AVG Standard: Reviews P&L # 4 determines the quality codes are NOT acceptable for

• URE1541 CURRENT CHAN 2 AXIAL FLUX DIFF

• URE1542 CURRENT CHAN 3 AXIAL FLUX DIFF

• ANM0121M PWR RNG CHANNEL N42 Q2 1-MIN AVG

• ANM0122M PWR RNG CHANNEL N43 Q1 1-MIN AVG Notifies the CRS the AFD Monitor does NOT met the criteria for Operable status If necessary prompt the candidate to completed OST-1021, Evaluator Cue:

Attachment 5 as required.

Comment:

- Denotes a Critical Step 2020 NRC Admin Exam RO A1-1 Rev FINAL

Appendix C Page 6 of 23 Form ES-C-1 PERFORMANCE INFORMATION OST-1021, Attachment 5, Page 2 of 3 Performance Step: 8 LOG current reading for the following instruments:

• NI-41C, PR 41 % FLUX

• NI-42C, PR 42 % FLUX

• NI-43C, PR 43 % FLUX

• NI-44C, PR 44 % FLUX Standard:

Locates JPM Cue sheet with attached MCB Indication images and logs current reading

• NI-41C, PR 41 % FLUX = 11% +/- 1%

• NI-42C, PR 42 % FLUX = 13% +/- 1%

• NI-43C, PR 43 % FLUX = 14% +/- 1%

• NI-44C, PR 44 % FLUX = 10% +/- 1%

Comment:

OST-1021, Attachment 5, Page 2 of 3 Performance Step: 9 DETERMINE and LOG Average (AVG) Reactor Power:

• NI-41B, PR 41 % POWER

• NI-42B, PR 42 % POWER

• NI-43B, PR 43 % POWER

• NI-44B, PR 44 % POWER Standard:

Locates JPM Cue sheet with attached MCB Indication images and logs current reading

• NI-41B, PR 41 % POWER = 90% +/- 1%

• NI-42B, PR 42 % POWER = 90% +/- 1%

• NI-43B, PR 43 % POWER = 90% +/- 1%

• NI-44B, PR 44 % POWER = 90% +/- 1%

Comment: Performs calculation to determine AVG Reactor Power and logs value on OST-1021 Attachment 5

- Denotes a Critical Step 2020 NRC Admin Exam RO A1-1 Rev FINAL

Appendix C Page 7 of 23 Form ES-C-1 PERFORMANCE INFORMATION OST-1021, Attachment 5, Page 2 of 3 Performance Step: 10 DETERMINE and LOG AFD Lower limit:

Standard: Critical action is to determine required limit.

Locates Reactor Operating Data Manual l and reviews Section 2.1, AFD Limits and determines the current Lower limits is:

-14.5% at 90% Reactor Power (+/- 1%)

Comment: May interpolate limit based on current power level OST-1021, Attachment 5, Page 2 of 3 Performance Step: 11 DETERMINE and LOG AFD Upper limit:

Standard: Critical action is to determine required limit.

Locates Reactor Operating Data Manual and reviews Section 2.1, AFD Limits and determines the current Upper limits is:

11.0% at 90% Reactor Power (+/- 1%)

Comment: May interpolate limit based on current power level OST-1021, Attachment 5, Page 2 of 3 Performance Step: 12 PERFORM evaluation of AFD limits Standard: Reviews current MCB readings and determines AFD Limits and determines two of four MCB indications are NOT within the curve for Acceptable Operation:

• NI-42C, PR 42 % FLUX = 13% +/- 1%

• NI-43C, PR 43 % FLUX = 14% +/- 1%

Notifies the CRS two of four MCB indications are NOT within the AFD curve for Acceptable Operation Comment: Must interpolate limit based on current power level

- Denotes a Critical Step 2020 NRC Admin Exam RO A1-1 Rev FINAL

Appendix C Page 8 of 23 Form ES-C-1 PERFORMANCE INFORMATION Technical Specifications Performance Step: 13 OBTAIN AND EVALUATE TECHNICAL SPECIFICATIONS Standard: Obtains Technical Specifications and refers to LCO 3.2.1 Determines that ACTION a. is applicable. (See page 14)

a. With the indicated AFD outside of the limits specified in the COLR, either:

1. Restore the indicated AFD to within the limits specified in the COLR within 15 minutes, or (0915)

2. Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within 30 minutes (0930)

After the candidate has determined the current values of Axial Flux Difference and its limits have been manually Evaluator Note: determined and performed a Technical Specification evaluation.

END OF JPM Current value of Axial Flux Difference has been manually Terminating Cue: determined and the Technical Specifications evaluation completed.

- Denotes a Critical Step 2020 NRC Admin Exam RO A1-1 Rev FINAL

Appendix C Page 9 of 23 Form ES-C-1 PERFORMANCE INFORMATION KEY

- Denotes a Critical Step 2020 NRC Admin Exam RO A1-1 Rev FINAL

Appendix C Page 10 of 23 Form ES-C-1 PERFORMANCE INFORMATION KEY

- Denotes a Critical Step 2020 NRC Admin Exam RO A1-1 Rev FINAL

Appendix C Page 11 of 23 Form ES-C-1 PERFORMANCE INFORMATION KEY

- Denotes a Critical Step 2020 NRC Admin Exam RO A1-1 Rev FINAL

Appendix C Page 12 of 23 Form ES-C-1 PERFORMANCE INFORMATION KEY

- Denotes a Critical Step 2020 NRC Admin Exam RO A1-1 Rev FINAL

Appendix C Page 13 of 23 Form ES-C-1 PERFORMANCE INFORMATION KEY AFD Lower AFD Upper Limit -14.5% Limit 11%

- Denotes a Critical Step 2020 NRC Admin Exam RO A1-1 Rev FINAL

Appendix C Page 14 of 23 Form ES-C-1 PERFORMANCE INFORMATION KEY Upper AFD limit 11.0% at 90% Reactor Power (+/- 1%)

1. The current AFD Limits are Lower AFD limit 14.5% at 90% Reactor Power (+/- 1%)

Circle the correct response that applies:

2. AFD Monitor Alarm is Operable / Inoperable

3. Technical Specification(s) and applicable LCOs 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> actions that apply (0915)

(0930)

- Denotes a Critical Step 2020 NRC Admin Exam RO A1-1 Rev FINAL

Appendix C Page 15 of 23 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2020 NRC Admin Exam RO A1-1 Determine Axial Flux Difference (AFD) with AFD Monitor INOP OP-163, ERFIS OST-1021, Daily Surveillance Requirements Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiners Signature: Date:

2020 NRC Admin Exam RO A1-1 Rev FINAL

Appendix C Form ES-C-1 JPM CUE SHEET

• The plant was at 90% power, with a load reduction in progress Initial Conditions:

• The load reduction has been stopped to evaluate AFD following oscillations at 0900 With the information provided complete Attachment 5 of OST-1021, Daily Surveillance Requirements to determine Axial Flux Difference.

After completing OST-1021, Attachment 5 evaluate the results and circle the response below.

Initiating Cue:

IF any 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or less Technical Specifications apply list the associated LCO action(s) and the required completion time(s).

Base any action completion times from the time of 0900.

When complete return your results to the evaluator.

Name:

Date:

1. The current AFD Limits are UPPER LOWER Circle the correct response that applies:

2. AFD Monitor Alarm is Operable / Inoperable 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or less Technical Specification(s) and applicable LCO Action(s) that apply:

2020 NRC Admin Exam RO A1-1 Rev FINAL

Appendix C Form ES-C-1 JPM CUE SHEET 2020 NRC Admin Exam RO A1-1 Rev FINAL

Appendix C Form ES-C-1 JPM CUE SHEET 2020 NRC Admin Exam RO A1-1 Rev FINAL

Appendix C Form ES-C-1 JPM CUE SHEET 2020 NRC Admin Exam RO A1-1 Rev FINAL

Appendix C Form ES-C-1 JPM CUE SHEET 2020 NRC Admin Exam RO A1-1 Rev FINAL

Appendix C Form ES-C-1 JPM CUE SHEET 2020 NRC Admin Exam RO A1-1 Rev FINAL

Appendix C Form ES-C-1 JPM CUE SHEET Indications at 0900 2020 NRC Admin Exam RO A1-1 Rev FINAL

Appendix C Form ES-C-1 JPM CUE SHEET Indications at 0900 2020 NRC Admin Exam RO A1-1 Rev FINAL

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Harris Nuclear Plant Task No.: 005016H101 Task

Title:

AOP-017 Attachment 4 manual JPM No.: 2020 NRC Exam makeup calculation Admin JPM RO A1-2 K/A

Reference:

G2.1.25 RO 3.9 SRO 4.2 ALTERNATE PATH - NO Examinee: ________________________ NRC Examiner: ________________

Facility Evaluator: ________________________ Date: ________________

Method of testing:

Simulated Performance: Actual Performance: X Classroom X Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate, discuss, or perform and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

• The plant is in Mode 3 Initial

• Instrument air leak resulted header pressure lowering to 45 psig Conditions:

• Automatic Blender automatic makeup is not available

• VCT level is currently 19% and stable The CRS has directed you to perform a Manual Makeup and to determine the following for these conditions:

• Required Boric acid flow rate

• The maximum possible makeup flow rate to achieve required Initiating boron concentration in the VCT.

Cue:

• Dilution flow rate Record your results in the space provided or on the applicable procedure Show all work.

2020 NRC Exam Admin JPM RO A1-2 Rev FINAL

Appendix C Job Performance Measure Form ES-C-1 Worksheet Task Standard: Determines Required boric acid flow to be 27.5 gpm (27.0-28.0) and required dilution flow is 72.5 gpm (72.0 - 73.0), using AOP-017 Attachment 4 and OP-107.1 OR 30 gpm and required dilution flow is 79 gpm, using AOP-017 Attachment 4 Note prior to Step 2.

Required Materials: AOP-017, Rev. 40 OP-107.01, Rev. 30 Calculator General

References:

AOP-017, Rev. 40 OP-107.01, Rev. 30 Handouts: AOP-017, Rev. 40, pages 47 - 50, Manual Makeup OP-107.01, Rev. 30, pages 120 - 128, Makeup Concentration Limits OR 2020 NRC Exam Frozen Procedures Folder JPM Cue Sheets Time Critical Task: No Validation Time: 15 minutes NOTE: Performance Step 9, 12 and 13 are only critical if the candidate performs the calculations in accordance with the note prior to Attachment 4 Step 2.

PERFORMANCE CRITICAL STEP JUSTIFICATION STEP Must calculate correct boric acid flow rate to ensure correct manual Step 7 makeup is performed.

Must calculate correct dilution flow rate to ensure correct manual Step 8 makeup is performed.

Must calculate correct Total flow rate to ensure correct manual makeup Step 9 is performed.

Must calculate correct boric acid flow rate to ensure correct manual Step 12 makeup is performed.

Must calculate correct dilution flow rate to ensure correct manual Step 13 makeup is performed.

2020 NRC Exam Admin JPM RO A1-2 Rev FINAL

Appendix C Page 3 of 12 Form ES-C-1 PERFORMANCE INFORMATION START TIME:

Performance Step: 1 Obtain a copy of the appropriate procedures (AOP-017)

Standard: Operator obtains a copy of AOP-017 to determine appropriate attachment is Attachment 4 to complete a manual makeup.

Comment:

AOP-017 ATT.4 Step 1 Performance Step: 2 Standard: References Reactivity sheet and uses the RCS Boron concentration of 1928.

Comment:

2020 NRC Exam Admin JPM RO A1-2 Rev FINAL

Appendix C Page 4 of 12 Form ES-C-1 PERFORMANCE INFORMATION AOP-017 ATT.4 NOTE before Step 2 Performance Step: 3 NOTE If RCS boron concentration is above 1750 ppm, blended makeup at 120 gpm may not be possible, due to the inability of the system to reliably deliver more than 30 gpm boric acid flow. In those cases, either select a conservatively low total makeup flow, or consult Attachment 7 of OP-107.01 to determine the maximum possible makeup flow.

Standard: Reads and placekeeps note and refers to OP-107.01, Attachment 7 OR performs calculation to select a conservatively low total makeup flow.

Comment:

Performance Step 4 - 8 are only applicable if the candidate Evaluator Note: performs the calculations in accordance with OP-107.01 Attachment 7.

OP-107.01 Attachment 7 Performance Step: 4 Determine maximum total flow with a RCS boron concentration of 1928 ppm Standard: References OP-107.01 Attachment 7 page 4 and determines the maximum total flow available to meet the 1928 ppm requirement is 100 gpm.

Comment:

2020 NRC Exam Admin JPM RO A1-2 Rev FINAL

Appendix C Page 5 of 12 Form ES-C-1 PERFORMANCE INFORMATION AOP-017 ATT. 4 step 2 Performance Step: 5 RECORD desired total makeup flow rate:

MBLEND = ________ gpm Standard: Records 100 gpm as the desired total makeup flow.

Comment:

AOP-017 ATT. 4 step 3 Performance Step: 6 RECORD most recent Boric Acid Tank boron concentration from Unit Status Board:

CBAT = ________ ppm Standard: References Reactivity data sheet and records 7000 ppm Comment:

2020 NRC Exam Admin JPM RO A1-2 Rev FINAL

Appendix C Page 6 of 12 Form ES-C-1 PERFORMANCE INFORMATION AOP-017 ATT. 4 step 4 Performance Step: 7 Standard: [(CBLEND) x (MBLEND)] / (CBAT)

(1928 ppm x 100gpm) / (7000ppm) = 27.5 gpm (27.0-28.0) gpm Comment:

AOP-017 ATT. 4 step 6 Performance Step: 8 Standard: Calculates 100 gpm - 27.5 gpm = 72.5 gpm (72.0 - 73.0) gpm Comment:

When the BA flow rate and total flow rate has been Evaluator Cue: determined. Evaluation on this JPM is complete.

END OF JPM Stop Time: _________

2020 NRC Exam Admin JPM RO A1-2 Rev FINAL

Appendix C Page 7 of 12 Form ES-C-1 PERFORMANCE INFORMATION Performance Step 9 - 13 are only applicable if the candidate Evaluator Note: performs the calculations in accordance with the note prior to Attachment 4 Step 2.

AOP-017 Attachment 4 Calculation Performance Step: 9 Determine maximum total flow with a RCS boron concentration of 1928 ppm Standard: References Note prior to AOP-017 Attachment 4 Step 2 and determines the maximum total flow available to meet the 1928 ppm requirement as follows:

30 gpm x 7000 ppm = 108.9 gpm 1928 ppm (Band 108 to 109 gpm)

Comment:

AOP-017 ATT. 4 step 2 Performance Step: 10 RECORD desired total makeup flow rate:

MBLEND = ________ gpm Standard: Records 108.9 gpm as the desired total makeup flow.

(Band 108 to 109 gpm)

Comment:

2020 NRC Exam Admin JPM RO A1-2 Rev FINAL

Appendix C Page 8 of 12 Form ES-C-1 PERFORMANCE INFORMATION AOP-017 ATT. 4 step 3 Performance Step: 11 RECORD most recent Boric Acid Tank boron concentration from Unit Status Board:

CBAT = ________ ppm Standard: References Reactivity data sheet and records 7000 ppm Comment:

AOP-017 ATT. 4 step 4 Performance Step: 12 DETERMINE required boric acid flow rate:

Standard: [(CBLEND) x (MBLEND)] / (

CBAT)

(1928 ppm x 109 gpm) / (7000ppm) = 30 gpm (Band 29.0 - 30.0 gpm)

Comment:

2020 NRC Exam Admin JPM RO A1-2 Rev FINAL

Appendix C Page 9 of 12 Form ES-C-1 PERFORMANCE INFORMATION AOP-017 ATT. 4 step 6 Performance Step: 13 Standard: Calculates 109 gpm - 30.0 gpm = 79.0 gpm (78.0 - 80.0) gpm Comment:

When the BA flow rate and total flow rate has been Evaluator Cue: determined. Evaluation on this JPM is complete.

END OF JPM Stop Time: _________

2020 NRC Exam Admin JPM RO A1-2 Rev FINAL

Appendix C Page 10 of 12 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2020 NRC Exam Admin JPM RO A1-2 AOP-017 Attachment 4 manual makeup calculation AOP-017 OP-107.01 Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiners Signature: Date:

2020 NRC Exam Admin JPM RO A1-2 Rev FINAL

Appendix C Form ES-C-1 JPM CUE SHEET

• The plant is in Mode 3 Initial

• Instrument air leak resulted header pressure lowering to 45 psig Conditions:

• Automatic Blender automatic makeup is not available

• VCT level is currently 19% and stable The CRS has directed you to perform Manual Makeup and to determine the following for these conditions:

• Required Boric acid flow rate

• The maximum possible makeup flow rate to achieve required Initiating boron concentration in the VCT.

Cue:

• Dilution flow rate Record your results in the space provided or on the applicable procedure Show all work.

Name:

Date:

1. Identify the procedure required to be entered to address the current plant conditions.

2. Record your results below or on the procedure section / attachment required to complete the Manual Makeup for the current plant conditions.

• Required Boric acid flow rate

• The maximum possible makeup flow rate to achieve required boron concentration in the VCT

• Dilution flow rate 2020 NRC Exam Admin JPM RO A1-2 Rev FINAL

Appendix C Form ES-C-1 JPM CUE SHEET 2020 NRC Exam Admin JPM RO A1-2 Rev FINAL

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Harris Nuclear Plant Task No.: 119013H304 Task

Title:

Determine Clearance Requirements JPM No.: 2020 NRC Exam for a CCW Pump Admin JPM RO A2 K/A

Reference:

G 2.2.13 RO 4.1 SRO 4.3 ALTERNATE PATH - NO Examinee: _________________________ NRC Examiner: _________________

Facility Evaluator: _________________________ Date: _________________

Method of testing:

Simulated Performance: Actual Performance: X Classroom X Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate, discuss, or perform and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

• The plant is defueled

• CCW Pump 1A-SA is required to be placed under a clearance for Initial Conditions: seal replacement

• There is NO known isolation boundary leakage

• eSOMS is currently OOS for an IT update You have been directed to determine the clearance requirements for CCW Pump 1A-SA. The AOM-Shift has approved using single valve isolation.

NOTE: LISTING OF CITS IS NOT REQUIRED FOR THIS JPM.

Initiating Cue:

IT IS NOT INTENDED THAT YOU ACTUALLY GENERATE A CLEARANCE. ONLY PROVIDE THE EVALUATOR WITH A LISTING OF THE REQUIRED COMPONENTS, POSITIONS AND THE INSTALLATION SEQUENCE.

2020 NRC Exam Admin JPM RO A2 Rev FINAL

Appendix C Job Performance Measure Form ES-C-1 Worksheet Task Standard: Provide complete electrical and mechanical isolation of CCW Pump 1A-SA Required Materials: AD-OP-ALL-0200, Equipment Clearance, pgs. 40, 41 and 42, Rev. 20 OP-145, Component Cooling Water, Rev. 80 SFD 2165 S-1319 CWD 6-B-401 941 Additional copies of page 12 of this JPM available General

References:

AD-OP-ALL-0200, Equipment Clearance, Rev. 20 OP-145, Component Cooling Water, Rev. 80 SFD 2165 S-1319, 1320, and 1321 CWD 6-B-401 941, 942, and 943 OR 2020 NRC Exam Frozen Procedures Folder Handouts: JPM Cue Sheets SFD 2165 S-1319 Time Critical Task: No Validation Time: 20 minutes PERFORMANCE CRITICAL STEP JUSTIFICATION STEP Step 2 Critical to remove power from the pump for personnel protection.

Step 3 Critical to isolate suction source to allow pump to be depressurized.

Step 4 Critical to isolate discharge path to allow pump to be depressurized.

Step 5 Critical to open vent path to allow pump to depressurize.

Step 6 Critical to open drain path to allow pump to depressurize.

NOTE: Provide applicants a copy of SFD 2165 S-1319, 1320 and 1321 along with CWD 6-B-401 Sheet 941, 942 and 943.

Laptops are to be used for this JPM.

Prior to starting this JPM: Ensure each candidate is familiar with the contents of the frozen procedures and are able to access the files containing OP-145, Component Cooling Water Activities and AD-OP-ALL-0200, Equipment Clearance.

2020 NRC Exam Admin JPM RO A2 Rev FINAL

Appendix C Page 3 of 10 Form ES-C-1 PERFORMANCE INFORMATION START TIME:

Performance Step: 1 Obtain a copy of the appropriate drawings and procedures (AD-OP-ALL-0200, OP-145, SFD 2165 S-1319, CWD 6-B-401 Sheet 941)

Standard: Operator obtains a copy of OP-145 to determine electrical requirements. SFD 2165 S-1319 to determine mechanical requirements. AD-OP-ALL-0200 to determine proper installation sequence for clearance.

Comment:

SEE JPM ATTACHMENT FOR A COMPLETE LISTING OF EACH COMPONENT AND REQUIRED POSITION. JPM Evaluator Note:

STEPS ARE NOT REQUIRED TO BE PERFORMED IN THE LISTED SEQUENCE.

Performance Step: 2 Determine the electrical supply breaker for CCW Pump 1A-SA Standard: Refers to CWD 6-B-401 Sheet 941, OP-145 (or any other valid source) and determines the electrical supply breaker for CCW Pump 1A-SA to be 6.9 KV Emergency Bus 1A-SA, Cubicle 8 (BREAKER RACKED OUT)

Also determines pump has MCB and ACP switch and includes a CIT on CCW Pump 1A-SA switch for each location Comment:

Evaluator Note: CRITICAL TO REMOVE POWER FROM PUMP.

- Denotes Critical Steps 2020 NRC Exam Admin JPM RO A2 Rev FINAL

Appendix C Page 4 of 10 Form ES-C-1 PERFORMANCE INFORMATION Performance Step: 3 Determine the discharge isolation for CCW Pump 1A-SA Standard: Refers to S-1319 and determines the valve to isolate CCW Pump 1A-SA discharge is 1CC-36, CCW Pump A Discharge Isol Valve (CLOSE)

Comment:

Performance Step: 4 Determine the suction valve for CCW Pump 1A-SA Standard: Refers to S-1319 and determines the suction valve for CCW Pump 1A-SA to be 1CC-27, CCW Pump A Suction Valve (CLOSE)

Comment:

Performance Step: 5 Determine the vent path for CCW Pump 1A-SA Standard: Refers to S-1319 and determines the valve to vent CCW Pump 1A-SA is 1CC-28, CCW Pump A Suction Pressure Tap (OPEN WITH CAP REMOVED)

Comment:

EITHER STEP 5 OR STEP 6 IS CRITICAL TO DEPRESSURIZE THE SYSTEM. ONE OR THE OTHER MUST BE Evaluator Note:

PERFORMED, BUT NOT BOTH. HOWEVER, IF BOTH ARE PERFORMED, THIS IS ALSO ACCEPTABLE.

- Denotes Critical Steps 2020 NRC Exam Admin JPM RO A2 Rev FINAL

Appendix C Page 5 of 10 Form ES-C-1 PERFORMANCE INFORMATION Performance Step: 6 Determine the drain path for CCW Pump 1A-SA Standard: Refers to S-1319 and determines the valves to drain CCW Pump 1A-SA suction piping to be 1CC-29, CCW Pump A Suction Drain Valve and discharge piping to be 1CC-30, CCW Pump A Discharge Drain Valve, and 1CC-31, CCW Pump A Discharge Line Drain Isol Valve (ALL OPEN)

Comment:

EITHER STEP 5 OR STEP 6 IS CRITICAL TO DEPRESSURIZE THE SYSTEM. ONE OR THE OTHER MUST BE Evaluator Note:

PERFORMED, BUT NOT BOTH. HOWEVER, IF BOTH ARE PERFORMED, THIS IS ALSO ACCEPTABLE.

When applicant completes and returns clearance list.

Evaluator Cue:

END OF JPM Stop Time: _________

- Denotes Critical Steps 2020 NRC Exam Admin JPM RO A2 Rev FINAL

Appendix C Page 6 of 10 Form ES-C-1 PERFORMANCE INFORMATION KEY JPM ATTACHMENT COMPONENT LISTING AND REQUIRED POSITIONS Critical sequences:

1) Remove power from the CCW Pump 1A-SA

2) Shut 1CC-36, CCW Pump 1A-SA Discharge Isol Valve

2) Shut 1CC-27, CCW Pump 1A-SA Suction Isol Valve

3) Open Vent and/or Drain to depressurize boundary COMPONENT POSITION

1) CCW Pump 1A-SA P.S. - 6.9 KV Emergency Bus 1A-SA, Cubicle 8. Racked Out

2) 1CC-36, CCW Pump 1A-SA, Discharge Isol Valve Shut

3) 1CC-27, CCW Pump 1A-SA, Suction Isol Valve Shut

4) Accept - EITHER one vent path OR the drain path or BOTH a vent path and drain path.

NOTE: Any of the following vent valves will support a vent path for the pump. One or more of these vent paths are required to be identified VENT PATHS 1CC-28, CCW Pump A Suction Pressure Tap Uncapped/Open

- OR -

1CC-606, CCW Pump 1A Casing Vent Valve Uncapped/Open

- OR -

1CC-32, PI-677B Root Isolation Valve Uncapped/Open DRAIN PATH 1CC-29, CCW Pump A Suction Drain Valve Open

- AND -

1CC-30, CCW Pump A Discharge Drain Valve Open

- AND -

1CC-31, CCW Pump A Discharge Drain Isolation Valve Open

- OR -

1CC-34, CCW Pump A Disch Line Inner Drain Valve Open

- AND -

1CC-35, CCW Pump A Disch Line Outer Drain Valve Uncapped/Open NOTE - CITs are NOT required for satisfactory completion of JPM.

2020 NRC Exam Admin JPM RO A2 Rev FINAL

Appendix C Page 7 of 10 Form ES-C-1 PERFORMANCE INFORMATION KEY 2020 NRC Exam Admin JPM RO A2 Rev FINAL

Appendix C Page 8 of 10 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2020 NRC Exam Admin JPM RO A2 Determine Clearance Requirements for a CCW Pump AD-OP-ALL-0200 OP-145 Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiners Signature: Date:

2020 NRC Exam Admin JPM RO A2 Rev FINAL

Appendix C Form ES-C-1 JPM CUE SHEET

• The plant is defueled

• CCW Pump 1A-SA is required to be placed under a clearance for Initial Conditions: seal replacement

• There is NO known isolation boundary leakage

• eSOMS is currently OOS for an IT update You have been directed to determine the clearance requirements for CCW Pump 1A-SA. The AOM-Shift has approved using single valve isolation.

NOTE: LISTING OF CITS IS NOT REQUIRED FOR THIS JPM.

Initiating Cue:

IT IS NOT INTENDED THAT YOU ACTUALLY GENERATE A CLEARANCE. ONLY PROVIDE THE EVALUATOR WITH A LISTING OF THE REQUIRED COMPONENTS, POSITIONS AND THE INSTALLATION SEQUENCE.

NOTE: Provide a list of components in the proper installation sequence to the examiner using the following page(s).

Additional pages are available upon request.

2020 NRC Exam Admin JPM RO A2 Rev FINAL

Appendix C Form ES-C-1 JPM CUE SHEET Name:

Date:

CCW Pump 1A-SA CLEARANCE COMPONENT LISTING AND REQUIRED POSITIONS SEQUENCE COMPONENT POSITION 2020 NRC Exam Admin JPM RO A2 Rev FINAL

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Harris Nuclear Plant Task No.: 344171H404 Task

Title:

Given a set of conditions, determine JPM No.: 2020 NRC Exam and apply the facility dose limits. Admin JPM RO A3 K/A

Reference:

G 2.3.7 RO 3.5 SRO 3.6 ALTERNATE PATH - NO Examinee: _________________________ NRC Examiner: _________________

Facility Evaluator: _________________________ Date: _________________

Method of testing:

Simulated Performance: Actual Performance: X Classroom X Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

• A fire has occurred in 1-A-SWGRA

• The reactor is tripped Initial Conditions:

• The operating crew is performing AOP-036.08, Fire Areas: 1-A-SWGRA, 1-A-SWGRB

• Charging flow cannot be controlled from the control room

• You have been assigned to locally control charging in accordance with AOP-036.08, Section 3.1, Step 10.d

• This is not considered to be an emergency evolution. Your accumulated TEDE dose for this year is 1550 mrem

• You will be performing the evolution under RWP # 23, Operations Activities Initiating Cue:

• Identify the Minimum Operation Activities Task # to perform this evolution

• Determine the maximum permissible stay time before the first Stop Work limit requires you to exit the area (ASSUME NO DOSE IN TRANSIT AND THE OPERATOR WILL REMAIN NEXT TO THE EQUIPMENT UNTIL THE STOP LIMIT IS REACHED.)

2020 NRC Exam Admin JPM RO A3 Rev FINAL

Appendix C Job Performance Measure Form ES-C-1 Worksheet Task Standard: Lowest facility limit determined and stay time calculated within tolerance band.

Required Materials: Calculator General

References:

AOP-036.08, Fire Areas: 1-A-SWGRA, 1-A-SWGRB, Rev. 21 AD-RP-ALL-2000, Preparation And Management Of Radiation Work Permits (RWP), Rev. 4 RWP # 23 Operations Activities, Rev. 12 Valve Map 9, RAB 236 Mechanical Penetration Area Survey HNP-M-20200621-4, RAB 236 Mechanical Penetration Area OR 2020 NRC Exam Frozen Procedures Folder Handout: JPM Cue Sheets pages 5 - 19 Time Critical Task: No Validation Time: 10 minutes PERFORMANCE CRITICAL STEP JUSTIFICATION STEP Must determine the location of the valve in order to calculate the dose Step 2 value until an alarm limit is reached Must determine the area classification of the valve location in order to Step 3 minimum task dose alarm setpoint and dose rate alarm limits Must determine the RWP limits in order to calculate the dose value until Step 4 an alarm limit is reached Must determine the time allowed in order to exit the area once the alarm Step 5 limit is reached 2020 NRC Exam Admin JPM RO A3 Rev FINAL

Appendix C Page 3 of 19 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a check mark)

START TIME:

Performance Step: 1 Determine the general location of the valves from AOP-036.08 on the survey map.

Standard: Uses Valve Map to determine location of the required valves (1CS-227 and 1CS-228)

Locates general area on the Survey Map.

Evaluator Cue:

• Provide the handout.

• Assume that all handout materials are the most recent, approved documents.

Comment:

Performance Step: 2 Determine the radiation level in the area of the valves.

Standard: Using Survey HNP-M-20200621-4, determines general radiation level in the area of the valves to be 3 mr/hr.

Comment:

Performance Step: 3 Determines the RCA classification of the work area.

Standard: Using Survey HNP-M-20200621-4 and RWP # 23 determines the work area is only a RA and Task # 1 Operations Activities (No HRA Access) is the minimum RWP task required to perform the evolution.

Comment:

- Denotes Critical Steps 2020 NRC Exam Admin JPM RO A3 Rev FINAL

Appendix C Page 4 of 19 Form ES-C-1 PERFORMANCE INFORMATION Performance Step: 4 Determine the first Stop Work limit.

Standard: Reviews RWP # 23 Task # 1 and determines first Stop Work limit will be reached when the Alarming Dosimeter actuates:

• 8 mr accumulated dose (80% of 10 mr) or

• 75 mr/hr dose rate.

Comment:

Performance Step: 5 Calculate maximum stay time.

Standard: (8 mr)(1 hr/3 mr) = 2.67 hours7.75463e-4 days <br />0.0186 hours <br />1.107804e-4 weeks <br />2.54935e-5 months <br /> or 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and 40 minutes 2.60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br /> 2.67 hours7.75463e-4 days <br />0.0186 hours <br />1.107804e-4 weeks <br />2.54935e-5 months <br /> or 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and 36 minutes 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and 40 minutes.

Evaluator Note: Tolerance allows for a delta of 4 minutes on the low end without exceeding the upper limit in the event the candidate truncates the answer down to the nearest minute (2.60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br />) based on the initiating cue.

Comment:

Terminating Cue: After stay time is reported: Evaluation on this JPM is complete.

STOP TIME:

- Denotes Critical Steps 2020 NRC Exam Admin JPM RO A3 Rev FINAL

Appendix C Page 5 of 19 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2020 NRC ADM JPM RO A3 Given a set of conditions, determine and apply the facility dose limits.

AD-RP-ALL-2000, RWP # 23, Operations Activities Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiners Signature: Date:

2020 NRC Exam Admin JPM RO A3 Rev FINAL

Appendix C Form ES-C-1 JPM CUE SHEET

• A fire has occurred in 1-A-SWGRA

• The reactor is tripped Initial Conditions:

• The operating crew is performing AOP-036.08, Fire Areas: 1-A-SWGRA, 1-A-SWGRB

• Charging flow cannot be controlled from the control room

• You have been assigned to locally control charging in accordance with AOP-036.08, Section 3.1, Step 10.d

• This is not considered to be an emergency evolution. Your accumulated TEDE dose for this year is 1550 mrem

• You will be performing the evolution under RWP # 23, Operations Activities Initiating Cue:

• Identify the Minimum Operation Activities Task # to perform this evolution

• Determine the maximum permissible stay time before the first Stop Work limit requires you to exit the area (ASSUME NO DOSE IN TRANSIT AND THE OPERATOR WILL REMAIN NEXT TO THE EQUIPMENT UNTIL THE STOP LIMIT IS REACHED.)

Name:

Date:

1. Minimum Operation Activities Task #

2. Maximum permissible stay time before the first Stop Work limit requires you to exit the area for the identified Task # is hrs and mins 2020 NRC Exam Admin JPM RO A3 Rev FINAL

Appendix C Form ES-C-1 JPM CUE SHEET 2020 NRC Exam Admin JPM RO A3 Rev FINAL

Appendix C Form ES-C-1 JPM CUE SHEET 2020 NRC Exam Admin JPM RO A3 Rev FINAL

Appendix C Form ES-C-1 JPM CUE SHEET 2020 NRC Exam Admin JPM RO A3 Rev FINAL

Appendix C Form ES-C-1 JPM CUE SHEET 2020 NRC Exam Admin JPM RO A3 Rev FINAL

Appendix C Form ES-C-1 JPM CUE SHEET 2020 NRC Exam Admin JPM RO A3 Rev FINAL

Appendix C Form ES-C-1 JPM CUE SHEET 2020 NRC Exam Admin JPM RO A3 Rev FINAL

Appendix C Form ES-C-1 JPM CUE SHEET 2020 NRC Exam Admin JPM RO A3 Rev FINAL

Appendix C Form ES-C-1 JPM CUE SHEET 2020 NRC Exam Admin JPM RO A3 Rev FINAL

Appendix C Form ES-C-1 JPM CUE SHEET 2020 NRC Exam Admin JPM RO A3 Rev FINAL

Appendix C Form ES-C-1 JPM CUE SHEET 2020 NRC Exam Admin JPM RO A3 Rev FINAL

Appendix C Form ES-C-1 JPM CUE SHEET 2020 NRC Exam Admin JPM RO A3 Rev FINAL

Appendix C Form ES-C-1 JPM CUE SHEET 2020 NRC Exam Admin JPM RO A3 Rev FINAL

Appendix C Form ES-C-1 JPM CUE SHEET 2020 NRC Exam Admin JPM RO A3 Rev FINAL

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Harris Nuclear Plant Task No.: 018003H101 Task

Title:

Determine AFD with AFD Monitor JPM No.: 2020 NRC Exam INOP and Evaluate Tech Specs Admin JPM SRO A1-1 K/A

Reference:

G 2.1.25 RO 3.9 SRO 4.2 ALTERNATE PATH - NO Examinee: _________________________ NRC Examiner: _________________

Facility Evaluator: _________________________ Date: _________________

Method of testing:

Simulated Performance: Actual Performance: X Classroom X Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate, discuss, or perform and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

• The plant was at 90% power, with a load reduction in progress Initial Conditions:

• The load reduction has been stopped to evaluate AFD following oscillations at 0900 With the information provided complete Attachment 5 of OST-1021, Daily Surveillance Requirements to determine Axial Flux Difference.

After completing OST-1021, Attachment 5 evaluate the results and circle the response below Initiating Cue:

IF any Technical Specifications apply list the associated LCO action(s) and the maximum allowed completion time(s).

Base any action completion times from the time of 0900.

When complete return your results to the evaluator.

2020 NRC Admin Exam SRO A1-1 Rev FINAL

Appendix C Job Performance Measure Form ES-C-1 Worksheet Task Standard: All calculations within +/- 1% of actual.

Correct Tech Spec and LCO actions are identified.

Required Materials: Calculator General

References:

OST-1021, Daily Surveillance Requirements, Rev. 114 OP-163, ERFIS, Rev. 42 Rod Control Manual, Unit One Reactor Operating Data, Rev. 8 Technical Specifications, Rev 185 Handouts: OP-163, Rev. 42, pages 1 - 8, Prerequisites, P&Ls OP-163, Rev. 42, pages 14 - 15, Section 6.2, (Continuous Use) - Axial Flux Differential (AFD) Monitor Rod Control Manual, Section 2.1, Axial Flux Difference Limits, Rev. 0 Technical Specification 3.2.1, Power Distribution Limits - Axial Flux Difference OR 2020 NRC Exam Frozen Procedures Folder OST-1021, Rev. 114, pages 44-46, Attachment 5, Axial Flux Difference Log JPM Cue Sheets Pages 16 - 20 Time Critical Task: No Validation Time: 10 minutes PERFORMANCE CRITICAL STEP JUSTIFICATION STEP Step 7 If the wrong values are selected then the results will NOT be correct Step 10 If the wrong Limit is determined a required Tech Spec LCO action could be exceeded Step 11 If the wrong Limit is determined a required Tech Spec LCO action could be exceeded Step 12 If operation outside of the acceptable region is allowed to continue fuel damage may result.

Step 13 If the wrong Tech Spec Action is selected an LCO action could be exceeded 2020 NRC Admin Exam SRO A1-1 Rev FINAL

Appendix C Page 3 of 23 Form ES-C-1 PERFORMANCE INFORMATION Start Time: __________.

OP-163 Performance Step: 1 OBTAIN PROCEDURE (provided in frozen procedure)

Standard: Obtains OP-163 and refers to Section 6.2.

Comment:

OP-163, Section 6.2.2, Step 1.a Performance Step: 2 REVIEW the automatic or On Demand report print-out to verify the following:

• The print-out monitored values are consistent with MCB indications.

Standard:

Locates JPM Cue sheet with attached On Demand and Shift Summary Report Comment:

OP-163, Section 6.2.2, NOTE prior to Step 1.b Performance Step: 3 NOTE: There may be rounding off differences between the automatic printout and the latest AFD curve generated by TE-NF-PWR-0809, Target AFD Calculation.

Standard: Operator reads and placekeeps notes Comment:

- Denotes a Critical Step 2020 NRC Admin Exam SRO A1-1 Rev FINAL

Appendix C Page 4 of 23 Form ES-C-1 PERFORMANCE INFORMATION OP-163, Section 6.2.2, Step 1.b Performance Step: 4 REVIEW the automatic or On Demand report print-out to verify the following:

• The printout Operating Band Low and Operating Band High values match the latest Axial Flux Difference Limits As A Function of Rated Thermal Power curve as shown in the ROD Manual.

Standard: Locates Reactor Operating Data Manual l and reviews Section 2.1, AFD Limits and determines the current limits are

-12.0% to + 8.0% at 100% Reactor Power

-26.0% to + 20.0% at 50% Reactor Power Comment:

OP-163, Section 6.2.2, Step 2 Performance Step: 5 CHANNEL CHECK the following AFD ERFIS points against MCB indication:

• URE1540 CURRENT CHAN 1 AXIAL FLUX DIFF

• URE1541 CURRENT CHAN 2 AXIAL FLUX DIFF

• URE1542 CURRENT CHAN 3 AXIAL FLUX DIFF

• URE1543 CURRENT CHAN 4 AXIAL FLUX DIFF Standard:

Locates JPM Cue sheet with attached MCB Indication images and compares to information from Shift Summary Report Comment:

- Denotes a Critical Step 2020 NRC Admin Exam SRO A1-1 Rev FINAL

Appendix C Page 5 of 23 Form ES-C-1 PERFORMANCE INFORMATION OP-163, Section 6.2.2, NOTE prior to Step 3 Performance Step: 6 NOTE: Only one (1) channel having an unacceptable quality does not make the AFD Monitor inoperable.

Standard: Operator reads and placekeeps notes Comment:

OP-163, Section 6.2.2, Step 3 Performance Step: 7 VERIFY the following AFD ERFIS points are restored to processing with acceptable quality codes as defined in Precaution & Limitation Step 4.0.4:

• URE1540 CURRENT CHAN 1 AXIAL FLUX DIFF

• URE1541 CURRENT CHAN 2 AXIAL FLUX DIFF

• URE1542 CURRENT CHAN 3 AXIAL FLUX DIFF

• URE1543 CURRENT CHAN 4 AXIAL FLUX DIFF

• ANM0120M PWR RNG CHANNEL N41 Q4 1-MIN AVG

• ANM0121M PWR RNG CHANNEL N42 Q2 1-MIN AVG

• ANM0122M PWR RNG CHANNEL N43 Q1 1-MIN AVG

• ANM0123M PWR RNG CHANNEL N44 Q3 1-MIN AVG Standard: Reviews P&L # 4 determines the quality codes are NOT acceptable for

• URE1541 CURRENT CHAN 2 AXIAL FLUX DIFF

• URE1542 CURRENT CHAN 3 AXIAL FLUX DIFF

• ANM0121M PWR RNG CHANNEL N42 Q2 1-MIN AVG

• ANM0122M PWR RNG CHANNEL N43 Q1 1-MIN AVG Notifies the CRS the AFD Monitor does NOT met the criteria for Operable status If necessary prompt the candidate to completed OST-1021, Evaluator Cue:

Attachment 5 as required.

Comment:

- Denotes a Critical Step 2020 NRC Admin Exam SRO A1-1 Rev FINAL

Appendix C Page 6 of 23 Form ES-C-1 PERFORMANCE INFORMATION OST-1021, Attachment 5, Page 2 of 3 Performance Step: 8 LOG current reading for the following instruments:

• NI-41C, PR 41 % FLUX

• NI-42C, PR 42 % FLUX

• NI-43C, PR 43 % FLUX

• NI-44C, PR 44 % FLUX Standard:

Locates JPM Cue sheet with attached MCB Indication images and logs current reading

• NI-41C, PR 41 % FLUX = 11% +/- 1%

• NI-42C, PR 42 % FLUX = 13% +/- 1%

• NI-43C, PR 43 % FLUX = 14% +/- 1%

• NI-44C, PR 44 % FLUX = 10% +/- 1%

Comment:

OST-1021, Attachment 5, Page 2 of 3 Performance Step: 9 DETERMINE and LOG Average (AVG) Reactor Power:

• NI-41B, PR 41 % POWER

• NI-42B, PR 42 % POWER

• NI-43B, PR 43 % POWER

• NI-44B, PR 44 % POWER Standard:

Locates JPM Cue sheet with attached MCB Indication images and logs current reading

• NI-41B, PR 41 % POWER = 90% +/- 1%

• NI-42B, PR 42 % POWER = 90% +/- 1%

• NI-43B, PR 43 % POWER = 90% +/- 1%

• NI-44B, PR 44 % POWER = 90% +/- 1%

Comment: Performs calculation to determine AVG Reactor Power and logs value on OST-1021 Attachment 5

- Denotes a Critical Step 2020 NRC Admin Exam SRO A1-1 Rev FINAL

Appendix C Page 7 of 23 Form ES-C-1 PERFORMANCE INFORMATION OST-1021, Attachment 5, Page 2 of 3 Performance Step: 10 DETERMINE and LOG AFD Lower limit:

Standard: Critical action is to determine required limit.

Locates Reactor Operating Data Manual and reviews Section 2.1, AFD Limits and determines the current Lower limits is:

-14.5% at 90% Reactor Power (+/- 1%)

Comment: May interpolate limit based on current power level OST-1021, Attachment 5, Page 2 of 3 Performance Step: 11 DETERMINE and LOG AFD Upper limit:

Standard: Critical action is to determine required limit.

Locates Reactor Operating Data Manual and reviews Section 2.1, AFD Limits and determines the current Upper limits is:

11.0% at 90% Reactor Power (+/- 1%)

Comment: May interpolate limit based on current power level OST-1021, Attachment 5, Page 2 of 3 Performance Step: 12 PERFORM evaluation of AFD limits Standard: Reviews current MCB readings and determines AFD Limits and determines two of four MCB indications are NOT within the curve for Acceptable Operation:

• NI-42C, PR 42 % FLUX = 13% +/- 1%

• NI-43C, PR 43 % FLUX = 14% +/- 1%

Notifies the CRS two of four MCB indications are NOT within the AFD curve for Acceptable Operation Comment: Must interpolate limit based on current power level

- Denotes a Critical Step 2020 NRC Admin Exam SRO A1-1 Rev FINAL

Appendix C Page 8 of 23 Form ES-C-1 PERFORMANCE INFORMATION Technical Specifications Performance Step: 13 OBTAIN AND EVALUATE TECHNICAL SPECIFICATIONS Standard: Obtains Technical Specifications and refers to LCO 3.2.1 Determines that ACTION a. is applicable. (See page 14)

a. With the indicated AFD outside of the limits specified in the COLR, either:

1. Restore the indicated AFD to within the limits specified in the COLR within 15 minutes, or (0915)

2. Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within 30 minutes (0930) and reduce the Power Range Neutron Flux - High Trip setpoints to less than or equal to 55% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. (1330)

After the candidate has determined the current values of Axial Flux Difference and its limits have been manually Evaluator Note: determined and performed a Technical Specification evaluation.

END OF JPM Current value of Axial Flux Difference has been manually Terminating Cue: determined and the Technical Specifications evaluation completed.

Stop Time: _________

- Denotes a Critical Step 2020 NRC Admin Exam SRO A1-1 Rev FINAL

Appendix C Page 9 of 23 Form ES-C-1 PERFORMANCE INFORMATION KEY

- Denotes a Critical Step 2020 NRC Admin Exam SRO A1-1 Rev FINAL

Appendix C Page 10 of 23 Form ES-C-1 PERFORMANCE INFORMATION KEY

- Denotes a Critical Step 2020 NRC Admin Exam SRO A1-1 Rev FINAL

Appendix C Page 11 of 23 Form ES-C-1 PERFORMANCE INFORMATION KEY

- Denotes a Critical Step 2020 NRC Admin Exam SRO A1-1 Rev FINAL

Appendix C Page 12 of 23 Form ES-C-1 PERFORMANCE INFORMATION KEY

- Denotes a Critical Step 2020 NRC Admin Exam SRO A1-1 Rev FINAL

Appendix C Page 13 of 23 Form ES-C-1 PERFORMANCE INFORMATION KEY AFD Lower AFD Upper Limit -14.5% Limit 11%

- Denotes a Critical Step 2020 NRC Admin Exam SRO A1-1 Rev FINAL

Appendix C Page 14 of 23 Form ES-C-1 PERFORMANCE INFORMATION KEY Upper AFD limit 11.0% at 90% Reactor Power (+/- 1%)

1. The current AFD Limits are Lower AFD limit 14.5% at 90% Reactor Power (+/- 1%)

Circle the correct response that applies:

2. AFD Monitor Alarm is Operable / Inoperable

3. Technical Specification(s) and applicable LCOs that apply a.1 0915 a.2 0930 a.2 1330

- Denotes a Critical Step 2020 NRC Admin Exam SRO A1-1 Rev FINAL

Appendix C Page 15 of 23 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2020 NRC Admin Exam SRO A1-1 Determine Axial Flux Difference (AFD) with AFD Monitor INOP and Evaluate Technical Specifications OP-163, ERFIS OST-1021, Daily Surveillance Requirements Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiners Signature: Date:

2020 NRC Admin Exam SRO A1-1 Rev FINAL

Appendix C Form ES-C-1 JPM CUE SHEET

• The plant was at 90% power, with a load reduction in progress Initial Conditions:

• The load reduction has been stopped to evaluate AFD following oscillations at 0900 With the information provided complete Attachment 5 of OST-1021, Daily Surveillance Requirements to determine Axial Flux Difference.

After completing OST-1021, Attachment 5 evaluate the results and circle the response below Initiating Cue:

IF any Technical Specifications apply list the associated LCO action(s) and the required completion time(s).

Base any action completion times from the time of 0900.

When complete return your results to the evaluator.

Name:

Date:

1. The current AFD Limits are UPPER LOWER Circle the correct response that applies:

2. AFD Monitor Alarm is Operable / Inoperable Technical Specification(s) and applicable LCO Action(s) that apply:

2020 NRC Admin Exam SRO A1-1 Rev FINAL

Appendix C Form ES-C-1 JPM CUE SHEET 2020 NRC Admin Exam SRO A1-1 Rev FINAL

Appendix C Form ES-C-1 JPM CUE SHEET 2020 NRC Admin Exam SRO A1-1 Rev FINAL

Appendix C Form ES-C-1 JPM CUE SHEET 2020 NRC Admin Exam SRO A1-1 Rev FINAL

Appendix C Form ES-C-1 JPM CUE SHEET 2020 NRC Admin Exam SRO A1-1 Rev FINAL

Appendix C Form ES-C-1 JPM CUE SHEET 2020 NRC Admin Exam SRO A1-1 Rev FINAL

Appendix C Form ES-C-1 JPM CUE SHEET Indications at 0900 2020 NRC Admin Exam SRO A1-1 Rev FINAL

Appendix C Form ES-C-1 JPM CUE SHEET Indications at 0900 2020 NRC Admin Exam SRO A1-1 Rev FINAL

Appendix C Page 1 of 12 Form ES-C-1 Worksheet Facility: Harris Nuclear Plant Task No.: 301079H401 Task

Title:

During a Loss of Shutdown Cooling, JPM No.: 2020 NRC Exam determine the time that the RCS will Admin JPM SRO A1-2 reach Core Boiling and Boil-Off K/A

Reference:

G2.1.20 RO 4.6 SRO 4.6 ALTERNATE PATH - NO Examinee: _________________________ NRC Examiner: _________________

Facility Evaluator: _________________________ Date: _________________

Method of testing:

Simulated Performance: Actual Performance: X Classroom X Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

The unit was operating at 100% power for the last 17 months.

On 10/31/20 at 0000 the plant was shut down for a refueling outage.

• While the Reactor cavity was being filled the A RHR pump tripped

• Motor repairs are not expected to be completed until 11/25/20

• The Reactor cavity fill was completed to the normal refueling levels

• No fuel has been moved due to problems with the Manipulator Crane Initial Conditions:

The current date and time is 11/20/20 at 1200

• The B RHR pump just tripped.

• Fuel remains in the vessel with LEVEL at the RV Flange

• SG primary manways are installed

• RCPs remain coupled

• Core exit thermocouples are rising; they are currently reading 105°F You are directed to determine:

1. The time to reach core boiling

2. Core boil-off time and

3. The action(s) required to maintain level and the associated band Initiating Cue:

Mark up your curves to indicate where you are determining these times.

Write your estimates of time to boil and time to boil-off and the required action(s) on the lines at the bottom of this page (below).

Calculate your times in hours and minutes 2020 NRC Exam Admin JPM SRO A1-2 Rev FINAL

Appendix C Page 2 of 12 Form ES-C-1 Worksheet Task Standard: Candidate obtains curves and correctly identifies the time to reach core boiling and core boil-off time Required Materials: Curve Book Straight Edge General

References:

AOP-020, Loss Of RCS Inventory Or Residual Heat Removal While Shutdown, Rev. 39 Curve H-X-8, RCS Boiling Curves From Mid Loop, Rev. 3 Curve H-X-9, RCS Boiling Curves At Vessel Flange, Rev. 3 Curve H-X-10, RCS Boiloff Curves From Mid Loop To TAF, Rev. 3 Curve H-X-11, RCS Boiloff Curves From Vessel Flange To TAF, Rev. 3 OR 2020 NRC Exam Frozen Procedures Folder Handout: JPM Cue Sheets pages 8 - 13 Time Critical Task: No Validation Time: 10 minutes PERFORMANCE CRITICAL STEP JUSTIFICATION STEP Step required in order to accurately determine time to boil using the Step 3 appropriate curve in order to determine the required actions in accordance with the appropriate plant procedure to maximize the available RCS inventory.

Step required in order to accurately determine time to boil-off using the Step 4 appropriate curve in order to determine the required actions in accordance with the appropriate plant procedure to maximize the available RCS inventory.

Step 5 Step required in order to determine the required actions in accordance with the appropriate plant procedure to maximize the available RCS inventory.

2020 NRC Exam Admin JPM SRO A1-2 Rev FINAL

Appendix C Page 3 of 12 Form ES-C-1 PERFORMANCE INFORMATION START TIME:

Performance Step: 1 OBTAIN CURVES NEEDED FOR CALCULATION (Curve Book will be provided to the candidate)

Standard: Refers to curves H-X-8 through H-X-11 Comment:

Performance Step: 2 Refers to provided data and determines that curve H-X-9 is required to calculate time to boil and curve H-X-11 is required to calculate boil-off time Standard: Reviews curves and determines which ones are appropriate to determine the time to boil and boil-off time Comment:

Performance Step: 3 Based on time since shutdown (10/31/20 - 11/20/20) 20 days 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> since shutdown and current RCS temperature of 105°F using curve H-X-9 determine time to boil.

(Interpolate 100°F - 125°F lines)

Standard: Reviews curve H-X-9 Determines that time to boil is ~30 minutes

(+ 2 minutes, 28 - 32 min is acceptable)

Comment:

2020 NRC Exam Admin JPM SRO A1-2 Rev FINAL

Appendix C Page 4 of 12 Form ES-C-1 PERFORMANCE INFORMATION Performance Step: 4 Based on time since shutdown (10/31/20 - 11/20/20) 20 days 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> since shutdown and current RCS temperature of 105°F using curve H-X-11 determine time to boil-off (Interpolate 100°F - 125°F lines)

Standard: Reviews curve H-X-11 Determines that time to boil-off is 4 hrs and 50 mins (4.8 hrs)

(+ 15 minutes) or (4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 35 minutes to 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 5 minutes)

Comment:

Performance Step: 5 Determine the action required to maintain level for the plant conditions Standard: Reviews AOP-020 Determines that the crew is required to REFER TO Table 1 below AND ADJUST CSIP flow to maintain level in accordance with current plant conditions.

Comment:

Terminating Cue: After completing the time to boil, time to boil-off calculation and determining the action required, the evaluation on this JPM is complete.

END OF JPM STOP TIME:

2020 NRC Exam Admin JPM SRO A1-2 Rev FINAL

Appendix C Page 5 of 12 Form ES-C-1 PERFORMANCE INFORMATION KEY Initial conditions: Reactor cavity filled for refueling without fuel movement due to Manipulator Crane problems. Core cooling is lost at 1200 and 20 days after shutdown. Core Exit Thermocouples are rising and are currently 105°F.

Estimated time to boiling onset will be approximately 30 minutes from the time of the loss of cooling event.

2020 NRC Exam Admin JPM SRO A1-2 Rev FINAL

Appendix C Page 6 of 12 Form ES-C-1 PERFORMANCE INFORMATION KEY Initial conditions: Reactor cavity filled for refueling without fuel movement due to Manipulator Crane problems. Core cooling is lost at 1200 and 20 days after shutdown. Core Exit Thermocouples are rising and are currently 105°F.

Estimated time to boil off will be approximately 4.9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> from the time of the loss of cooling event.

2020 NRC Exam Admin JPM SRO A1-2 Rev FINAL

Appendix C Page 7 of 12 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2020 NRC Exam Admin JPM SRO A1-2 During a Loss of Shutdown Cooling, determine the time that the RCS will reach Core Boiling, Boil-Off and Required Actions Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiners Signature: Date:

2020 NRC Exam Admin JPM SRO A1-2 Rev FINAL

Appendix C Form ES-C-1 JPM CUE SHEET The unit was operating at 100% power for the last 17 months.

On 10/31/20 at 0000 the plant was shut down for a refueling outage.

• While the Reactor cavity was being filled the A RHR pump tripped.

• Motor repairs are not expected to be completed until 11/25/20.

• The Reactor cavity fill was completed to the normal refueling levels

• No fuel has been moved due to problems with the Manipulator Crane Initial Conditions:

The current date and time is 11/20/20 at 1200

• The B RHR pump just tripped.

• Fuel remains in the vessel with LEVEL at the RV Flange

• SG primary manways are installed

• RCPs remain coupled

• Core exit thermocouples are rising; they are currently reading 105°F You are directed to determine:

1. The time to reach core boiling

2. Core boil-off time and

3. The action(s) required to maintain level and the associated band Initiating Cue:

Mark up your curves to indicate where you are determining these times.

Write your estimates of time to boil and time to boil-off and the required action(s) on the lines at the bottom of this page (below).

Calculate your times in hours and minutes Name ___________________________________________________________

Date __________

Record your calculations here and return your curves to the examiner:

TIME TO BOIL (hours / minutes) _________________________

TIME TO BOIL-OFF (hours / minutes) _____________________

REQUIRED ACTION(S) TO MAINTAIN LEVEL AND ASSOCIATED BAND ________

2020 NRC Exam Admin JPM SRO A1-2 Rev FINAL

Appendix C Form ES-C-1 JPM CUE SHEET 2020 NRC Exam Admin JPM SRO A1-2 Rev FINAL

Appendix C Form ES-C-1 JPM CUE SHEET 2020 NRC Exam Admin JPM SRO A1-2 Rev FINAL

Appendix C Form ES-C-1 JPM CUE SHEET 2020 NRC Exam Admin JPM SRO A1-2 Rev FINAL

Appendix C Form ES-C-1 JPM CUE SHEET 2020 NRC Exam Admin JPM SRO A1-2 Rev FINAL

Appendix C Page 1 of 7 Form ES-C-1 Worksheet Facility: Harris Nuclear Plant Task No.: 002001H201 Task

Title:

Review (for approval) a completed JPM No.: 2020 NRC Exam surveillance for PORV block valves Admin SRO JPM A2 and Evaluate Tech Specs K/A

Reference:

G 2.1.25 RO 3.7 SRO 4.1 ALTERNATE PATH - NO Examinee: _________________________ NRC Examiner: _________________

Facility Evaluator: _________________________ Date: _________________

Method of testing:

Simulated Performance: Actual Performance: X Classroom X Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

• Today is 11/19/20

• The unit is operating at 100% power

• PRZ PORV PCV-445B (1RC-116) has a failure in the SHUT circuit Initial Conditions:

• 1RC-115 has been closed and power is removed

• TS 3.4.4 Action b is in effect. LCOTR T-20-00431 has been initiated

• The control room crew has completed OST-1017, Pressurizer PORV Block Valve Full Stroke Test Quarterly Interval Modes 1-2-3-4 You are the CRS. Review the completed OST for approval. Identify ALL discrepancies and the required actions, if applicable.

Initiating Cue: IF any Technical Specifications apply list the associated LCO action(s) and the required completion time(s).

Base any action completion times from the time of 0900.

When complete return your results to the evaluator.

2020 NRC Admin Exam JPM SRO A2 Rev FINAL

Appendix C Page 2 of 7 Form ES-C-1 Worksheet Task Standard: Both errors and the correct Technical Specification actions identified.

Required Materials: None General

References:

OST-1017, Pressurizer PORV Block Valve Full Stroke Test Quarterly Interval Modes 1-2-3-4, Rev. 22 Handout: Completed OST-1017 with errors that align with the JPM content.

Time Critical Task: No Validation Time: 25 Minutes PERFORMANCE CRITICAL STEP JUSTIFICATION STEP There are 2 items that will make the surveillance UNSAT. Either of NOTE:

which when identified would require a performance retest.

The stopwatch is beyond the calibration date -all timing data collected with the use of this out of calibration device is non reliable therefore the Step 2 test is invalid until a satisfactory stop watch calibration check is performed.

The shut time for valve 1RC-113 has exceeded the limit - if not Step 3 identified an inoperable component could fail when needed to perform its intended action.

If the wrong Tech Spec Action is selected an LCO action could be Step 4 exceeded 2020 NRC Admin Exam JPM SRO A2 Rev FINAL

Appendix C Page 3 of 7 Form ES-C-1 PERFORMANCE INFORMATION START TIME:

Performance Step: 1 Obtain procedure.

Standard: Reviews Sections 3.0, 4.0, 5.0, 6.0.

Evaluator Cue: Provide handout for 2020 NRC Exam Admin JPM SRO A2.

Evaluator Note:

• The steps of reviewing the procedure can be completed in any order.

• There are two errors in the procedure. Only the errors are documented in the JPM.

Comment:

Performance Step: 2 Review the completed OST-1017.

Standard: Identifies Stopwatch beyond calibration date per Prerequisite

3.0.4. Comment

Performance Step: 3 Review the completed OST-1017.

Standard: Identifies SHUT time for 1RC-113 exceeds LIMITING VALUE,

() should be retest in accordance with Attachment 3 of OST-1017 or () declared Inoperable and an AR should be initiated.

Evaluator Cue: If a retest of 1RC-113 is determine inform the candidate the second stroke time results are the same as the first test.

Comment:

- Denotes Critical Steps 2020 NRC Admin Exam JPM SRO A2 Rev FINAL

Appendix C Page 4 of 7 Form ES-C-1 PERFORMANCE INFORMATION Performance Step: 4 Obtain and Evaluate Technical Specifications Standard: Obtains Technical Specifications and refers to LCO 3.4.4 Determines that ACTION c. is applicable (1000) and ACTION b.1 would become applicable as directed by ACTION c(2) once the associated PRZ PORV PCV-444B SB is declared Inoperable.

(Restore to PORV Block operable by 1000 on 11/22/20 or be in HSB by 1600 on 11/22/20 and HSD by 2200 on 11/22/20)

(See page 5)

After the candidate has identified the 2 errors in the procedure and performed a Technical Specification Evaluator Note: evaluation.

END OF JPM Current status of OST-1017 has been determined and the Terminating Cue:

Technical Specifications evaluation completed.

STOP TIME:

- Denotes Critical Steps 2020 NRC Admin Exam JPM SRO A2 Rev FINAL

Appendix C Page 5 of 7 Form ES-C-1 PERFORMANCE INFORMATION KEY

b. 1000 b.1 1000 on 11/22 Or HSB by 1600 HSD by 2200 c.1 1000 c.2 1000

- Denotes Critical Steps 2020 NRC Admin Exam JPM SRO A2 Rev FINAL

Appendix C Page 6 of 7 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2020 NRC Admin SRO JPM A2 Review (for approval) a completed surveillance procedure for PORV block valves. OST-1017 Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiners Signature: Date:

2020 NRC Admin Exam JPM SRO A2 Rev FINAL

Appendix C Page 7 of 7 Form ES-C-1 JPM CUE SHEET

• Today is 11/19/20

• The unit is operating at 100% power

• PRZ PORV PCV-445B (1RC-116) has a failure in the SHUT circuit Initial Conditions:

• 1RC-115 has been closed and power is removed

• TS 3.4.4 Action b is in effect. LCOTR T-20-00431 has been initiated

• The control room crew has completed OST-1017, Pressurizer PORV Block Valve Full Stroke Test Quarterly Interval Modes 1-2-3-4 You are the CRS. Review the completed OST for approval. Identify ALL discrepancies and the required actions, if applicable.

Initiating Cue: IF any Technical Specifications apply list the associated LCO action(s) and the maximum allowed completion time(s).

Base any action completion times from the time of 0900.

When complete return your results to the evaluator.

NAME: ___________________________________________

DATE: _____________________

IF discrepancies were identified from your review of OST-1017 list ALL of them on the lines below and any Technical Specification(s) along with the applicable LCO Action(s) that apply:

2020 NRC Admin Exam JPM SRO A2 Rev FINAL

Appendix C Page 1 of 11 Form ES-C-1 WORKSHEET Facility: Harris Nuclear Plant Task No.: 341021H102 Task

Title:

Review and complete Operations Actions JPM No.: 2020 NRC Exam of AP-545, Attachment 3,Section II. Pre- Admin JPM SRO A3 Entry Planning Actions K/A

Reference:

G.2.3.13 RO 3.4 SRO 3.8 ALTERNATE PATH - NO Examinee: ________________________ NRC Examiner: _________________

Facility Evaluator: ________________________ Date: ________

Method of testing:

Simulated Performance: Actual Performance: X Classroom X Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

The plant is operating at 100% power Initial Conditions: FIN is preparing AP-545, Attachment 3, RCB Entry Permit to identify the source of Containment sump in-leakage You are the WCC SRO and have been asked to complete the Operations Actions of the Attachment 3,Section II. Pre-Entry Actions, using the attached Information sheet. Note any problems or required actions in the spaces Initiating provided.

Cue:

When complete return your AP-545, Attachment 3 to the evaluator.

2020 NRC Exam Admin JPM SRO A3 Rev. 3

Appendix C Page 2 of 11 Form ES-C-1 WORKSHEET Task Standard: Completes the Operations portion of AP-545, Attachment 3,Section II.

Identifies the MIDS system is tagged out, the PAL is Operable, and but OST-1082 will be required to performed for the PAL.

Required Materials: None General

References:

AP-545, Containment Entries, Rev 61 OR 2020 NRC Exam Frozen Procedures Folder Handout: JPM Information Sheet Partially completed AP-545, Attachment 3 JPM Cue Sheet for LCOTR T-20-00346 and T-20-00311 Time Critical Task: No Validation Time: 15 minutes PERFORMANCE CRITICAL STEP JUSTIFICATION STEP Must ensure the MIDS system is tagged out to prevent inadvertent Step 2 exposure to a source of radiation that has not been evaluated during entry inside containment.

Must determine operability status for the PAL and the EAL to comply Step 3 with Technical Specifications Must determine surveillance requirements for the PAL and the EAL to Step 4 comply with Technical Specifications 2020 NRC Exam Admin JPM SRO A3 Rev. 3

Appendix C Page 3 of 11 Form ES-C-1 PERFORMANCE INFORMATION START TIME:

Performance Step: 1 Reviews AP-545, Attachment 3, Section I:Entry Description, for the completed RCB Entry Permit Standard: Ensures proper conditions, signatures/initials, entry location and may verify the current revision of the procedure Comment:

Performance Step: 2 Reviews AP-545, Attachment 3, Section II: Pre-Entry Planning Actions, Operations Actions, Establish a clearance for all Incore Detector movement Standard: Reviews information sheet and determines OPS-1-16-1050-MIDSCLEAR-1292 has been established to tag-out the MIDS system and document the information on AP-545, Attachment 3 on Sheet 2 of 4.

Comment:

Performance Step: 3 Reviews AP-545, Attachment 3, Section II: Pre-Entry Planning Actions, Operations Actions, Determine operability of entry location Standard: Reviews provided LCOTR information and Technical Specification 4.6.1.3 to determine the PAL is Operable based on the last performance of the surveillance for the door.

Documents the information on AP-545, Attachment 3 by checking the Operable box on Sheet 2 of 4.

Comment:

- Denotes Critical Steps 2020 NRC Exam Admin JPM SRO A3 Rev. 3

Appendix C Page 4 of 11 Form ES-C-1 PERFORMANCE INFORMATION Performance Step: 4 Reviews AP-545, Attachment 3, Section II: Pre-Entry Planning Actions, Operations Actions, Determine if TS surveillance requirement 4.6.1.3.b (OST-1082) is met for the door to be used for entry.

Standard: Reviews LCOTR information and Technical Specification 4.6.1.3 to determine the PAL is NOT WITHIN PERIODICITY and documents the information on AP-545, Attachment 3 by circling NOT WITHIN PERIODICITY on Sheet 2 of 4.

Documents that OST-1082 is required to be performed for the PAL on the JPM Cue sheet.

Comment:

Performance Step: 5 Reviews AP-545, Attachment 3, Section II: Pre-Entry Planning Actions, Operations Actions, Determine if TS surveillance requirement 4.6.1.3.b (OST-1082) is met for the door to be used for entry.

Standard: Reviews LCOTR information and Technical Specification 4.6.1.3 to determine the EAL is WITHIN PERIODICITY and documents the information on JPM cue sheet if OST-1082 is WITHIN PERIODICITY.

Comment:

Performance Step: 6 Reviews AP-545, Attachment 3, Section II: Pre-Entry Planning Actions, Operations Actions, Establish maximum cooling mode.

Standard: Reviews information sheet and determines Containment Cooling is in the Maximum Cooling Mode and initials AP-545, Attachment 3 on Sheet 2 of 4.

Comment:

- Denotes Critical Steps 2020 NRC Exam Admin JPM SRO A3 Rev. 3

Appendix C Page 5 of 11 Form ES-C-1 PERFORMANCE INFORMATION Performance Step: 7 Reviews AP-545, Attachment 3, Section II: Pre-Entry Planning Actions, Operations Actions, RCB elevator breaker operation.

Standard: Reviews information sheet and determines RCB elevator breaker operation is not required and initials action as N/A on AP-545, Attachment 3 on Sheet 2 of 4.

Comment:

Evaluator Note and When the procedure is returned: Evaluation on this JPM is Terminating Cue: complete.

STOP TIME:

- Denotes Critical Steps 2020 NRC Exam Admin JPM SRO A3 Rev. 3

Appendix C Page 6 of 11 Form ES-C-1 PERFORMANCE INFORMATION KEY

- Denotes Critical Steps 2020 NRC Exam Admin JPM SRO A3 Rev. 3

Appendix C Page 7 of 11 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2020 NRC Exam Admin JPM SRO A3 - Review and complete Operations Actions of AP-545, Attachment 3, RCB Entry Permit,Section II. Pre-Entry Planning Actions AP-545, Containment Entries, Attachment 3, RCB Entry Permit Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiners Signature: Date:

2020 NRC Exam Admin JPM SRO A3 Rev. 3

Appendix C Form ES-C-1 JPM CUE SHEET The plant is operating at 100% power Initial Conditions: FIN is preparing AP-545, Attachment 3, RCB Entry Permit to identify the source of Containment sump in-leakage You are the WCC SRO and have been asked to complete the Operations Actions of the Attachment 3 Section II. Pre-Entry Actions using the attached Information sheet. Note any problems or required actions in the spaces Initiating provided.

Cue:

When complete return your AP-545, Attachment 3 to the evaluator.

NAME ___________________________________________ DATE _____________________

IF any action(s) were identified in the review of AP-545 list them on the lines below 2020 NRC Exam Admin JPM SRO A3 Rev. 3

Appendix C Form ES-C-1 JPM CUE SHEET 2020 NRC JPM SRO A3 Information Sheet

• Reactor Power is 98%

• Entry Date: November 19, 2020

• Entry Time: 0900

• Containment Temperature: 97F

• Allowable Reactor Power Band: 97% to 100%

• Entry

Description:

CNMT Entry to look for CNMT sump in-leakage. Remote robots will be used inside the bio-shield

• Entry Type: Planned

• Entry RWO Lead: FIN SRO.

• Entry Location: PAL

• RCB Elevator Operation is not required

• Clearance OPS-1-16-1050- MIDSCLEAR-1292 is hanging

• Containment Fan Coolers are in Maximum Cooling mode in accordance with OP-169

• LCOTR T-20-00346 and T-20-00311 are provided 2020 NRC Exam Admin JPM SRO A3 Rev. 3

Appendix C Form ES-C-1 JPM CUE SHEET 2020 NRC Exam Admin JPM SRO A3 Rev. 3

Appendix C Form ES-C-1 JPM CUE SHEET 2020 NRC Exam Admin JPM SRO A3 Rev. 3

Appendix C Job Performance Measure Form ES-C-1 Worksheet

`Facility: Harris Nuclear Plant Task No.: 345001H602 Task

Title:

Classify an Event JPM No.: 2020 NRC Exam Admin JPM SRO A4 K/A

Reference:

G2.4.38 RO 2.4 SRO 4.4 ALTERNATE PATH - NO G2.4.41 RO 2.9 SRO 4.6 Examinee: _______________________ NRC Examiner: _________ _____

Facility Evaluator: _______________________ Date: _________________

Method of testing:

Simulated Performance: Actual Performance: X Classroom X Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate, discuss or perform, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

This is a TIME CRITICAL JPM.

Given the following plant conditions:

• A shutdown for refueling is underway

• RCS Temperature is 193°F Fuel movement is taking place in the Spent Fuel Pool (SFP) when the Bridge Crane operator noted that the pool water level is rapidly lowering.

The Control Room was notified and an AO was dispatched to investigate the possible leakage source.

• The SFP Area radiation monitors are all reading slightly <1.0 Initial Conditions: mr/hr The following occurs at 1115:

• A loss of offsite power occurs The time is now 1131:

• The leak was identified on the 'A' SFP suction strainer and is now isolated

• Offsite power has been restored

• Spent fuel pool A level is at 280.6' at AEP-2

• Several SFP Area radiation monitors have increased to 2.5 mr/hr 2020 NRC Exam Admin JPM SRO A4 Rev FINAL

Appendix C Job Performance Measure Form ES-C-1 Worksheet Evaluate the EAL Matrix and determine the HIGHEST classification required for these plant conditions.

Initiating Cue:

NOTE: DO NOT use SEC judgment.

Write out the HIGHEST EAL classification in blank provided then return your assessment page to the Evaluator.

Task Standard: Event classified as an Unusual Event (RU2.1) within 15 minutes.

Required Materials: None General

References:

CSD-EPHNP-0101-01, EAL Technical Basis Document, Rev 01 CSD-EPHNP-0101-02, EAL Matrix, Rev 00 OR 2020 NRC Exam Frozen Procedures Folder Handouts: CSD-EPHNP-0101-01, EAL Technical Basis Document, Rev 01 CSD-EPHNP-0101-02, EAL Matrix, Rev 00 Attached Initial Conditions Time Critical Task: YES - 15 minutes for classification.

Validation Time: 15 minutes for classification PERFORMANCE CRITICAL STEP JUSTIFICATION STEP Classification of the event is critical for determining State and County Step 2 notifications, public information notices, site information notices, and event reportability to the Nuclear Regulatory Commission.

Timely classification of the event is critical for determining State and Step 4 County notifications, public information notices, site information notices, and event reportability to the Nuclear Regulatory Commission.

2020 NRC Exam Admin JPM SRO A4 Rev FINAL

Appendix C Page 3 of 8 Form ES-C-1 PERFORMANCE INFORMATION Start Time for this portion of JPM begins when the Evaluator Cue:

individual has been briefed.

START TIME:

Performance Step: 1 OBTAINS EAL Technical Basis Document and EAL Matrix.

Standard : Obtains EAL Technical Basis Document and EAL Matrix.

Comments:

Performance Step: 2 Identify EAL Classification for events in progress Standard : The candidate should evaluate three potential classifications for these conditions at a minimum:

CU1.2 Unusual Event RCS water level cannot be monitored AND EITHER

- UNPLANNED increase in any Table C-1 sump or tank due to a loss of RCS inventory

- Visual observation of UNISOLABLE RCS leakage CU2.1 Unusual Event AC power capability, Table C-6, to emergency 6.9 KV buses 1A-SA and 1B-SB reduced to a single power source for 15 min. (Note 1)

AND Any additional single power source failure will result in loss of all AC power to SAFETY SYSTEMS RU2.1 Unusual Event is MET for these conditions UNPLANNED water level drop in the REFUELING PATHWAY as indicated by low water level alarm or indication (LI-01SF-5101A/LI-01SF-5102A/LI-01SF-5103A, LI-403 or RCS standpipe)

AND UNPLANNED rise in corresponding area radiation levels as indicated by any Table R-2 area radiation monitors Comments:

- Denotes Critical Steps 2020 NRC Exam Admin JPM SRO A4 Rev FINAL

Appendix C Page 4 of 8 Form ES-C-1 PERFORMANCE INFORMATION Performance Step: 3 Verify Classification Standard : Reviews EAL Technical Basis Document to verify classification Comments:

Performance Step: 4 Verify Classification Completion Time Standard : Stop minus start time less than or equal to 15 minutes Comments:

After the candidate returns this JPM Classification, Examiners Cue: document the stop time and then announce.

END of JPM.

STOP TIME:

START TIME STOP TIME Stop minus start time less than or equal to 15 minutes

- Denotes Critical Steps 2020 NRC Exam Admin JPM SRO A4 Rev FINAL

Appendix C Page 5 of 8 Form ES-C-1 PERFORMANCE INFORMATION

- Denotes Critical Steps 2020 NRC Exam Admin JPM SRO A4 Rev FINAL

Appendix C Page 6 of 8 Form ES-C-1 PERFORMANCE INFORMATION

- Denotes Critical Steps 2020 NRC Exam Admin JPM SRO A4 Rev FINAL

Appendix C Page 7 of 8 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2020 NRC Exam Admin JPM SRO A4 Classify an Event CSD-EPHNP-0101-01, EAL Technical Basis Document CSD-EPHNP-0101-02, EAL Matrix Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiners Signature: Date:

2020 NRC Exam Admin JPM SRO A4 Rev FINAL

Appendix C Form ES-C-1 JPM CUE SHEET This is a TIME CRITICAL JPM.

Given the following plant conditions:

• A shutdown for refueling is underway

• RCS Temperature is 193°F Fuel movement is taking place in the Spent Fuel Pool (SFP) when the Bridge Crane operator noted that the pool water level is rapidly lowering.

The Control Room was notified and an AO was dispatched to investigate the possible leakage source.

• The SFP Area radiation monitors are all reading slightly <1.0 Initial Conditions: mr/hr The following occurs at 1115:

• A loss of offsite power occurs The time is now 1131:

• The leak was identified on the 'A' SFP suction strainer and is now isolated

• Offsite power has been restored

• Spent fuel pool A level is at 280.6' at AEP-2

• Several SFP Area radiation monitors have increased to 2.5 mr/hr Evaluate the EAL Matrix and determine the HIGHEST classification required for these plant conditions.

Initiating Cue:

NOTE: DO NOT use SEC judgment.

Write out the HIGHEST EAL classification in blank provided then return your assessment page to the Evaluator.

Name:

Date:

Highest EAL Classification for the plant conditions:

2020 NRC Exam Admin JPM SRO A4 Rev FINAL