ML18239A448

302 Exam Final Items (ADAMS-2B)- Delay Release 2 Yrs

ML18239A448
Person / Time
Site:	Brunswick
Issue date:	08/27/2018
From:	NRC/RGN-II
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Download: ML18239A448 (146)

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Appendix 0 Scenario Outline Form ES-D-f Facility: Brunswick Scenario No.: NRC 2017 Retake I Op-Test No.: Ejfll Examiners: Dan Bacon Operators: ATC - Bill Jessup Initial Conditions:

A2X sequence at SteplO, Item 165.

GP-02 is complete up to step 6.3.46.

Permission for continuous withdrawal has been granted for the rods going from 12-48.

The 1A NSW pump is under clearance for planned maintenance.

Turnover ATC operator is to complete GP-1 0, A2X sequence, Step 10.

Critical Tasks: 1. Start DG3 or DG4 to re-energize E3 or E4 within 60 minutes of Loss of Offsite Power.

2. Close ADS Valve E before exceeding Pressure Suppression Pressure Event MaIf. Event Event No. No. Type* Description 1 n/a R Raise power using control rods Control Rod Over travel 2# RDO16M - ATC APP-A-05 (4-2), TS 3.1.3, IS. 3.1.6 HPCI Logic Bus A Auto Start Failure 3# ESO13F - ATC TS 3.5.1 LOOP 4a EEOO9F M RSP, AOP-36.1 DGOO4F DG3 trips 4b# DGOO5F c DG4 fail to start ESOO2F SRV Valve E Fails open with SRV E Tailpipe Rupture 5# CAO19F c RVCP, PCCP, AOP-30 (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, fM)ajor

1. Not used on previous two NRC Exams

Appendix 0 Scenario Outline Form ES-D-1 Event Event Description Summary The crew will raise power by withdrawing control rods in preparation for placing the Mode switch to RUN lAW GP-02. Rod withdrawal will commence at Step 10 item 165 (18-15 @ 12) of the A2X sequence lAW GP-1 0.

Event #2 will automatically trigger when CR 1 0-23 is withdrawn for Step 10 item 166 of A2X.

The ATC will respond to a control rod over-travel for Control Rod 10-23 lAW A-05 (4-2) ROD OVER TRAVEL and A-OS (3-2) ROD DRIFT. The CRS will evaluate IS 3.1.3. Condition C and 1.5. 3.1.6 Condition A. After the TS are 2 addressed the ATC will continue withdrawing rods in Step 10 of the A2X sequence.

The chief examiner can move to event #3 when satisfied with the number of Control Rod reactivity manipulations.

The ATC will respond to a blown HPCI logic power fuse lAW A-O1 (5-5) HPCI LOGIC BUS A PWR FAILURE. HPCI will be manually isolated per the APP.

3 The CRS will address T.S. 3.5.1 Condition D.

After HPCI is isolated and the applicable TS is addressed, the chief examiner can move to Event #4.

A Loss of Offsite Power and subsequent reactor scram on MSIV closure will occur. The CRS will direct entry into EOP-O1-RSP and AOP-36.1 .The crew 4a will perform scram immediate actions, maintain reactor pressure and level lAW RSP, and perform applicable AOP-36.1 actions.

Coincident with the LOOP and scram, DG3 will trip and DG4 will fail to start.

The crew will manually start DG4 and energize buses E4.

4b When scram immediate actions are complete and E4 is energized, the chief examiner may move to Event #5.

At the direction of the chief examiner, ADS SRV E will fail open with a tail pipe break. The CRS will direct entry into RVCP and PCCP based on Drywell pressure, and entry into AOP-30 for stuck open SRV E. The crew will perform 5 AOP-3O actions to close SRV E. CRS will direct Torus sprays based on Torus pressure.

When SRV E has been closed and RVCP and PCCP have been entered, the scenario may be terminated at the direction of the chief examiner.

BRUNSWICK TRAINING SECTION OPERATIONS TRAINING INITIAL LICENSED OPERATOR SIMULATOR EVALUATION GUIDE 2017-1 NRC SCENARIO 1 LOW POWER, PULL RODS, ROD OVERTRAVEL, HPCI LOGIC POWER LOSS,LOOP,DG FAILURES, STUCK OPEN SRV REVISION 0 Developer: Daniel Hulgin Date: 11/07/17 Technical Review: Bob Bolin Date: 11/07/17 Validators: Seth Roberts Date: 11/21/17 Anthony Fairweather Tom Baker Facility Representative: John Miller Date: 11/21/17

2017-1 NRC SCENARIO 1 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 2 of 76 REVISION

SUMMARY

0 Scenario developed for 2017-1 NRC Exam.

2017-1 NRC SCENARIO 1 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 3 of 76 TABLE OF CONTENTS 1.0 SCENARIO OUTLINE .................................................................................................................. 4 2.0 SCENARIO DESCRIPTION

SUMMARY

.................................................................................. 5 3.0 CREW CRITICAL TASKS ........................................................................................................... 6 4.0 TERMINATION CRITERIA .......................................................................................................... 7 5.0 IMPLEMENTING REFERENCES .............................................................................................. 7 6.0 SETUP INSTRUCTIONS ............................................................................................................. 8 7.0 INTERVENTIONS....................................................................................................................... 10 8.0 OPERATOR RESPONSE AND INSTRUCTIONAL STRATEGIES .................................... 12 ATTACHMENT 1 - Scenario Quantitative Attribute Assessment ..................................................... 61 ATTACHMENT 2 - Shift Turnover ........................................................................................................ 76

2017-1 NRC SCENARIO 1 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 4 of 76 1.0 SCENARIO OUTLINE Event Malf. No. Type* Event Description 1 n/a R Raise power using control rods Control Rod Over travel 2 RD016M C - ATC APP-A-05 (4-2), TS 3.1.3 HPCI Logic Bus A Auto Start Failure 3 ES013F C - ATC TS 3.5.1 LOOP 4a EE009F M RSP, AOP-36.1 DG004F DG3 trips 4b DG005F C DG4 fail to start ES002F ADS Valve E Fails open with SRV E Tailpipe Rupture 5 CA019F C RVCP, PCCP, AOP-30

• (N)ormal, (R)eactivity, (C)omponent or Instrument, (M)ajor, Critical (T)ask

2017-1 NRC SCENARIO 1 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 5 of 76 2.0 SCENARIO DESCRIPTION

SUMMARY

Event Description The crew will raise power by withdrawing control rods in preparation for placing the Mode switch to RUN IAW GP-02. Rod withdrawal will commence at Step 10 item 165 (18-15 @ 12) of the A2X sequence IAW GP-10.

1 Event #2 will automatically trigger when CR 10-23 is withdrawn for Step 10 item 166 of A2X.

The ATC will respond to a control rod over-travel for Control Rod 10-23 IAW A-05 (4-

2) ROD OVER TRAVEL and A-05 (3-2) ROD DRIFT. The CRS will evaluate TS 3.1.3.

Condition C and T.S. 3.1.6 Condition A. After the TS are addressed the ATC will 2 continue withdrawing rods in Step 10 of the A2X sequence.

The chief examiner can move to event #3 when satisfied with the number of Control Rod reactivity manipulations The ATC will respond to a blown HPCI logic power fuse IAW A-01 (5-5) HPCI LOGIC BUS A PWR FAILURE. HPCI will be manually isolated per the APP. The CRS will address T.S. 3.5.1 Condition D.

3 After HPCI is isolated and the applicable TS is addressed, the chief examiner can move to Event #4.

A Loss of Offsite Power and subsequent reactor scram on MSIV closure will occur.

The CRS will direct entry into EOP-01-RSP and AOP-36.1.The crew will perform 4a scram immediate actions, maintain reactor pressure and level IAW RSP, and perform applicable AOP-36.1 actions.

Coincident with the LOOP and scram, DG3 will trip and DG4 will fail to start. The crew will manually start DG4 and energize buses E4.

4b When scram immediate actions are complete and E4 is energized, the chief examiner may move to Event #5.

At the direction of the chief examiner, ADS SRV E will fail open with a tail pipe break.

The CRS will direct entry into RVCP and PCCP based on Drywell pressure, and entry into AOP-30 for stuck open SRV E. The crew will perform AOP-30 actions to close SRV E. The CRS will direct Torus sprays based on Torus pressure.

5 When SRV E has been closed and RVCP and PCCP have been entered, the scenario may be terminated at the direction of the chief examiner.

2017-1 NRC SCENARIO 1 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 6 of 76 3.0 CREW CRITICAL TASKS Critical Task #1 Start DG4 to re-energize E4 within 60 minutes of Loss of Offsite Power.

Critical Task #2 Close ADS Valve E before exceeding Pressure Suppression Pressure

2017-1 NRC SCENARIO 1 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 7 of 76 4.0 TERMINATION CRITERIA When SRV E has been closed and RVCP and PCCP have been entered, the scenario may be terminated at the direction of the chief examiner.

5.0 IMPLEMENTING REFERENCES NOTE: Refer to the most current revision of each Implementing Reference.

Number Title 2APP-A-01 (5-5) HPCI Logic Bus A Pwr Failure 2APP-A-05 (3-2) Rod Drift 2APP-A-05 (4-2) Rod Over Travel 0AOP-02.0 Control Rod Malfunction/Misposition 0AOP-30.0 Safety/Relief Valve Failures 0AOP-36.1 Loss of Any 4160V Buses Or 480V E-Buses 0GP-02 Approach To Criticality And Pressurization Of The Reactor 0GP-10 Rod Sequence Checkoff Sheets 2OP-07 Reactor Manual Control System Operating Procedure 2OP-19 High Pressure Coolant Injection System Operating Procedure 2EOP-01-RSP Reactor Scram Procedure 2EOP-01-RVCP Reactor Vessel Control Procedure 0EOP-02-PCCP Primary Containment Control Procedure 0EOP-01-SEP-02 Drywell Spray Procedure 0EOP-01-SEP-03 Torus Spray Procedure T.S. 3.1.3 Control Rod OPERABILITY T.S. 3.1.6 Rod Pattern Control T.S. 3.5.1 ECCSOperating

2017-1 NRC SCENARIO 1 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 8 of 76 6.0 SETUP INSTRUCTIONS

1. PERFORM TAP-409, Miscellaneous Simulator Training Guidelines, Attachment 5, Checklist for Simulator Exam Security.

2. RESET the Simulator to IC-06.

3. ENSURE the RWM is set up as required for the selected IC.

4. ENSURE appropriate keys have blanks in switches.

5. RESET alarms on SJAE, MSL, and RWM NUMACs.

6. ENSURE no rods are bypassed in the RWM.

7. PLACE all SPDS displays to the Critical Plant Variable display (#100).

8. ENSURE hard cards and flow charts are cleaned up

9. TAKE the SIMULATOR OUT OF FREEZE

10. LOAD Scenario File.

11. ALIGN the plant as follows:

Manipulation

1. Insert control rods through Step 164 of GP-10, Sequence A2X is completed.

2. Verify level is stable

3. Verify drive water pressure is at 260 psid.

12. IF desired, take a SNAPSHOT and save into an available IC for later use.

13. PLACE a clearance on the following equipment.

Component Position None N/A

14. INSTALL Protected Equipment signage and UPDATE RTGB placard as follows:

Protected Equipment 2A/2B NSW pumps for 1A NSW planned maintenance

15. VERIFY 0ENP 24.5 Form 2 (Immediate Power Reduction Form) for IC-10 is in place.

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16. ENSURE each Implementing References listed in Section 5 is intact and free of marks.

17. ENSURE all materials in the table below are in place and marked-up to the step identified.

Required Materials 0GP-02 up to Step 6.3.46 (excluding step 42) (mark step 47 complete) 0GP-10 up to step 10 item 165

18. ADVANCE the recorders to prevent examinees from seeing relevant scenario details.

19. PROVIDE Shift Briefing sheet for the CRS.

20. VERIFY all actions contained in TAP-409, Miscellaneous Simulator Training Guidelines, Attachment 4, Simulator Training Instructor Checklist, are complete.

2017-1 NRC SCENARIO 1 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 10 of 76 7.0 INTERVENTIONS TRIGGERS Trig Type ID 1 Malfunction ES013F - [HPCI LOGIC BUS A AUTO START FAILS]

1 Malfunction ES014F - [INADVERTANT HPCI SYS INITIATION]

2 Remote Function HP_ZVHP041M - [SUPP SUCTION VLV E41-F041]

3 Remote Function HP_ZVHP042M - [TORUS SUCTION VLV E41-F042]

4 Malfunction EE009F - [LOSS OF OFF-SITE POWER]

5 Malfunction DG026F - [DG3 DIFFERENTIAL FAULT]

6 Remote Function SW_IAVSW193 - [SW-V193 MAN ISOL NSW TO RBCCW]

6 Remote Function SW_VHSW146L - [CONV SW TO RBCCW HXS V146]

7 Remote Function RP_IAEPAMGA - [RPS M-G SET A EPA BKRS]

7 Remote Function RP_IARPSA - [RESTART RPS MG SET A]

8 Remote Function RP_IAEPAMGB - [RPS M-G SET B EPA BKRS]

8 Remote Function RP_IARPSB - [RESTART RPS MG SET B]

9 Remote Function ED_ZIEDH08 - [PNL 2AB PWR (E7=NORM/E8=ALT)]

9 Remote Function ED_ZIEDH11 - [PNL 2AB-RX PWR (E7=NORM/E8=ALT)]

9 Remote Function ED_ZIEDHX0 - [PNL 32AB PWR (E7=NORM/E8=ALT)]

10 Malfunction ES002F - [ADS VALVE E FAILS OPEN]

10 Malfunction CA019F - [SRV E TAIL PIPE RUPTURE]

Trig # Trigger Text 5 Q4F06DG8 - [LOADED (RED) DG-3]

MALFUNCTIONS Malf Mult Current Target Rmp Description Actime Dactime Trig ID ID Value Value time RD016M 10-23 CONTROL ROD UNCOUPLED True True ES013F HPCI LOGIC BUS A AUTO START FAILS False True 1 ES014F INADVERTANT HPCI SYS INITIATION False True 00:00:02 1 DG005F DG4 AUTO START FAILURE True True EE009F LOSS OF OFF-SITE POWER False True 4 DG026F DG3 DIFFERENTIAL FAULT False True 00:00:10 5 ES002F ADS VALVE E FAILS OPEN False True 10 CA019F SRV E TAIL PIPE RUPTURE False True 10

2017-1 NRC SCENARIO 1 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 11 of 76 REMOTES Mult Current Target Rmp Remf Id Description Actime Trig Id Value Value time HP_ZVHP041M SUPP SUCTION VLV E41-F041 ON OFF 2 HP_ZVHP042M TORUS SUCTION VLV E41-F042 ON OFF 3 SW_VHSW146L CONV SW TO RBCCW HXS V146 SHUT OPEN 6 RP_IARPSA RESTART RPS MG SET A NORMAL RESET 7 RP_IAEPAMGA RPS M-G SET A EPA BKRS SET SET 00:00:05 7 RP_IARPSB RESTART RPS MG SET B NORMAL RESET 8 RP_IAEPAMGB RPS M-G SET B EPA BKRS SET SET 00:00:05 8 SW_IAVSW193 SW-V193 MAN ISOL NSW TO RBCCW OPEN CLOSE 6 ED_ZIEDH08 PNL 2AB PWR (E7=NORM/E8=ALT) NORMAL ALT 00:00:30 9 ED_ZIEDH11 PNL 2AB-RX PWR (E7=NORM/E8=ALT) NORMAL ALT 00:02:30 9 ED_ZIEDHX0 PNL 32AB PWR (E7=NORM/E8=ALT) NORMAL ALT 00:04:00 9 PANEL OVERRIDES Position / Actual Override Rmp Tag ID Description Actime Dactime Trig Target Value Value time ANNUNCIATORS Override Window Description Tagname OVal AVal Actime Dactime Trig Type

2017-1 NRC SCENARIO 1 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 12 of 76 8.0 OPERATOR RESPONSE AND INSTRUCTIONAL STRATEGIES EVENT 1/2: RAISE POWER USING CONTROL RODS/ROD OVERTRAVEL Simulator Operator Actions Ensure Monitored Parameters is open and Scenario Based Testing Variables are loaded.

While withdrawing control rods, ENSURE RD016M IS ACTIVE when Control Rod 10-23 is withdrawn to position 48 (uncoupled control rod)

When control rod 10-23 has been fully inserted, DELETE over travel RD016M to allow resetting of the ROD DRIFT alarm.

Simulator Operator Role Play If asked as the RE:

Continuous rod withdrawal is allowed.

Will perform second check of rod movements (GP-11) after rod is bypassed.

If contacted as I&C acknowledge the request.

If contacted as the WCC SRO to disarm CR, acknowledge the request.

If necessary and at the direction of the Chief examiner, after CR 10-23 has been fully inserted, notify CRS as SM to continue raising reactor power IAW GP-02.

Evaluator Notes Plant Response: The crew will continue raising power by pulling control rods in preparation for placing the Mode switch to RUN. Rod pulls will commence at Sequence A2X Step 165 (18-15

@ 12). While withdrawing control rod 10-23 to position 48, Four rod group display shows dark window for rod which has over traveled. "ROD DRIFT" indication on full core display for rod 10-23. ROD DRIFT (A-05 3-2) in alarm. ROD OVERTRAVEL (A-05 4-2) in alarm.

Objectives: SRO - Directs and monitor reactor power ascension with control rods.

Directs OATC to address applicable APPs.

Evaluate TS 3.1.3 Condition C.

RO - Raise reactor power using control rods.

Diagnose uncoupled control rod, and respond IAW A-05 (03-2), and (4-2).

BOP - Monitor balance of plant Success Path: Controls Rods are withdrawn to raise reactor power. For uncoupled control rod, fully insert rod 10-23 and reset ROD DRIFT alarm. Evaluate Tech Spec 3.1.3 Control Rod Operability.

Event Termination: Go to Event 3 when the chief examiner is satisfied with the number of CR withdrawals.

2017-1 NRC SCENARIO 1 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 13 of 76 EVENT 1/2: RAISE POWER USING CONTROL RODS/ROD OVERTRAVEL Time Pos EXPECTED Operator Response NOTES May conduct a brief (see Enclosure 1 on page 61 for SRO format)

Directs RO to raise reactor power by withdrawing control rods IAW 0GP-10 Item 10 Step 165.

(Continuous withdrawal allowed)

Direct RO to perform/reference APPs (A-05 3-2 and A-05 4-2).

May direct entry into AOP-2.0, Control Rod Malfunction/Misposition.

Direct I&C to investigate Contacts RE Evaluate Tech Spec:

3.1.3 Control Rod Operability

• Condition C. One or more control rods inoperable for reasons other than Condition A or B

o Required Action C.1 Fully insert control rod (3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />)

• AND o Required Action C.2 Disarm the associated CRD(4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />)

2017-1 NRC SCENARIO 1 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 14 of 76 EVENT 1/2: RAISE POWER USING CONTROL RODS/ROD OVERTRAVEL Time Pos EXPECTED Operator Response NOTES 3.1.6 Rod Pattern Control

• Condition A One or more OPERABLE control rods not in compliance with BPWS o Required Action A.1 (NOTE) Control rod may be bypassed in the rod worth minimizer (RWM) or RWM may be bypassed as allowed by LCO 3.3.2.1, "Control Rod Block Instrumentation." Move associated control rod(s) to correct position.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> OR SRO o Required Action A.2 Declare associated control rod(s) inoperable.

8 Hours 3.3.2.1 control Rod Block Instrumentation

• Condition C. Rod worth minimizer (RWM) inoperable during reactor startup o Verify movement of bypassed control rod(s) is in compliance with banked position withdrawal sequence (BPWS) by a second licensed operator or other qualified member of the technical staff.

SRO Direct RO to fully insert CR 10-23 to Full In May contact WCC SRO to have CR 10-23 SRO disarmed and for Caution Tag.

May direct RO to bypass CR10-23 in the RWM SRO IAW 2OP-07. (Must bypass to perform step 11 item 171)

Directs RO to continue raising power with SRO Control Rods.

2017-1 NRC SCENARIO 1 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 15 of 76 EVENT 1/2: RAISE POWER USING CONTROL RODS/ROD OVERTRAVEL Time Pos EXPECTED Operator Response NOTES BOP Monitors Plant ATC Commence rod withdrawal at step 165 of GP-10 Stops withdrawing control rods when Control ATC Rod Overtravel alarm is received Respond to ROD OVERTRAVEL (A-05 4-2)

ATC alarm when rod 10-23 exceeds 48 ATC Verify ROD DRIFT alarm Fully insert CR 10-23 when directed ATC by SRO and reset ROD DRIFT alarm.

If directed, Bypasses CR 10-23 in RWM.

ATC Notifies RE of bypassing rod.

Re-commences rod withdrawal at step 167 of ATC GP-10 with RE as second verifier

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2017-1 NRC SCENARIO 1 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 33 of 76 EVENT 3: HPCI LOGIC BUS A AUTO START FAILURE Simulator Operator Actions When directed by lead evaluator, INITIATE TRIGGER 1 ES013F to activate HPCI fuse failure.

If requested to open breakers for E41-F041 and F042 (MCC 2XDA) when valves are shut, monitor valve positions on panel mimic (P601 Section A2).

At direction of RO, when E41-F041 indicates closed, OPEN BREAKER (TRG 2 HP_ZVHP041M).

At direction of RO, when E41-F042 indicates closed, OPEN BREAKER (TRG 3 HP_ZVHP042M).

Simulator Operator Role Play If asked as AO to investigate, report all circuit breakers in DC SWBD 2A & Panel 4A are closed If asked as I&C to investigate, wait 2 minutes and report fuse E41-F1 in panel P620 is blown (blows again if replaced).

If asked as WCC SRO for clearance or Equipment Control tags, acknowledge request.

If requested to open breakers for E41-F041 and F042 (MCC 2XDA) when valves are shut, monitor valve positions on panel mimic (P601 Section A2). (Triggers 3 and 4).

Evaluator Notes Plant Response: The HPCI logic power fuse will blow requiring HPCI to be manually isolated per the APP and declared Inoperable per TS 3.5.1.

Objectives: SRO - Directs OATC to address applicable APPs.

Evaluate TS 3.5.1 Condition D RO - Diagnose logic failure, and respond IAW A-01 (5-5)

BOP - Monitor balance of plant Success Path: HPCI declared inoperable IAW TS 3.5.1 and isolated IAW A-01 (5-5)

Event Termination: Once HPCI is isolated with TSs addressed or upon Chief Examiner direction if the applicant elects not to pursue TSs at this time, the Chief Examiner can move to Event 4.

2017-1 NRC SCENARIO 1 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 34 of 76 EVENT 3: HPCI LOGIC BUS A AUTO START FAILURE Time Pos EXPECTED Operator Response Comments SRO Direct annunciator response for A-1 (5-5) and (6-4)

Determines depressurization of steam supply is SRO NOT required Contacts I&C to investigate HPCI LOGIC BUS A SRO PWR FAILURE 3.5.1 ECCS Operating:

CONDITION D: HPCI system inoperable REQUIRED ACTION:

D.1 Verify by administrative means RCIC System is OPERABLE.

Immediately AND SRO D.2. Restore HPCI System to OPERABLE status.

TRM 3.6 Bus Power Monitors:

Condition A - Verify bus power availability to the system's logic in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

Condition B - Declare associated supported equipment inoperable.

May request equipment control tags to support SRO abnormal HPCI system alignment.

May conduct a brief SRO (see Enclosure 1 on page 63 for format)

2017-1 NRC SCENARIO 1 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 35 of 76 EVENT 3: HPCI LOGIC BUS A AUTO START FAILURE Time Pos EXPECTED Operator Response Comments Acknowledge and report annunciators A-1 (5-5)

ATC and (6-4)

May report HPCI Suction is aligned to both the ATC CST and Suppression Pool.

Performs A-1 (5-5) actions:

1. Close the Condensate Storage Tank Suction Valve, E41-F004.

2. Isolate the HPCI Steam Supply per OP-19, Section 6.3.5.

1) CLOSE STEAM SUPPLY INBOARD ISOL VLV, E41-F002.

2) CLOSE STEAM SUPPLY OUTBOARD ATC ISOL VLV, E41-F003.

Continues A-1 (5-5) actions:

3. Close the Turbine Exhaust Vacuum Breaker Valve, E41-F075.

Contacts RBAO to standby for opening breakers on MCC 2XDA when the following valves indicate Full Closed.

4. Close the Torus Suction Valve, E41-F041.

5. Close the Torus Suction Valve, E41-F042.

ATC/ Verifies RCIC in standby lineup (Administratively operable)

BOP BOP Monitors Plant

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2017-1 NRC SCENARIO 1 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 43 of 76 EVENT 4a/4b: : LOOP / SCRAM / DG FAILURES Simulator Operator Actions At the discretion of the lead evaluator, Initiate Trigger 4 (EE009F) to active the LOOP.

If directed to align RBCCW to CSW cooling, wait 4 minutes and Initiate Trigger 6.

If directed to restart RPS MG sets, wait 3 minutes and insert the following as requested: For RPS A Initiate Trigger 7 and/or for RPS B Initiate Trigger 8 If directed to transfer AB panels, Initiate Trigger 9 Simulator Operator Role Play If requested to monitor DGs, acknowledge alarms on DG local Alarm Panel If directed to align RBCCW to CSW cooling, wait 4 minutes and inform Sim Operator to align RBCCW to CSW cooling then report valve open.

If directed to restart RPS MG sets, wait 3 minutes and inform Sim Operator to restart RPS then report actions complete.

If directed as RBAO to ensure BFIV latching mechanisms are disengaged, wait two minutes, then report latches are disengaged.

If contacted for cross-tying E7 to E8 provide permission and acknowledge request for racking in breakers.

Evaluator Notes Plant Response: The crew will respond to a Loss of Offsite Power. The reactor will scram on MSIV closure on the LOOP. DG4 will fail to auto start on the LOOP signal. The BOP operator will start DG4 to energize Buses E4. ATC will perform scram immediate actions and RSP.

Objectives: SRO - Enter and direct actions of RSP Direct entry into AOP3-6.1 RO - Perform scram IAs and actions in RSP BOP - Start DG4 and energize E4 Perform actions in AOP-36.1 Success Path: Scram immediate operator actions are complete and E4 is energized.

Event Termination: When Scram immediate actions are complete and E4 is energized, and at the direction of the Chief examiner got to event 5.

2017-1 NRC SCENARIO 1 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 44 of 76 EVENT 4a/4b: : LOOP / SCRAM / DG FAILURES Time Pos EXPECTED Operator Response Comments Enters and directs actions of RSP.

SRO Direct pressure band Direct water level band May choose to enter and direct actions of SRO RVCP (due to no method of pressure control at this time.)

SRO Direct AOP-36.1 entry SRO Calls WCC for UAT back feed Contacts Maintenance for failure of DG3 and SRO DG4 to auto start.

May perform a brief (see enclosure 1 on page SRO 61 for format.

Announces reactor scram and performs scram ATC IAs.

Performs actions for RSP as directed:

ATC/BOP Maintains established reactor level and pressure bands.

Recognizes and reports trip of DG3 on ATC/BOP Differential Overcurrent Recognizes and reports failure of DG4 to start, ATC/BOP CRITICAL TASK #1 manually starts DG4 and energizes E4

2017-1 NRC SCENARIO 1 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 45 of 76 EVENT 4a/4b: : LOOP / SCRAM / DG FAILURES Time Pos EXPECTED Operator Response Comments Performs AOP 36.1 Actions:

• Dispatch AO to monitor DGs

• Ensures pneumatics to DW

• Aligns 230Kv PCBs ATC/BOP

• Calls for UAT back feed

• Transfer RCC to conventional header

• Directs transfer to alternate power for 2AB, 32AB, and 2AB-RX.

• Directs start of RPS MG set

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2017-1 NRC SCENARIO 1 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 58 of 76 EVENT 5: SRV E FAILURE WITH SRV TAIL PIPE RUPTURE Simulator Operator Actions At the direction of the Lead, INITIATE TRIGGER 10 to fail SRV E (ES002F) and to rupture the SRV E tailpipe (CA019F)

When the SRV is cycled by the operator, delete ES002F When directed by the Lead Evaluator, place the simulator in FREEZE DO NOT RESET THE SIMULATOR PRIOR TO RECEIPT OF CONCURRENCE TO DO SO FROM THE LEAD EXAMINER Simulator Operator Role Play If contacted as I&C about SRV E failure, acknowledge the request Evaluator Notes Plant Response: SRV E will fail open with an SRV E tailpipe rupture pressurizing containment. AOP-30, PCCP, and RVCP will be entered. The SRV will reset using the control switch.

Objectives: SRO - Direct entry into AOP30.0. Direct entry and actions of RVCP and PCCP.

ROs - Perform RVCP and PCCP actions as directed by the CRS. Perform 0AOP-30.0 actions to close SRV E.

Success Path: AOP-30.0 Immediate Actions will close the SRV, and Torus sprays will reduce containment pressure.

Scenario Termination: When SRV E is closed and PCCP and RVCP have been entered, the Chief Examiner can terminate this scenario.

Remind students not to erase any charts and not to discuss the scenario until told to do so by the evaluator/instructor.

2017-1 NRC SCENARIO 1 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 59 of 76 EVENT 5: SRV E FAILURE WITH SRV TAIL PIPE BREAK Time Pos EXPECTED Operator Response Comments Directs enter and announce AOP30.0 and for SRO RO to perform immediate actions to close CRITICAL TASK #2 SRV E.

Enters PCCP and if not already entered, enters SRO RVCP.

Directs Torus sprays IAW EOP-01-SEP-03 SRO (See enclosure 2 on pages 62-64)

Directs Drywell sprays IAW EOP-01-SEP-02 when/if Suppression Chamber exceeds 11.5 SRO psig (See enclosure 3 on page 65-71)

Directs torus cooling when/if torus temperature reaches 95°F SRO (See enclosure 4 on page 72-73)

2017-1 NRC SCENARIO 1 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 60 of 76 EVENT 5: SRV E FAILURE WITH SRV TAIL PIPE BREAK Diagnoses and reports SRV E failure and ATC/BOP rising drywell pressure.

Announces and enters 0AOP-30.0.

ATC/BOP CRITICAL TASK #2

• Cycles control switch for stuck open E SRV.

Maintains reactor level and pressure as ATC/BOP directed by the CRS When directed by the CRS, places Torus ATC/BOP Sprays in service.

(Enclosure 2, Pages 62-64)

If directed by the CRS, places Drywell ATC/BOP Sprays in service.

(Enclosure 3, Pages 65-71)

If directed by the CRS, places Torus Cooling in service.

ATC/BOP (Enclosure 4, Pages 72-73)

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2017-1 NRC SCENARIO 1 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 75 of 76 ATTACHMENT 1 - Scenario Quantitative Attribute Assessment Scenario written for evaluation of the ATC position only.

Category Standard Scenario Content Total Malfunctions 5-8 5 Malfunctions after EOP 1-2 2 Entry Abnormal Events 2-4 2 Major Transients 1-2 1 EOPs Used 1-2 2 EOP Contingency 1-2 1 Run Time 60-90 min 60 Crew Critical Tasks >2 2 Tech Specs 2 2 Instrument / Component 2 - ATC 2 - ATC Failures before Major 2 - BOP 0 - BOP Instrument / Component 2 2 Failures after Major Normal Operations 1 0 Reactivity manipulation 1 1

LOI SIMULATOR EVALUATION GUIDE Page 76 of 76 ATTACHMENT 2 - Shift Turnover Brunswick Unit 2 Plant Status Station Duty Workweek J. Pierce D. Hunter Manager: Manager:

Mode: 2 Rx Power: 2%

Plant Risk:

Green Current EOOS Risk Assessment is:

SFP Time to 35.7 hrs Days Online: 0 days 200 Deg F:

IAW the reactivity plan the OATC is to raise power to 6-10%.

A2X sequence at step 165.

Turnover: Permission for continuous withdrawal has been granted for the rods going from 12-48.

The 1A NSW pump is under clearance for planned maintenance.

Protected 2A/2B NSW pumps for 1A NSW planned maintenance.

Equipment:

0GP-02, Approach to Criticality and Pressurization of the Reactor, is Comments:

complete up to step 6.3.46

Appendix D Scenario Outline Form ES-D-1 Facility: Brunswick Scenario No.: NRC 2017 Retake 2 Op-Test No.: Final Examiners: Dan Bacon Operators: CRS Bill Jessup Initial Conditions:

At 100% power.

1A NSW Pump is under clearance for planned maintenance.

SRV B is inoperable.

Turnover Complete Quarterly PT-07.2.4B, Core Spray Pump Loop B operability.

Critical Tasks: 1. Isolate RCIC or Insert a manual reactor scram prior to exceeding Max Safe Operating Temperature Limit.

2. Inhibit ADS prior to teaching LL3.

3. Insert control rods lAW LEP-02.

Event Maif. No. Event Event No. Type* Description 1# n/a N Perform Quarterly PT-07.2.4B, Core Spray Pump Loop B operability Core Spray Pump B Overload 2# ESO8OF - ATC 15 3.5.1 cS_VHCSO Torus High Water Level 3# 2AD - ATC APP-A-01 (3-7), OP-17, AOP-14 RCIC Isolable Steam Leak 4 ESO25F C - ATC AOP-5.0, TS 3.5.3 MSO31F MTLO Controller Failure 5# MSO17F BOP Main Turbine High Vibrations Scram/A1WS 6# RPOIOF M RSP, A1WS, LEP-02 RWCU Isolation Failure

1. RWO16F SL_IASLRA Both SLC Pumps Trip SL_IASLRB c LEP-03 CRD FCV Failure

1. RDO17F c (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor

1. Not used on previous two NRC Exams

Appendix D Scenario Outline Form ES-D-1 Event Event Description Summary The Unit will be operating at rated power with 1A NSW Pump under clearance for planned maintenance and SRV B inoperable. Quarterly OPT-07.2.4B, Core 1 Spray Pump Loop B operability is in progress and completed up to Step 7.4 (Pump Testing). The ATC operator will perform OPT-07.2.4B, Core Spray Pump Loop B operability flow test.

After flow is established, the pump overload will alarm requiring the 2B CS 2

pump to be tripped and Tech Specs addressed Torus water level will rise, the crew will pump the torus to radwaste lAW OAOP 14.0 I OP-17.

A break in the RCIC steam line in the south RHR room will occur. The break 4 can be isolated by closing either the E51 -F007 or the E51 -F008. The crew will respond to the steam leak lAW AOP-05.0.

Main Turbine Temperature Controller will fail closed and Turbine Lube Oil will heat up. The rising Lube Oil temperature will result in high Turbine Vibration.

Vibration will approach the TSl setpoint requiring a manual scram and the turbine to be tripped.

Most control rods will fail to insert on the scram. The crew will respond per OEOP-01-ATWS.

RWCU will fail to isolate when SLC pumps are started.

When SLC initiation is attempted, both SLC pumps will trip. The crew will enter 6 LEP-03 and align for alternate boron injection using CRD.

The CRD flow control valve will fail closed preventing control rod insertion with RMCS. The other sections of LEP-02 will be utilized to insert control rods.

Once the crew has inserted all control rods in accordance with LEP-02 the Chief Examiner can terminate this scenario.

BRUNSWICK TRAINING SECTION OPERATIONS TRAINING INITIAL LICENSED OPERATOR SIMULATOR EVALUATION GUIDE 2017-1 NRC SCENARIO 2 CS PT, CS B OVERLOAD, TORUS HI LEVEL, RCIC STEAM LEAK, MTLO CONTROLLER FAILURE, TURBINE HI VIBS, ATWS, RWCU ISOLATION FAILURE, SLC BLOCKAGE, CRD FCV FAILURE REVISION 0 Developer: NRC - Bob Bolin Date: 11/07/2017 Technical Review: Dan Hulgin Date: 11/07/2017 Validators: Seth Roberts Date: 11/21/17 Anthony Fairweather Tom Baker Facility Representative: John Miller Date: 11/21/17

2017-1 NRC SCENARIO 2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 2 of 66 REVISION

SUMMARY

0 NRC developed scenario for the 2017-1 NRC Exam.

2017-1 NRC SCENARIO 2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 3 of 66 TABLE OF CONTENTS 1.0 SCENARIO OUTLINE .................................................................................................................. 4 2.0 SCENARIO DESCRIPTION

SUMMARY

.................................................................................. 5 3.0 CREW CRITICAL TASKS ........................................................................................................... 6 4.0 TERMINATION CRITERIA .......................................................................................................... 6 5.0 IMPLEMENTING REFERENCES .............................................................................................. 7 6.0 SETUP INSTRUCTIONS ............................................................................................................. 8 7.0 INTERVENTIONS....................................................................................................................... 10 8.0 OPERATOR RESPONSE AND INSTRUCTIONAL STRATEGIES .................................... 12 ATTACHMENT 1 - Scenario Quantitative Attribute Assessment ..................................................... 49 ATTACHMENT 2 - Shift Turnover ........................................................................................................ 66

2017-1 NRC SCENARIO 2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 4 of 66 1.0 SCENARIO OUTLINE Event Malf. No. Type* Event Description 1 n/a N Perform Quarterly PT-07.2.4B, Core Spray Pump Loop B operability 2 ES080F C - BOP Core Spray Pump B Overload TS 3.5.1 CS_VHCS0 Torus High Water Level 3 2AD C - ATC APP-A-01 (3-7), OP-17, AOP-14 4 ES025F C - ATC RCIC Isolable Steam Leak AOP-5.0, TS 3.5.3 MS031F MTLO Controller Failure 5 MS017F BOP Main Turbine High Vibrations Scram RP0010F RSP 6 M ATWS ATWS, LEP-02 RW016F C RWCU Isolation Failure SL_IASLRA Both SLC Pumps Trip SL_AISLRB C LEP-03 RD017F C CRD FCV Failure

• (N)ormal, (R)eactivity, (C)omponent or Instrument, (M)ajor, Critical (T)ask

2017-1 NRC SCENARIO 2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 5 of 66 2.0 SCENARIO DESCRIPTION

SUMMARY

Event Description The Unit will be operating at rated power with 1A NSW Pump under clearance for planned maintenance and SRV B inoperable. Quarterly 0PT-07.2.4B, Core Spray 1 Pump Loop B operability is in progress and completed up to Step 7.4 (Pump Testing).

The ATC operator will perform 0PT-07.2.4B, Core Spray Pump Loop B operability flow test.

After flow is established, the pump overload will alarm requiring the 2B CS pump to be 2

tripped and Tech Specs addressed Torus water level will rise, the crew will pump the torus to radwaste IAW AOP-14 / OP-3 17.

A break in the RCIC steam line in the south RHR room will occur. The break can be 4 isolated by closing either the E51-F007 or the E51-F008. The crew will respond to the steam leak IAW AOP-05.0.

Main Turbine Temperature Controller will fail closed and Turbine Lube Oil will heat up.

5 The rising Lube Oil temperature will result in high Turbine Vibration. Vibration will approach the TSI setpoint requiring a manual scram and the turbine to be tripped.

Most control rods will fail to insert on the scram. The crew will respond per 0EOP ATWS.

RWCU will fail to isolate when SLC pumps are started.

6 When SLC initiation is attempted, both SLC pumps trip. The crew will enter LEP-03 and align for alternate boron injection using CRD.

The CRD flow control valve will fail closed preventing control rod insertion with RMCS.

The other sections of LEP-02 will be utilized to insert control rods. .

2017-1 NRC SCENARIO 2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 6 of 66 3.0 CREW CRITICAL TASKS Critical Task #1 Isolate RCIC or Insert a manual reactor scram prior to exceeding Max Safe Operating Temperature Limit.

Critical Task #2 Inhibit ADS prior to reaching LL3.

Critical Task #3 Insert control rods IAW LEP-02.

4.0 TERMINATION CRITERIA Once the crew has inserted all control rods in accordance with LEP-02 the Chief Examiner can terminate this scenario.

2017-1 NRC SCENARIO 2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 7 of 66 5.0 IMPLEMENTING REFERENCES NOTE: Refer to the most current revision of each Implementing Reference.

Number Title A-01 (3-7) Suppression Chamber Lvl Hi/Lo A-03 (6-7) Core Spray Pump 2B Overload UA-18 (6-1) Bus E4 4KV Motor Ovld UA-05 (1-9) Fan Clg Unit CS Pump Rm A Inl Press Lo UA-05 (2-9) Fan Clg Unit CS Pump Rm B Inl Press Lo UA-03 (2-7) Area Rad Rx Bldg High UA-03 (4-5) Process Rx Bldg Vent Rad High UA-03 (3-5) Process Rx Bldg Vent Rad Hi-Hi UA-05 (6-10) Rx Bldg Isolated UA-23 (1-6) Turb or RFP Brg Temp High UA-23 (6-1) Turbine Vibrations High 2OP-16 Reactor Core Isolation Cooling System Operating Procedure 2OP-17 Residual Heat Removal System Operating Procedure 0PT-07.2.4B Core Spray System Operability Test - Loop B 0AOP-05.0 Radioactive Spills, High Radiation, And Airborne Activity 0AOP-14.0 Abnormal Primary Containment Conditions 2EOP-01-RSP Reactor Scram Procedure 2EOP-01-ATWS ATWS Procedure 0EOP-01-LEP-02 Alternate Control Rod Insertion 0EOP-01-LEP-03 Alternate Boron Injection

2017-1 NRC SCENARIO 2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 8 of 66 6.0 SETUP INSTRUCTIONS

1. PERFORM TAP-409, Miscellaneous Simulator Training Guidelines, Attachment 5, Checklist for Simulator Exam Security.

2. RESET the Simulator to IC-13.

3. ENSURE the RWM is set up as required for the selected IC.

4. ENSURE appropriate keys have blanks in switches.

5. RESET alarms on SJAE, MSL, and RWM NUMACs.

6. ENSURE no rods are bypassed in the RWM.

7. PLACE all SPDS displays to the Critical Plant Variable display (#100).

8. ENSURE hard cards and flow charts are cleaned up

9. TAKE the SIMULATOR OUT OF FREEZE

10. LOAD Scenario File.

11. ALIGN the plant as follows:

Manipulation Ensure the calibration date for the stopwatch is valid.

12. IF desired, take a SNAPSHOT and save into an available IC for later use.

13. PLACE a clearance on the following equipment.

Component Position SRV B Red Cap

14. INSTALL Protected Equipment signage and UPDATE RTGB placard as follows:

Protected Equipment 2A/B NSW Pumps due to 1A NSW pump maintenance

15. ENSURE each Implementing References listed in Section 7 is intact and free of marks.

2017-1 NRC SCENARIO 2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 9 of 66

16. ENSURE all materials in the table below are in place and marked-up to the step identified.

Required Materials Quarterly 0PT-07.2.4B, Core Spray System Operability Test - Loop B completed up to Step 7.4 (Pump Testing).

17. ADVANCE the recorders to prevent examinees from seeing relevant scenario details.

18. PROVIDE Shift Briefing sheet for the CRS.

19. VERIFY all actions contained in TAP-409, Miscellaneous Simulator Training Guidelines, Attachment 4, Simulator Training Instructor Checklist, are complete.

2017-1 NRC SCENARIO 2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 10 of 66 7.0 INTERVENTIONS TRIGGERS Trig Type ID 1 Malfunction ES080F - [CORE SPRAY PUMP MOTOR OVERLOAD]

2 Remote Function ED_IABKCF06 - [BKR CTL DC FUSES CORE SPRAY PUMP 2B]

3 Remote Function CS_VHCS02BD - [CS LOOP B CST SUCT VALVE (0:1)]

4 Remote Function RH_ZBRH049T - [E11-F049 RHR TO RAD WASTE]

5 Malfunction ES025F - [RCIC STM BRK - SOUTH RHR]

6 Malfunction MS031F - [MTLO TEMP CNTRLR FAILS]

7 Malfunction MS017F - [TURBINE BEARING VIBRATION]

7 Malfunction MS017F - [TURBINE BEARING VIBRATION]

7 Malfunction MS017F - [TURBINE BEARING VIBRATION]

8 Remote Function EP_IAEOPJP1 - [BYPASS LL-3 GROUP I ISOL (SEP-10)]

9 Malfunction RP005F - [AUTO SCRAM DEFEAT]

10 Remote Function EP_IACS993P - [DW CLR A & D OVERIDE - NORMAL/STOP]

10 Remote Function EP_IACS994P - [DW CLR B & C OVERIDE - NORMAL/STOP]

11 Malfunction RD017F - [CRD FCV FAILS CLOSED]

12 Remote Function SL_IASLRA - [2A SLC PUMP MOTOR BKR]

12 Remote Function SL_IASLRB - [2B SLC PUMP MOTOR BKR]

Trig # Trigger Text 7 ZUA2316 - [TURB OR RFP BRG TEMP HIGH]

11 K2501PP7 - [RX SCRAM A]

12 !K2119NWD - Not [S/B LIQ PUMP A & B]

2017-1 NRC SCENARIO 2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 11 of 66 MALFUNCTIONS Malf Mult Curren Target Rmp Description Actime Dactime Trig ID ID t Value Value time ES080F B CORE SPRAY PUMP MOTOR OVERLOAD False True 1 ES025F RCIC STM BRK - SOUTH RHR 0.00 5.000000 00:10:00 5 MS031F MTLO TEMP CNTRLR FAILS False True 6 MS017F 3 TURBINE BEARING VIBRATION 0.00 8.000000 00:05:00 7 MS017F 2 TURBINE BEARING VIBRATION 0.00 7.000000 00:05:00 7 MS017F 4 TURBINE BEARING VIBRATION 0.00 6.000000 00:05:00 7 RP005F AUTO SCRAM DEFEAT False True 9 RW016F G31-F004 FAILURE TO AUTO CLOSE True True RP010F ATWS 3 True True RD017F FCV A CRD FCV FAILS CLOSED False True 11 REMOTES Current Target Rmp Remf Id Mult Id Description Actime Trig Value Value time ED_IABKCF06 BKR CTL DC FUSES CORE SPRAY PUMP 2B IN OUT 2 CS_VHCS02BD CS LOOP B CST SUCT VALVE (0:1) 0 0.5000 3 RH_ZBRH049T E11-F049 RHR TO RAD WASTE OFF ON 4 EP_IAEOPJP1 BYPASS LL-3 GROUP I ISOL (SEP-10) OFF ON 8 EP_IACS993P DW CLR A & D OVERIDE - NORMAL/STOP NORMAL STOP 10 EP_IACS994P DW CLR B & C OVERIDE - NORMAL/STOP NORMAL STOP 10 SL_IASLRA 2A SLC PUMP MOTOR BKR CLOSE OPEN 0:00:01 12 SL_IASLRB 2B SLC PUMP MOTOR BKR CLOSE OPEN 0:00:05 12 ANNUNCIATORS Override Window Description Tagname OVal AVal Actime Dactime Trig Type PANEL OVERRIDES Position / Actual Override Rmp Tag ID Description Actime Dactime Trig Target Value Value time Q2206LGO MAN INJ GREEN ON/OFF ON OFF Q2206RRO MAN INJ RED ON/OFF ON ON Q1506LGJ SRV VLV B21-F013B GREEN ON/OFF ON OFF Q1506RRJ SRV VLV B21-F013B RED ON/OFF OFF OFF Q1518SA9 AMBER LED +5V ON/OFF OFF OFF

2017-1 NRC SCENARIO 2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 12 of 66 8.0 OPERATOR RESPONSE AND INSTRUCTIONAL STRATEGIES EVENT 1/2: CORE SPRAY PT / PUMP OVERLOAD Simulator Operator Actions Ensure Monitored Parameters is open and Scenario Based Testing Variables are loaded.

Initiate Trigger 1 when 2B CS pump is started and flow is being raised.

If asked to place clearance on CS 2B Pump, Initiate Trigger 2 to pull control power fuses.

Simulator Operator Role Play When asked, as RBAO report CS suction pressure is 6 psig, lubricant level is normal, and you are stationed to monitor system piping When requested, report SW-V123 is open (Room Cooler SW valve)

When requested to slowly open E21-V5002 (E21-PI-7119B Instrument Isolation Valve), report that the valve is open.

If asked, as outside AO report:

51 device on B phase showing target at pump breaker on E4 (if pump did not auto trip) 51 device on all 3 phases showing target at pump breaker on E4 (if pump did auto trip)

If asked as I&C to investigate, acknowledge the request.

If asked as RBAO or Maintenance to perform a visual inspection of CS Pump 2B, wait 2 minutes and report there is no visual damage to the pump.

If asked to place clearance on CS 2B Pump, wait 3 minutes then inform Sim Operator to initiate trigger 2 and inform control room when complete.

Evaluator Notes Plant Response: Core Spray Pump B Overload alarms, pump does not trip (should not for B phase overload).

Objectives: SRO - Direct actions for the performance of Core Spray B quarterly test BOP - Perform Core Spray B quarterly test Success Path: Complete performance of 0PT-07.2.4B, Section 7.4.

Event Termination: Go to Event 3 at the discretion of the lead evaluator.

2017-1 NRC SCENARIO 2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 13 of 66 EVENT 1/2: CORE SPRAY PT / PUMP OVERLOAD Time Pos EXPECTED Operator Response Comments CRS Conduct shift turnover shift briefing.

CRS Direct continuation of PT-07.2.4B.

Direct core spray B be tripped after overload CRS alarm is received or Direct to take the actions of the APPs.

CRS Direct I&C to investigate.

Refer to Tech Spec 3.5.1:

Required Action CRS A.1 Restore low pressure ECCS injection/spray subsystem to OPERABLE status within 7 Days.

BOP Monitors the plant

2017-1 NRC SCENARIO 2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 14 of 66 EVENT 1/2: CORE SPRAY PT / PUMP OVERLOAD Perform Core Spray System Operability Test IAW PT-07.2.4B Perform PT-07.2.4B, Section 7.4.

Direct an AO to perform step 1 Performs steps 2 through 5.

ATC Ensure an operator is stationed to perform pump check, and to obtain motor current (at E4). (steps 6 through 8)

Makes a PA announcement for starting 2B Core Spray Pump. Should also check that Bus E4 is clear of personnel Performs steps 9 through 15 Acknowledge and report:

ATC A-03 (6-6) CORE SPRAY PUMP 2B OVERLOAD UA-18 (6-1) BUS E4 4KV MOTOR OVLD ATC Return Core Spray to standby alignment

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2017-1 NRC SCENARIO 2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 20 of 66 EVENT 3: Torus High Water Level Simulator Operator Actions When directed to begin event 4, Insert Trigger 3 (THIS TAKES ~ 4 MINUTES BEFORE THE ALARM AT -27 COMES IN)

When contacted to turn on breaker for E11-F049 (RHR TO RADWASTE INBD ISOL VALVE),

wait 1 minute then Initiate Trigger 4 When contacted to turn off breaker for E11-F049 (RHR TO RADWASTE INBD ISOL VALVE),

wait 1 minute then Modify Remote Function: RH_ZBRH049T, OFF Simulator Operator Role Play If asked to investigate, wait until after suppression chamber level is >-27, then report flow noise past valve E21-F002B (CORE SPRAY PUMP SUCTION VALVE FROM THE CST), it may not be seated correctly. If directed to close the E21-F002B, then report closed, Delete Remote Function CS_ VHCS02BD, 0.5 If asked to check CST level locally, report the same level as control room indication.

If contacted as Radwaste about draining the torus, acknowledge the communication. After 1 minute report access control has been established.

If contacted as Radwaste, report adequate capacity exists in the aux Surge tank or waste surge tank.

If contacted as E&C about transfer to the aux surge tank, the 10Ci limit will not be exceeded.

If contacted as Radwaste to monitor tank levels, acknowledge the communication.

If contacted as AO to perform fill and vent of piping, report that it is complete IAW 2OP-17 Section 6.3.1.

Evaluator Notes Plant Response: Torus level will rise until the E21-F002B is manually shut. HPCI Pump suction is swapped to the Suppression Pool by opening the normally closed Suppression Pool Suction Valves, E41-F042 and E41-F041 at -25 in the torus.

Objectives: CRS- Direct entry into AOP-14.0 (PCCP when level >-27).

Evaluate tech specs if level gets >-27.

ATC- respond to high level in the torus, and pump the torus to Radwaste IAW OP-17 .

Success Path: The crew will direct the closure of the E21-F002B, and pump the torus to Radwaste IAW OP-17.

Event Termination: Go to Event 4 after draining has been established or at the direction of the Lead Evaluator.

2017-1 NRC SCENARIO 2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 21 of 66 EVENT 3: Torus High Water Level Time Pos EXPECTED Operator Response Comments Direct Entry into 0AOP-14.0 (ABNORMAL CRS PRIMARY CONTAINMENT CONDITIONS) for high suppression pool level.

When level >-27, direct entry into 0EOP CRS PCCP (PRIMARY CONTAINMENT CONTROL PROCEDURE).

Direct suppression pool be lowered by pumping CRS to Radwaste per OP-17 When >-27, Tech Spec 3.6.2.2 (Suppression CRS Pool Water Level) and determine condition A applies (2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> completion time).

BOP Monitor plant parameters during evolution Recognize and report rising torus level.

ATC If > -27.75 inches respond to APP A-01 (3-7)

If >-25 inches verifies HPCI suction swap Enter and announce 0AOP-14.0 (Abnormal ATC Primary Containment Conditions).

ATC Dispatch AOs to locate source of in-leakage to torus.

Direct AO to attempt to seat the E21-F002B ATC (Core Spray Pump Suction Valve from the CST)

ATC Pump the torus to radwaste IAW OP-17.

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2017-1 NRC SCENARIO 2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 29 of 66 EVENT 4: RCIC ISOLABLE STEAM LEAK Simulator Operator Actions At the direction of the Lead Evaluator, Initiate Trigger 5 to initiate a RCIC steam leak.

(Increase as necessary to have room temperatures slowly rising until system is isolated)

Simulator Operator Role Play After the initial alarms for the steam leak are received, report as RB AO steam is blowing out of the -17 foot in South RHR room and you are leaving the building.

If contacted as I&C to investigate, acknowledge the request.

If contacted to close 2-FP-PIV33, Unit 2 Reactor Building Sprinkler Shutoff Valve, wait three minutes and report that the valve is closed.

If contacted as HPs, acknowledge any request.

If asked, cameras show observable steam leak on RCIC.

Evaluator Notes Plant Response: A break in the RCIC steam line in the south RHR room will occur. The break can be isolated. If the system is delayed from being isolated, observe temperatures in the Reactor Building (specifically South RHR Room temperature), before any area exceeds MSOTL, a Reactor Manual Scram should be inserted. The RCIC system should be declared inoperable and Tech Specs entered.

Objectives: SRO - Determine RCIC should be isolated and actions required for LCO per Technical Specifications RO - Respond to an isolable RCIC steam line break.

Success Path: Evaluate Tech Specs to determine required actions as outlined in SRO actions below.

Event Termination: Go to Event 5 at the direction of the Lead Evaluator.

2017-1 NRC SCENARIO 2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 30 of 66 EVENT 4: RCIC ISOLABLE STEAM LEAK Time Pos EXPECTED Operator Response Comments CRS Diagnose RCIC leak and direct RCIC isolation CRITICAL TASK #1 CRS May direct entry into 0AOP-05.0 CRS May direct reactor building evacuated Contact maintenance about the RCIC steam CRS leak Refers to Tech Spec 3.5.3 RCIC System and determines:

CONDITION A. RCIC System inoperable.

REQUIRED ACTION:

CRS A.1 Verify by administrative means HPCI System is OPERABLE.

Immediately AND A.2. Restore RCIC System to OPERABLE status.

14 days May conduct a brief CRS (see Enclosure 1 on page 49 for format)

BOP Monitors the plant May announce and enter AOP-05.

May direct AO to close 2-FP-PIV33.

BOP May look at ARMs and report which ones are reading high.

2017-1 NRC SCENARIO 2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 31 of 66 EVENT 4: RCIC ISOLABLE STEAM LEAK Time Pos EXPECTED Operator Response Comments Respond to alarms:

UA-05 1-9, Fan Clg Unit CS Pump Rm A Inl Press Lo ATC UA-05 2-9, Fan Clg Unit CS Pump Rm B Inl or Press Lo BOP UA-03 2-7, Area Rad Rx Bldg High UA-03 4-5, Process Rx Bldg Vent Rad High UA-03 3-5, Process Rx Bldg Vent Rad Hi-Hi UA-05 6-10, Rx Bldg Isolated ATC Verifies Service Water aligned to the Vital or Header (the SW-V111 or SW-V117 open).

BOP Isolate RCIC by closing either isolation CRITICAL TASK #1 valve:

ATC E51-F007 (Steam Supply Inboard Isol Vlv) and/or E51-F008 (Steam Supply Outboard Isol Vlv)

May reference procedure 2OP-16, Section ATC 6.3.4.

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2017-1 NRC SCENARIO 2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 40 of 66 EVENT 5: MTLO CONTROLLER FAILURE / MAIN TURBINE HI VIBS / SCRAM Simulator Operator Actions At the direction of the Lead Evaluator, Initiate Trigger 6 to activate the Main Turbine Lube Oil Controller failure closed and cause turbine vibrations to rise.

Verify turbine vibrations on 2, 3, and 4 begin to rise after receiving UA-23 1-6.

Simulator Operator Role Play If asked as the TB AO to investigate, report that the temperature control valve to the MTLO is closed. (There is no bypass valve).

If asked as I&C to investigate, acknowledge the request Evaluator Notes Plant Response: Main Turbine lube oil cooler controller fails closed. When high temperature alarm annunciates activate trigger to accelerate turbine vibrations.

Objectives: SRO -Direct action in response to an abnormal turbine vibration per UA-23 6-1 and UA-23 6-3 RO - Respond to an abnormal turbine vibration per UA-23 6-1 and UA-23 6-3.

Success Path: Reactor Scram and Turbine trip when vibrations reach setpoint IAW APPs.

Event Termination: Go to Event 6 at the direction of the Lead Evaluator.

2017-1 NRC SCENARIO 2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 41 of 66 EVENT 5: MTLO CONTROLLER FAILURE / MAIN TURBINE HI VIBS / SCRAM Time Pos EXPECTED Operator Response Comments Acknowledge report of APPs.

CRS UA-23 1-6 Turb or RFP Brg Temp High UA-23 6-1 Turbine Vibration High When vibrations rise to above the TSI setpoint, direct manual scram and turbine trip per the vibration APP CRS (12 mils on bearings 1-8, 10 mils on bearings 9-10)

(As conservative decision making may insert before setpoint).

May direct breaking condenser vacuum after the CRS turbine is tripped.

May conduct a brief on when Reactor Scram is CRS required (see Enclosure 1 on page 49 for format)

ATC Plant Monitoring When directed by the CRS

1. Inserts a manual reactor scram.

ATC

2. Trips the main turbine.

ATC Recognize and report an ATWS.

2017-1 NRC SCENARIO 2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 42 of 66 EVENT 5: MTLO CONTROLLER FAILURE / MAIN TURBINE HI VIBS / SCRAM Time Pos EXPECTED Operator Response Comments Recognize and report rising lube oil BOP temperatures.

BOP Dispatch TB AO to investigate TCV.

Perform actions of APPs UA-23 1-6 Turb or RFP Brg Temp High UA-23 6-1 Turbine Vibration High If vibration is at or above 12 mils on bearings 1-BOP 8 or 10 mils on bearings 9 & 10 and an adjacent bearing has also exhibited a significant increase in vibration, then perform the following:

(1) SCRAM the reactor (2) Trip the turbine (3) If directed by the Unit CRS, break condenser vacuum.

Monitor turbine bearing temperatures and BOP vibrations (PC display 630)

May place the Main Turbine Lube Oil controller BOP in manual and attempt to operate the valve.

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2017-1 NRC SCENARIO 2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 46 of 66 EVENT 6: ATWS / RWCU FAILURE / SLC FAILURE / CRD FCV FAILURE Simulator Operator Actions If requested to defeat Group I LL3, wait 2 minutes, and install jumpers Initiate Trigger 8 If requested to install LEP-02, Section 2.3 jumpers, wait 5 minutes and Initiate Trigger 9 and then inform the CRS that the jumpers are installed If requested to defeat Drywell Cooler LOCA Lockout, wait three minutes and Initiate Trigger 10 to install the jumpers.

When RPS is reset and 2-A-7 (5-1) is clear then delete ATWS03 Simulator Operator Role Play Acknowledge any request for I&C to investigate failures.

Evaluator Notes Plant Response: Most control rods will fail to insert on the scram. The crew will respond to the ATWS per EOP-01-ATWS. When SLC initiation is attempted, both SLC pumps will trip. The crew will enter LEP-03 and align for alternate boron injection using CRD. The crew will insert rods IAW LEP-02.

Objectives: SRO - Direct actions to control reactor power per EOP-01-ATWS..

RO - Perform actions for an ATWS per EOP-01-ATWS.

Success Path: Insert control rods IAW LEP-02.

Scenario Termination: When all rods are inserted the scenario may be terminated.

Remind students not to erase any charts and not to discuss the scenario until told to do so by the evaluator/instructor.

2017-1 NRC SCENARIO 2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 47 of 66 EVENT 6: ATWS / RWCU FAILURE / SLC FAILURE / CRD FCV FAILURE Time Pos EXPECTED Operator Response Comments Enter RSP and transition to ATWS.

Direct Main Turbine Tripped Direct mode switch to shutdown when steam flow < 3 Mlbs/hr.

Direct ARI initiation.

CRS Direct Recirc Pumps Tripped.

Direct SLC initiation, then LEP-03.

Direct ADS inhibited. CRITICAL TASK #2 Direct RWCU isolation.

Direct LEP-02, Alternate Rod Insertion CRITICAL TASK #3 CRS Direct Group 10 switches to override reset.

Contact I/C to investigate failures:

SLC pump trips CRS RWCU Isolation CRD FCV If power is greater than 2%, direct terminate and CRS prevent HPCI/Feedwater (CS/RHR if a LOCA signal received) to lower level to 90 inches.

When level reaches 90 inches, evaluate Table Q-2 (will not be met with MSIVs open):

If not met, establishes a level band of LL4 to +90 CRS inches.

If met, direct injection established to maintain RPV level LL4 to TAF (or the level at which APRMs indicate downscale)

2017-1 NRC SCENARIO 2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 48 of 66 EVENT 6: ATWS / RWCU FAILURE / SLC FAILURE / CRD FCV FAILURE Time Pos EXPECTED Operator Response Comments Performs Scram Hard Card (See Enclosure 2 (page 50)

RO Defeats Group 10 Isolation Trips main turbine when directed by CRS RO Inhibit ADS Critical Task #2 Performs LEP-02, Reset RPS and Insert Critical Task #3 manual scram. (See Enclosure 5, page 54)

RO Determines RMCS wont work as the CRD FCV is failed closed and report to CRS.

Informs CRS when all rods are inserted.

Determines that RWCU Isolation did not occur upon initiation of SLC, Isolates RWCU, Reports to CRS.

RO Determines SLC pumps have tripped and report to CRS.

Directs AO actions for LEP-03, Alternate Boron Injection.

Terminates and prevents injection from:

RO HPCI (see Enclosure 3, page 51).

Feedwater (see Enclosure 4, page 52).

When APRMs are downscale, maintain reactor water level as directed by CRS.

RO (See Enclosure 6 for re-aligning and starting Feedwater, page 62)

RO Maintains reactor pressure as directed by CRS

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2017-1 NRC SCENARIO 2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 65 of 66 ATTACHMENT 1 - Scenario Quantitative Attribute Assessment Scenario written for evaluation of the CRS position only.

Category Standard Scenario Content Total Malfunctions 5-8 8 Malfunctions after EOP 1-2 3 Entry Abnormal Events 2-4 2 Major Transients 1-2 1 EOPs Used 1-2 2 EOP Contingency 1-2 2 Run Time 60-90 min 60 Crew Critical Tasks >2 3 Tech Specs 2 2 Instrument / Component 2 - OATC 3 - OATC Failures before Major 2 - BOP 0 - BOP Instrument / Component 2 3 Failures after Major Normal Operations 1 1 Reactivity manipulation 1 0

LOI SIMULATOR EVALUATION GUIDE Page 66 of 66 ATTACHMENT 2 - Shift Turnover Brunswick Unit 2 Plant Status Station Duty Workweek K. Krueger D. Hunter Manager: Manager:

Mode: 1 Rx Power: 100%

Plant Risk:

Green Current EOOS Risk Assessment is:

SFP Time to 76.7 hrs Days Online: 220 days 200 Deg F:

Quarterly 0PT-07.2.4B, Core Spray System Operability Test - Loop B Turnover: operability is in progress and completed up to Step 7.4 (Pump Testing).

Perform 0PT-07.2.4B, Core Spray Pump Loop B Operability Flow Test.

Protected 2A/B NSW Pumps due to 1A NSW pump maintenance Equipment:

BOP operator is to complete 0PT-07.2.4B, Core Spray Pump Loop B operability flow test.

Comments:

1A NSW Pump is under clearance for planned maintenance.

SRV B is inoperable.