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8.0 OPERATOR RESPONSE AND INSTRUCTIONAL STRATEGIES

EVENT 1: RAISE REACTOR POWER WITH RR TO 80% POWER

Simulator Operator Actions

Ensure Monitored Parameters is open and Scenario Based Testing Variables are loaded.

Simulator Operator Role Play

If contacted as RE, concur with any recommendations provided by the crew.

If asked the RE will perform the Alternate Power verification at 80% power.

Evaluator Notes

Plant Response: Power will be raised using Recirc flow from 75% to 80%.

Objectives: SRO - Direct actions for power increase using Recirc flow.

RO - Raise power.

BOP - Monitor balance of plant

Success Path: Power is raised using Recirc flow from 75% to 80% monitoring the Power-to-Flow

Map and balance of plant

Event Termination: Once reactor power is steady at 80%, the Chief Examiner can move to Event 2.

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EVENT 1: RAISE REACTOR POWER WITH RR TO 80% POWER

Time Pos EXPECTED Operator Response NOTES

SRO Conduct shift turnover shift briefing.

Directs power to be raised using recirculation

flow

May conduct a brief (see Enclosure 1 on page

57 for format)

ATC May reference 2OP-02 section 6.1.3

ATC Request peer checker / reactivity team

Speed changes are accomplished by

Raises power using recirculation flow to ~80% depressing Raise Slow or Raise

power. Medium pushbuttons. The Raise Slow

pushbutton changes Recirc pump

Raise recirc pump speed by depressing the speed at 0.06%/increment at 1

Master Raise Slow or Medium pushbutton. rpm/second. The Raise Medium

pushbutton changes Recirc pump

speed at 0.28%/increment at 5

Confirm the following:

rpm/second

A rise in Recirc Pump A(B) Speed

Demand, Calculated Speed, and a rise in

Actual Speed.

A rise in reactor power

ATC * A rise in B32-R617(R613) [Recirc Pump

A(B) Discharge Flow]

A rise in B32-VFD-IDS-003A(B) [Recirc

VFD 2A(B) Output Wattmeter]

A rise in B32-VFD-IDS-001A(B) [Recirc

VFD 2A(B) Output Frequency Meter]

May null the DVM as power is raised.

Continues raising recirc pump speed until

80% power is obtained

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EVENT 1: RAISE REACTOR POWER WITH RR TO 80% POWER

Time Pos EXPECTED Operator Response NOTES

Verifies operation on the Power to Flow Map

BOP Monitors and adjusts balance of plant conditions

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EVENT 2: RECIRCULATION PUMP 2A SEAL FAILURE

Simulator Operator Actions

At the direction of the Lead Evaluator, Initiate Trigger 1 to fail Recirc Pump 2A Seal #1,

followed by Seal #2 failure one minute later.

Simulator Operator Role Play

If contacted as RE acknowledge the request. If contacted about implementing thermal penalties

acknowledge the request.

If contacted as chemistry to sample for >15% power change, acknowledge request.

If contacted as I&E, acknowledge any requests.

Evaluator Notes

Plant Response: Reactor Recirc Pump 2A seal #1 will fail and seal pressures will equalize. Shortly

after the seal #1 failure, a seal #2 failure will occur. The crew will respond to the

Recirc Pump seal failure and the rising drywell temperature and pressure per AOP-

14.0. AOP-14.0 will direct the Recirc Pump be shutdown and then be isolated. If the

pump is not isolated, a reactor scram will occur on high drywell pressure.

Objectives: SRO - Direct Shift Response To Recirculation Pump Trip

RO - Respond To Recirc Pump Trip

Success Path: Shutdown and Isolate Recirc Pump 2A

Event Termination: Once the plant is stable 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 3.

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EVENT 2: RECIRCULATION PUMP 2A SEAL FAILURE

Time Pos EXPECTED Operator Response Comments

Direct entry into and actions of 0AOP-14.0 for

SRO abnormal drywell parameters.

May brief (Enclosure 1 page 61)

Direct Recirc Pump 2A shutdown then

SRO Critical Task #1

isolated.

Direct entry into and actions of 2AOP-04.0,

LOW CORE FLOW

Direct power reduction to 50% IAW 0ENP--

24.5 and recirc flow to greater than 30.8 Mlbs/hr.

Enters TS 3.4.1 Condition A

Condition A: Requirements of the LCO not

SRO met.

Required Action: Satisfy the requirements

of the LCO

Completion Time: 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months

Review the following alarms during this event:

A-06:

5-3, OUTER SEAL LEAKAGE FLOW

DETECTION HI

6-3, PUMP A SEAL STAGING FLOW

ATC HIGH/LOW

A-04:

1-2 DRYWELL FLR DR SUMP LVL HI

Diagnoses and reports failure of the inner seal

then the outer RR pump seals.

ATC Enter and announce AOP-14.0

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EVENT 2: RECIRCULATION PUMP 2A SEAL FAILURE

Time Pos EXPECTED Operator Response Comments

Performs actions IAW AOP-14.0 to secure

Critical Task #1

and isolate RR pump 2A:

Stop Recirculation Pump A by depressing

the A Recirc Pump VFD STOP pushbutton.

Close Pump A Disch Vlv, B32-F031A.

Close Seal Injection Vlv, B32-V22

Close Pump A Suction Vlv,

B32-F023A

Close Disch Bypass Vlv, B32-F032A

ATC Enter and announce AOP-04.0

Reduces Reactor power to 50 % IAW

ENP24.5 and ensure operation within the Power

to Flow map.

Ensures recirc flow is maintained between

30.8 - 45 Mlbs/hr.

ATC May reduce CRD flow to 30 GPM

May notify Reactor Engineer to perform 0PT-

13.2, Jet Pump Baseline Data

BOP Monitors and adjusts balance of plant conditions

BOP May vent containment IAW 2OP-10.

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EVENT 3: REMOVE ONE RFP FROM SERVICE

Simulator Operator Actions

WHEN in DFCS MAN and lowering speed, than for the applicable RFP:

EITHER initiate Trigger 2 for RFP 2A (CF063F ramp to 40% over 1.5 minute)

OR initiate Trigger 3 for RFP 2B (CF063F ramp to 40% over 1.5 minute)

Simulator Operator Role Play

If directed by the lead examiner: Contact the CRS as the SM and direct the BOP operator to

idle a RFP IAW 0GP-12 and 2OP-32.

When contacted as RP acknowledge the request and provide name.

When contacted as Chemistry acknowledge the request and provide name.

When contacted as Radwaste acknowledge the request.

Evaluator Notes

Plant Response: One RFP feeding the RPV with One RFP idled or secured.

Objectives: SRO -Direct Reactor Feed Pump shutdown from two pump operation IAW OP-32.

BOP - Remove RFP from operation IAW OP-32 section 6.2.1.

Success Path: One RFP idling IAW OP-32.

Event Termination: Event 4 is manually triggered when the RFP speed reaches ~1200 rpm

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EVENT 3: REMOVE ONE RFP FROM SERVICE

Time Pos EXPECTED Operator Response Comments

Direct BOP to secure or idle one RFP IAW OP-

32.

May conduct a brief

SRO (see Enclosure 1 on page 61 for format)

ATC Monitors the plant.

Performs Actions IAW OP-32 to secure or idle

one RFP:

Notifies RP

Notifies Chemistry

Contacts Radwaste

Adjust level setpoint to 190 on 2-C32-SIC-

R600

Opens Recirc valve

Adjusts bias

Places controller in manual

Lowers speed

Closes discharge valve

Returns level setpoint to 187

Places MAN/DFCS in MAN

Continues to lower speed to 1000 RPM

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EVENT 4: FAILURE OF THE IDLED RFP SPEED CONTROLLER IN MAN

Simulator Operator Actions

WHEN in DFCS MAN and lowering speed ~2400 rpm, than for the applicable RFP:

EITHER initiate Trigger 2 for RFP 2A (CF063F ramp to 40% over 90 seconds )

OR initiate Trigger 3 for RFP 2B (CF063F ramp to 40% over 90 seconds)

Simulator Operator Role Play

If contacted as maintenance, acknowledge the request.

If contacted as the TBAO to investigate, after 5 minutes report you cant see any cause.

If contacted as WCC, acknowledge the request

Evaluator Notes

Plant Response: The idle RFP TM25 will fail resulting in the opening of the LP supply valves to the idle

RFP. The operator will trip the RFP.

Objectives: SRO - Direct tripping of the RFP

BOP: Respond to TM-25 failure by tripping the RFP.

Success Path: Identifies increasing RFP speed due to TM-25 failure, RFP tripped.

Event Termination: Once the idled RFP has been tripped, the Chief Examiner can move to Event 5.

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EVENT 4: FAILURE OF THE IDLED RFP SPEED CONTROLLER IN MAN

Time Pos EXPECTED Operator Response Comments

Acknowledge BOP report of increasing RFP

speed, may direct trip of RFP.

May direct entry into 0AOP-23.0

May brief (Enclosure 1 page 61)

ATC Plant Monitoring

.

Identifies increasing RFP speed, and makes

report.

BOP If directed enters and announces 0AOP-23.0

BOP Trips RFP IAW 2OP-32 Section 6.2.1 step 27.

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EVENT 5: FAILURE OF G31-F004 FAILURE TO ISOLATE

Simulator Operator Actions

At the direction of the Lead Evaluator, Initiate Trigger 4 to insert RWCU tube leak causing

rising RWCU filter inlet temps.

Simulator Operator Role Play

If contacted as mechanical maintenance to examine the cause of the failure acknowledge

request, and if asked there is no time estimate for completion.

If contacted as RB AO, report no abnormalities observed with the RWCU system.

If contacted as chemistry to perform RCS sample for conductivity, acknowledge the request.

Evaluator Notes

Plant Response: A02 (4-6) NON REGEN HX DISCH HIGH TEMP alarms. RWCU temperatures rise.

The 2-G31-F004 fails to isolate.

Objectives: SRO - Direct isolation of the G31-F004.

BOP: Respond to rising RWCU temperatures and manually isolate G31-F004

Success Path: Manual isolation of G31-F004.

Event Termination: Once diagnosis of RWCU isolation failure and closure of the 2-G31-F004 is

complete, the Chief Examiner can move to Event 6

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EVENT 5: FAILURE OF G31-F004 FAILURE TO ISOLATE

Time Pos EXPECTED Operator Response Comments

Acknowledge report of

A-04 (2-5) CLEANUP FILT INLET TEMP HI

SRO A-02 (4-6) NON REGEN HX DISCH HIGH

TEMP

May brief (Enclosure 1 page 61)

Contacts maintenance to investigate failure of

the G31-F004 to isolate.

May contact chemistry to satisfy the

requirements of TR 3.13.2

Address and report

A-04 (2-5) CLEANUP FILT INLET TEMP HI

A-02 (4-6) NON REGEN HX DISCH HIGH

TEMP

Perform APP actions for A-02 (4-6):

Verifies temperature on G31-TI-R607,

points 2 and 3, and recognizes rising

ATC temperatures.

Diagnoses and reports >135°F which failed

to automatically isolate the G31-F004.

Manually isolates the G31-F004.

BOP Plant Monitoring.

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EVENT 6: FAILURE OF EFCV 2-B21-IV-2455

Simulator Operator Actions

At the direction of the Lead Evaluator, Initiate Trigger 5 to activate NB015F which results in 2-

UA-24 (1-4), B21-IV-2455 closure, and upscale indication on R604A.

Simulator Operator Role Play

If contacted as AO, report that the line was bumped by scaffolding work in the area. Personnel

have been coached and a plant status control monitor in place, work is done. No abnormal

conditions observed. All requested secondary containment conditions are normal.

If asked as maintenance, acknowledge request.

At the direction of the lead evaluator, contact the CRS as the SM and direct the excess flow

check valve returned to service per OI-44.

If asked as WCC, report that an operator will complete OI-44, Attachment 1, Excess Flow

Check Valve Documentation.

Evaluator Notes

Plant Response: Excess flow check for pen X 49B-A (B21-IV-2455) will close resulting in UA-24 (1-4)

alarm, upscale indication on B21-LI-R604A will require entry into TS 3.3.3.1 Condition

A until the valve can be re-opened.

Objectives: SRO - Acknowledge report of UA-24 (1-4) enter TS 3.3.3.1 Condition A.

ROs - Report receipt of and address UA-24 (1-4). Perform excess flow check valve

position indication evaluation IAW 0OI-44. Re-open B21-IV-2455.

Success Path: TS 3.3.3.1 Condition A entered, excess flow check valve position indication

evaluation performed, and B21-IV-2455 re-opened.

Event Termination: Once action to reset the EFCV is complete, go to Event 7.

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EVENT 6: FAILURE OF EFCV 2-B21-IV-2455

Time Pos EXPECTED Operator Response Comments

Acknowledge report of UA-24 (1-4).

May brief (Enclosure 1 page 61)

Enters 3.3.3.1 Post Accident Monitoring (PAM)

Instrumentation Condition A for loss of wide

range 0-210 indicator 604A.

CONDITION A: One or more Functions with one

SRO required channel inoperable.

REQUIRED ACTION: Restore required channel

to OPERABLE status.

COMPLETION TIME: 30days

SRO May Contact maintenance/I&E

ATC Monitors Plant

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EVENT 6: FAILURE OF EFCV 2-B21-IV-2455

Time Pos EXPECTED Operator Response Comments

BOP Enter and address UA-24 (1-4)

May verify level indication 604A ( which will

indicate upscale).

Perform excess flow check valve position

BOP indication evaluation IAW 0OI-44.

BOP Re-opens B21-IV-2455.

May verify level indication 604A returns to

normal.

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EVENT 7/8/9: SPURIOUS GROUP 1/ATWS/SLC FAILURE/CRD PUMP TRIP

Simulator Operator Actions

At the direction of the Lead Evaluator, INITIATE TRIGGER 6 to initiate the Group I MISV

closure followed by ATWS and 30 seconds later a trip of the running CRD pump.

If requested to defeat Group I LL3, wait 2 minutes, and install jumpers (TRIGGER 7)

If requested to install LEP-02, Section 2.3 jumpers, wait 5 minutes, and inform the SRO that the

jumpers are installed . DO NOT INSTALL JUMPERS.

Delete ATWS when scram reset and air header re-pressurized.

Simulator Operator Role Play

Acknowledge request as Maintenance/I&C to investigate failures (CRD, Group I, SLC, and

Scram reset logic) acknowledge the requests.

Acknowledge request to perform LEP-03 actions.

If requested to verify scram jumpers, acknowledge request

When a level band is established IAW ATWS step RC/L-16 and 17, and at the direction of the

lead evaluator: insert RP005F, and report that the issue with the LEP-02 section 2.3 jumpers

has been corrected (bad jumper continuity).

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Evaluator Notes

Plant Response: A spurious Group I isolation signal will occur resulting in an automatic scram signal.

Most control rods will fail to insert on the scram. The crew will respond IAW ATWS

and perform T&P actions. In addition, the crew will be required to control pressure

with SRVs, resulting in torus water temperature above 110°F. This will require further

T&P based on Table Q-2 (until APRMs downscale (<2%) or TAF) and also requires

maximization of torus cooling IAW PCCP.

When SLC initiation is attempted, the switch positions will not work. The crew will

enter LEP-03 and align for alternate boron injection using CRD. The scram cannot

be reset due to a failure in the scram reset logic. The crew will also start a CRD

pump and drive rods using LEP-02. Once level is lowered per RC/L-16&17 the scram

can be reset, and a reactor scram will be successful.

Objectives: SRO - Enter and Direct actions to control reactor power, and Torus temperature IAW

ATWS and PCCP.

ROs - Perform ATWS and PCCP actions as directed by the CRS:

SCRAM Immediate Actions, Control pressure with SRVs, Terminate and

Prevent injection, Initiate SLC / LEP-03, Insert rods, and Align torus Cooling

Success Path: Reduce reactor power by tripping recirc pumps, lowering reactor water level IAW

ATWS and inserting rods IAW LEP-02. Aligns torus cooling IAW PCCP.

Scenario Termination: When all rods are inserted and level is being restored, 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.

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EVENT 7/8/9: SPURIOUS GROUP 1/ATWS/SLC FAILURE/CRD PUMP TRIP

Time Pos EXPECTED Operator Response Comments

Enters RSP, transitions to ATWS and

announces to crew.

Directs:

Mode switch to shutdown when steam

flow is <3 Mlbms/hr

ARI initiation RC/Q-2

RR pumps verified tripped RC/Q-5

SLC injection IAW ATWS

SRO CRITICAL TASK #2

insertion of rods per LEP-02

pressure band 800-1000 psig

Terminate and Prevent Injection

(based on APRM >2% and level >90

inches).RC/L-2

When SLC is reported as failed to inject, directs

injection of Boron IAW LEP-03

When Torus temp is > 95°F:

SRO * enters and announces PCCP

directs maximize torus cooling

When table Q-2 conditions are met, directs

CRITICAL TASK #2

SRO continuation of terminate and prevent until table

Q-2 is no longer met. (APRM downscale, TAF)

If DW temp reaches 150°F directs:

SRO * defeat DW coolers LOCA lockout per

EOP-01-SEP-10

maximize DW cooling

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EVENT 7/8/9: SPURIOUS GROUP 1/ATWS/SLC FAILURE/CRD PUMP TRIP

When all rods inserted, exits ATWS and enters

and directs actions IAW RVCP.

Diagnoses and reports MSIV closure and

reactor scram

ATC Performs SCRAM IA (Enclosure 2 Page 62)

When directed performs initial ATWS actions:

places MODE switch in shutdown when

steam flow is <3 Mlbms/hr

verifies tripped RR pumps

reports reactor power

CRITICAL TASK #2

When directed performs LEP-02 actions:

Reports trip of CRD pump, restarts CRD

pump and inserts rods IAW LEP-02

(Enclosure 4, Pages 66)

ATC * Requests scram jumpers installed

When LEP 02 Section 2.3 jumpers are

installed performs section 2.3 manual

scram actions.

Monitors reactor power and reports if APRM

downscales are reached.

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EVENT 7/8/9: SPURIOUS GROUP 1/ATWS/SLC FAILURE/CRD PUMP TRIP

BOP Controls RPV pressure using SRVs

BOP Maintains level as directed by the CRS

CRITICAL TASK #2

When directed, performs Terminate and

Prevent. (Enclosure 6 Pages 75)

When directed, injects SLC and diagnoses and

reports failure of SLC pumps.

When directed, aligns CRD for Boron injection

IAW LEP-03 (Enclosure 5, Page 74)

BOP When directed, inhibits ADS

BOP When directed, defeats Group 10 isolation

When directed, Initiates or verifies any isolations

BOP and actuations for level which should have

occurred.

When directed performs terminate and CRITICAL TASK #2

prevent based on Table Q-2. (Enclosure 5,

Page 74)

BOP Note- this may be a continuation of the initial

terminate and prevent based on power, but will

just be directed to continue until APRM

downscale or TAF whichever occurs first.

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EVENT 7/8/9: SPURIOUS GROUP 1/ATWS/SLC FAILURE/CRD PUMP TRIP

When APRM downscales or TAF is reached,

maintains RPV level as directed by CRS by

BOP recommencing injection with previously

terminated and prevented systems as

necessary.

When Torus temperature is greater than 95° F,

BOP places Torus Cooling in service.

(Enclosure 3, Pages 64)

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ENCLOSURE 1 Page 1 of 1

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ENCLOSURE 2 Page 1 of 2

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ENCLOSURE 3 Page 1 of 2

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ENCLOSURE 4 Page 1 of 8

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ENCLOSURE 5 Page 1 of 1

Rest of the steps are AO field actions

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ENCLOSURE 6 Page 1 of 2

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ENCLOSURE 6 Page 1 of 2

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ATTACHMENT 1 - Scenario Quantitative Attribute Assessment

Category Scenario Content

Rev. 2 Supp. 1 Req.

Total Malfunctions 5-8 8

Malfunctions after EOP

1-2 2

Entry

Abnormal Events 2-4 4

Major Transients 1-2 1

EOPs Used 1-2 2

EOP Contingency 0-2 2

Run Time 60-90 min 90

Crew Critical Tasks 2-3 2

Tech Specs 2 2

Instrument / Component 2 - OATC

Failures before Major 4

2 - BOP

Instrument / Component

2 2

Failures after Major

Normal Operations 1 1

Reactivity manipulation 1 1

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ATTACHMENT 2 - Shift Turnover

Brunswick Unit 2 Plant Status

Station Duty Workweek

J. Pierce D. Hunter

Manager: Manager:

Mode: 1 Rx Power: 75%

Plant Risk:

Green

Current EOOS Risk Assessment is:

SFP Time to

49.7 hrs Days Online: 80 days

200 Deg F:

Rod Adjustment has been completed. The reactivity plan directs raising

Turnover: reactor power to 80% using recirculation flow in accordance with 0GP-

12.

Protected

ADHR / FPC Loop A / Demin Transfer Pump

Equipment:

Comments: A severe thunderstorm watch is in effect for SE North Carolina

Appendix D Scenario Outline Form ES-D-1

Facility: Brunswick Scenario No.: NRC-2 Rev 0 Op-Test No.: 2017-301

Developer: J. Viera

Technical Review: Validators: _____________________________

__________________________ _____________________________

Facility Representative: _____________________________

__________________________

Initial Conditions: Unit 2 is pressurized at the POAH. Following recent testing the 2B RHR Loop is in

Torus Cooling. A severe thunderstorm watch is in effect for SE North Carolina.

Turnover: Place the Master RFPT Controller to AUTO in accordance with 0GP-02, Section 6.3, Step

46. Once complete, continue power ascension using control rod withdrawal in accordance with 0GP-

03, Section 6.1, Step 5.

Event Malf. Event Event

No. No. Type* Description

Place the Master RFPT Controller to AUTO

1 n/a N (BOP)

(0GP-02)

I (ATC) RWM inoperable during Reactor Startup.

2 1

TS (SRO) (0GP-03, 0GP-10, 2OP-07, 2APP-A-05, 0GP-11, TS 3.3.2.1)

Increase Reactor Power using control rod withdrawal.

3 n/a R (ATC)

(0GP-03, 0GP-10, 0GP-11)

Respond to annunciator 2-UA-03 (4-3), OFF GAS FILTER DIFF-

4 2 C (BOP)

HIGH (2APP-UA-03, 2OP-30)

CW Lube Water Header Leak

5 3 C - BOP

(2APP-UA-24)

C - ATC RCIC low suction pressure switch failure

6 4

TS - CRS (A-03, TS 3.5.3)

Multiple control rod drifts requiring scram / SDV Leak (LOCA) with

7 5, 6, 7 M trip of running RFP and CRD Pumps

(2EOP-01-RSP, 2EOP-01-RVCP, 0EOP-03-SCCP)

8, 9,

8 n/a Failure of HP injection sources (2EOP-01-RVCP)

10

Restore RPV injection using a single RFP prior to TAF

9 T (ATC)

(2EOP-01-RVCP, 2OP-32)

ED when > 2 areas above max safe

10 T (BOP)

(2APP-UA-12, 0EOP-03-SCCP, 0EOP-01-EDP)

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, Critical (T)ask

Event 1: Place the Master RFPT Controller to AUTO

(0GP-02, Section 6.3, Step 46)

The scenario should start with plant conditions established to perform 0GP-02,

Section 6.3, Step 46. If necessary, a pre-marked up copy of 0GP-02 should be

available.

The crew will move to Event 2 by continuing the reactor startup.

Event 2: RWM inoperable during reactor startup

(0GP-03, 0GP-10, 2OP-07, 2APP-A-05, 0GP-11, TS 3.3.2.1)

The applicant crew will continue a reactor startup using a copy of 0GP-03,

Section 6.1, pre-marked to Step 5. Appropriate rods already pulled will be

provided on a pre-marked up copy of 0GP-10, using the A2X(?) sequence.

Following withdrawal of the second rod, the ATC will respond to annunciation of

2-A-5 (5-2) with the RWM ODA displaying UNKNOWN (mid-display will be

blank with no soft key selections available).

If consulted as Reactor Engineer or Shift Management, notify the crew that they

are to continue the reactor startup.

It is expected that the operating crew will transition to using 0GP-11 (from 0GP-

10) to continue the reactor startup. When plant management permission is

requested per 0GP-11 (4.1) to bypass the RWM, ensure permission is given. The

ATC is expected to bypass the RWM prior to continuing the startup.

The SRO is expected to enter TS LCO 3.3.2.1, Condition C.

The crew will move to Event 3 by continuing the reactor startup.

Event 3: Reactor Startup

(0GP-03, 0GP-10, 0GP-11)

The operating crew will continue to withdraw rods to raise reactor power. Once a

sufficient power change has been observed, the Chief Examiner can transition to

Event 4.

It is not desired to proceed to the point of placing the MODE switch in RUN (15%

RTP is RPS limit in Mode 2).

Event 4: Respond to annunciator 2-UA-03 (4-3), OFF GAS FILTER DIFF-HIGH

(2APP-UA-03, 2OP-30, Section 6.3.3)

The BOP operator will respond to receipt of annunciator 2-UA-03 (4-3) and is

expected to perform 2OP-30, Section 6.3.3, Placing the Off Gas Standby Filter in

Service (as directed by the APP). Ensure instructions exist for booth operator to

report completion of Unit 1 steps (2 - 4) and Unit 2 field steps (5 - 6) when

prompted by applicant. Per Chief Examiner direction, this event can be run

concurrently with Event 5.

Event 5: CW Lube Water Header Leak

(2APP-UA-24)

Annunciator UA-24 (6-7), CW DISCH PMP LUBE WATER PRESSURE LOW and

UA-24 (5-7), CW DISCH PMP LUBE WATER FLOW LOW. The BOP operator is

expected to start the 2B Bearing Lube Water Pump (no auto start enabled).

Event 6: RCIC low suction pressure switch failure

(A-03, TS 3.5.3)

A3 4-3, RCIC Pump Suction Low Pressure, 13 seconds later A-02 2-6, RCIC

System Press Low and A3 5-3, RCIC Turbine Tripped, annunciators are

received. The RCIC suction pressure switch fails low which causes the RCIC

turbine to trip. The RCIC E51-V8 will not auto close and the operator should

make the auto action occur. RCIC will not be available for the rest of the

scenario.

Event 7: Scram Discharge Volume (SDV) Leak (LOCA) with trip of running Reactor

Feed Pump (RFP) and Control Rod Drive (CRD) Pumps

(2EOP-01-RSP, 2EOP-01-RVCP, 0EOP-03-SCCP)

When entered, an unisolable SDV leak will commence in the U2 RB. An

automatic reactor SCRAM is expected when level lowers < 166. At the time of

the SDV leak, the running RFP and CRD Pumps will inadvertently trip.

It is expected for the SRO to enter 2EOP-01-RSP. If the scram is attempted to be

reset, the SDV Vents and Drains fail.

Following SCRAM immediate actions, it is expected for the ATC to report reactor

water level < 166 based on indications &/or alarms. It is expected for the BOP

operator to report receipt of annunciator(s) 2-UA-12 (2-1) NORTH CS RM

FLOOD LEVEL HI (after a period of time also expect (2-2), NORTH RHR RM

FLOOD LEVEL HI)

It is expected for the SRO to transition to both 2EOP-01-RVCP and 0EOP-03-

SCCP.

Event 8: Failure of HP injection sources

(2EOP-01-RVCP)

It is expected for the SRO and the ATC operator to attempt RPV injection using

one (or all) of the following sources (Table L-1), all attempts will be unsuccessful.

o CRD Pumps - Pump control switch actuation will be unsuccessful

o RCIC - Will not actuate on LL-2 and control switch actuation will be

unsuccessful

o HPCI - Will not actuate on LL-2 and control switch actuation will be

unsuccessful

It is not expected for the SRO to invoke availability of Table L-2 alternate

injection subsystems. If any of these systems are requested, the simulator

operator will acknowledge the report. Any attempted use of SLC injection will be

unsuccessful.

o SLC Pumps - Pump control switch actuation will be unsuccessful

Event 9: Restore RPV injection using a single RFP prior to Top of Active Fuel (TAF)

(2EOP-01-RVCP, 2OP-32)

If maintenance investigation of the tripped RFP is requested, the simulator

operator will acknowledge the request but provide no follow-up report.

The ATC operator is expected to restore RPV injection using either the tripped

RFP or with injection of the idle RFP. (Critical Task is met if RPV water level is

maintained > TAF with a RFP in service following initiation of Event 7, due to not

challenging the RPV level control mitigation strategy)

Chief Examiner discretion will be utilized to deliver the second area Max Safe

water level limit. This is to permit sufficient time for applicants to attempt RPV

injection prior to ED criteria.

Event 10: ED when > 2 areas above max safe

(2APP-UA-12, 0EOP-03-SCCP, 0EOP-01-EDP)

The BOP operator is expected to continue performance of 2APP-UA-12 actions

for received annunciators (no actions apart from field reports expected).

If any crew member requests field actions to perform a SCRAM reset, the

simulator operator will acknowledge the report. (no actions taken to reset the

SCRAM)

The operating crew may elect to Anticipate Emergency Depressurization. There

will be no failures associated with crew performance of Anticipation.

Chief Examiner discretion will be utilized to deliver the second area Max Safe

water level limit. This is to permit sufficient time for applicants to attempt RPV

injection prior to ED criteria.

The BOP operator is expected to recognize that ED criteria is met when the

second area Max Safe water level limit is reached. (Critical Task is met when the

crew performs an Emergency Depressurization upon receipt of 2 area water

levels above Max Safe limits)

It is expected for the SRO to direct the BOP operator to perform an Emergency

Depressurization.

Once the applicant crew has initiated an Emergency Depressurization in accordance

with 0EOP-01-EDP the Chief Examiner can terminate this scenario.

BRUNSWICK TRAINING SECTION

OPERATIONS TRAINING

INITIAL LICENSED OPERATOR

SIMULATOR EVALUATION GUIDE

2017 NRC SCENARIO 2

MASTER RFP IN AUTO, RWM INOP, INCREASE POWER WITH RODS,

OFFGAS FILTER DP, CW LUBE WATER PUMP, RCIC SUCTION PRESSURE

SWITCH, SDV LEAK, HP INJ LOSS, EMERGENCY DEPRESS

REVISION 0

Developer: NRC - Joe Viera Date: 3/31/2017

Technical Review: Bob Bolin Date: 4/24/2017

Validators: Mike Long Date: 5/5/17

Rob Lax

Trey Bunnell

Facility Representative: Craig Oliver Date: 5/24/17

2017 NRC SCENARIO 2

LOI SIMULATOR EVALUATION GUIDE Rev. 0

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REVISION SUMMARY

0 NRC developed scenario for the 2017 NRC Exam.

2017 NRC SCENARIO 2

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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 .................................... 13

ATTACHMENT 1 - Scenario Quantitative Attribute Assessment ..................................................... 54

ATTACHMENT 2 - Shift Turnover ........................................................................................................ 64

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1.0 SCENARIO OUTLINE

Event Malf. No. Type* Event Description

Place 2A RFPT level control in automatic

1 N - BOP

(0GP-02)

C - ATC RWM Inop

2 RD044F

TS - CRS (0GP-02, 0GP-10, 2OP-07, A-05, 0GP-11, TS 3.3.2.1)

Raise reactor power using control rods

3 R - ATC

(0GP-02, 0GP-10, 0GP-11)

Off Gas Filter Hi d/P

4 ZUA343 C - BOP

(UA-03, 2OP-30)

CW Lube Water Pump Trip / Standby Failure

5 C - BOP

(UA-24)

C - ATC RCIC low suction pressure switch failure

6 ZA343

TS - CRS (A-03, TS 3.5.3)

Rod Drifts/ Scram/ SDV Leak

7 RD045F M

(RSP)(RVCP)(SCCP)(AOP-05.0)

RD183F Failure of HP Injection

8 CF_IAFWATRP

C

(RVCP)

Restore RPV Injection prior to TAF

9 T

(RVCP, 2OP-32)

ED when >2 areas above max safe

10 ZUA1214 T

(UA-12, SCCP, EDP)

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

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2.0 SCENARIO DESCRIPTION SUMMARY

Event Description

Step 6.3.46 of 0GP-02, Approach to Criticality and Pressurizations of the Reactor will

1

be completed starting at Step 6.3.46.

The crew will raise power by pulling control rods in preparation for placing the Mode

switch to RUN. Rod pulls will commence at Step 164 (42-39 @ 12) of the A2X

2/3

sequence. There will be a power loss to the Rod Worth Minimizer. The crew will

have to implement 0GP-11 IAW the Tech Specs to continue the startup.

After Tech Specs are addressed the Off Gas Filter Hi d/P alarm will be received. The

4

standby Off Gas filter will be placed in service.

Annunciator UA-24 (6-7), CW DISCH PMP LUBE WATER PRESSURE LOW and UA-

5 24 (5-7), CW DISCH PMP LUBE WATER FLOW LOW. The BOP operator is expected

to start the 2B Bearing Lube Water Pump (no auto start enabled).

A3 4-3, RCIC Pump Suction Low Pressure, 13 seconds later A-02 2-6, RCIC System

Press Low and A3 5-3, RCIC Turbine Tripped, annunciators are received. The RCIC

6 suction pressure switch fails low which causes the RCIC turbine to trip. The RCIC

E51-V8 will not auto close and the operator should make the auto action occur.

RCIC will not be available for the rest of the scenario.

A reactor SCRAM will be inserted when multiple control rods start to drift in. When the

scram pushbuttons are depressed a trip of CRD Pump A and RFP A will occur. When

7

the scram occurs an unisolable SDV leak will commence in the U2 RB. The scram will

not be able to be reset due to a failure of the SDV Vents and Drains.

It is expected for the SRO and the ATC operator to attempt RPV injection using one

(or all) of the following sources, all attempts will be unsuccessful.

CRD Pumps - Pump control switch actuation will be unsuccessful

8

RCIC - already INOP

HPCI - Will not actuate on LL2 and Aux Oil Pump failure

SLC Pumps - Pump control switch actuation will be unsuccessful

The ATC operator is expected to restore RPV injection using either the tripped RFP

or with injection of the idle RFP. (Critical Task is met if RPV water level is maintained

9

> TAF with a RFP in service following initiation of Event 7, due to not challenging the

RPV level control mitigation strategy)

The operating crew may elect to Anticipate Emergency Depressurization. The BOP

operator is expected to recognize that ED criteria is met when the second area Max

10 Safe water level limit is reached. (Critical Task is met when the crew performs an

Emergency Depressurization upon receipt of 2 area water levels above Max Safe

limits).

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3.0 CREW CRITICAL TASKS

Critical Task #1

Restore RPV injection using a single RFP prior to TAF

Potential Crew Critical Task, if RFP is not started - ED prior to or at LL4.

Critical Task #2

ED when > 2 areas above max safe

4.0 TERMINATION CRITERIA

Once the crew has initiated an Emergency Depressurization in accordance with EDP the

Chief Examiner can terminate this scenario.

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5.0 IMPLEMENTING REFERENCES

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

Number Title

A-05 (5-2) Rod Block RWM/RMCS Sys Trouble

UA-03 (4-3) Off Gas Filter Diff-High

UA-24 (5-7) CW Disch Pmp Lube Water Flow Low

UA-24 (6-7) CW Disch Pmp Lube Water Pressure Low

2OP-07 Reactor Manual Control System Operating Procedure

2OP-30 Condenser Air Removal And Off-Gas Recombiner System

0GP-02 Approach To Criticality And Pressurization Of The Reactor

0GP-10 Rod Sequence Checkoff Sheets

0GP-11 Second Operator Rod Sequence Checkoff Sheets

0EOP-01-LEP-01 Alternate Coolant Injection

0EOP-01-LEP-02 Alternate Control Rod Insertion

0EOP-01-SEP-09 CRD Flow Maximization

0AOP-05.0 Radioactive Spills, High Radiation, And Airborne Activity

2EOP-01-RSP Reactor Scram Procedure

2EOP-01-RVCP Reactor Vessel Control Procedure

0EOP-02-SCCP Secondary Containment Control Procedure

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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

Insert control rods up to Step 163 of GP-10, Sequence A2X is completed.

Raise pressure set to 900 psig

Verify level is stable

Verify drive water pressure is at 260 psid.

Set V177 to approximately 1/2 Mlbms flow

2A Bearing Lube Water Pump in service

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

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

Protected Equipment

1. 2A FPC Pump/Hx, 2D RCC Pump, and 2C Demin Transfer Pump.

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

16. 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 164

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.

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7.0 INTERVENTIONS

TRIGGERS

Trig Type ID

1 Malfunction RD044F - [RWM LOSS OF POWER]

2 Annunciator ZUA343 - [OFF GAS FILTER DIFF-HIGH]

3 DI Override K4B35A - [C.B. BRG WTR LUBE PMP 2A CONTROL SWITCH]

3 DI Override K4B35B - [C.B. BRG WTR LUBE PMP 2A POINT SELECT]

3 DI Override K4B35A - [C.B. BRG WTR LUBE PMP 2A CONTROL SWITCH]

4 Trigger Command did:k4b36a

5 Annunciator ZA353 - [RCIC TRUBINE TRIPPED]

5 Annunciator ZA226 - [RCIC SYSTEM PRESS LOW]

5 Annunciator ZA343 - [RCIC PUMP SUCTION LO PRESS]

5 AO Override G1H08G1M - [RCIC PUMP SUCT PRESS]

7 Malfunction RD041F - [LOSS OF CNTRL AIR TO THE SCRAM VLVS]

7 Malfunction RD045F - [SCRAM DISCHARGE VOLUME RUPTURE]

8 Annunciator ZUA1224 - [SOUTH RHR RM FLOOD LEVEL HI]

9 Annunciator ZUA1214 - [SOUTH RHR RM FLOOD LEVEL HI-HI]

10 Remote Function SL_IASLCTST - [SLC SUCT. LINEUP (NORM=SLC TNK / ALT=JUMPER HOSE)]

10 Remote Function SL_IASLCSRC - [SLC JUMPER HOSE SOURCE (ALT=FP / NORM=DEMIN)]

11 Malfunction RD183F - [CRD PUMP MOTOR WINDING FAULT]

11 Remote Function CF_IAFWATRP - [LOCAL RFP A TRIP]

20 Trigger Command and:zua343

Trig # Trigger Text

4 K4B36JB5 - [C.B. BRG WTR LUBE PMP 2B CONTROL SWITCH]

8 ZUA1213 - [SOUTH CS RM FLOOD LEVEL HI-HI]

11 K2501PP7 - [RX SCRAM A]

20 QK214RRZ - [AOG SYS ISOL HCV-101 RED]

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MALFUNCTIONS

Malf Mult Current Target Rmp

Description Actime Dactime Trig

ID ID Value Value time

RD044F RWM LOSS OF POWER False True 1

ES040F HPCI FAILURE TO AUTO START True True

RD183F A CRD PUMP MOTOR WINDING FAULT False True 11

SCRAM DISCHARGE VOLUME

RD045F 0.00 100.0 7

RUPTURE

ES041F RCIC FAILURE TO AUTO START True True

LOSS OF CNTRL AIR TO THE SCRAM

RD041F 0.00 1.0e-4 0:01:00 7

VLVS

REMOTES

Current Target Rmp

Remf Id Mult Id Description Actime Trig

Value Value time

CF_IAFWATRP LOCAL RFP A TRIP NORMAL TRIPPED 11

SLC SUCT. LINEUP (NORM=SLC TNK /

SL_IASLCTST NORMAL ALT 10

ALT=JUMPER HOSE)

SLC JUMPER HOSE SOURCE (ALT=FP /

SL_IASLCSRC NORMAL NORMAL 10

NORM=DEMIN)

Override

Window Description Tagname OVal AVal Actime Dactime Trig

Type

4-3 OFF GAS FILTER DIFF-HIGH ZUA343 ON ON OFF 2

2-6 RCIC SYSTEM PRESS LOW ZA226 ON ON OFF 00:00:13 5

2-4 SOUTH RHR RM FLOOD LEVEL HI ZUA1224 ON ON OFF 8

SOUTH RHR RM FLOOD LEVEL

1-4 ZUA1214 ON ON OFF 9

HI-HI

4-3 RCIC PUMP SUCTION LO PRESS ZA343 ON ON OFF 5

5-3 RCIC TRUBINE TRIPPED ZA353 ON ON OFF 00:00:13 5

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PANEL OVERRIDES

Position / Actual Override Rmp

Tag ID Description Actime Dactime Trig

Target Value Value time

K2205A CRD PMP B START OFF OFF

K2119A S/B LIQ PUMP A & B PUMP_A OFF OFF

K2119A S/B LIQ PUMP A & B PUMP_A&B OFF OFF

K2119A S/B LIQ PUMP A & B PUMP_B OFF OFF

K1126A AUX OIL PMP AUTO ON OFF

K1126A AUX OIL PMP LOCK OFF ON

K1126A AUX OIL PMP START OFF OFF

K1126A AUX OIL PMP STOP OFF OFF

C.B. BRG WTR LUBE PMP 2A

K4B35B POINT_SELECT OFF ON 00:00:02 3

POINT SELECT

C.B. BRG WTR LUBE PMP 2A

K4B35A NEUT ON OFF 3

CONTROL SWITCH

C.B. BRG WTR LUBE PMP 2A

K4B35A START OFF OFF 3

CONTROL SWITCH

C.B. BRG WTR LUBE PMP 2A

K4B35A STOP OFF ON 3

CONTROL SWITCH

C.B. BRG WTR LUBE PMP 1 PT

Q4B352W5 ON/OFF OFF OFF

SELEC

C.B. BRG WTR LUBE PMP 2B

K4B36A NEUT ON OFF

CONTROL SWITCH

C.B. BRG WTR LUBE PMP 2B

K4B36A START OFF OFF

CONTROL SWITCH

C.B. BRG WTR LUBE PMP 2B

K4B36A STOP OFF ON

CONTROL SWITCH

K2213A DISCH VOL TEST NORMAL ON ON

K2213A DISCH VOL TEST ISOLATE OFF OFF

G1H08G1M RCIC PUMP SUCT PRESS -24.9904 55.6018 55.60185 5

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8.0 OPERATOR RESPONSE AND INSTRUCTIONAL STRATEGIES

EVENT 1: PLACING 2A RFPT CONTROLLER IN AUTOMATIC

Simulator Operator Actions

Ensure Monitored Parameters is open and Scenario Based Testing Variables are loaded.

Simulator Operator Role Play

Evaluator Notes

Plant Response: Place RFPT Master Controller in Automatic IAW 0GP-02, Step 6.3.46

Objectives: SRO - Direct BOP to perform Step 6.3.46 of 0GP-02

BOP - Place RFPT Level Controller is placed in Automatic

ATC - Monitors plant

Success Path: RFPT Master Level Controller is in Automatic and Reactor water level is controlled in

band.

Event Termination: Go to Event 2 at the direction of the Lead Evaluator.

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EVENT 1: PLACING 2A RFPT CONTROLLER IN AUTOMATIC

Time Pos EXPECTED Operator Response Comments

SRO Direct BOP to perform Step 6.3.46 of 0GP-02

RO Monitors the plant

Place RFPT Master Controller in Automatic IAW

0GP-02, Step 6.3.46.

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EVENT 2/3: Raise Reactor Power / RWM Power Failure

Simulator Operator Actions

At the direction of the Lead Evaluator, Initiate Trigger 1 to fail the RWM.

Simulator Operator Role Play

If asked as the RE, continuous rod withdrawal is allowed.

If contacted as plant management, concur and/or approve bypassing the RWM.

If crew is hesitating in continuing startup, notify crew as SM that they are to continue with the

reactor startup.

If asked as the RE report that the RWM has not been INOP during a startup in the last calendar

year.

If contacted as I&C, acknowledge any requests.

Evaluator Notes

Plant Response: RWM will lose power. A-5 (5-2) Rod Block RWM/RMCS Sys Trouble, will annunciate.

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

Direct actions in response to a loss of power to the RWM.

Determine actions required for LCO per Technical Specifications

RO - Withdraw control rods to raise reactor power

Respond to a loss of the RWM

Success Path: Determines RWM Inop and implement 0GP-11, Second Operator Rod Sequence

Checkoff Sheets. Control rods withdrawn to position 48.

Event Termination: Go to Event 4 at the direction of the Lead Evaluator.

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EVENT 2/3: Raise Reactor Power / RWM Power Failure

Time Pos EXPECTED Operator Response Comments

May conduct a brief

SRO (see Enclosure 1 on page 48 for format)

Directs power to be raised IAW 0GP-10, using

SRO Sequence A2X starting with step 164

SRO Acknowledges receipt of A-5 alarm

Review Tech Specs: 3.3.2.1 (see page 31)

Determines RWM is Inop - Condition C applies:

C.2.1.1 - Verifies >12 rods have been withdrawn

and

C.2.2 - Startup can continue with a second

independent verification (0GP-11).

SRO Directs RWM placed in BYPASS

Establishes second verifier using 0GP-11,

Second Operator Rod Sequence Checkoff

Sheets

BOP Monitor plant parameters during evolution

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EVENT 2/3: Raise Reactor Power / RWM Power Failure

Time Pos EXPECTED Operator Response Comments

Continues rod withdrawal per GP-10 (see page

20) IAW guidance of 2OP-07 (see page 22).

NOTE: Verify that an over-travel check is

performed for each rod at position 48.

Acknowledge, report, review A-5 (5-2), Rod

Block RWM/RMCS Sys Trouble. (see page 25)

Reports APP reference to TS 3.3.2.1 and 3.1.6

ATC Determines failure of RWM

When directed by CRS, places the RWM in

BYPASS

Continues rod withdrawal per GP-10 (see page

20) IAW guidance of 2OP-07 (see page 22) and

establishes second verifier IAW 0GP-11 (see

page 30)

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RSB

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EVENT 4: OFF GAS FILTER HI D/P

Simulator Operator Actions

At the direction of the lead evaluator, Initiate Trigger 2 to bring in Off-Gas Filter Diff-Hi

annunciator

Simulator Operator Role Play

IF contacted as Outside AO to verify Off-gas filter Diff pressure, report local DP indication is

reading 13 inches water.

IF contacted as Unit One report steps 6.3.3.2 and 3 are complete. (1-OG-FV-244-4, 1-OG-FV-

244-5, and 1-AOG-HCV-101 are closed)

IF contacted as AO report 1-OG-CD-V7 is CLOSED (Step 4)

IF contacted as AO report 2-OG-CD-V7 is OPEN (Step 5)

IF contacted as Outside AO to verify Off-gas filter Diff pressure after filter swap, report local DP

indication is reading 3 inches water.

When contacted as AO report 2AOG-HCV-101 is in OPEN position.

Evaluator Notes

Plant Response: Off-Gas Filter Diff-Hi alarm annunciates.

Objectives: SRO -Direct actions in response to a Off-gas Filter Diff-Hi alarm.

BOP - Respond to clogged off-gas filter IAW APP and 2OP-30.

Success Path: Swap Off-gas filters per OP-30.

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

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EVENT 4: OFF GAS FILTER HI D/P

Time Pos EXPECTED Operator Response Comments

Direct crew to perform the actions of UA-3, 4-3,

SRO OFF GAS FILTER DIFF-HIGH alarm

Direct crew to swap Off-gas filters per 2OP-30

SRO Section 6.3.3.

May conduct a brief

(see Enclosure 1 on page 48 for format)

ATC Monitors the plant.

Respond to UA-3, 4-3, OFF GAS FILTER DIFF-

HIGH alarm

Dispatch Outside AO to verify Off-gas filter Diff

Hi locally

Place Off-gas Standby filter in service per OP-

30 Section 6.3.3

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EVENT 5: CW LUBE WATER PUMP TRIP

Simulator Operator Actions

At the direction of the Lead Evaluator, Initiate Trigger 3 to fail Bearing Lube Water Pump A.

Simulator Operator Role Play

NOTE: The AO is performing rounds at Caswell Beach.

If directed to investigate as AO report Bearing Lube Water Pump A has a thermal overload.

If asked, after started, report Bearing Lube Water Pump B running SAT.

If asked after starting CW Discharge pumps report all started are SAT

If asked as Unit One to verify all CW Discharge Pumps are running, report that all are running.

Evaluator Notes

Plant Response: Annunciator UA-24 (6-7), CW DISCH PMP LUBE WATER PRESSURE LOW and UA-

24 (5-7), CW DISCH PMP LUBE WATER FLOW LOW due to a trip of the running

pump and failure of the standby pump to start. The BOP operator is expected to start

the 2B Bearing Lube Water Pump.

Objectives: SRO - Direct actions to restore Bearing Lube water pressure and flow.

BOP - Start the standby Bearing Lube Water Pump

Success Path: Lube water pressure and flow re-established before a trip of the CWOD pumps

occurs.

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

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EVENT 5: CW LUBE WATER PUMP TRIP

Time Pos EXPECTED Operator Response Comments

Acknowledges annunciator report for:

UA-24 (6-7), CW DISCH PMP LUBE WATER

PRESSURE LOW

UA-24 (5-7), CW DISCH PMP LUBE WATER

FLOW LOW

SRO Directs starting of the standby lube water pump

If CW Discharge Pumps have tripped, after

starting Bearing Lube Water Pump B, direct

SRO restarting CW Discharge Pumps.

(May direct IAW OP-29)

May contact Unit One to verify all CW Discharge

Pumps are running.

May conduct a brief

(see Enclosure 1 on page 48 for format)

ATC Plant Monitoring

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EVENT 5: CW LUBE WATER PUMP TRIP

Time Pos EXPECTED Operator Response Comments

Acknowledges, reports and reviews

annunciators:

BOP UA-24 (6-7), CW DISCH PMP LUBE WATER

PRESSURE LOW and

UA-24 (5-7), CW DISCH PMP LUBE WATER

FLOW LOW

Determines failure of the standby pump to start.

Depresses the point select pushbutton and then

places the B CW Lube Water Pump to start.

May reset the supervisory by depressing reset

pushbutton.

If CW Discharge pumps have tripped, will restart

CW Discharge Pumps. (May use OP-29)

Depresses the point select pushbutton and then

places the CW Discharge Pump to start for each

pump desired to be started.

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EVENT 6: RCIC PUMP SUCTION LO PRESS

Simulator Operator Actions

At the direction of the Lead Evaluator, Initiate Trigger 5 to activate the RCIC low suction

pressure condition.

Simulator Operator Role Play

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

If directed to investigate as AO report that you dont see anything wrong

Evaluator Notes

Plant Response: A3 4-3, RCIC Pump Suction Low Pressure, 13 seconds later A-02 2-6, RCIC System

Press Low and A3 5-3, RCIC Turbine Tripped, annunciators are received. The RCIC

suction pressure switch fails low which causes the RCIC turbine to trip. The RCIC

E51-V8 will not auto close and the operator should make the auto action occur. RCIC

will not be available for the rest of the scenario.

Objectives: SRO - Directs RCIC auto actions completed.

Determines Tech Spec implication

RO - Closes RCIC E51-V8

Success Path: Tech Specs addressed and RCIC E51-V8 closed

Event Termination: Go to Event 7 at the direction of the Lead Evaluator.

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EVENT 6: RCIC PUMP SUCTION LO PRESS

Time Pos EXPECTED Operator Response Comments

Acknowledge report of RCIC alarms.

A-03 4-3, RCIC Pump Suction Lo Press.

SRO After a 13 second time delay

A-03 5-3, RCIC Turbine Tripped.

A-02 2-6, RCIC System Press Low

SRO Direct the RO to close the RCIC E51-V8.

Enters Tech Specs LCO 3.5.3 Condition A:

A1, Verify by administrative means High

Pressure Coolant Injection System is

Operable immediately and

A2, Restore RCIC System to Operable status in

14 days

May conduct a brief (See Enclosure 1, page 48

SRO for format of the brief.

Announce and reference APPs.

A-03 4-3, RCIC Pump Suction Lo Press

ATC After a 13 second time delay

A-03 5-3, RCIC Turbine Tripped

A-02 2-6, RCIC System Press Low

Closes the RCIC E51-V8

ATC OR

May depress Turbine Trip pushbutton.

BOP Monitor plant

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EVENT 7/8/9: CRD and RFP Trip / SDV Rupture / HP Injection Loss

Simulator Operator Actions

At the direction of the Lead Evaluator, Initiate Trigger 7 to activate Control rod drifts and SDV

rupture.

CRD and RFP A will trip when scram pushbuttons are depressed. HPCI AOP will fail if

attempted to place in service, RCIC has already failed, control switches are failed for SLC and

the standby CRD pump.

After the unit has scrammed delete remote CF_IAFWATRP

Simulator Operator Role Play

If contacted as the AO, report:

A RFP Tripped on Emergency Shutdown which has cleared.

CRD pump is tripped on overcurrent.

HPCI Aux Oil Pump trip and will not reset.

If contacted, acknowledge request for EQ evaluations for the reactor building.

If dispatched to line up Demin water to SLC wait 4 minutes Initiate Trigger 10 and report

actions are complete.

When contacted as maintenance, acknowledge requests for the various failures.

After the crew recognizes rising secondary containment temperatures, call control room as

RBAO and report steam coming from south side of 20', and that you have left the building.

Evaluator Notes

Plant Response: control rods will start to drift in requiring a manual scram. The RB 20 temperature

rises rapidly and may exceed the MSOT. SCS room temperature and water level will

start rising and will exceed MSO level after several minutes. The FW system should

remain available (starts standby pump) for level control. If cooldown is effectively

implemented the various RB temperatures may not exceed MSOT. The scram

cannot be reset as the leak would be isolated so the SDV Vents and Drains fail.

Objectives: SRO - Directs actions for a Reactor Scram, and SCCP.

ROs - Start a Reactor Feed Pump.

Success Path: RFP started to restore/maintain level.

Event Termination: When RFP is started to restore/maintain level.

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EVENT 7/8/9: CRD and RFP Trip / SDV Rupture / HP Injection Loss

Time Pos EXPECTED Operator Response Comments

Directs insertion of a manual reactor scram

(multiple rod drifts).

After reactor scram, directs actions from RSP:

1. Directs level band (166-206 inches). (HPCI,

SRO RCIC, SLC, and CRD will all fail)

2. Directs pressure band (800 - 1000 psig)

3. Directs LEP-02 for resetting the scram

If level cannot be maintained above 166 inches

SRO enters RVCP, may direct LEP-01

When an area exceeds max normal operating

value, directs SCCP actions:

SRO 1. Directs vital header aligned to service water.

2. Directs RHR Room Coolers started.

3. Directs engineering to evaluate EQ

envelopes.

Directs scram reset IAW LEP-02.

Direct I/C to investigate SDV Vents and Drains

failure.

Determine N026 instruments inop when

SRO Rx Bldg 50' exceeds 140°F

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EVENT 7/8/9: CRD and RFP Trip / SDV Rupture / HP Injection Loss

Determines a reactor manual scram is required

(multiple rod drifts)

Perform immediate actions for reactor scram:

1. Ensures scram valves are open.

2. After steam flow is less than 3 Mlb/hr, place

ATC the reactor mode switch to shutdown.

3. When APRM downscale trip, then trip the

main turbine.

4. Ensure the master reactor level controller

setpoint is 170 inches.

Performs Scram Hard Card (See Enclosure 2

(page 49)

May perform LEP-02 to reset the scram. (See

Enclosure 4, page 52)

Steps 7 and 8 are N/A

Report SDV Vents and Drain Failure.

Maintains pressure and level as directed by the

CRS.

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EVENT 7/8/9: CRD and RFP Trip / SDV Rupture / HP Injection Loss

BOP Restart a RFP (See Enclosure 3, page 50)

If HPCI is attempted to be started the Aux Oil

Pump will fail.

If RCIC is attempted to be started the Turbine

Steam Supply Vlv., E51-F045, will overload.

BOP If the standby CRD pump is attempted to be

started, the pump will not start due to a failed

control switch.

May dispatch AO to lineup SLC to Demin Water

IAW LEP-01. When lined up and the SLC

pumps will not start due to a failed control

switch.

Announce and enter 0AOP-05.0, Radioactive

Spills, High Radiation, And Airborne Activity.

1. Evacuate Reactor Building.

2. Direct closure of 2-FP-PIV33 (Unit 2

Reactor Building Sprinkler Shutoff Valve)

Aligns service water to the vital header by

opening either:

Conv SW to Vital Header Vlv SW-V111 or

Nuc SW to Vital Header Vlv SW-V117.

BOP Starts RHR Room Coolers

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EVENT 10: ED - Anticipate ED

Simulator Operator Actions

At the direction of the Lead Evaluator, Initiate Trigger 9 to activate South RHR Hi-Hi water

level.

NOTE: If nothing is injecting to vessel make sure Trigger 9 occurs prior to reaching TAF.

Do not reset the simulator until receipt of concurrence to do so from the lead examiner

Simulator Operator Role Play

Evaluator Notes

Plant Response: The reactor building temperatures and water levels continue to rise. If cooldown is

effectively implemented the various RB temperatures may not exceed MSOT. If

scram is reset the leak will be isolated.

Objectives: SRO - Directs actions for anticipating emergency depressurization when the second

area is approaching a max safe operating limits or for emergency

depressurization when two areas have exceeded max safe operating limits.

ROs - Perform actions for anticipating emergency depressurization when the second

area is approaching a max safe operating limits or for emergency

depressurization when two areas have exceeded max safe operating limits.

Success Path: Reactor is depressurized to less than 100 psig.

Scenario Termination: When the crew has initiated an Emergency Depressurization in accordance with

0EOP-01-EDP the scenario can be terminated.

Remind students not to erase any charts and not to discuss the scenario until told to do

so by the evaluator/instructor.

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EVENT 10: ED - Anticipate ED

Time Pos EXPECTED Operator Response Comments

May direct SEP-15, Anticipate Emergency

Depressurization, when a second area is

approaching a max safe operating limit. (South

RHR Hi Water level)

Directs Emergency depressurization when two

areas exceed their max safe operating limits.

SRO 1. Directs RO to control RPV injection

2. Directs RO to defeats Group 10 isolation

3. Directs RO to open 7 ADS Valves

If directed, performs SEP-15, Anticipate

RO Emergency Depressurization. (See Enclosure 5,

page 55)

If directed, performs Emergency

Depressurization actions:

RO 1. Controls RPV injection

2. Defeats Group 10 isolation

3. Opens 7 ADS Valves

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ATTACHMENT 1 - Scenario Quantitative Attribute Assessment

LOSS OF CONDENSER VACUUM 0AOP-37.0

Category Scenario Content

Rev. 2 Supp. 1 Req.

Total Malfunctions 5-8 7

Malfunctions after EOP

1-2 3

Entry

Abnormal Events 2-4 2

Major Transients 1-2 1

EOPs Used 1-2 3

EOP Contingency 0-2 2

Run Time 60-90 min 90

Crew Critical Tasks 2-3 2

Tech Specs 2 2

Instrument / Component 2 - OATC

Failures before Major 4

2 - BOP

Instrument / Component

2 2

Failures after Major

Normal Operations 1 1

Reactivity manipulation 1 1

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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 164.

Turnover: Permission for continuous withdrawal has been granted for the rods

going from 12-48.

Protected

ADHR / FPC Loop A / Demin Transfer Pump

Equipment:

The BOP operator is to complete Step 6.3.46 of 0GP-02, Approach to

Comments: Criticality and Pressurization of the Reactor.

A severe thunderstorm watch is in effect for SE North Carolina.

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Appendix D Scenario Outline Form ES-D-1

Facility: Brunswick Scenario No.: NRC-3 Rev 0 Op-Test No.: 2017-301

Developer: J. Viera

Technical Review: Validators: _____________________________

__________________________ _____________________________

Facility Representative: _____________________________

__________________________

Initial Conditions: Unit 2 is operating at 90% RTP. 2A CS Pump and 2A CRD Pump are currently

under clearance. A severe thunderstorm watch is in effect for SE North Carolina.

Turnover: Place the 2A SJAE in FULL LOAD in accordance with 2OP-30, Section 6.3.1.

Event Malf. Event Event

No. No. Type* Description

PLACE THE 2A SJAE IN FULL LOAD

1 n/a N (BOP)

(2OP-30)

C(ATC) OUTWARD ROD DRIFT

2 1, 2

TS (SRO) (2APP-A-05, 0AOP-02.0, 2OP-07, TS 3.1.3)

RESPOND TO RECEIPT OF 2-UA-14 (5-1), DEMIN WATER

3 3 C (BOP)

XFR PUMP HDR PRESS LOW/PWR LOSS (2APP-UA-14)

C (ATC) RESPOND TO RECEIPT OF A-01 (2-5) HPCI FIC POWER

4 4

TS (SRO) LOSS

5 5 C (BOP) RCC FAILURE (0AOP-16.0)

LOSS OF CONDENSER VACUUM

6 6 R (ATC)

(0AOP-37.0)

SCRAM/LOOP

7 7 M

(0AOP-36.1, RSP, RVCP)

C FAILURE EDG4

8 8

(BOP/ATC) (AOP 36.1)

LOCA

9 9 M

(RVCP/PCCP)

T INHIBIT ADS PRIOR TO LL3 ACTUATION

10,11, C FAILURE OF ALL INJECTION SOURCES

10

12,13 (BOP/ATC) (RVCP/PCCP)

STEAM COOLING/ED-LL5

11

(SC via RVCP,ED)

RESTORE LEVEL >LL4 WITH 2A RHR PUMP

12 T

(RVCP)

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, Critical (T)ask

Event 1: Place the 2A SJAE in FULL LOAD

(2OP-30, Section 6.3.1)

Initial scenario alignment will have both SJAEs in HALF LOAD. BOP operator is

expected to perform 2OP-30, Section 6.3.2.

Once Step 7 of section 6.3.1 (depressing Off Gas Train B Master Switch

Off/Reset pushbutton) is complete., the Chief Examiner can move to Event 2.

Event 2: Inward Rod Drift

(2APP-A-05, 0AOP-02.0, 2OP-07, TS 3.1.3)

Once initiated, a low Rod Worth Control Rod will begin to slowly drift out. The

ATC operator is expected to respond to receipt of annunciator 2-A-5 (3-2), ROD

DRIFT, and take action per the APP to arrest the rod motion using a momentary

INSERT signal using the RMCS IAW APP Step 2.a.1. It is expected for correct

operator action to be successful in arresting the rod motion. There are no TS

entry criteria met following the ROD DRIFT with successful arrest.

It is expected for the operating crew to enter 0AOP-02.0 (no operator actions

required). When the simulator staff is contacted for further direction as Reactor

Engineering per 0AOP-02.0, inform the applicant crew to fully insert the rod. A

pre-marked 0GP-10 rod pull sheet will be required to deliver to applicants.

(NOTE: Applicants may elect to attempt rod motion IAW 2APP-A-05 (3-2), Step

5.a.3, without RE consultation.)

Once rod motion is attempted, rod motion will not be possible. Operators will

attempt actions to insert rod IAW 2OP-07, Section 6.3.3. All attempts at rod

insertion will be unsuccessful.

Upon determination that rod cannot be inserted, the SRO is expected to enter TS

3.1.3, Condition A for this rod. The RE will inform the CRS that there are no slow

rods for separation criteria.

Once TSs are addressed or upon Chief Examiner direction if the applicant elects

not to pursue TSs at this time, the Chief Examiner can move to Event 3.

Event 3: Respond to receipt of 2-UA-14 (5-1), DEMIN WATER XFR PUMP HDR

PRESS LOW/PWR LOSS

(2APP-UA-14)

Once initiated, a DEMIN HDR low pressure condition will initiate with a failure of

the AUTO pump to start. The pump running at scenario start will remain in

operation.

Expect BOP response IAW annunciator 2-UA-14 (5-1) to manually start the pump

selected to the AUTO position. Once this pump is started, system pressure will

return to an expected two-pump operation value.

Once this annunciator is clear with at least one pump in operation, the Chief

Examiner can move to Event 4.

Event 4: Respond to Receipt Of A-01 (2-5) HPCI FIC POWER LOSS

(2APP-A-1, TS 3.5.1)

A loss of power to the HPCI FIC will occur requiring the ATC operator to respond

IAW the APP and place the HPCI aux oil pump in pull-to-lock.

Expect SRO to identify entry into TS 3.5.1, Conditions D and E.

Once TSs are addressed or upon Chief Examiner direction if the applicant elects

not to pursue TSs at this time, the Chief Examiner can move to Event 5.

Event 5: Respond to RCC FAILURE

(0AOP16, 2-UA-03 (2-5)

Trip of 2A RCC pump with a failure of the standby 2C RCC pump to auto-start

will occur. BOP operator is expected to diagnose failure of auto-start and

manually start the 2C RCC pump.

Expect SRO to direct entry in AOP-16.

Once the 2C RCC pump is started, the Chief Examiner can move to Event 6.

Event 6: Lowering condenser vacuum

(0AOP-37.0)

With indications of lowering condenser vacuum, expect the ATC operator to carry

out immediate actions of 0AOP-37.0 to lower reactor power IAW 0ENP-24.5 to

maintain condenser vacuum.

The ATC operator is expected to pursue either a recirculation flow reduction

and/or insert rods or a manual runback to lower power.

Ensure that 22.4 inches of vacuum (or the critical parameter established by the

SRO) is not challenged and that power reduction offers sufficient time for the

ATC operator to reduce reactor power.

Once plant conditions are stable with a power reduction > 5% power completed,

the Chief Examiner can move to Event 7.

Event 7: SCRAM/LOOP

(2EOP-01-RSP, RVCP, 0AOP36.1)

The condenser vacuum will degrade further resulting in a reactor scram. Once

the reactor has scrammed, a SAT lockout will occur resulting in a LOOP when

the turbine is tripped

The ATC is expected to perform scram IAs.

The CRS is expected to enter and announce RSP and AOP-36.1.

The CRS may enter RVCP

The ATC/BOP is expected to diagnose and report SAT failure and enter and

announce AOP36.1 and control reactor pressure with SRVs during scram report.

Event 8: FAILURE OF EDG4

(0AOP36.1)

EDG4 will fail to start on the LOOP due to a lockout on E4.

BOP operator is expected to diagnose the lockout on E4 and perform actions

IAW 0AOP36.1.

SRO is expected to direct enter and announce of AOP36.1if not already directed.

Event 9/10: LOCA/FAILURE OF ALL INJECTION SOURCES

(RVCP/PCCP)

A small recirc suction line break will occur, resulting in lowering RPV level and

rising DW pressure.

The ATC/BOP is expected to announce rising DW pressure and lowering level as

they occur.

As level lowers:

Critical Task is met if ADS is inhibited prior to actuation of LL3.

RCIC will not operate due to a failure of the E51-F045, the ATC/BOP operator

will diagnose and report the failure.

RHR D motor overload and trip when LL2 occurs or DW press 1.7 psig w/410

reactor pressure. ATC/BOP operator will diagnose and report the failure

RHR LOOP A will experience a loss of power to F015A due to trip a of 2XA-

2/DF3. ATC/BOP operator will diagnose and report the failure.

When the ATC/BOP attempts to inject SLC, SLC will not inject due to a line

blockage in the discharge line. ATC/BOP operator will diagnose and report the

failure.

The CRS is expected to announce, enter and direct actions of RVCP (if not

already entered) and PCCP (as primary containment conditions dictate)

Event 11: STEAM COOLING/ED ON LL-5

(STEAM COOLING portion of RVCP, ED)

When RPV level lowers to TAF, the CRS is expected Exit RC/P flowpath and

proceed to and direct actions of Steam Cooling IAW RVCP.

ATC/BOP operator is expected to maintain RPV press no more than 200psig

above the initial pressure when TAF was reached.

When RPV level lowers to LL-5, the CRS is expected to exit steam cooling and

go to EDP and direct an ED.

ATC/BOP will open 7 ADS SRVs when directed.

Event 12: RESTORE INJECTION W/ 2A RHR PUMP >LL4

(ED,RVCP)

When 7 SRVs have been opened, power will be restored to the E11-F015A.

The CRS will direct injection with RHR pump A to restore level > LL4.

Critical Task is met if after 7 SRVs are opened, operating crew restores injection

with the 2A RHR pump to restore level above LL-4.

Once the applicant crew has restored injection to the RPV following the ED, the Chief

Examiner can terminate this scenario.

BRUNSWICK TRAINING SECTION

OPERATIONS TRAINING

INITIAL LICENSED OPERATOR

SIMULATOR EVALUATION GUIDE

2017 NRC SCENARIO 3

2A SJAE IN FULL LOAD, ROD DRIFT (OUT), DEMIN HEADER LOW

PRESSURE, HPCI FIC POWER LOSS, RCC FAILURE, LOWERING

CONDENSER VACUUM, LOOP, LOCA, LOSS OF ALL INJECTION (STM

COOLING), ED LL5

REVISION 0

Developer: NRC - Joe Viera Date: 3/31/2017

Technical Review: Dan Hulgin Date: 4/24/2017

Validators: Mike Long Date: 5/5/17

Rob Lax

Trey Bunnell

Facility Representative: Craig Oliver Date: 5/24/17

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REVISION SUMMARY

0 Scenario developed for 2017 NRC Exam.

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TABLE OF CONTENTS

1.0 SCENARIO OUTLINE .................................................................................................................. 4

2.0 SCENARIO DESCRIPTION SUMMARY .................................................................................. 5

3.0 CREW CRITICAL TASKS ........................................................................................................... 9

4.0 TERMINATION CRITERIA ........................................................................................................ 10

5.0 IMPLEMENTING REFERENCES ............................................................................................ 11

6.0 SETUP INSTRUCTIONS ........................................................................................................... 12

7.0 INTERVENTIONS ....................................................................................................................... 14

8.0 OPERATOR RESPONSE AND INSTRUCTIONAL STRATEGIES .................................... 17

ATTACHMENT 1 - Scenario Quantitative Attribute Assessment ..................................................... 76

ATTACHMENT 2 - Shift Turnover ........................................................................................................ 80

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1.0 SCENARIO OUTLINE

Event Malf. No. Type* Event Description

PLACE THE 2A SJAE IN FULL LOAD

1 N (BOP)

(2OP-30)

C(ATC)/

RD005M OUTWARD ROD DRIFT

2

RD012M TS (SRO) (2APP-A-05, 0AOP-02.0, 2OP-07, TS 3.1.3)

RESPOND TO RECEIPT OF 2-UA-14 (5-1), DEMIN

MI_AS_DTPB

3 C (BOP) WATER XFR PUMP HDR PRESS LOW/PWR LOSS

KR

(2APP-UA-14)

C (ATC) RESPOND TO RECEIPT OF A-01 (2-5) HPCI FIC

4 ES015F

TS (SRO) POWER LOSS

5 K4521A C (BOP) RCC FAILURE (0AOP-16.0)

LOSS OF CONDENSER VACUUM

6 CN001F R (ATC)

(0AOP-37.0)

7 EE009A M SCRAM/LOOP

8 DG027F C (BOP/ATC) FAILURE EDG4

9 NB009F M (All) LOCA

RI001F

ES058F

10 RH_ZVRH15AM C (BOP/ATC) FAILURE OF ALL INJECTION SOURCES

SL_VHSL008M

T Inhibit ADS prior to LL3 actuation

11 STEAM COOLING/ED-LL5

12 T RESTORE LEVEL >LL4 WITH 2A RHR PUMP

(N)ormal, (R)eactivity, (C)omponent or Instrument, (M)ajor

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2.0 SCENARIO DESCRIPTION SUMMARY

Event Description

2A SJAE in FULL LOAD IAW 2OP-30, Section 6.3.1.

Initial scenario alignment will have both SJAEs in HALF LOAD. BOP operator is

expected to perform 2OP-30, Section 6.3.1.

1

Once Step 7 of section 6.3.1 (depressing Off Gas Train B Master Switch Off/Reset

pushbutton) is complete., the Chief Examiner can move to Event 2.

Outward Rod Drift (2APP-A-05, 0AOP-02.0, 2OP-07, TS 3.1.3)

Once initiated, a low Rod Worth Control Rod will begin to slowly drift out. The ATC

operator is expected to respond to receipt of annunciator 2-A-5 (3-2), ROD DRIFT,

and take action per the APP to arrest the rod motion using a momentary INSERT

signal using the RMCS IAW APP Step 2.a.1. It is expected for correct operator action

to be successful in arresting the rod motion. There are no TS entry criteria met

following the ROD DRIFT with successful arrest.

It is expected for the operating crew to enter 0AOP-02.0 (no operator actions

required). When the simulator staff is contacted for further direction as Reactor

Engineering per 0AOP-02.0, inform the applicant crew to fully insert the rod. A pre-

marked 0GP-10 rod pull sheet will be required to deliver to applicants. (NOTE:

2

Applicants may elect to attempt rod motion IAW 2APP-A-05 (3-2), Step 5.a.3, without

RE consultation.)

Once rod motion is attempted, rod motion will not be possible. Operators will then

attempt actions to insert rod IAW 2OP-07, Section 6.3.3. Attempts at rod insertion will

be unsuccessful as drive pressure is raised.

The SRO is expected to enter TS 3.1.3, Condition A for this rod. The RE will inform

the CRS that there are no slow rods for separation criteria.

Once TSs are addressed or upon Chief Examiner direction if the applicant elects not

to pursue TSs at this time, the Chief Examiner can move to Event 3

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2-UA-14 (5-1), DEMIN WATER XFR PUMP HDR PRESS LOW/PWR LOSS DUE TO

TRIP OF DEMIN XFER PUMP 2B, WITH FAILURE OF 2A AND 2C DEMIN XFR

PUMPS TO AUTOSTART

DEMIN HDR low pressure condition will initiate due to a trip of the 2B Demin xfer

pump with a failure of the AUTO pumps to start.

3 Expect BOP response IAW annunciator 2-UA-14 (5-1) to manually start the pump

selected to the AUTO-1 position. Once this pump is started, system pressure will

return to an expected one-pump operation value.

Once this annunciator is clear with at least one pump in operation, the Chief Examiner

can move to Event 4.

RECEIPT OF A-01 (2-5) HPCI FIC POWER LOSS

A loss of power to the HPCI FIC will occur requiring the ATC operator to respond IAW

the APP and place the HPCI aux oil pump in pull-to-lock. The Unit CRS will enter TS

4 3.5.1 Condition D and E.

Once TSs are addressed or upon Chief Examiner direction if the applicant elects not

to pursue TSs at this time, the Chief Examiner can move to Event 5

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RCC FAILURE 0AOP16, 2-UA-03 (2-5)

Trip of 2A RCC pump with a failure of the standby 2C RCC pump to auto-start. The

5 crew will enter AOP-16, and manually start the 2C RCC pump.

Once the 2C RCC pump is started, the Chief Examiner can move to Event 6

A leak will occur in the condenser, and with lowering condenser vacuum, expect the

ATC operator to carry out immediate actions of 0AOP-37.0 to lower reactor power

IAW 0ENP-24.5 to maintain condenser vacuum.

The ATC operator is expected to pursue either a recirculation flow reduction and/or

rod isnertion or a manual runback to lower power.

6

Ensure that 22.4 inches of vacuum (or the critical parameter established by the SRO)

is not challenged and that power reduction offers sufficient time for the ATC operator

to reduce reactor power.

Once the ATC has established a power reduction > 5%, the Chief Examiner can

move to Event 7.

SCRAM/LOOP

The condenser vacuum will degrade further resulting in a reactor scram. Once the

reactor has scrammed, a SAT lockout will occur resulting in a LOOP when the turbine

is tripped.

7

The ATC is expected to perform scram IAs.

The CRS is expected to enter and announce RSP and AOP-36.1.

The CRS may enter and direct RVCP.

The ATC/BOP is expected to diagnose and report SAT failure and enter and

announce AOP36.1 and control reactor pressure with SRVs during scram report.

FAILURE OF EDG4

EDG4 will fail to start on the LOOP due to a lockout on E4.

8

BOP operator is expected to diagnose the lockout on E4 and perform actions IAW

0AOP36.1.

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LOCA/FAILURE OF ALL INJECTION SOURCES

A small recirc suction line break will occur, resulting in lowering RPV level and rising

DW pressure.

The ATC/BOP is expected to announce rising DW pressure and lowering level as they

occur.

As level lowers:

ADS will be inhibited prior to actuation of LL3.

RCIC will not operate due to a failure of the E51-F045, the ATC/BOP operator will

diagnose and report the failure.

9/10

RHR D motor overload and trip when LL2 occurs or DW press 1.7 psig w/410 reactor

pressure. ATC/BOP operator will diagnose and report the failure

RHR LOOP A will experience a loss of power to F015A due to trip a of 2XA-2/DF3.

ATC/BOP operator will diagnose and report the failure.

When the ATC/BOP attempts to inject SLC, SLC will not inject due to a line blockage

in the discharge line. ATC/BOP operator will diagnose and report the failure.

The CRS is expected to announce, enter and direct actions of RVCP (if not already

entered) and PCCP (as primary containment conditions dictate).

STEAM COOLING/ED ON LL-5

When RPV level lowers to TAF, the CRS is expected Exit RC/P flowpath and proceed

to and direct actions of Steam Cooling IAW RVCP.

ATC/BOP operator is expected to maintain RPV press no more than 200psig above

11

the initial pressure when TAF was reached.

When RPV level lowers to LL-5, the CRS is expected to exit steam cooling and go to

EDP and direct an ED.

ATC/BOP will open 7 ADS SRVs when directed.

RESTORE INJECTION W/ 2A RHR PUMP >LL4

When 7 SRVs have been opened, power will be restored to the E11-F015A.

12 The CRS will direct injection with RHR pump A to restore level > LL4.

Once the applicant crew has restored injection to the RPV following the ED, the Chief

Examiner can terminate this scenario.

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3.0 CREW CRITICAL TASKS

Critical Task #1

Critical Task is met if ADS is inhibited prior to actuation of LL3.

Critical Task #2

Critical Task is met if after 7 SRVs are opened, operating crew restores injection with the 2A RHR

pump to restore level above LL-4.

Pre-identified potential Critical Task

If Crew Emergency Depressurizes prior to LL-5 this creates a potential new critical task.

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4.0 TERMINATION CRITERIA

Once the applicant crew restores injection with the 2A RHR pump, the Chief Examiner can

terminate this scenario.

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5.0 IMPLEMENTING REFERENCES

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

Number Title

2-A-01 (2-5) HPCI FIC POWER LOSS

2-A-05 (3-2) ROD DRIFT

2-A-05 (5-5) PRI CTMT HI/LO PRESS

2-UA-03 (2-5) RBCCW PUMP DISCH HEADER PRESS LOW

2-UA-14 (5-1) DEMIN WATER XFR PUMP HDR PRESS LOW/PWR LOSS

2-UA-44 SJAE DISCHARGE PRESS HIGH

2OP-07 REACTOR MANUAL CONTROL SYSTEM OPERATING PROCEDURE

CONDENSER AIR REMOVAL AND OFF-GAS RECOMBINER

2OP-30

SYSTEM

0AOP-02.0 CONTROL ROD MALFUNCTION/MISPOSITION

0AOP-16.0 RBCCW SYSTEM FAILURE

0AOP-36.1 LOSS OF ANY 4160V BUSES OR 480V E-BUSES

0AOP-37.0 LOW CONDENSER VACUUM

2EOP-01-RSP REACTOR SCRAM PROCEDURE

2EOP-01-RVCP REACTOR VESSEL CONTROL PROCEDURE

0EOP-02-PCCP PRIMARY CONTAINMENT CONTROL PROCEDURE

0EOP-01-EDP EMERGENCY DEPRESSURIZATION PROCEDURE

U2 TS 3.1.3 CONTROL ROD OPERABILITY

U2 TS 3.5.1 ECCSOPERATING

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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-11.

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. Ensure Reactor power has been reduced to ~90% power using Recirc.

2. Ensure Demin Xfr pump 2B is running with 2A in position1 and 2C in position 2.

3. Ensure 2B CRD pump is running.

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

CS PUMP 2A Red Tag

2A CRD PUMP Red Tag

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

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

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

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

Required Materials

N/A

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.

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7.0 INTERVENTIONS

TRIGGERS

Trig Type ID

1 Malfunction RD005M - [CONTROL ROD WITHDRAWAL DRIFT]

2 Malfunction RD012M - [STUCK CONTROL ROD]

3 Remote Function MI_AS_DTPBKR - [2B DEMIN WATER XFER PUMP BREAKER]

4 Malfunction ES015F - [HPCI POWER SUPPLY FAILURE]

5 DI Override K4521A - [RB CCW PMP B AUTO]

6 Malfunction CN001F - [LOSS OF CONDENSER VACUUM]

7 Malfunction EE020F - [UNIT 2 SAT RELAY FAILURE]

7 Malfunction DG027F - [DG4 DIFFERENTIAL FAULT]

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

9 Remote Function ED_ZIEDH14 - [PNL 2AB-TB PWR (E8=NORM/E7=ALT)]

10 Malfunction NB009F - [SMALL RECIRC PMP SUCT LINE RUPTURE]

10 Trigger Command dod:Q1201LGN

12 Trigger Command mfi:RD005M,False,0,0,0,12,10-27

Trig # Trigger Text

7 K3C56IT6 - [EMERG TRIP SYS TRIPPED]

12 K2620JVD - [ROD MOVEMENT CONROL]

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MALFUNCTIONS

Malf Mult Current Target Rmp

Description Actime Dactime Trig

ID ID Value Value time

RD005 CONTROL ROD WITHDRAWAL

10-27 False True 1

M DRIFT

RD012

10-27 STUCK CONTROL ROD False True 2

M

ES015F HPCI POWER SUPPLY FAILURE False True 4

900.0

CN001F LOSS OF CONDENSER VACUUM 0.00 0:03:00 6

000

EE020F UNIT 2 SAT RELAY FAILURE False True 7

DG027F DG4 DIFFERENTIAL FAULT False True 0:00:45 7

SMALL RECIRC PMP SUCT LINE 50.00

NB009F A 0.00 0:30:00 10

RUPTURE 000

RHR PUMP MOTOR WINDING

ES058F D True True

FAULT

TURB STEAM SUPPLY * VLV E51-

RI001F E51-F045 True True

F045

REMOTES

Current Target Rmp

Remf Id Mult Id Description Actime Trig

Value Value time

BKR CTL DC FUSES CORE SPRAY PUMP

ED_IABKCF05 OUT OUT

2A

MI_AS_DTPBK

2B DEMIN WATER XFER PUMP BREAKER CLOSED OPEN 3

R

SW_VHSW146

CONV SW TO RBCCW HXS V146 SHUT OPEN 8

L

NORMA

ED_ZIEDH14 PNL 2AB-TB PWR (E8=NORM/E7=ALT) ALT 9

L

RH_ZVRH15A

E11-F015A INBD INJ VLV OFF OFF

M

SL_VHSL008M INBOARD MANUAL INJ VLV F008 CLOSE CLOSE

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PANEL OVERRIDES

Actu

Position / Override Rmp

Tag ID Description al Actime Dactime Trig

Target Value time

Value

K2204A CRD PMP A AUTO OFF OFF

K2204A CRD PMP A START OFF OFF

K2204A CRD PMP A STOP ON ON

Q2204LG

CRD PMP A GREEN ON/OFF ON OFF

D

Q2204RR

CRD PMP A RED ON/OFF OFF OFF

D

K5701A DEMIN WTR XFR PMP 2A 1 ON OFF

K5701A DEMIN WTR XFR PMP 2A 2 OFF OFF

K5703A DENIM WTR XFR PMP 2C 1 OFF OFF

K5703A DENIM WTR XFR PMP 2C 2 ON OFF

K4522A RBCCW PMP C AUTO AUTO ON OFF

K4521A RB CCW PMP B AUTO OFF OFF ON 5

K4521A RB CCW PMP B AUTO AUTO OFF OFF 5

K4521A RB CCW PMP B AUTO ON ON OFF 5

Q1201LG RHR VLV E11-F021A

ON/OFF OFF ON

N GREEN

Q2206RR

MAN INJ RED ON/OFF ON ON

O

Q2206LG

MAN INJ GREEN ON/OFF ON OFF

O

Override

Window Description Tagname OVal AVal Actime Dactime Trig

Type

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8.0 OPERATOR RESPONSE AND INSTRUCTIONAL STRATEGIES

EVENT 1: PLACE THE 2A SJAE IN FULL LOAD IAW 2OP-30

Simulator Operator Actions

Ensure Monitored Parameters is open and Scenario Based Testing Variables are loaded.

Simulator Operator Role Play

If contacted as TBAO to remain available for valve or breaker problems, acknowledge request

If contacted for status of service air injection, report it is not aligned to SJAE 2B.

If contacted to close SA valves (V890/V888), wait 1 minute report closed

If contacted to close V5023, wait 30 seconds and report closed.

If contacted as E&C provide name, if contacted to perform sample acknowledge request..

Evaluator Notes

Plant Response: 2B SJAE operating at half load will be S/D and 2A SJAE operating at half load will be

in full load.

Objectives: SRO - Direct BOP operator to place 2A SJAE in full load secure Off Gas Train B.

RO - Monitor plant parameters.

BOP - Place 2A SJAE in full load, secures Off Gas Train B.

Success Path: 2A SJAE is placed in full load IAW 2OP-30 Section 6.3.1

Event Termination: Once Step 7 of section 6.3.1 (depressing Off Gas Train B Master Switch Off/Reset

pushbutton) is complete., the Chief Examiner can move to Event 2.

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EVENT 1: PLACE THE 2A SJAE IN FULL LOAD IAW 2OP-30

Time Pos EXPECTED Operator Response NOTES

SRO Conduct shift turnover shift briefing.

SRO Directs BOP operator to full load IAW 2OP-30

May conduct a brief (see Enclosure 1 on page

76 for format)

ATC Monitors plant parameters

May contact TB AO to remain available to

respond to any valve or breaker problems

Performs 2OP-30 Section 6.3.1

Depresses 2-OG-CS-4290, Off Gas

Train A Full Load pushbutton

NOTE: UA-45 6-3 will alarm when the full

load pushbutton is depressed. Applicant

should diagnose that this is normal until the

BOP Off Gas Train B Off button is depressed and

the CO-V17 closes.

Verifies valves

Monitors SJAE Off-Gas rad monitors

Secures Off Gas train B

Direct Chemistry to perform surveillance

for SR 3.7.5.1

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EVENT 2: OUTWARD ROD DRIFT

Simulator Operator Actions

At the direction of the Lead Evaluator, Initiate Trigger 1 (RD005M for CR10-27) to slowly drift

the rod out.

Once the initial rod withdrawal has been arrested, Initiate Trigger 2 (RD012M for CR10-27) to

stick CR10-27. (make sure it settles into a position before you stick it, or it will not have position

indication)

Simulator Operator Role Play

If contacted as RE acknowledge the request, and inform the crew to fully insert CR10-27 using

continuous insert. Provide pre-marked copy of 0ENP-24.5 individual rod movement instructions.

When contacted as AO to locally provide drive pressure, monitor CRD drive header d/p

(G2910g1d) and state drive press (actual value + current reactor pressure)

Once Condition A is entered, notify the CRS that there are no slow rods.

Evaluator Notes

Plant Response: CR10-27 will drift out, the ATC will momentarily place the RMCS switch to insert and

arrest rod motion. Further attempts to insert the rod will be unsuccessful. CR10-27

will remain at a more outward position and reactor power will be slightly higher.

Objectives: SRO - Direct entry into 0AOP-02.0. Enter TS 3.1.3 Condition A.

ATC - Respond To Control Rod Drift alarm for CR10-27. Arrest rod motion for

CR10-27. Attempt to fully insert rod 10-27 IAW 0AOP-2.0 and 2OP-07.

Success Path: CR10-27 withdrawal arrested and TS 3.1.3 Condition A entered.

Event Termination: Once TSs are addressed or upon Chief Examiner direction if the applicant

elects not to pursue TSs at this time, the Chief Examiner can move to

Event 3.

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EVENT 2: OUTWARD ROD DRIFT

Time Pos EXPECTED Operator Response Comments

Direct entry into and actions of 0AOP-02.0 for

Rod Drift.

May brief (enclosure 1 page 76)

May enter 0AOP-03.0

SRO May contact RE about drifting rod CR10-27.

SRO Direct CR10-27 fully inserted

When rod has been determined to be stuck,

Enters TS 3.1.3 Condition A

Condition A: One withdrawn control rod

stuck

Required Action: Verify stuck control rod

separation criteria are met

Completion Time: Immediately

AND

Required Action: Disarm the associated

control rod drive (CRD)

Completion Time: 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months

AND

Required Action: Perform SR 3.1.3.2 for

SRO each withdrawn OPERABLE control rod

Completion Time: 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months from

discovery of Condition A concurrent with

THERMAL POWER greater than the low

power setpoint (LPSP) of the RWM

AND

Required Action: Perform SR 3.1.1.1

Completion Time: 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months

Note:

Applicant may choose to delay entry into the TS

until the CR is scrammed as the bases states,

A control rod is considered stuck if it will not

insert by either CRD drive water or scram

pressure.

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EVENT 2: EVENT 2: OUTWARD ROD DRIFT

Time Pos EXPECTED Operator Response Comments

Reviews A-05 (3-2 ) Rod Drift:

Notifies CRS CR10-27 is drifting out of

the core.

Arrests rod motion by momentarily

placing the RMCS switch to insert.

May notify RE

Notifies CRS CR10-27 is no longer

drifting and position of CR10-27

At the direction of the CRS, attempts to fully

ATC insert CR10-27 IAW A-05 (3-2) or as specified

by the RE.

Attempts to insert CR10-27 using 2OP-07

section 6.3.3

Raise CR drive DP to 300 psid

Attempt insert

Raise CR drive DP to 350 psid

Attempt insert

Raise CR drive DP to 400 psid

Attempt insert

Raise CR drive DP to 450 psid without

exceeding 1450 psig drive header

pressure limit

Attempt insert

Lower CR drive D/P 260-275 psid

Notifies RE

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EVENT 2: EVENT 2: OUTWARD ROD DRIFT

Time Pos EXPECTED Operator Response Comments

BOP Monitors and adjusts balance of plant conditions

BOP May provide peer check of rod manipulations

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EVENT 3: DEMIN WTR XFER PUMP 2B TRIP w/ DEMIN WTR XFR PUMPS AUTOSTART FAILURE

Simulator Operator Actions

At the direction of the lead evaluator Insert Trigger 3 (MI-AS-DTPBKR OPEN) to open the

breaker for Demin XFR Pump 2B.

If contacted as RW operator to investigate, acknowledge request.

Simulator Operator Role Play

If contacted as WCC or Maint acknowledge the request.

Evaluator Notes

Plant Response: Demin Xfer pump 2B will trip resulting in lowering Demin Hdr pressure. The pumps

selected to auto 1 (2A) and auto 2 (2C) will fail to auto start. Once 2A and/or 2C is/are

manually started, Demin Hdr pressure will return to normal with one or two pump

operation.

Objectives: BOP - Respond IAW 2-UA-14 (5-1) and start 2A and/or 2C Demin Water Xfer Pump.

Success Path: Start 2A Demin Water Xfer Pump

Event Termination: Once this annunciator is clear with one or two pumps in operation, the Chief

Examiner can move to Event 4.

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EVENT 3: DEMIN WTR XFER PUMP 2B TRIP w/ DEMIN WTR XFR PUMPS AUTOSTART FAILURE

Time Pos EXPECTED Operator Response Comments

May conduct a brief

SRO (see Enclosure 1 on page 76 for format)

ATC Monitors the plant.

Responds to 2-UA-14 (5-1)

Diagnoses low Hdr pressure and failure

of 2A and 2C Demin Xfer pumps to auto

start.

BOP * Notifies the CRS of failure

Starts 2A Demin Xfer Pump (may start

the 2C pump or both 2A and 2C)

May place the 2B Xfer pump switch in

OFF

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EVENT 4: RECEIPT OF A-01 (2-5) HPCI FIC POWER LOSS

Simulator Operator Actions

At the direction of the lead evaluator, INSERT TRIGGER 4 (malfunction ES015F) to fail the

power supply to the HPCI FIC.

Simulator Operator Role Play

If asked as the WCC to investigate, wait 2 minutes and report that the fuse E41-F25 is blown.

If asked to investigate as RBAO acknowledge request.

If asked to replace the fuse, report fuse immediately blew again when replaced.

If contacted as WCC to verify RCIC status, report no work is scheduled for RCIC.

If contacted as WCC/Maint for repair/investigation of blown fuse E41-F25, acknowledge

request.

Evaluator Notes

Plant Response: Indicator on: E41-FIC-R600, Pump Suction Pressure E41-PI-R606, Turbine Steam

Supply Pressure E41-PI-R602, Turbine Steam Exhaust Pressure E41-PI-R603, and

Pump Discharge Pressure E41-PI-R601 all read downscale. A-01 (2-5) HPCI FIC

POWER LOSS is received. If an auto initiation signal is received and power is lost to

the flow controller, but not to the initiation logic, HPCI will slow to a very low speed

that will be a function of the amount of steam leakage past the turbine control valves

or would stop altogether. If the turbine were to continue to run, the speed would

probably be erratic due to insufficient flow to maintain the discharge check valve

open.

Objectives: SRO - Enter TS 3.5.1 Condition D and E

ATC - Perform actions IAW A-01 (2-5), place HPCI AUX oil pump in pull-to-lock.

Verifies by administrative means RCIC System is OPERABLE

Success Path: Place HPCI Aux Oil Pump in pull to lock, verify by administrative means RCIC System

is OPERABLE, and enter LCO 3.5.1 Conditions D and E.

Event Termination: Once HPCI aux oil pump is pin pull to lock, and TSs are addressed or upon Chief

Examiner direction if the applicant elects not to pursue TSs at this time, the Chief

examiner can move to Event 5

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EVENT 4: RECEIPT OF A-01 (2-5) HPCI FIC POWER LOSS

Time Pos EXPECTED Operator Response Comments

May conduct a brief

(see Enclosure 1 on page 76 for format)

Enters TS LCO 3.5.1 Condition D and E:

D. Condition: HPCI System inoperable

Action: D.1 Verify by administrative means RCIC

System is OPERABLE.

Completion Time: Immediately

AND

D.2 Restore HPCI System to OPERABLE status

Completion Time: 14 days

SRO E. Condition: HPCI System inoperable.

AND

One low pressure ECCS injection/spray

subsystem is inoperable.

Action: E.1 Restore HPCI System to

OPERABLE status.

Completion Time: 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months

OR

E.2 Restore low pressure ECCS injection/spray

subsystem to OPERABLE status: 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months

SRO Directs replacement of fuse E41-F25

SRO May contact maintenance or WCC to investigate

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EVENT 4: RECEIPT OF A-01 (2-5) HPCI FIC POWER LOSS

Time Pos EXPECTED Operator Response Comments

Acknowledges, reports, and performs actions of

A-01 (2-5), HPCI FIC POWER LOSS:

Contacts RBAO to investigate.

Places HPCI aux oil pump in pull-to-lock.

ATC When directed verifies RCIC is OPERABLE.

.

BOP Monitors the plant.

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EVENT 5: RCC FAILURE

Simulator Operator Actions

At the direction of the Lead Evaluator, INITIATE TRIGGER 5 (K4520A) to trip the 2B RCC

Pump

Simulator Operator Role Play

If directed as the RB AO to investigate RCC low pressure, report RCC Pump 2B Motor is hot to

the touch, breaker is tripped.

If contacted as the RB AO, inform the control room prestart checks of the 2C RCC pump are

complete

If directed to investigate as I&C acknowledge the request

Evaluator Notes

Plant Response: The crew will respond to a trip of the 2B RCC pump and pressure will lower. The 2C

RCC Pump will fail to auto start and the low pressure alarm will be received. Starting

the 2C RCC pump will restore pressure to normal

Objectives: SRO - Directs BOP to enter and execute 0AOP-16.0

BOP - Refers to 2-UA-3 2-5 and 0AOP-16.0 to respond to the 2C Pump failure to start

Success Path: Starting the 2C RCC pump will restore pressure to normal.

Event Termination: Once the 2C RCC pump is started, the Chief Examiner can move to Event 6

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EVENT 5: RCC FAILURE

Time Pos EXPECTED Operator Response Comments

May conduct a brief

(see Enclosure 1 on page 76 for format)

Directs BOP operator to enter and announce

0AOP-16.0

Directs start of 2C RCC pump if BOP fails to

recognize auto start failure

Directs Maintenance to investigate 2B RBCCW

pump trip, and 2C auto-start failure

May direct BOP to place 2B RBCCW Pump in

OFF

ATC Monitors the plant

Recognize the failure of the 2C RCC pump to

auto start at 65 psig

BOP Manually starts 2C RBCCW Pump

Refers to Annunciator Response 2-UA-3 2-5

(RBCCW Disch Header Press Lo)

When directed, enters and announces 0AOP-

16.0, RBCCW System Failures

Dispatches AO to investigate cause of RBCCW

low pressure

BOP May place 2B RBCCW Pump switch to OFF

BOP Verifies RBCCW System is operating normally

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EVENT 6: LOSS OF CONDENSER VACUUM 0AOP-37.0

Simulator Operator Actions

When directed, INSERT TRIGGER 6 (CN001F) condenser in-leak of 900 over 3 minutes.

Adjust the vacuum leak as necessary to obtain a 5% power reduction by the crew.

When power has been reduced 5%, and when directed by NRC move to event 7.

Simulator Operator Role Play

If contacted as WCC to get a team to look for the condenser leak acknowledge the request.

If contacted as Outside AO to investigate screens acknowledge request, wait 2 minutes and

report screens are normal.

If contacted as TBAO to investigate leaks acknowledge requests

Evaluator Notes

Plant Response: Condenser vacuum will slowly lower and off gas flow will rise. Lowering power will

stabilize condenser vacuum. AOG will bypass due to high off gas flow.

Objectives: SRO - Direct entry into 0AOP-37.0. Direct RO to lower power.

BOP - Recognize and report lowering condenser vacuum and rising off gas flow

ATC - Lower power as required to maintain condenser vacuum greater than 24.5

inches Hg.

Success Path: Lower reactor power to stabilize vacuum.

Event Termination: When reactor power has been reduced 5%, the lead examiner may proceed to

event 7

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EVENT 6: LOSS OF CONDENSER VACUUM 0AOP-37.0

Time Pos EXPECTED Operator Response Comments

SRO Direct entry into 0AOP-37.0

SRO Direct RO to lower power

Lower power using Reactor Recirc flow and/or

May initiate a manual runback to

ATC Rod insertion to maintain condenser vacuum

initially reduce power

greater than 24.5 inches Hg.

Recognize and report lowering condenser

vacuum and rising off gas flow

BOP Enter and announce 0AOP-37.0

May dispatch operators into the field to hunt for

the vacuum leak

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EVENT 7/8: SCRAM/LOOP/FAILURE OF EDG4

Simulator Operator Actions

At the direction of the Lead Evaluator, MODIFY CN001F to increase in-leakage into the main

condenser to ensure a reactor scram (~2500). ENSURE TRIGGER 7 (EE020F) ACTIVATES

ON TURBINE TRIP in order to lockout the SAT and initiate the LOOP .

If directed to align RBCCW to CSW cooling, wait 4 minutes and Initiate TRIGGER 8 Open SW-

V146 (SW_VHSW146L)

If directed to swap AB panels wait 2 min Initiate TRIGGER 9 2AB-TB to ALT (ED_ZIEDH14)

If requested to x-tie of service air, wait 3 min & MODIFY RF AI_VHAIV07L, OPEN

Simulator Operator Role Play

If requested to monitor DGs, acknowledge alarms on DG local Alarm Panel, report alarms if

requested. If asked as AO to investigate E4/DG4, report device 86DP tripped @ E4 switchgear.

If asked to swap Panel 2AB-TB to alternate, notify Sim Operator to activate Trigger 9 (2 min)..

If directed to align RBCCW to CSW cooling, wait 4 minutes and inform Sim Operator to align

RBCCW to CSW Trigger 8

If asked as load dispatcher, transmission line crews are investigating cause and no current

estimates of restoration

If contacted as Maint/I&C to investigate DG4 or SAT, acknowledge request.

Evaluator Notes

Plant Response: LOOP on Unit 2 (Unit 1 maintains off-site power), Reactor scram, MSIV closure,

DG4 auto starts, then trips on differential overcurrent. DG3 starts and energizes

E3.

Objectives: SRO - Enter and Direct actions IAW RSP/RVCP, PCCP and AOP-36.1

ROs - Perform RSP/RVCP,PCCP, and AOP-36.1actions as directed by the CRS:

SCRAM IAs.

Control Pressure with SRVs

Align RCC to CSW

Swap AB panels

Evaluator Notes continued

Success Path: Perform Scram IAs, control pressure with SRVs, and execute AOP-3.6.1 actions to

realign RCC and AB panels.

Event Termination: When Scram immediate actions have been completed, and at the direction of the

lead evaluator proceed to event 10.

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EVENT 7/8: SCRAM/LOOP/FAILURE OF EDG4

Time Pos EXPECTED Operator Response Comments

May direct manual scram or rapid reactor

shutdown, prior to vacuum reaching 22.4 hg

Enters and directs RSP (may transition to

RVCP):

SRO * Directs control of reactor pressure 800-

1000 psig

Directs a water level band of 166-206

inches

Enters and directs PCCP at applicable PCCP

entry conditions:

Torus Temp 95°F ;DW Temp 150°F; DW press

1.7 psig; Torus Water level > -27 or < -31

SRO Direct AOP-36.1 entry.

SRO Contacts maintenance for failure of EDG-4

May insert a scram or rapid reactor shutdown

prior to vacuum reaching 22.4 hg.

Diagnoses and reports MSIV closure and

reactor scram

ATC Performs SCRAM IA (Enclosure 2 Pages 77-78

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EVENT 7/8: SCRAM/LOOP/FAILURE OF EDG4

When directed stabilizes and controls Reactor

ATC Pressure 800-1000 psig with SRVs

/BOP

When directed controls Reactor Level 166-206

ATC inches

/BOP

ATC Diagnose and report LOOP, and EDG-4 failure

/BOP May direct AO to investigate.

Enter, announce, and perform AOP-36.1

actions:

ATC * Direct AO to monitor Diesels

/BOP * Transfer RBCCW heat exchangers from

the NSW header to the CSW header

Swap AB panel power (2AB-TB)

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EVENT 9/10/11/12: LOCA/ LOSS OF ALL INJECTION (STM COOL) / ED LL5/ RESTORE LEVEL

Simulator Operator Actions

At the direction of the Lead Evaluator, INITIATE TRIGGER 10 (NB009F) to initiate the LOCA .

As soon as 7 ADS valves are opened, report E11-F015A has been repaired and MODIFY

RH_ZVRH15AM to ON

Simulator Operator Role Play

If requested to investigate failure of E51-F045, wait 5 minutes and report breaker is open

Tripped on thermals, and it will not reset if asked to reset.

If requested to investigate RHR D motor overload, wait 5 minutes and for local report: motor

very hot to touch, and for electrical report: breaker will not reset if asked to reset.

If requested to investigate failure of E11-F015A, wait 5 minutes and report breaker tripped

(2XA-2/DF3) will not reset if asked to reset. If asked to manually open, acknowledge request,

and after 5 minutes report valve will not manually open.

If asked to investigate failure of SLC acknowledge the request. If asked to line up SLC for

Demin injection acknowledge request.

Evaluator Notes

Plant Response: A small recirc break will occur resulting in lowering level, and rising DW press.

SLC line blockage will occur when SLC is started. RCIC F045 will lose power and

will not open when RCIC starts. RHR pump D immediately trip on overload after

start. E11-F015A will lose power. The above losses and the previous losses (HPCI

FIC, LOOP) will result in a loss of all injection, and require steam cooling from TAF

to LL5, when LL5 is reached ED is required. After ED, the F015A will be repaired

and injection will be restored to >LL4 with RHR.

Objectives: SRO - Direct injection with any available sources IAW RVCP as level lowers to TAF,

establish steam cooling at TAF, direct ED at LL5, direct restoration of level.

ROs - Attempt to inject with available resources, and diagnose and report failures of

RCIC, SLC, and RHR. Execute steam cooling as directed and perform

emergency depressurization as directed. Restore level with RHR > LL4

following ED.

Evaluator Notes continued

Success Path: Perform SC at TAF to LL5. Perform ED at LL5. Restore injection with RHR to >LL4.

Scenario Termination: Once an ED has been performed and reactor level has been restored > LL4,

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.

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EVENT 9/10/11/12: LOCA/ LOSS OF ALL INJECTION (STM COOL) / ED LL5/ RESTORE LEVEL

Enter and Direct actions IAW RVCP as level

lowers, directs:

ADS inhibited

Table L-1 and L-2 systems aligned for

SRO injection **CRITICAL TASK #1

Steam Cooling at TAF**

Transition to EOP-01-EDP at LL-5

Restoration of RPV level using RHR

following ED

Enters and directs EDP at LL5:

Directs 7 ADS valves opened

When DW press reaches 1.7 psig: Enters and

directs actions IAW PCCP.

DW cooling

H2/O2 monitoring

Contacts maintenance/I&C/WCC for:

RCIC F045

SRO * RHR Pump D

E11-F015A

SLC line blockage

When RCIC receives an automatic start signal

or is manually started:

/ATC * Diagnoses and reports failure of RCIC

(E51-F045).

Contacts AO to investigate.

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EVENT 9/10/11/12: LOCA/ LOSS OF ALL INJECTION (STM COOL) / ED LL5/ RESTORE LEVEL

BOP When directed, starts SLC and

/ATC diagnoses/reports failure (line blockage)

When RHR pump D starts:

BOP * Diagnoses and reports failure (motor

/ATC overload)

Contacts AO to investigate

Diagnoses and reports loss of power to E11- CRITICAL TASK #2

F015A .

BOP Contacts AO to investigate.

/ATC

Performs Steam Cooling:

BOP * Notifies CRS as level lowers: TAF,LL4, CRITICAL TASK #1

/ATC LL5

Maintains pressure as directed by CRS.

BOP When directed performs ED

/ATC * Opens Seven ADS valves

CRITICAL TASK #2

BOP When power is restored to the E11 F015A,

/ATC restores RPV level > LL4.

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ENCLOSURE 1 Page 1 of 1

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ENCLOSURE 2 Page 1 of 2

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ENCLOSURE 2 Page 2 of 2

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ATTACHMENT 1 - Scenario Quantitative Attribute Assessment

Category Scenario Content

Rev. 2 Supp. 1 Req.

Total Malfunctions 5-8 7

Malfunctions after EOP

1-2 2

Entry

Abnormal Events 2-4 3

Major Transients 1-2 2

EOPs Used 1-2 2

EOP Contingency 0-2 1

Run Time 60-90 min 90

Crew Critical Tasks 2-3 2

Tech Specs 2 2

Instrument / Component 2 - OATC

Failures before Major 4 (2/2)

2 - BOP

Instrument / Component

2 2

Failures after Major

Normal Operations 1 1

Reactivity manipulation 1 1

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ATTACHMENT 2 - Shift Turnover

Brunswick Unit 2 Plant Status

Station Duty Workweek

J. Pierce D. Hunter

Manager: Manager:

Mode: 1 Rx Power: 90%

Plant Risk:

Green

Current EOOS Risk Assessment is:

SFP Time to

49.7 hrs Days Online: 80 days

200 Deg F:

Place 2A SJAE in FULL LOAD and shutdown 2B SJAE IAW 2OP-30,

Turnover:

Section 6.3.1

Protected

2B CRD, ADHR/FPC/ Demin Xfer Pump, Remaining LP ECCS

Equipment:

A severe thunderstorm watch is in effect for SE North Carolina

Comments: 2A CS PUMP is tagged out for maintenance

2A CRD PUMP is tagged out for maintenance

Appendix D Scenario Outline Form ES-D-1

Facility: Brunswick Scenario No.: NRC-4 Rev 0 Op-Test No.: 2017-301

Developer: J. Viera

Technical Review: Validators: _____________________________

__________________________ _____________________________

Facility Representative: _____________________________

__________________________

Initial Conditions: Unit 2 Reactor Power is at 55% RTP with 2PT-40.2.12 currently in progress. Testing

of BPVs 1 through 7 have been completed. A severe thunderstorm watch is in effect for SE North

Carolina.

Turnover: Complete 2PT-40.2.12 beginning with Bypass Valve #8, Section 7.11, Step 1. Following PT

completion, perform reactor power reduction IAW 0GP-12 to 50% RTP using control rods.

Event Malf. Event Event

No. No. Type* Description

Perform 2PT-40.2.12, Section 7.11.

1 n/a N (BOP)

(2PT-40.2.12)

BPVs 9 and 10 Stuck Shut

2 1, 2 TS (SRO)

(2PT-40.2.12, TS 3.7.6)

Lower power using control rods

3 n/a R (ATC)

(0GP-12)

Failure of DWED pump to run

4 3 C (ATC)

(2APP-A-04)

Failure of CRD Flow Controller in AUTO Mode

5 5 C (ATC)

(2APP-A-05)

C (BOP) Loss of Stack Rad Monitor, failure of RB Ventilation isolation

6 6, 7

TS (SRO) (previously used)

UAT Ground

7 4 C (BOP)

(2APP-UA-13)

8, 9, LOOP (Dual Unit) with EDG 1 Lockout and EDG 3 failure in AUTO

8 M

10 (2EOP-01-RSP, 0AOP-36.1)

Unit 1 requests to cross-tie E1 to E3

9 n/a n/a

(0AOP-36.1)

Operate EDG 3 to not exceed > 3850 kW loading for 2 minutes

10 T (BOP)

(0AOP-36.1)

Failure of EDG 3 and 4 (Unit 2 SBO)

11 11, 12 n/a

(2EOP-01-RSP, 2EOP-01-RVCP, 2EOP-01-SBO)

100o F/hr cooldown rate initiated within 60 minutes of SBO start

12 T (ATC)

(2EOP-01-RVCP)

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, Critical (T)ask

Event 1: Perform 2PT-40.2.12, Section 7.11

(2PT-40.2.12)

Ensure an in-progress 2PT-40.2.12 is pre-marked up to Section 7.11 with a

complete copy available to the applicant crew for pre-review.

The BOP operator is expected to perform 2PT-40.2.12, Section 7.11, Testing

Bypass Valve Number 8. Upon conclusion of this section, the applicant crew will

proceed to Event 2.

Event 2: BPVs 9 and 10 Stuck Shut

(2PT-40.2.12, TS 3.7.6)

The BOP operator is expected to proceed with 2PT-40.2.12, Sections 7.12 and

7.13, to test BPVs 9 and 10. During performance, the BOP operator is expected

to discover that both BPVs 9 and 10 are stuck fully shut and will not open upon

RTGB demand.

Facility consultation required to ensure correct TS application, as the PT

specifies failure of two BPVs will result in an INOPERABLE BPV system (ref

Section 5.0 NOTE on page 6) yet TS Bases 3.7.6 specifies that failure of three

BPVs will result in an INOPERABLE BPV system.

Per 2PT-40.2.12 acceptance criteria, the SRO is expected to enter a LCO for TS

3.7.6, Condition A.

Once the PT is complete 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 3.

Event 3: Lower power using control rods

(0GP-12)

Ensure that initial plant configuration is consistent with 0GP-12 for starting power

level (e.g. one RFPT currently idled, one HDP secured, etc).

Applicant crew coordination required to meet plant turnover required activities.

Ensure pre-filled 0GP-10 sheets are available at crew turnover. Expect the

operating crew to lower power to as-directed 50% reactor power. During power

reduction, applicant manipulation of HD-V57 and CO-FIC-49 may be required.

If applicant crew contacts shift management following PT performance, ensure a

Simulator Booth cue is available to instruct the applicant crew to complete the

shift turnover direction to lower power.

Following observation of sufficient power reduction, the Chief Examiner can

move to Event 4.

Event 4: Failure of DWED pump to run

(2APP-A-04)

Following receipt of annunciator 2-A-4 (1-1), the ATC operator is expected to

diagnose a failure of the DWED pump to run. The ATC is then expected to start a

DWED pump IAW the automatic actions of annunciator 2-A-4 (1-1).

Upon initiation of this event, the Chief Examiner can move directly to Event 5.

Event 5: Failure of CRD Flow Controller in AUTO Mode

(2APP-A-05)

Upon initiation, a failure of the CRD Flow Controller in AUTO Mode (i.e. lack of

CRD flow) will result in elevated HCU temperatures causing receipt of alarm 2-A-

5 (1-2), CRD HYD TEMP HIGH. When a field operator is dispatched, report that

HCU (xx) is indicating approximately 400oF.

Upon receipt of this annunciator, the ATC operator is expected to take MANUAL

control of the CRD Flow Controller and re-establish flow IAW 2OP-08 (referred

from 2APP-A-05 (1-2)).

When the CRD Flow Controller is in MANUAL control, the Chief Examiner can

move to Event 7. It is expected that shortly after flow is re-established

annunciator 2-A-5 (1-2) will clear.

Event 6: Stack Rad Monitor Failure

(previously used)

Loss of UPS power to the Stack Rad Monitor will initiate a Group 6 isolation.

Group 6 valves will isolate, but RB Ventilation will fail to isolate. The BOP

operator is expected to perform the manual isolation required.

This is a scenario event previously used on the 2014-301 exam (ref scenario

LOIX-032, Event 4)

Once RB Ventilation actions are complete 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 8

Event 7: UAT Ground

(APP-UA-16

A UAT ground alarm will be received. The crew will respond IAW UA-13 (2-10)

UAT WINDING Y GRD CURRENT. Investigation by I&C will indicate the alarm is

valid requiring Buses 2C & 2D to be transferred to the SAT.

After the first bus is transferred activate the LOOP..

Event 8: LOOP (Dual Unit), Loss of EDG 1, EDG 3 failure to start in AUTO

(2EOP-01-RSP, 0AOP-36.1)

Upon initiation, a LOOP will affect the operating crew. An automatic SCRAM and

closure of MSIVs will result due to the loss of power on Unit 2. It is expected for

the applicant crew to enter both 2EOP-01-RSP and 0AOP-36.1.

It is expected that the BOP operator will diagnose the failure of EDG 3 to start in

AUTO and will start EDG 3 in CR-MANUAL. The ATC operator is expected to be

manually controlling SRVs.

Once EDG 3 is running in CR-MANUAL, the Chief Examiner can move to Event

9.

Event 9: Unit 1 requests to cross-tie E1 to E3

(0AOP-36.1)

Upon initiation, the simulator booth will contact the applicant crew to inform them

that EDG 1 has suffered a lockout and is unavailable, additionally, Unit 1 will

request to perform a cross-tie between E1 and E3.

It is expected that the BOP operator will perform action associated with closure of

breaker AG0 concurrent with Simulator Booth (as Unit 1 operator).

Following completion of cross-tie, the Simulator Booth (as Unit 1 CRS) will

contact the applicant SRO and inform them that Unit 1 will be starting loads on

E1.

Event 10: Operate EDG 3 to not exceed > 3850 kW loading for 2 minutes

(0AOP-36.1)

Following the Unit 1 notification above, the simulator booth will simulate starting

the following loads on E1 (i.e. E3). Each load should be timed in 15 second

increments.

o Batt Chgr 1A-1 and 1A-2 (128 kW)

o CS Pump 1A (940 kW)

o CRD Pump 1A (190 kW)

o FP Cooling Pump 1A (50kW)

o NSW Pump 1A (225 kW)

o RB Vent Sup Fan 1A and 1C (150 kW)

o RHR Pump 1C (750 kW)

o RBCCW Pumps 1A and 1C (96 kW)

o CSW Pump 1B (225 kW)

o RHRSW Pump 1C (600 kW)

It is anticipated that following start of RHRSW Pump 1C, EDG 3 loading will

exceed 3850 kW (including 480V house loads). (Will require validation during

prep week)

(Critical Task is met when operator action is taken to reduce loading or to instruct

Unit 1 to reduce loading to not exceed > 3850 kW loading for 2 minutes.) Facility

consultation required to finalize bounding criteria for this Critical Task.

Once operator action is taken to mitigate EDG 3 loading or once two minutes has

elapsed with EDG 3 loading > 3850 kW, the Chief Examiner can proceed to

Event 11.

Event 11: Failure of EDG 3 and 4 (Unit 2 SBO)

(2EOP-01-RSP, 2EOP-01-RVCP, 2EOP-01-SBO)

Upon entry into this event, the applicant crew will receive indications of a SBO

(EDG 3 and 4 lockouts). It is expected for the SRO to transition from 2EOP-01-

RSP to 2EOP-01-SBO and 2EOP-01-RVCP.

It is expected for the SRO to direct entry into 0EOP-01-SBO-01, 0EOP-01-SBO-

02, and 0EOP-01-SBO-04. Additionally, it is expected for the crew to carry out

2EOP-01-RVCP pressure control actions.

Event 12: 100oF/hr cooldown rate initiated within 60 minutes of SBO start

(2EOP-01-RVCP)

IAW RVCP Step RC/P-6, it is expected for the SRO to direct the lowering of

reactor pressure to a control band of 150 to 300 psig. Critical Task to be

performed within 60 minutes of entry into SBO per 0OI-37.4, Section 5.19.2.

(Critical Task is met when operator action to lower pressure results in a cooldown

rate of 100oF/hr within 60 minutes from SBO start.) Facility consultation

required to determine upper bounding of cooldown rate for this Critical Task.

Once the required CDR is established (operators will most likely select SRVs as

the system used) with applicant control of pressure, the Chief Examiner can

terminate this scenario.

BRUNSWICK TRAINING SECTION

OPERATIONS TRAINING

INITIAL LICENSED OPERATOR

SIMULATOR EVALUATION GUIDE

2017 NRC SCENARIO 4

2PT-40.2.12, LOWER POWER, DWED PUMP FAILURE, CRD FLOW

CONTROLLER FAILURE, STACK RAD MONITOR FAILURE, UAT GROUND,

LOOP, SBO

REVISION 0

Developer: NRC - Joe Viera Date: 3/31/2017

Technical Review: Bob Bolin Date: 4/24/2017

Validators: Mike Long Date: 5/5/17

Rob Lax

Trey Bunnell

Facility Representative: Craig Oliver Date: 5/24/17

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REVISION SUMMARY

0 NRC developed scenario for the 2017 NRC Exam.

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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 ..................................................... 59

ATTACHMENT 2 - Shift Turnover ........................................................................................................ 67

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1.0 SCENARIO OUTLINE

Event Malf. No. Type* Event Description

Complete 2PT-40.2.12, Section 7.11.

1 N - BOP

(2PT-40.2.12)

BPVs 8, 9 and 10 Stuck Shut

2 TS - CRS

(2PT-40.2.12, TS 3.7.6)

Failure of DWED pump to run

3 C - ATC

(A-04)

Lower power using control rods

4 R - ATC

(0GP-05)

Failure of CRD Flow Controller in AUTO Mode

5 C - ATC

(A-05)

C - BOP Loss of Stack Rad Monitor (GRP 6, RB Vent, SBGT all fail)

6

TS - CRS (2OP-52)

UAT Ground

7 ZUA13210 C - BOP

(UA-13)

LOOP (Dual Unit) DG1 Lockout / DG3 failure in AUTO

8 M

(RSP, 0AOP-36.1)

Unit 1 requests to cross-tie E1 to E3

9

(0AOP-36.1)

Operate DG3 not exceed >3850 kW loading for 2 minutes

10 T

(0AOP-36.1)

Failure of DG3 and 4 (Unit 2 SBO)

11

(RSP, RVCP, SBO)

100°F/hr cooldown rate initiated within 60 minutes of SBO

12 T

(RVCP, SBO)

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

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2.0 SCENARIO DESCRIPTION SUMMARY

Event Description

Completes 2PT-40.2.12, starting at Section 7.10, Testing Bypass Valve Number 7.

1/2 During performance, the BOP operator is expected to discover that BPVs 8, 9 and 10

are stuck fully shut and will not open upon RTGB demand. Refers to TS 3.7.6

Condition A.

Following receipt of annunciator A-4 (1-1), the crew is expected to diagnose a failure

3

of the DWED pump to run. The ATC is then expected to start a DWED pump.

4 The crew will lower power by inserting control rods.

A failure of the CRD Flow Controller in AUTO Mode will result in elevated HCU temps

5 causing receipt of alarm A-5 (1-2), CRD HYD TEMP HIGH. When a field operator is

dispatched, report that HCU (xx) is indicating approximately 400°F.

Loss of UPS power to the Stack Rad Monitor which should initiate a Group 6 isolation,

6 SBGT start, and RB Ventilation isolation (None of which occur). The crew will re-

energize from the alternate power supply IAW 2OP-52.

A UAT ground alarm will be received. The crew will respond IAW UA-13 (2-10) UAT

7 WINDING Y GRD CURRENT. Investigation by I&C will indicate the alarm is valid

requiring Buses 2C & 2D to be transferred to the SAT

A LOOP will affect the operating crew. An automatic SCRAM and closure of MSIVs

8 will result due to the loss of power on Unit 2. It is expected for the applicant crew to

enter both 2EOP-01-RSP, RVCP ,and 0AOP-36.1.

The simulator booth will contact the applicant crew to inform them that DG1 has

9 suffered a lockout and is unavailable, additionally, Unit 1 will request the crew to

perform a cross-tie between E1 and E3

10 Operate EDG 3 to not exceed > 3850 kW loading for 2 minutes

The crew will receive indications of a SBO (DG3 and 4 lockouts). It is expected for the

11

CRS to transition from RSP/RVCP to SBO.

CRS to direct the lowering of reactor pressure to a control band of 150 to 300 psig.

12

(100°F/hr cooldown may be exceeded)

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3.0 CREW CRITICAL TASKS

Critical Task #1

Operator action is taken to reduce loading, or to instruct Unit 1 to reduce loading, to not

exceed >3850 kW loading for 2 minutes

Critical Task #2

Operator action taken to control RPV level/pressure IAW RVCP to maintain DW

temperature <300°F.

4.0 TERMINATION CRITERIA

Once the cooldown is established with target band between 150-300 psig, the Chief

Examiner can terminate this scenario.

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5.0 IMPLEMENTING REFERENCES

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

Number Title

A-04 (1-1) Drywell Equip Drain Sump Lvl Hi

A-05 (1-2) CRD Hyd Temp High

A-05 (2-1) CRD Charging Wtr Press Hi

UA-13 (2-10) UAT Winding Y Grd Current

2OP-07 Reactor Manual Control System Operating Procedure

2OP-08 Control Rod Drive Hydraulic System Operating Procedure

2OP-52 120 Volt AC UPS, Emergency, And Conventional Electrical Systems

Operating Procedure

0GP-10 Rod Sequence Checkoff Sheets

0GP-12 Power Changes

2PT-40.2.12 Main Turbine Bypass Valves Operability Test

0AOP-36.1 Loss Of Any 4160V Buses Or 480V E-Buses

2EOP-01-RSP Reactor Scram Procedure

2EOP-01-RVCP Reactor Vessel Control Procedure

2EOP-01-SBO Station Black Out

0EOP-01-SBO-01 Plant Monitoring

0EOP-01-SBO-02 Blacked Out Unit Initial Actions

0EOP-01-SBO-04 Blacked Out Unit Local Actions

0EOP-01-SBO-06 4160V E-Bus Crosstie

0EOP-01-SBO-07 480V E-Bus Crosstie

0EOP-01-SBO-08 Supplemental DG Alignment

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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-25.

3. ENSURE the RWM is set up for A2 sequence.

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

Insert GP-10 Sequence A2 control rods up to step 68 (~55% power)

Shutdown a heater drain pump and open the 57 valve to maintain level ~48 inches

Idle one of the RFPs

Place one of the DWEDS momentarily to STOP (to reset timers)

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

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

Protected Equipment

None

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15. VERIFY 0ENP 24.5 Form 2 (Immediate Power Reduction Form) for IC-25 is in place.

16. ENSURE each Implementing References listed in Section 7 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

2PT-40.2.12 completed up to Section 7.10.

0GP-10 up to step 68 (Item 508)

0GP-05 Steps 6.1.6, 6.1.7, and 6.1.8 marked as completed

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.

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7.0 INTERVENTIONS

TRIGGERS

Trig Type ID

1 Annunciator ZA411 - [DRYWELL EQUIP DRAIN SUMP LVL HI]

2 Annunciator ZA512 - [CRD HYD TEMP HIGH]

2 DI Override K2222A - [CRD FLOW CONT]

3 Trigger Command and:za512

4 Remote Function ED_IAUPB2A6 - [UPS LOAD BKR DIST PNL 2A TO SMPL DT SKD]

5 Remote Function ED_IAUPDSSW - [UPS SAMPLE DET SKD XFER SW (N=U2/A=U1)]

6 Annunciator ZUA13210 - [UAT WINDING Y GRD CURRENT]

7 Trigger Command and:zua13210

8 Malfunction EE031F - [STATION BLACKOUT EE]

10 Malfunction DG026F - [DG3 DIFFERENTIAL FAULT]

10 Malfunction DG027F - [DG4 DIFFERENTIAL FAULT]

11 Remote Function ED_IASWAG0 - [X-TIE E1-E3 4-POS SW (L=N/F/S R=MAINT)]

11 Remote Function ED_IASWAJ5 - [X-TIE E3-E1 4-POS SW (L=N/F/S R=MAINT)]

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

Trig # Trigger Text

7 K4101BO8 - [SAT INC LINE TO BUS 2D SYNCHROSCOPE]

8 !K4101NWD - Not [SAT INC LINE TO BUS 2D SYNCHROSCOPE]

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MALFUNCTIONS

Malf Mult Current Target Rmp

Description Actime Dactime Trig

ID ID Value Value time

MS020F BPV #10 TURB BPV FAILS CLOSED True True

MS020F BPV #9 TURB BPV FAILS CLOSED False False

MS020F BPV #8 TURB BPV FAILS CLOSED True True

MS020F BPV #7 TURB BPV FAILS CLOSED True True

EE031F STATION BLACKOUT EE False True 8

DG026F DG3 DIFFERENTIAL FAULT False True 10

DG027F DG4 DIFFERENTIAL FAULT False True 10

DG024F DG1 DIFFERENTIAL FAULT True True

DG004F DG3 AUTO START FAILURE True True

REMOTES

Current Target Rmp

Remf Id Mult Id Description Actime Trig

Value Value time

CO-V110 MANUAL INLET ISOLATION TO CO-

CF_VHCFV110O OPEN OPEN

FV-49

ED_IAUPB2A6 UPS LOAD BKR DIST PNL 2A TO SMPL DT SKD CLOSE OPEN 4

ED_IAUPDSSW UPS SAMPLE DET SKD XFER SW(N=U2/A=U1) NORMAL ALT 5

ED_IASWAG0 X-TIE E1-E3 4-POS SW (L=N/F/S R=MAINT) LOCAL REMOTE 11

ED_IASWAJ5 X-TIE E3-E1 4-POS SW (L=N/F/S R=MAINT) LOCAL REMOTE 11

ED_IAE1LOAD E1 LOAD FROM UNIT 1 (0:2930 KW) 1259.90 1259.90

ED_IAE3LOAD E3 LOAD FROM UNIT 1 (0:1350 KW) 0 0

SW_VHSW146L CONV SW TO RBCCW HXS V146 SHUT OPEN 12

PANEL OVERRIDES

Position / Actual Override Rmp

Tag ID Description Actime Dactime Trig

Target Value Value time

K2222A CRD FLOW CONT AUTO OFF OFF 2

K2222A CRD FLOW CONT BAL OFF OFF 2

K2222A CRD FLOW CONT 0-100 OFF OFF 2

K2222A CRD FLOW CONT MAN OFF ON 2

K2222A CRD FLOW CONT O-100 OFF OFF 2

K6106A CAC PURGE & VENT VLV ISOL OFF OFF OFF

K6106A CAC PURGE & VENT VLV ISOL OVERRIDE OFF ON

Override

Window Description Tagname OVal AVal Actime Dactime Trig

Type

1-1 DW EQUIP DRAIN SUMP LVL HI ZA411 ON ON OFF 1

1-2 CRD HYD TEMP HIGH ZA512 OFF OFF OFF 0:00:15 2

2-10 UAT WINDING Y GRD CURRENT ZUA13210 ON ON OFF 6

2-1 -1 GEN DIFF OVCT TRIP ZUA1921 OFF OFF OFF

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8.0 OPERATOR RESPONSE AND INSTRUCTIONAL STRATEGIES

EVENT 1/2: 2PT-40.2.12, Main Turbine Bypass Valves Operability Test

Simulator Operator Actions

Ensure Monitored Parameters is open and Scenario Based Testing Variables are loaded.

Simulator Operator Role Play

If crew stops performance of the PT-40.2.12, as the SM direct the crew to finish the

performance of the PT.

If contacted as the RE to change thermal limits, acknowledge the request.

Evaluator Notes

Plant Response: Bypass valves 8, 9, & 10 are failed shut

Objectives: SRO - Direct BOP to complete 2PT-40.2.12

Evaluate Tech Spec 3.7.6

BOP - Perform 2PT-40.2.12

ATC - Monitors plant

Success Path: Completes PT-40.2.12 and determines TS 3.7.6 condition A applies.

Event Termination: Go to Event 3 at the direction of the Lead Evaluator.

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EVENT 1/2: 2PT-40.2.12, Main Turbine Bypass Valves Operability Test

Time Pos EXPECTED Operator Response Comments

Direct BOP to complete 2PT-40.2.12 starting

with Section 7.12.

SRO Determines TS 3.7.6 Condition A applies

May conduct a brief

SRO (see Enclosure 1 on page 59 for format)

RO Monitors the plant

Completes the performance of 2PT-40.2.12,

Main Turbine Bypass Valves Operability Test.

Informs CRS that Turbine Bypass Valves

10 has failed PT.

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From Bases:

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EVENT 3: DWEDT PUMP FAILURE

Simulator Operator Actions

At the direction of the Lead Evaluator or at simulator time 35 minutes, Initiate Trigger 1 to

activate the DWED Sump Lvl Hi Annunciator.

(NOTE: This event can be performed in conjunction with Events 1 and 2)

If the simulator is left in run the DWED Sump Lvl Hi Alarm will annunciate on its own after

NOTE approximately 44 minutes. (The sumps will automatically start pumping if allowed to

annunciate)

When either sump pump has been running for ~30 seconds delete malfunction for the DWED

Sump Lvl Hi Annunciator.

Simulator Operator Role Play

Acknowledge requests as I&C for troubleshooting DWED Sump Pump auto start failure.

If asked, the last time the sumps were pump was ~4 hours ago.

Evaluator Notes

Plant Response: Annunciator A-04 (1-1), Drywell Equip Drain Sump Lvl Hi.

Objectives: RO - Pump the DWEDT

Success Path: Pumps the DWEDT.

Event Termination: Go to Event 4 at the direction of the Lead Evaluator.

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EVENT 3: DWEDT PUMP FAILURE

Time Pos EXPECTED Operator Response Comments

Direct actions of APPs

Direct RO to start DWEDS Pump, if asked.

Contact I/C for troubleshooting the failure of the

DWEDS to auto start.

May conduct a brief

SRO (see Enclosure 1 on page 59 for format)

Refer to APP:

RO

A-04 (1-1), Drywell Equip Drain Sump Lvl Hi

Diagnose failure of DWEDS Pump

Start a DWEDS Pump

(may use 0OP-47 Section 5.3.5)

Verifies pump shuts off after a period of time.

BOP Monitors the plant

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EVENT 4: Lower Reactor Power

Simulator Operator Actions

Simulator Operator Role Play

If contacted as RE, report that you will be monitoring the shutdown.

If directed by the Chief Examiner direct the crew to continue the plant shutdown IAW GP-05.

Evaluator Notes

Plant Response: Crew will insert control rods to reduce power to ~50%.

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

RO - Inserts control rods to lower reactor power

Success Path: Reactor power reduced to ~50% power.

Event Termination: When power has been reduced to ~50% power or at the discretion of the Lead

Evaluator go to Event 5.

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EVENT 4: Lower Reactor Power

Time Pos EXPECTED Operator Response Comments

May conduct a brief

SRO (see Enclosure 1 on page 59 for format)

Directs power to be lowered IAW 0GP-10, using

SRO Sequence A2X starting with step 69

BOP Monitor plant parameters during evolution

May need to throttle open HD-V57 (Deaerator

BOP Fill And Drain Valve) to control deaerator level

between 45 and 59 inches

Inserts control rods per 0GP-10 (see page 26)

ATC IAW guidance of 2OP-07 (see page 28 for

continuous insert or page 30 for notch insert).

ATC May null the DVM as needed.

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EVENT 5: FAILURE OF CRD CONTROLLER AUTO MODE

Simulator Operator Actions

At the direction of the Lead Evaluator, Initiate Trigger 2 to fail the CRD Flow Controller.

After flow is re-established Initiate Trigger 3 to remove the high temperature alarm.

Simulator Operator Role Play

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

If dispatched to report CRD Hyd Temps, report highest reading is 380°F on CRD 26-35. All

CRD Hyd Temps are slowly rising.

After CRD Cooling Water flow is restored report that temperatures are lowering.

When alarm is cleared, report all temperatures are less than 340°F.

Evaluator Notes

Plant Response: Elevated HCU temperatures causing receipt of alarm 2-A-5 (1-2), CRD HYD TEMP

HIGH. The crew will place the CRD Flow Controller in MANUAL and re-establish flow

IAW 2OP-08.

Objectives: Restore CRD flow.

Success Path: Place CRD Flow Controller in Manual

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

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EVENT 5: FAILURE OF CRD CONTROLLER AUTO MODE

Time Pos EXPECTED Operator Response Comments

Acknowledge report of annunciators:

SRO A-05 (1-2), CRD Hyd Temp High

A-05 (2-1), CRD Charging Wtr Press Hi

Directs placing the CRD Controller in MANUAL

and setting flow to 30 - 60 gpm.

Or may direct swapping FCVs IAW 2OP-08

Section 6.3.3

May direct a compensatory action to close CRD

Flow Controller on a reactor scram.

May conduct a brief (See Enclosure 1, page 59

SRO for format of the brief.

Acknowledges reports and reviews annunciators

A-05 (1-2), CRD Hyd Temp High

A-05 (2-1), CRD Charging Wtr Press Hi

IAW AD-OP-ALL-1000, places CRD Flow

Controller in MANUAL and adjusts CRD

parameters (IAW OP-08, Attachment 1, see

page 38)

Or Performs steps in 2OP-08 Section 6.3.3 to

transfer to manual

May dispatch operator locally for swapping flow

control valves.

When the applicant places the controller in

manual flow will be re-established.

BOP Monitor plant

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EVENT 6: LOSS OF POWER TO STACK RAD MONITOR - RBHVAC FAILS TO ISOLATE

Simulator Operator Actions

At the direction of the Lead Evaluator, Initiate Trigger 4 to fail Stack Rad Monitor downscale

(loss of power).

Transfer Stack Rad Monitor to Unit 1 UPS if requested (Trigger 5).

Simulator Operator Role Play

If asked to investigate, report Ckt #6 on UPS Panel 2A to the Stack Rad Monitor is tripped

If contacted as Unit One, report that Unit One has the same alarms present.

If contacted as I&C to investigate, acknowledge the request. After the Tech Spec call is made,

report it is a breaker failure, and not a load fault. (if asked recommend ok to transfer to alt

power)

If contacted as HP, acknowledge the request.

Evaluator Notes

Plant Response: Loss of UPS power to the Stack Rad Monitor which should initiate a Group 6

isolation, SBGT start, and RB Ventilation isolation (None of which occur). The

crew will re-energize from the alternate power supply IAW 2OP-52.

Objectives: SRO - Determine actions required for LCO per Technical Specifications.

RO - Respond to a process radiation monitoring downscale/inop annunciator.

Isolate RBHVAC, Start SBGT, and isolate GRP 6 valves.

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

Event Termination: Go to Event 7 at the direction of the Lead Evaluator.

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EVENT 6: LOSS OF POWER TO STACK RAD MONITOR - RBHVAC FAILS TO ISOLATE

Time Pos EXPECTED Operator Response Comments

Direct actions of the APPs for the Main Stack

Rad Monitor. (2UA3 5-4,6-3,6-4) (2UA25 1-8)

SRO Direct verification of Group 6 isolation.

SRO May direct entry into 0AOP-12.0.

Direct I/C to investigate loss of UPS 2A.

May direct transfer to alternate power supply after I&C

diagnosis.

(May reference Ops LCO Database)

Technical Specification / TRM

3.3.6.1 PCIS Instrumentation, Function 2c NOTE: 3.3.6.1 Condition

Condition A1, Place in trip condition in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . B is complete when

isolations are manually

Condition B1, Restore Isolation capability in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months

initiated.

3.4.5 RCS Leakage Detection Instrumentation

Condition B.1, Analyze grab samples every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

Condition B.2, Restore operable in 30 days

3.6.4.2 Secondary Containment Isolation Dampers NOTE: May not declare

Condition A.1 isolate 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 3.6.4.2 depending on if it

Condition A.2 verify isolated 92 days is not determined that

TRM 3.4 Post Accident Monitoring, Functions 2, 5, 6 and 7 the SCID logic has

Condition A.1 (F2/F6), Restore 31 days failed.

Condition B.1, (F2/F5), Restore one required channel in

7 days.

SRO * ODCM 7.3.2 Gaseous Effluent Monitoring, Function 1

A.1, Enter the Condition referenced in Table 7.3.2-1

B.1, Take a grab sample once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

B.2, Analyze the grab sample for gross noble gas activity

within 24 hrs

B.3, Restore the channel in 30 days

C.1, C.1.1, Immediately Initiate actions to establish

auxiliary sampling equipment to continuously collect

samples from the associated effluent release pathway as

required by Table 7.3.7-1

C.2, Restore the channel in 30 days

D.1, Estimate the flow rate through the associated

pathway in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months

D.2, Restore the channel in 30 days

7.3.7 and 7.3.13 do not apply

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EVENT 6: LOSS OF POWER TO STACK RAD MONITOR - RBHVAC FAILS TO ISOLATE

Time Pos EXPECTED Operator Response Comments

May conduct a brief

(see Enclosure 1 on page 59 for format)

Monitor reactor plant parameters:

ATC May open the SW-V111 or V117 to supply cooling

water to the vital header IAW UA- 05 1-9 or 2-9.

Report loss of Main Stack Rad Monitor and

references the following APPs:

UA-03

5-4, PROCESS OG VENT PIPE RAD HI-

HI

BOP 6-3, PROCESS SMPL OG VENT PIPE

DNSC/INOP

6-4, PROCESS OG VENT PIPE RAD - HI

UA-25

1-8, CTMT ATMOS RAD MON

DNSC/INOP

Report TS review for the CRS from the

Annunciator reviews.

3.4.5

BOP * 3.3.6.1 Table 3.3.6.1-1, function 2c

3.6.4.2

ODCM 7.3.2 Table 7.3.2-1 Function 1

7.3.7, and 7.3.13

TRM 3.4, Table 3.4.2 function 5

Isolates RBHVAC, Starts SBGT, closes GRP 6

valves (See page 44 for GRP 6 Valves).

Dispatch AO to investigate UPS 2A condition.

BOP May direct to transfer to the alternate power

supply IAW 2OP-52 Section 6.3.7 (See page 41)

May depress RIP Isolation pushbuttons to match

solenoid status with the valve position.

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GROUP 6 ISOLATION VALVES

CONTROL ROOM PANEL XU-51

CAC-SV-4540 CAC-V9

CAC-SV-4409-1/2/3/4 CAC-V10

CAC-SV-1260 CAC-V49

CAC-SV-1261 CAC-V50

CAC-SV-1262 CAC-V55

CAC-SV-4541 CAC-V56

CAC-SV-4410-1/2/3/4 CAC-V22

CAC-V 216 CAC-V 23

CAC-V 58 CAC-V 172

CAC-V 15 CAC-V 160

CAC-V 4 CAC-V 161

CAC-V 5 CAC-SV-3440

CAC-V6 CAC-SV-3439

CAC-V7 CAC-V162

CAC-V8 CAC-V163

CONTROL ROOM PANEL XU-2

X206A-A X57-A

X49B-B X57-B

X76-B X54-E

X73-A X54-F

X73-B X244-B

X73-C X209B-A

X73-E X245-E

X60-E

BACK PANELS

XU-75 XU-79

RXS-SV-4186 RXS-SV-4187

RXS-SV-4188 RXS-SV-4189

1 S/1377

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EVENT 7: UAT GROUND

Simulator Operator Actions

At the direction of the Lead Evaluator, Initiate Trigger 6 to activate UAT ground alarm.

Monitor BOP bus transfers and ensure Triggers 7 & 8 automatically initiates when Bus 2D

synch switch is placed to ON

Simulator Operator Role Play

If asked as AO to investigate, report no ground targets visible on Buses 2C or 2D 4kV E-

Busses, or the UAT.

If asked as I&C to investigate, wait 2 minutes and report UAT Y winding ground is valid

If asked as Unit One state that 1D Service Air Compressor is in LEAD.

Evaluator Notes

Plant Response: A UAT ground alarm will be received. The crew will respond IAW UA-13 (2-10) UAT

WINDING Y GRD CURRENT. Investigation by I&C will indicate the alarm is valid

requiring Buses 2C & 2D to be transferred to the SAT. After the first Bus is

transferred the LOOP will occur.

Objectives: SRO - Direct BOP Buses transferred to the SAT.

BOP - Transfers BOP Bus 2C to the SAT

Success Path: BOP Bus 2C transferred to the SAT.

Event Termination: Go to Event 8 after the BOP Bus 2C is transferred to the SAT.

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EVENT 7: UAT GROUND

Time Pos EXPECTED Operator Response Comments

Acknowledges report of UA-13 2-10 UAT

WINDING Y GRD CURRENT

SRO Informs I&C verify UAT ground alarm is valid.

May conduct a brief

SRO (see Enclosure 1 on page 59 for format)

Directs BOP Buses(2C & 2D) be transferred to

the SAT IAW OP-50

ATC Monitors the plant.

Acknowledges, refers to & reports annunciator

2-10 UAT WINDING Y GRD CURRENT

Directs TBAO to walk down Buses 2C & 2D

looking for ground targets.

May direct OSAO to walk down the UAT.

Notifies SRO that no ground targets present on

BOP Buses 2C or 2D and that these buses should be

transferred to the SAT if the ground is valid.

Transfers BOP Bus 2C to the SAT utilizing 2OP-

50, Section 6.2.1

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EVENT 8/9/10: Dual Unit LOOP

Simulator Operator Actions

The Dual Unit LOOP is actuated when the 2D Bus synch Switch is placed to ON.

Two minutes after being dispatched to perform 0AOP-36.1 Step 4.2.11.1d, Initiate Trigger 11

to perform field actions for E1 to E3 crosstie.

After E1 to E3 crosstie performed, modify remotes to increase loading of DG3 to >3850 kW

When group 1 loads started change IAE1LOAD value to 2800

When group 2 loads are started change IAE3LOAD value to 1350.

When group 3 loads are started change IAE1LOAD value to 2930.

When instructed to lower loading reduce DG3 loading to <3850 kW.

Initiate Trigger 12, two minutes after RCC on CSW is requested.

Simulator Operator Role Play

If called, as the Load Dispatcher report there are major problems with the grid due to the

storms, crews are investigating, and there are no estimates for return to service at this time.

After DG3 is started in Control Room Manual call as U1 CRS to request:

1. U2 permission to crosstie E1 to E3.

2. For U2 to perform the actions to crosstie E1 to E3 (0AOP-36.1 Steps 4.2.11.1d and e.)

After dispatched to perform E1 to E3 crosstie field actions (0AOP-36.1 Step 4.2.11.1d) and

Trigger 11 initiated, report that the E1 to E3 crosstie breakers can be closed.

If AO is requested to place RCC on CSW, wait two minutes and report actions complete.

Provide phone call to Unit Two RO stating Starting loads on DG3 for each group listed:

1. SBGT, DW Coolers, Batt Chgr, CRD, RCC, CSW, NSW

2. RHR and RHRSW

3. CS

Evaluator Notes

Plant Response: LOOP will cause the MSIVs to close initiating a reactor scram. DG3 will fail to auto

start and will be started in Control Room Manual. DG1 will lockout. Unit One will

request E3 to E1 crosstie. Unit One will start loading DG3, crew should prevent DG

from exceeding 3850 kW.

Objectives: SRO - Directs actions for a Reactor Scram, and 0AOP-36.1.

ROs - Start a DG in Control Room Manual mode..

Success Path: DG3 is started and loading is not exceeded.

Event Termination: Go to Event 11 at the direction of the Lead Evaluator.

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EVENT 8/9/10: Dual Unit LOOP

Time Pos EXPECTED Operator Response Comments

After reactor scram, directs actions from

RSP/RVCP:

SRO 1. Directs level band (166-206 inches).

2. Directs pressure band (800 - 1000 psig)

3. May direct LEP-02 for resetting the scram

4. May direct torus cooling placed in service

Directs starting DG3 if RO has not performed

immediate operator action.

Perform immediate actions for reactor scram:

1. Ensures scram valves are open.

2. After steam flow is less than 3 Mlb/hr, place

the reactor mode switch to shutdown.

3. When APRM downscale trip, then trip the

main turbine.

4. Ensure the master reactor level controller

setpoint is 170 inches.

Performs Scram Hard Card (See Enclosure 2

(page 60)

May perform LEP-02 to reset the scram. (See

ATC Enclosure 3, page 61)

Steps 7 and 8 are N/A

Maintains RPV pressure (SRVs) and level

(HPCI/RCIC) as directed by the CRS.

May place torus cooling in service IAW hard

card. (See Enclosure 4, page 64)

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EVENT 8/9/10: Dual Unit LOOP

Time Pos EXPECTED Operator Response Comments

BOP Starts DG3 in control room manual mode.

Dispatches AO to perform field actions for E1 to

BOP E3 Crosstie. (0AOP-36.1 Step 4.2.11.1d)

(See page 53)

May request an AO to place RBCCW on CSW

IAW AOP-36.1

Closes E1 to E3 crosstie breakers by placing

control switch for Breaker AG0 and AJ5 to

close until both breakers are closed and

undervoltage alarm clears.

Critical Task #1:

Reduces loading, or instructs

Unit 1 to reduce loading, to not

Monitors DG3 operation and limit kW loading exceed >3850 kW loading for >2

to less than 3850 kW. minutes.

START: ___________

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EVENT 11/12: Station Blackout / Cooldown

Simulator Operator Actions

At the direction of the Lead Evaluator, Initiate Trigger 10 to fail DG3 and DG4.

Do not reset the simulator until receipt of concurrence to do so from the lead examiner

Simulator Operator Role Play

As AO acknowledge request to:

1. Open panel doors in the control room

2. Perform 0EOP-01-SBO-04

3. Perform 0EOP-01-SBO-06

4. Perform 0EOP-01-SBO-07

5. Perform 0EOP-01-SBO-08

If requested as AO report Diff L/O on both DG3 and DG4.

Evaluator Notes

Plant Response: DG3 and DG4 fail, the crew will enter Station Blackout Procedure as the Blacked Out

Unit. RPV pressure is to be reduced to 150-300 psig, may exceed 100°F/hr

cooldown rate.

Objectives: SRO - Directs actions for Station Blackout as the Blacked Out Unit.

ROs - Perform actions for Station Blackout as the Blacked Out Unit.

Success Path: Reactor pressure is being lowered to 150-300 psig.

Scenario Termination: Once the cooldown is established with target band between 150-300 psig, 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.

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EVENT 11/12: Station Blackout / Cooldown

Time Pos EXPECTED Operator Response Comments

Directs Station Blackout actions as the Blacked

Out Unit.

1. Directs RPV pressure reduced to 150- Critical Task #2:

300 psig, may exceed 100°F cooldown

Operator action taken to control

rate.

RPV level/pressure IAW RVCP to

2. Directs 0EOP-01-SBO-01 to monitor plant

maintain DW temperature <300°F.

parameters.

3. Directs 0EOP-01-SBO-02 to perform

SRO Blacked Out Unit actions.

4. Directs 0EOP-01-SBO-04 to perform

Blacked Out Unit local actions.

5. Directs 0EOP-01-SBO-06 for actions to

crosstie E2 to E4.

6. Directs 0EOP-01-SBO-07 for actions to

crosstie E7 to E8.

7. Directs 0EOP-01-SBO-08 for actions to

crosstie E1 to E3.

When directed, reduces RPV pressure to

RO 150-300 psig, may exceed 100°F cooldown

rate.

Performs 0EOP-01-SBO-01 actions:

Performs 0EOP-01-SBO-02 actions:

1. Starts Control Room A/C or dispatches AO

to open panel doors.

2. Aligns RCIC and HPCI to torus.

3. Align Switchyard, DGs, RCC, and S/D

Cooling for restoration.

Dispatches AOs to perform:

1. 0EOP-01-SBO-04 to perform Blacked Out

Unit local actions.

2. 0EOP-01-SBO-06 for actions to crosstie E2

RO to E4.

3. 0EOP-01-SBO-07 for actions to crosstie E7

to E8.

4. 0EOP-01-SBO-08 for actions to crosstie E1

to E3.

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ENCLOSURE 1 Page 1 of 1

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ENCLOSURE 3 Page 1 of 3

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ATTACHMENT 1 - Scenario Quantitative Attribute Assessment

Category Scenario Content

Rev. 2 Supp. 1 Req.

Total Malfunctions 5-8 7

Malfunctions after EOP

1-2 3

Entry

Abnormal Events 2-4 2

Major Transients 1-2 1

EOPs Used 1-2 3

EOP Contingency 0-2 2

Run Time 60-90 min 90

Crew Critical Tasks 2-3 2

Tech Specs 2 2

Instrument / Component 2 - OATC

Failures before Major 4

2 - BOP

Instrument / Component

2 2

Failures after Major

Normal Operations 1 1

Reactivity manipulation 1 1

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ATTACHMENT 2 - Shift Turnover

Brunswick Unit 2 Plant Status

Station Duty Workweek

J. Pierce D. Hunter

Manager: Manager:

Mode: 1 Rx Power: 55%

Plant Risk:

Green

Current EOOS Risk Assessment is:

SFP Time to

121.7 hrs Days Online: 450 days

200 Deg F:

2PT-40.2.12 is in progress, Bypass Valves 7 and 8 have failed. I/C

have performed trouble shooting of the test circuitry and have identified

no problems with the circuitry. Complete 2PT-40.2.12 Sections 7.12

and 13 to test Bypass valves 9 and 10.

Turnover:

After completion of 2PT-40.2.12, continue plant shutdown IAW 0GP-05

(Step 6.1.4) to lower power to 100 MWe. (A2 sequence at step 68.)

0GP-05 is in-progress (Steps 6.1.6, 6.1.7, and 6.1.8 complete)

Protected

None

Equipment:

The BOP is to complete the performance of 2PT-40.2.12 Section 7.12,

Testing Bypass Valve Number 9 and Section 7.13, Testing Bypass

Comments: Valve Number 10.

A severe thunderstorm watch is in effect for SE North Carolina.

DUKE ENERGY

BRUNSWICK TRAINING SECTION

LESSON TITLE: Shift CRD pumps IAW OP-08 (AP Two Scrammed Rods)

(JPM A RO/ISRO)

LESSON NUMBER: LOT-SIM-JP-008-B04

REVISION NO: 0

Phil Capehart 03/13/17

PREPARER / DATE

Daniel Hulgin 03/13/17

TECHNICAL REVIEWER / DATE

Trey Bunnel 05/05/17

Rob Lax 05/05/17

VALIDATOR / DATE

Craig Oliver 05/24/17

LINE SUPERVISOR / DATE

Ed Rau 05/24/17

TRAINING SUPERVISION APPROVAL / DATE

LOT-SIM-JP-008-B04 Page 1 of 13 Rev.0

RELATED TASKS:

201023B101 Restart The CRD Hydraulic System Following A Loss Of A CRD Pump

Per OP-08

K/A REFERENCE AND IMPORTANCE RATING:

210001 Control Rod Drive Hydraulic System

A2 Ability to (a) predict the impacts of the following on the CONTROL ROD DRIVE

HYDRAULIC SYSTEM; and (b) based on those predictions, use procedures to

correct, control, or mitigate the consequences of those abnormal conditions or

operations:

A2.04 Scram conditions

RO 3.8 / SRO 3.9

REFERENCES:

2OP-08, Control Rod Drive Hydraulic System Operating Procedure

0AOP-02.0, Control Rod Malfunction/Misposition

0OI-37.17, EOP HARD CARDS

TOOLS AND EQUIPMENT:

None

SAFETY FUNCTION (from NUREG 1123, Rev. 2, Supp. 1):

1 - Reactivity Control

SETUP INSTRUCTIONS

IC: IC commensurate with ~20% power

TRGs: (TRG for scram of 2 control rods)

MFs:

ORs:

RFs

ENSURE CRD PARAMETERS ARE IN SPEC IAW 2OP-08

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SAFETY CONSIDERATIONS:

1. None.

EVALUATOR NOTES: (Do not read to performer)

1. The applicable procedure section WILL be provided to the trainee.

2. Prior to the first JPM of the JPM set, provide the JPM briefing contained in NUREG-1021,

Appendix E, or similar briefing (for non-regulated exams) to the trainee(s).

Read the following to the JPM performer.

TASK CONDITIONS:

1. Unit Two is operating at 20% power.

2. CRD is in normal operation per 2OP-08 with the CRD Pump 2A running

3. Maintenance is to be performed on CRD Pump 2A.

INITIATING CUE:

You are directed by the CRS to shift the CRD pumps from CRD 2A running to CRD pump 2B

running.

LOT-SIM-JP-008-B04 Page 3 of 13 Rev.0

PERFORMANCE CHECKLIST

NOTE: Sequence is assumed unless otherwise indicated, comments required for any step evaluated as UNSAT.

TIME START: ___________

Step 1 - Obtain a copy of 2OP-08.

Copy of 2OP-08 obtained.

SAT/UNSAT

Step 2- Review applicable precautions and limitations.

P&Ls reviewed.

SAT/UNSAT

Step 3- Verifies from the initial conditions that Section 5 Prerequisites have been completed.

Section 5 prerequisites verified (given in initial conditions).

SAT/UNSAT

Step 4- (6.3.2 Step 1) Ensure CRD System in operation per Section 6.1.1.

CRD verified in operation (given in initial conditions).

SAT/UNSAT

Step 5- (6.3.2 Step 2) IF starting CRD Pump 2A AND securing CRD Pump 2B, THEN perform

the following: ...

N/A (Task is to start 2B and Secure 2A).

SAT/UNSAT

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Examiner Cue: When contacted as RBAO, report section 6.3.2 steps 3 a, b, and c have been

completed.

Step 6- (6.3.2 Step 3a, b, and c) IF starting CRD Pump 2B AND securing CRD Pump 2A,

THEN perform the following:

Ensure 2-C12-F013B (CRD Pump 2B Suction Isolation Valve) LOCKED OPEN

Ensure 2-C12-F014B (CRD Pump 2B Discharge Isolation Valve) LOCKED

OPEN

Ensure 2-C12-F015B (CRD Pump 2B Recirculation Line Isolation Valve)

LOCKED OPEN

Directs AO to perform 6.3.2 Steps 3a to 3c

SAT/UNSAT

CAUTION

Failure to reduce CRD flow rate prior to starting the non-operating CRD pump could cause rod

drifts and require a manual reactor scram.

Step 7- (6.3.2 Step 4) Shift 2-C12-FC-R600 (CRD Flow Control) to BAL.

2-C12-FC-R600 selector rotated clockwise to the BAL position.

SAT/UNSAT

Step 8- (6.3.2 Step 5) Null C12-FC-R600 (CRD Flow Control) using the manual potentiometer.

2-C12-FC-R600 nulled by rotating knob to match flows (manual output matches

auto setpoint).

SAT/UNSAT

Step 9- (6.3.2 Step 6) Shift C12-FC-R600 (CRD Flow Control) to MAN.

2-C12-FC-R600 selector rotated clockwise to the MAN position.

SAT/UNSAT

NOTE

When CRD flow rate is set to 35 gpm, annunciator A-05, 2-1, CRD Charging Wtr Press Hi,

may ALARM.

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Step 10- (6.3.2 Step 7) Set CRD flow rate to 35 gpm.

CRD Flow adjusted to 35 gpm by rotating knob flowrate is set to 35 gpm.

If in alarm, announces and addresses A-05 2-1 with no actions necessary,

alarm due to adjusting CRD flow for pump start.

SAT/UNSAT

Step 11- (6.3.2 Step 8) IF starting CRD Pump 2A AND securing CRD Pump 2B, THEN

perform the following: ..

N/A (Task is to start 2B and Secure 2A).

SAT/UNSAT

Examiner Note: When the 2B pump is started and the 2A pump is stopped, 2 control rods will

scram beginning the Alternate Path portion of the JPM.

Examiner Note: When the 2B pump is started A-05 2-1 (CRD Charging Wtr Press Hi) and A-

05 6-1 (CRD pump filter inlet DP Hi ) may alarm..

Step 12- (6.3.2 Step 9a) IF starting CRD Pump 2B AND securing CRD Pump 2A, THEN

perform the following: Start CRD Pump 2B

CRD Pump 2B started by rotating the CS clockwise to the start position,

releasing switch., and observing Red light ON/Green Light OFF. (*CRITICAL

STEP)

If in alarm, announces and addresses A-05 2-1 and A-05 6-1 with no actions

necessary, alarms due to pump start. (Not critical)

- CRITICAL STEP** SAT/UNSAT

Sim Note: When the 2A pump is stopped, insert malfunction to scram 2 control rods.

Step 13- (6.3.2 Step 9b) IF starting CRD Pump 2B AND securing CRD Pump 2A, THEN

perform the following: Stop CRD Pump 2A

CRD Pump 2A stopped by rotating control switch counter-clockwise to the STOP

position, releasing switch, and observing Green light ON/Red light OFF.

- CRITICAL STEP** SAT/UNSAT

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- Begin Alternate Path **

Step 14- Announce scram of 2 control rods, and inserting reactor scram.

Announces A-05 3-2, Rod Drift.

Diagnoses the scram of 2 control rods while less than 25% power, announces

scram of 2 control rods and inserting reactor scram.

SAT/UNSAT

Step 15- (0AOP-02.0 step 3) IF less than or equal to 25% power, AND more than one control

rod scrams, THEN insert a manual scram AND enter 2EOP-01-RSP, Reactor Scram

Procedure.

Reactor scram inserted by depressing manual scram pushbuttons.

- CRITICAL STEP** SAT/UNSAT

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Step 16- (Unit 2 SCRAM Immediate Actions) Perform scram immediate actions:

Ensure SCRAM valves OPEN by manual SCRAM or ARI initiation.

WHEN steam flow less than 3.0 Mlb/hr, THEN place reactor mode switch in

SHUTDOWN.

IF reactor power below 2% (APRM downscale trip), THEN trip main turbine.

Ensure master RPV level controller setpoint at +170 inches.

IF: Two reactor feed pumps running AND RPV level above +160 inches AND

RPV level rising, THEN trip one.

Scram immediate actions performed as follows:

Observes RPS de-energized eight white lights are extinguished and rods are

inserted.

Mode switch rotated counter-clockwise to Shutdown when steam flow on C32-

R602 (Main Steam Flow) is less than 3.0 Mlb/hr (red line on gauge)

Turbine Trip pushbutton depressed when APRM power is downscale (<2% or

APRM downscale lights lit)

As RWL is rising above 160 inches (observed on N004 narrow range), trips A or

B RFP by depressing trip pushbutton.

- CRITICAL STEP** SAT/UNSAT

TERMINATING CUE: When a scram has been inserted and the scram immediate actions

have been performed, this JPM is complete.

TIME COMPLETED: _____________

COLLECT AND CONTROL ALL JPM EXAM MATERIALS FOR EXAM SECURITY.

LOT-SIM-JP-008-B04 Page 8 of 13 Rev.0

Step Critical / Not Critical Reason

1 Not Critical Administrative

2 Not Critical Given in initial conditions

3 Not Critical Given in initial conditions

4 Not Critical Given in initial conditions

5 Not Critical Not part of task N/A

6 Not Critical Communication

7 Not Critical Manipulation not critical task

8 Not Critical Manipulation not critical task

9 Not Critical Manipulation not critical task

10 Not Critical Manipulation not critical task

11 Not Critical Not part of task N/A

12 Critical Critical to task starting pump

13 Critical Critical to task stopping pump

14 Not Critical Communication

15 Critical IA required

16 Critical IA required

LOT-SIM-JP-008-B04 Page 9 of 13 Rev.0

WORK PRACTICES:

Comments are required for any step evaluated as UNSAT

A. CORE 4 SAT/ UNSAT/ NE

1. Task Preview / Pre-Job Briefs

2. Take-A-Minute

3. Correct Component Verification (CCV), Validate

Assumptions

4. Procedure and Work Instruction Use and Adherence

(PU&A)

B. Communications (proper content, repeat backs, 3 step SAT/ UNSAT/ NE

communications, etc.)

C. STAR (Use of Stop, Think, Act, Review) SAT/ UNSAT/ NE

D. Peer Checking (if performer requests or discusses peer checking) SAT/ UNSAT/ NE

E. Proper Equipment Use (observe starting limitations, throttle valve SAT/ UNSAT/ NE

closures, etc.)

F. Safety Compliance (use of PPE, knowledge of safety equipment, SAT/ UNSAT/ NE

etc.)

G. Electrical Safety And Arc Flash Protection Compliance (refer to SAT/ UNSAT/ NE

AD-HS-ALL-0110, as applicable)

H. Security Compliance (controlled area entry and exit, key control, SAT/ UNSAT/ NE

etc.)

I. Proper Tool Use (proper tool for the job, calibration dates, etc.) SAT/ UNSAT/ NE

J. Radiation Protection (ALARA, understanding and use of RWP, SAT/ UNSAT/ NE

frisking, etc.)

Comments:

LOT-SIM-JP-008-B04 Page 10 of 13 Rev.0

REVISION SUMMARY

0 New JPM- Initial Revision.

(Provide sufficient detail for reviewers and evaluators to understand the scope of any

technical and/or administrative changes).

LOT-SIM-JP-008-B04 Page 11 of 13 Rev.0

Validation Time: 15 Minutes (approximate).

Time Taken: ____ Minutes

APPLICABLE METHOD OF TESTING

Performance: Simulate Actual X Unit: 2

Setting: In-Plant Simulator X Admin

Time Critical: Yes No X Time Limit N/A

Alternate Path: Yes X No

EVALUATION

Performer:

JPM: Pass Fail

Remedial Training Required: Yes No

Comments:

Comments reviewed with Performer

Evaluator Signature: Date:

LOT-SIM-JP-008-B04 Page 12 of 13 Rev.0

TASK CONDITIONS:

1. Unit Two is operating at 20% power.

2. CRD is in normal operation per 2OP-08 with the CRD Pump 2A running

3. Maintenance is to be performed on CRD Pump 2A.

INITIATING CUE:

You are directed by the CRS to shift the CRD pumps from CRD 2A running to CRD pump 2B

running.

Page 13 of 13

DUKE ENERGY

BRUNSWICK TRAINING SECTION

LESSON TITLE: Reduce RPV Water Level Using RWCU To Radwaste

(JPM B RO / ISRO).

LESSON NUMBER: LOT-SIM-JP-014-A02

REVISION NO: 1

Phil Capehart 03/13/17

PREPARER / DATE

Daniel Hulgin 03/13/17

TECHNICAL REVIEWER / DATE

Trey Bunnel 05/05/17

VALIDATOR / DATE

Craig Oliver 05/24/17

LINE SUPERVISOR / DATE

Ed Rau 05/24/17

TRAINING SUPERVISION APPROVAL / DATE

LOT-SIM-JP-014-A02 Page 1 of 11 Rev.1

RELATED TASKS:

204002B101, Place The RWCU System In Service With The Reactor Not In Cold

Shutdown Per OP-14

K/A REFERENCE AND IMPORTANCE RATING:

204000 Reactor Water Cleanup System

A4 Ability to manually operate and/or monitor in the control room: (CFR: 41.7 / 45.5

to 45.8)

08 Reactor water level

RO 3.4 / SRO 3.4

REFERENCES:

2OP-14 Reactor Water Cleanup System Operating Procedure

TOOLS AND EQUIPMENT:

None

SAFETY FUNCTION (from NUREG 1123, Rev. 2, Supp. 1):

2 - Inventory Control (Reactor Water Cleanup)

SETUP INSTRUCTIONS

IC-11

Trigger None

Malfunction None

Override None.

Remote None

Insert a scram (perform immediate and hard card scram actions).

Allow RPV level to rise to ~ 200 inches. Ensure alarm A-07 2-2 is sealed in.

Make sure level set at 187 when coming out of freeze.

LOT-SIM-JP-014-A02 Page 2 of 11 Rev.1

SAFETY CONSIDERATIONS:

1. None.

EVALUATOR NOTES: (Do not read to performer)

1. The applicable procedure section WILL be provided to the trainee.

2. Prior to the first JPM of the JPM set, provide the JPM briefing contained in NUREG-1021,

Appendix E, or similar briefing (for non-regulated exams) to the trainee(s).

Read the following to the JPM performer.

TASK CONDITIONS:

1. Unit Two is in MODE 3 following a reactor scram.

2. RPV Water level band is 166 to 206 inches.

3. RWCU is in service.

4. Radwaste Control Room has been notified, and sufficient capacity exists for reject.

INITIATING CUE:

You are directed by the Unit CRS to:

Establish RWCU reject to Radwaste in accordance with 2OP-14 Section 6.3.14.

Lower RPV level to a target of 187 inches

LOT-SIM-JP-014-A02 Page 3 of 11 Rev.1

PERFORMANCE CHECKLIST

NOTE: Sequence is assumed unless otherwise indicated, comments required for any step evaluated as UNSAT.

Step 1 - Obtain current revision of 2OP-14.

Current revision of 2OP-14 is obtained.

SAT/UNSAT

TIME START: ___________

Evaluator Note: If operator asks to use hard card, repeat the initiating cue.

Step 2 - Confirm the following Initial Conditions are met:

RWCU is in service.

RPV level control using RWCU reject is desired following a Scram.

Given in task conditions and initiating cue.

SAT/UNSAT

CAUTION:

During reactor reject operations, simultaneously opening G31-F035 (Reject To Radwaste Vlv)

and G31-F034 (Reject To Cndsr Vlv) when there is vacuum in the main condenser may cause

vacuum to be lost via Radwaste.

Step 3 - Open one of the following valves as directed by the Unit CRS to align RWCU reject

flow:

IF condenser hotwells are available, THEN open G31-F034, (Reject To Condsr Vlv).

IF condenser hotwells are NOT available, THEN open G31-F035 (Reject To

Radwaste Vlv).

The control switch for G31-F035, Reject To Radwaste Vlv, is placed to OPEN

and spring return to NEUT. The red light is observed ON and the green light

observed OFF

- CRITICAL STEP** SAT/UNSAT

LOT-SIM-JP-014-A02 Page 4 of 11 Rev.1

PROMPT: If contacted as Radwaste, state sufficient capacity exists for reject.

Step 4 - IF rejecting to Radwaste, THEN notify the Radwaste Control Room

Identifies Radwaste Control has been notified per initial conditions or Radwaste

Control Room is notified of aligning RWCU reject to Radwaste.

SAT/UNSAT

CAUTION:

G31-F004 (RWCU Outboard Isol Vlv) will close if Filter Inlet temperature reaches 135°F.

Failure to limit reject flow to 90 to 105 gpm, indicated on G31-FI-R602 (Reject Flow) while in

MODE 1, 2 or 3 could result in damage to the heat exchangers

Step 5 - Slowly throttle G31-F033, (RWCU Reject Flow Control Vlv) to establish desired reject

flow rate NOT exceeding 90 to 105 gpm on G31-FI-R602 (Reject Flow).

The knob for the G31-F033, RWCU Reject Flow Control Vlv, is slowly rotated in

the clockwise direction to establish flow 105 gpm on G31-FI-R602, Reject Flow

- CRITICAL STEP** SAT/UNSAT

CAUTION:

When reactor water temperature indicated on G31-TI-R607 (RWCU Temp) point 1, is greater

than or equal to 300°F and reactor water level is greater than 105", maximum system flow is

limited to less than or equal to 290 gpm indicated on G31-FI-R609 (Pump Flow).

Step 6 - Maintain pump flow less than or equal to 290 gpm on G31-FI-R609 (Pump Flow) and

Filter Inlet temperature, G31-TI-R607 (RWCU Temp) point 3, less than 130°F, by

throttling the following valves:

G31-F042 (Return To Vessel Vlv).

G31-F033 (RWCU Reject Flow Control Vlv).

Maintains filter inlet temperature less than 135°F on Regen HX Outlet, Point 2,

and/or Filter Inlet, Point 3, on G31-TI-R607 by throttling G31-F033.

- CRITICAL STEP** SAT/UNSAT

LOT-SIM-JP-014-A02 Page 5 of 11 Rev.1

NOTE:

Flashing may occur at less than 500 psig. Flashing is recognized by oscillations on G31-FI-

R602 (Reject Flow).

Step 7 - IF heatup rates CANNOT be achieved OR reject line flashing occurs, THEN throttle

open G31-F031 (Orifice Bypass Vlv).

Throttles G31-F031 as necessary

SAT/UNSAT

Evaluator Note: Based on current water level, evaluator may provide a new target water

level.

Step 8 - Lower RPV water level at or below 187 as indicated by C32-LI-N004A/B/C.

When RPV level is in band (target 187 inches or new target level) reduces reject

flow by rotating G31-F033 in the close direction.

- CRITICAL STEP** SAT/UNSAT

Step 9 - Inform CRS that RPV water level has been restored to the target value.

CRS informed that RPV water level has been restored to the target value of 187

inches.

SAT/UNSAT

TERMINATING CUE: When RPV level has been lowered to the established band (target 187

inches) and the CRS notified this JPM is complete.

TIME COMPLETED: _____________

COLLECT AND CONTROL ALL JPM EXAM MATERIALS FOR EXAM SECURITY.

LOT-SIM-JP-014-A02 Page 6 of 11 Rev.1

Step Critical / Not Critical Reason

1 Not Critical Administrative

2 Not Critical Given in task conditions

3 Critical Necessary for RWCU reject lineup

4 Not Critical Communication given in task conditions

5 Critical Necessary for RWCU reject lineup

6 Critical Necessary to prevent isolation

7 Not Critical Conditional step

8 Critical Necessary per task cue

9 Not Critical Communication

LOT-SIM-JP-014-A02 Page 7 of 11 Rev.1

WORK PRACTICES:

Comments are required for any step evaluated as UNSAT

A. CORE 4 SAT/ UNSAT/ NE

1. Task Preview / Pre-Job Briefs

2. Take-A-Minute

3. Correct Component Verification (CCV), Validate

Assumptions

4. Procedure and Work Instruction Use and Adherence

(PU&A)

B. Communications (proper content, repeat backs, 3 step SAT/ UNSAT/ NE

communications, etc.)

C. STAR (Use of Stop, Think, Act, Review) SAT/ UNSAT/ NE

D. Peer Checking (if performer requests or discusses peer checking) SAT/ UNSAT/ NE

E. Proper Equipment Use (observe starting limitations, throttle valve SAT/ UNSAT/ NE

closures, etc.)

F. Safety Compliance (use of PPE, knowledge of safety equipment, SAT/ UNSAT/ NE

etc.)

G. Electrical Safety And Arc Flash Protection Compliance (refer to SAT/ UNSAT/ NE

AD-HS-ALL-0110, as applicable)

H. Security Compliance (controlled area entry and exit, key control, SAT/ UNSAT/ NE

etc.)

I. Proper Tool Use (proper tool for the job, calibration dates, etc.) SAT/ UNSAT/ NE

J. Radiation Protection (ALARA, understanding and use of RWP, SAT/ UNSAT/ NE

frisking, etc.)

Comments:

LOT-SIM-JP-014-A02 Page 8 of 11 Rev.1

REVISION SUMMARY

1 Reformatted to new template

JPM has been rewritten in entirety to conform to procedural guidance.

0 New JPM developed by NRC for 2003 license exam

(Provide sufficient detail for reviewers and evaluators to understand the scope of any

technical and/or administrative changes).

LOT-SIM-JP-014-A02 Page 9 of 11 Rev.1

Validation Time: 10 Minutes (approximate).

Time Taken: ____ Minutes

APPLICABLE METHOD OF TESTING

Performance: Simulate Actual X Unit: 2

Setting: In-Plant Simulator X Admin

Time Critical: Yes No X Time Limit N/A

Alternate Path: Yes No X

EVALUATION

Performer:

JPM: Pass Fail

Remedial Training Required: Yes No

Comments:

Comments reviewed with Performer

Evaluator Signature: Date:

LOT-SIM-JP-014-A02 Page 10 of 11 Rev.1

TASK CONDITIONS:

1. Unit Two is in MODE 3 following a reactor scram.

2. RPV Water level band is 166 to 206 inches.

3. RWCU is in service.

4. Radwaste Control Room has been notified, and sufficient capacity exists for reject.

INITIATING CUE:

You are directed by the Unit CRS to:

Establish RWCU reject to Radwaste in accordance with 2OP-14 Section 6.3.14.

Lower RPV level to a target of 187 inches

Page 11 of 11

DUKE ENERGY

BRUNSWICK TRAINING SECTION

LESSON TITLE: Re-Establish Drywell Cooling during SBO

(JPM C RO / ISRO)

LESSON NUMBER: LOT-SIM-JP-303-A11

REVISION NO: 0

Phil Capehart 03/13/17

PREPARER / DATE

Daniel Hulgin 03/13/17

TECHNICAL REVIEWER / DATE

Trey Bunnel 05/05/17

Rob Lax 05/05/17

VALIDATOR / DATE

Craig Oliver 05/24/17

LINE SUPERVISOR / DATE

Ed Rau 05/24/17

TRAINING SUPERVISION APPROVAL / DATE

LOT-SIM-JP-303-A11 Page 1 of 11 Rev.0

RELATED TASKS:

262004B401 Respond To A Total Loss Of All AC Electrical Distribution (Station

Blackout) Per EOP-01-SBO

K/A REFERENCE AND IMPORTANCE RATING:

400000 Component Cooling Water System (CCWS)

A4. Ability to manually operate and / or monitor in the control room: (CFR: 41.7 / 45.5

to 45.8)

01 CCW indications and control

RO 3.1 / SRO 3.0

REFERENCES:

2EOP-01-SBO-12 Unit 2 SBO Drywell Cooling

2OP-21 Reactor Building Closed Cooling Water System Operating Procedure

TOOLS AND EQUIPMENT:

None

SAFETY FUNCTION (from NUREG 1123, Rev. 2, Supp. 1):

Safety Function 8 - Component Cooling Water System

SETUP INSTRUCTIONS

(See next page)

LOT-SIM-JP-303-A11 Page 2 of 11 Rev.0

SETUP INSTRUCTIONS

1. Reset to IC-14, place RBCCW B & C to ON, A to AUTO, override AUTO position OFF

for RBCCW Pump 2A and override RBCCW Pump B in OFF.

2. Initiate Event Trigger E1 and allow plant to stabilize. Take required operator actions to

stabilize the plant.

3. Take initial SBO actions, cooldown using SRVs to 150-300 psig.

4. Cross-tie E1-E3, then, E7-E8 per SBO.

5. Ensure DG1 load <3000 KW using Remote Functions as required.

6. Insert batch file to defeat drywell cooler LOCA lockout.

7. Energize MCC 2PA - Delete Malfunction EE030M 2PA

8. Install control power fuses for 2A NSW - Delete Remote Function ED_ IABKCF12 - IN

9. Ensure NSW 2A in service and Pump Discharge Valve, SW-V19, is OPEN.

10. When the plant is stable, place the simulator in FREEZE.

11. INSERT REMOTE FUNCTION EP_IAEOPJ14 (V103) [2.3 Step 8] AND EP_IAEOPJ15

(V106) [2.3 Step 7]

12. V103 is open and power removed (EE030M, 2XB)

13. Defeat LOCA/LOOP trips of RCC Pumps (EP_IAEOP12, IN)

14. Ensure 2XE is energized if necessary delete malfunction EE030M, 2XE.

Triggers

Event Trigger Description

E1 Manually Initiated - Station Blackout and EDG Failures

E2 Manually Initiated - Load Strip E1/E3 and cross tie them

E3 Manually Initiated - Load strip all 480 VAC buses

E4 Manually Initiated - Cross Tie all 480 VAC buses

Malfunctions

Event System Tag Title Value Activate Deactivate Time

(ramp rate) Time (sec) (sec)

A DG DG027F DG4 NA NA NA

Differential

E1 EE EE031F Station N/A N/A N/A

Blackout

Remote Functions

Event Tag Title Value

(ramp rate)

A ED_IADCAPD3 DG-3 DC Bkr Ctl Power OFF

LOT-SIM-JP-303-A11 Page 3 of 11 Rev.0

SAFETY CONSIDERATIONS:

1. None

EVALUATOR NOTES: (Do not read to performer)

1. The applicable procedure sections WILL be provided to the trainee.

2. Prior to the first JPM of the JPM set, provide the JPM briefing contained in NUREG-1021,

Appendix E, or similar briefing (for non-regulated exams) to the trainee(s).

Read the following to the JPM performer.

TASK CONDITIONS:

The sequence of events was as follows:

1. Unit One and Unit Two have lost all off-site power.

2. DG3 is under clearance and DG4 tripped on differential overcurrent.

3. DG1 is running and tied to E1, DG2 is running tied to E2.

4. E1 was cross-tied to E3 (including required load stripping).

5. E8 was cross-tied to E7 (including required stripping).

6. E4 cannot be energized due to trip of 86DP on E4.

7. Drywell cooler LOCA lockout circuit alterations have been performed per the guidance

of EOP-02-PCCP and SEP-10.

8. NSW 2A has been started per 2EOP-01-SBO-12 Section 2.3.

9. 2EOP-01-SBO-12 has been completed up to Section 2.3 step 18.f.

10. Jumper 37 has been installed per 2EOP-01-SBO-12 Section 2.3 step 18.b.

11. 2OP-21 Section 6.3.7 has been completed up to step 5c for RBCCW pump C

12. Attachment 7 wait times have been completed.

13. An auxiliary operator is on station for performance of 2OP-21.

INITIATING CUE:

You have been directed by the Unit CRS to:

Continue re-establishing Drywell Cooling per 2EOP-01-SBO-12 starting at Section 2.3

step 18.f and 2OP-21 Section 6.3.7 step 5c.

Inform the CRS when Drywell Cooling is re-established.

LOT-SIM-JP-303-A11 Page 4 of 11 Rev.0

PERFORMANCE CHECKLIST

NOTE: Sequence is assumed unless otherwise indicated, comments required for any step evaluated as UNSAT.

Step 1 - Obtain current revision of 2EOP-01-SBO-12.

Current revision of 2EOP-01-SBO-12 obtained.

SAT/UNSAT

TIME START: ___________

Step 2 - (2.3 Step 18f) IF any drywell temperature limit exceeded, THEN start RBCCW per

2OP-21 with high drywell temperature.

Obtains current revision of 2OP-21.

SAT/UNSAT

Step 3 - (6.3.7 step 5c) WHEN directed by Attachment 7, Required Drywell Cooldown Time

Prior to RBCCW Pump Restart to restart RBCCW pumps, THEN perform the

following for the pump to be started in RBCCW Mode:

a. Start the RBCCW pump:

RBCCW PUMP 2A

RBCCW PUMP 2B

RBCCW PUMP 2C

RBCCW PUMP 2D

RBCCW pump 2C started by placing control switch to start. Observes no red

light or RCC pressure indication changes.

- CRITICAL STEP** SAT/UNSAT

NOTE: When the pump CS is placed in run it will not start.

LOT-SIM-JP-303-A11 Page 5 of 11 Rev.0

Step 4 - (6.3.7 step 5d) WHEN directed by Attachment 7, Required Drywell Cooldown Time

Prior to RBCCW Pump Restart to restart RBCCW pumps, THEN perform the

following for the pump to be started in RBCCW Mode:

b. Slowly open the discharge valve throttled closed for pump start until it is fully

OPEN:

2-RCC-V38 (RBCCW Pump A Discharge Valve)

2-RCC-V36 (RBCCW Pump B Discharge Valve)

2-RCC-V34 (RBCCW Pump C Discharge Valve)

2-RCC-V5111 (RBCCW Pump 2D Discharge Valve)

May contact field AO to OPEN 2-RCC-V34.

SAT/UNSAT

NOTE: Step may not be performed.

Prompt: If applicant contacts the AO to reopen the 2-RCC-V34, report valve has been re-

opened.

- Begin Alternate Path **

Step 5 - Inform CRS of failure to start of RBCCW Pump 2C

CRS informed of failure to start of RBCCW pump or 2C.

SAT/UNSAT

Prompt: When applicant informs CRS, acknowledge failure to start.

If needed, prompt applicant to start any available pump.

Step 6 - (6.3.7 step 5b) WHEN directed by Attachment 7, Required Drywell Cooldown Time

Prior to RBCCW Pump Restart to restart RBCCW pumps, THEN perform the

following for the pump to be started in RBCCW Mode:

b. Throttle the discharge valve CLOSED 80% to 90%:

2-RCC-V38 (RBCCW Pump A Discharge Valve)

2-RCC-V36 (RBCCW Pump B Discharge Valve)

2-RCC-V34 (RBCCW Pump C Discharge Valve)

2-RCC-V5111 (RBCCW Pump 2D Discharge Valve)

Contacts field AO to throttle the 2-RCC-V38 closed 80% to 90%.

SAT/UNSAT

Prompt: When applicant contacts AO to throttle the 2-RCC-V38, report valve has been

throttled close to 90%.

LOT-SIM-JP-303-A11 Page 6 of 11 Rev.0

Step 7 - (6.3.7 step 5c) WHEN directed by Attachment 7, Required Drywell Cooldown Time

Prior to RBCCW Pump Restart to restart RBCCW pumps, THEN perform the

following for the pump to be started in RBCCW Mode:

c. Start the RBCCW pump:

RBCCW PUMP 2A

RBCCW PUMP 2B

RBCCW PUMP 2C

RBCCW PUMP 2D

RBCCW pump 2A started by placing control switch in the start position and

observing red light illuminates and green light off. Observes RCC discharge

pressure rises.

- CRITICAL STEP** SAT/UNSAT

TERMINATING CUE: When the RBCCW pump is started in step 9, this JPM is complete.

TIME COMPLETED: _____________

COLLECT AND CONTROL ALL JPM EXAM MATERIALS FOR EXAM SECURITY.

Step Critical / Not Critical Reason

1 Not Critical Administrative

2 Not Critical Administrative

3 Critical Pump start necessary to reestablish DW cooling

4 Not Critical Communication

5 Not Critical Communication

6 Not Critical Communication

7 Critical Pump start necessary to reestablish DW cooling

LOT-SIM-JP-303-A11 Page 7 of 11 Rev.0

WORK PRACTICES:

Comments are required for any step evaluated as UNSAT

A. CORE 4 SAT/ UNSAT/ NE

1. Task Preview / Pre-Job Briefs

2. Take-A-Minute

3. Correct Component Verification (CCV), Validate

Assumptions

4. Procedure and Work Instruction Use and Adherence

(PU&A)

B. Communications (proper content, repeat backs, 3 step SAT/ UNSAT/ NE

communications, etc.)

C. STAR (Use of Stop, Think, Act, Review) SAT/ UNSAT/ NE

D. Peer Checking (if performer requests or discusses peer checking) SAT/ UNSAT/ NE

E. Proper Equipment Use (observe starting limitations, throttle valve SAT/ UNSAT/ NE

closures, etc.)

F. Safety Compliance (use of PPE, knowledge of safety equipment, SAT/ UNSAT/ NE

etc.)

G. Electrical Safety And Arc Flash Protection Compliance (refer to SAT/ UNSAT/ NE

AD-HS-ALL-0110, as applicable)

H. Security Compliance (controlled area entry and exit, key control, SAT/ UNSAT/ NE

etc.)

I. Proper Tool Use (proper tool for the job, calibration dates, etc.) SAT/ UNSAT/ NE

J. Radiation Protection (ALARA, understanding and use of RWP, SAT/ UNSAT/ NE

frisking, etc.)

Comments:

LOT-SIM-JP-303-A11 Page 8 of 11 Rev.0

REVISION SUMMARY

0 New JPM initial revision, modified from LOT-SIM-JP-303-A07 Rev 2.

(Provide sufficient detail for reviewers and evaluators to understand the scope of any

technical and/or administrative changes).

LOT-SIM-JP-303-A11 Page 9 of 11 Rev.0

Validation Time: 15 Minutes (approximate).

Time Taken: ____ Minutes

APPLICABLE METHOD OF TESTING

Performance: Simulate Actual X Unit: 2

Setting: In-Plant Simulator X Admin

Time Critical: Yes No X Time Limit N/A

Alternate Path: Yes X No

EVALUATION

Performer:

JPM: Pass Fail

Remedial Training Required: Yes No

Comments:

Comments reviewed with Performer

Evaluator Signature: Date:

LOT-SIM-JP-303-A11 Page 10 of 11 Rev.0

TASK CONDITIONS:

The sequence of events was as follows:

1. Unit One and Unit Two have lost all off-site power.

2. DG3 is under clearance and DG4 tripped on differential overcurrent.

3. DG1 is running and tied to E1, DG2 is running tied to E2.

4. E1 was cross-tied to E3 (including required load stripping).

5. E8 was cross-tied to E7 (including required stripping).

6. E4 cannot be energized due to trip of 86DP on E4.

7. Drywell cooler LOCA lockout circuit alterations have been performed per the guidance

of EOP-02-PCCP and SEP-10.

8. NSW 2A has been started per 2EOP-01-SBO-12 Section 2.3.

9. 2EOP-01-SBO-12 has been completed up to Section 2.3 step 18.f.

10. Jumper 37 has been installed per 2EOP-01-SBO-12 Section 2.3 step 18.b.

11. 2OP-21 Section 6.3.7 has been completed up to step 5c for RBCCW pump C

12. Attachment 7 wait times have been completed.

13. An auxiliary operator is on station for performance of 2OP-21.

INITIATING CUE:

You have been directed by the Unit CRS to:

Continue re-establishing Drywell Cooling per 2EOP-01-SBO-12 starting at Section 2.3

step 18.f and 2OP-21 Section 6.3.7 step 5c.

Inform the CRS when Drywell Cooling is re-established.

Page 11 of 11

DUKE ENERGY

BRUNSWICK TRAINING SECTION

LESSON TITLE: Spray the Drywell IAW SEP-02 (LOOP-B)

(JPM D RO / ISRO / USRO)

LESSON NUMBER: LOT-SIM-JP-300-K26

REVISION NO: 0

Phil Capehart 03/13/17

PREPARER / DATE

Daniel Hulgin 03/13/17

TECHNICAL REVIEWER / DATE

Trey Bunnel 05/05/17

Rob Lax 05/05/17

VALIDATOR / DATE

Craig Oliver 05/24/17

LINE SUPERVISOR / DATE

Ed Rau 05/24/17

TRAINING SUPERVISION APPROVAL / DATE

LOT-SIM-JP-300-K26 Page 1 of 13 Rev.0

RELATED TASKS:

200049B501 Spray The Drywell Per EOP-01-SEP-02.

K/A REFERENCE AND IMPORTANCE RATING:

295024 High Drywell Pressure

EA 1 Ability to operate and/or monitor the following as they apply to HIGH DRYWELL

PRESSURE: (CFR: 41.7 / 45.6)

11 Drywell spray: Mark-I&II

RO 4.2 / SRO 4.2

REFERENCES:

0EOP-01-SEP-02 Drywell Spray Procedure

2OP-17 Residual Heat Removal System Operating Procedure

2OP-43 Service Water System Operating Procedure

TOOLS AND EQUIPMENT:

None

SAFETY FUNCTION (from NUREG 1123, Rev. 2, Supp. 1):

Safety Function 5, Containment Integrity

SETUP INSTRUCTIONS

IC 11

Malfunctions : NB009F Small Recirc Suction Line Rupture Value 5%

Insert malfunction

Insert a Reactor scram and perform Operator immediate actions

Maintain MSIVs open and allow EHC to control Reactor pressure

If needed, allow RCIC/HPCI to automatically start and inject

When Suppression Chamber pressure exceeds 11.5 psig, reduce the Recirc

Suction Leak value (size) to 2%.

Place A loop RHR in Torus Spray

Start NSW 2A pump

LOT-SIM-JP-300-K26 Page 2 of 13 Rev.0

SAFETY CONSIDERATIONS:

1. None.

EVALUATOR NOTES: (Do not read to performer)

1. The applicable procedure section WILL be provided to the trainee.

2. Prior to the first JPM of the JPM set, provide the JPM briefing contained in NUREG-1021,

Appendix E, or similar briefing (for non-regulated exams) to the trainee(s).

Read the following to the JPM performer.

TASK CONDITIONS:

1. A LOCA inside Primary Containment has caused a reactor scram due to high

containment pressure.

2. Suppression Chamber Pressure has exceeded 11.5 psig.

INITIATING CUE:

You are directed by the Unit CRS to:

Place the B Loop of RHR in Drywell Sprays using SEP-02, DRYWELL SPRAY

PROCEDURE.

Notify the Unit CRS when all required actions are complete.

LOT-SIM-JP-300-K26 Page 3 of 13 Rev.0

PERFORMANCE CHECKLIST

NOTE: Sequence is assumed unless otherwise indicated, comments required for any step evaluated as UNSAT.

Step 1 - Obtain the current revision of 0EOP-01-SEP-02, DRYWELL SPRAY PROCEDURE.

Current revision of SEP-02 is obtained.

SAT/UNSAT

EVALUATOR NOTE: Applicant may obtain 3095 keys from the RO desk.

TIME START: ___________

Step 2 - Ensure both reactor recirculation pumps tripped.

Both RR pumps tripped by depressing trip pushbutton for A&B RR pumps.

- CRITICAL STEP** SAT/UNSAT

PROMPT: May ask if load stripping has occurred, provide that load stripping has not occurred.

Step 3 - IF E-bus load stripping has occurred, THEN:.

Step not performed.

SAT/UNSAT

EVALUATOR NOTE: The Drywell Coolers should stop when placed in OFF (L/O). Steps 5,6,

and 7 of the JPM (steps 4,5, and 6 of SEP-02) direct energizing the LOCA Lockout Relays to

secure Drywell Coolers if they continue to run. This should not be required for this JPM since

no loss of pneumatics to the Drywell Cooler Discharge Dampers is present.

Step 4 - Place all drywell cooler control switches to OFF (L/O).

All 8 Drywell Cooler Control Switches are placed in OFF and each fan has a

green indicating light illuminated.

- CRITICAL STEP** SAT/UNSAT

LOT-SIM-JP-300-K26 Page 4 of 13 Rev.0

Step 5 - Unit 1 Only: IF drywell coolers continue to run, THEN:...

Step not performed.

SAT/UNSAT

Step 6 - Unit 2 Only: IF drywell coolers continue to run, THEN:

Step not performed.

SAT/UNSAT

Step 7 - IF drywell coolers continue to run, THEN secure drywell coolers per Attachment 1 and

continue at Section 2.1.3 Step 7.

Step not performed.

SAT/UNSAT

Step 8 - Ensure SW-V141 (Well Water to Vital Header Vlv) CLOSED.

SW-V141 verified CLOSED (green light lit and red light out).

SAT/UNSAT

Step 9 - Ensure one valve OPEN:

SW-V111 (Conv SW To Vital Header Vlv)

SW-V117 (Nuc SW To Vital Header Vlv)

SW-V111, places control switch in open and/or verifies red light lit and green light

out

-OR-

SW-V117, places control switch in open (throttle valve) and/or verifies red light lit

and green light out.

SAT/UNSAT

Step 10 - IF Loop A RHR will be used for drywell spray, THEN:.

Step not performed.

SAT/UNSAT

LOT-SIM-JP-300-K26 Page 5 of 13 Rev.0

NOTE:

E11-F017B will remain OPEN for five minutes following a LOCA signal.

Step 11 - IF Loop B RHR will be used for drywell spray, THEN:

a. IF E11-F015B (Inboard Injection Vlv) OPEN, THEN close E11-F017B (Outboard

Injection Vlv).

F015B is verified is closed (green light lit, red light out).

SAT/UNSAT

Step 12 - IF Loop B RHR will be used for drywell spray, THEN:

b. Place E11-CS-S18B (2/3 Core Height LPCI Initiation Override Switch) to

MANUAL OVERRD).

E11-CS-S18B is placed in the MANUAL OVERRD position by switching keys and

turning switch clockwise to the manual override position.

- CRITICAL STEP** SAT/UNSAT

Step 13 - IF Loop B RHR will be used for drywell spray, THEN:

c. Momentarily place E11-CS-S17B (Containment Spray Valve Control Switch) to

MANUAL.

E11-CS-S17B momentarily rotated to the right (spring return to center position)

MANUAL position. Observes white lights illuminate.

- CRITICAL STEP** SAT/UNSAT

Step 14 - IF Loop B RHR will be used for drywell spray, THEN:

d. Ensure E11-F024B (Torus Cooling Isol Vlv) CLOSED.

E11-F024B verified closed (green light lit, red light out).

SAT/UNSAT

Step 15 - IF Loop B RHR will be used for drywell spray, THEN:

e. Ensure one Loop B RHR Pump running.

B or D RHR pump is started by placing control switch in start position and

observing red light lit and green light out.

- CRITICAL STEP** SAT/UNSAT

LOT-SIM-JP-300-K26 Page 6 of 13 Rev.0

NOTE: The Applicant may use the ERFIS display or Figure 1 of SEP-02 to determine position

on the Drywell Spray Initiation Limit Graph.

Step 16 - IF Loop B RHR will be used for drywell spray, THEN:

f. Confirm requirements for Drywell Spray Initiation are met:

Safe region of the Drywell Spray Initiation Limit

Torus level below +21 inches

Verifies position on the Drywell Spray Initiation Limit Graph is within the Safe

region and Suppression Pool level below +21 inches

SAT/UNSAT

Step 17 - IF Loop B RHR will be used for drywell spray, THEN:

g. Open E11-F021B (Drywell Spray Inbd Isol Vlv).

E11-F021B is opened by placing control switch in the open position and

observing red light on and green light off.

- CRITICAL STEP** SAT/UNSAT

NOTE: One RHR will provide 8000 gpm with F016B full open. The Operator may start a

second RHR pump and establish a flow of 11,500 gpm. The Operator may also state

that the Drywell is being sprayed.

Step 18 - IF Loop B RHR will be used for drywell spray, THEN:

h. Throttle open E11-F016B (Drywell Spray Otbd Isol Vlv) to obtain between 8,000

gpm and 10,000 gpm flow.

E11-F016B throttled open until RHR flow is between 8,000 gpm and 10,000 gpm

as indicated on E11-FI-R603B, RHR System B Flow.

- CRITICAL STEP** SAT/UNSAT

Step 19 - IF Loop B RHR will be used for drywell spray, THEN:

i. IF E-bus load stripping has occurred, THEN go to Section 2.1.3 Step 11

Step not performed.

SAT/UNSAT

LOT-SIM-JP-300-K26 Page 7 of 13 Rev.0

PROMPT: If asked if additional flow is required, state it is not required.

Step 20 - IF Loop B RHR will be used for drywell spray, THEN:

j. IF additional flow required, THEN start the other RHR pump and limit flow to less

than or equal to 11,500 gpm.

IF a second pump is started, flow is limited to 11,500 gpm.

SAT/UNSAT

TERMINATING CUE: When drywell spray has been established >8,000 gpm, this JPM is

complete. Inform the applicant that another operator will complete the

rest of the procedure.

TIME COMPLETED: _____________

COLLECT AND CONTROL ALL JPM EXAM MATERIALS FOR EXAM SECURITY.

LOT-SIM-JP-300-K26 Page 8 of 13 Rev.0

Step Critical / Not Critical Reason

1 Not Critical Administrative

2 Critical Verification

3 Not Critical Step not performed

4 Critical Necessary to protect DW coolers

5 Not Critical Step not performed

6 Not Critical Step not performed

7 Not Critical Step not performed

8 Not Critical Verification

9 Not Critical Cooling

10 Not Critical Step not performed

11 Not Critical Verification

12 Critical Necessary to align sprays

13 Critical Necessary to align sprays

14 Not Critical Verification

15 Critical RHR pump needed for spray

16 Not Critical Verification

17 Critical Necessary to align sprays

18 Critical Necessary to align sprays

19 Not Critical Step not performed

20 Not Critical 2nd RHR pump not required

LOT-SIM-JP-300-K26 Page 9 of 13 Rev.0

WORK PRACTICES:

Comments are required for any step evaluated as UNSAT

A. CORE 4 SAT/ UNSAT/ NE

1. Task Preview / Pre-Job Briefs

2. Take-A-Minute

3. Correct Component Verification (CCV), Validate

Assumptions

4. Procedure and Work Instruction Use and Adherence

(PU&A)

B. Communications (proper content, repeat backs, 3 step SAT/ UNSAT/ NE

communications, etc.)

C. STAR (Use of Stop, Think, Act, Review) SAT/ UNSAT/ NE

D. Peer Checking (if performer requests or discusses peer checking) SAT/ UNSAT/ NE

E. Proper Equipment Use (observe starting limitations, throttle valve SAT/ UNSAT/ NE

closures, etc.)

F. Safety Compliance (use of PPE, knowledge of safety equipment, SAT/ UNSAT/ NE

etc.)

G. Electrical Safety And Arc Flash Protection Compliance (refer to SAT/ UNSAT/ NE

AD-HS-ALL-0110, as applicable)

H. Security Compliance (controlled area entry and exit, key control, SAT/ UNSAT/ NE

etc.)

I. Proper Tool Use (proper tool for the job, calibration dates, etc.) SAT/ UNSAT/ NE

J. Radiation Protection (ALARA, understanding and use of RWP, SAT/ UNSAT/ NE

frisking, etc.)

Comments:

LOT-SIM-JP-300-K26 Page 10 of 13 Rev.0

REVISION SUMMARY

0 Initial revision, modified from LOT-SIM-JP-300-K08 Rev 2

Changed to Loop B which requires different service water alignment.

(Provide sufficient detail for reviewers and evaluators to understand the scope of any

technical and/or administrative changes).

LOT-SIM-JP-300-K26 Page 11 of 13 Rev.0

Validation Time: 15 Minutes (approximate).

Time Taken: ____ Minutes

APPLICABLE METHOD OF TESTING

Performance: Simulate Actual X Unit: 2

Setting: In-Plant Simulator X Admin

Time Critical: Yes No X Time Limit N/A

Alternate Path: Yes No X

EVALUATION

Performer:

JPM: Pass Fail

Remedial Training Required: Yes No

Comments:

Comments reviewed with Performer

Evaluator Signature: Date:

LOT-SIM-JP-300-K26 Page 12 of 13 Rev.0

TASK CONDITIONS:

1. A LOCA inside Primary Containment has caused a reactor scram due to high

containment pressure.

2. Suppression Chamber Pressure has exceeded 11.5 psig.

INITIATING CUE:

You are directed by the Unit CRS to:

Place the B Loop of RHR in Drywell Sprays using SEP-02, DRYWELL SPRAY

PROCEDURE.

Notify the Unit CRS when all required actions are complete.

Page 13 of 13

DUKE ENERGY

BRUNSWICK TRAINING SECTION

LESSON TITLE: Restarting RCIC after AUTO initiation and Turbine Trip using the

Hard Card - Controller Failure

(JPM E RO / ISRO)

LESSON NUMBER: LOT-SIM-JP-016-01

REVISION NO: 2

Phil Capehart 03/13/17

PREPARER / DATE

Daniel Hulgin 03/13/17

TECHNICAL REVIEWER / DATE

Trey Bunnel 05/05/17

Rob Lax 05/05/17

VALIDATOR / DATE

Craig Oliver 05/24/17

LINE SUPERVISOR / DATE

Ed Rau 05/24/17

TRAINING SUPERVISION APPROVAL / DATE

LOT-SIM-JP-016-01 Page 1 of 11 Rev. 2

Restarting RCIC after AUTO initiation and Turbine Trip using the Hard Card - Controller Failure

RELATED TASKS:

217 200 B4 01

Restart The RCIC System After Auto Initiation And Turbine Trip Per OP-16.

K/A REFERENCE AND IMPORTANCE RATING:

217000 K4.06 3.5,3.5

A1.01 3.7, 3.7

A1.02 3.3, 3,3

REFERENCES:

OP-16, Section 6.3.7, Restarting the RCIC System After Auto Initiation and Turbine trip

OP-16, Att. 7, Restarting RCIC After Auto Initiation and Turbine Trip (OP-16 Section 8.7),

Hard Card S/928

TOOLS AND EQUIPMENT:

N/A

SAFETY FUNCTION (from NUREG 1123, Rev. 2, Supp. 1):

2 - Inventory Control.

LOT-SIM-JP-016-01 Page 2 of 11 Rev. 2

Restarting RCIC after AUTO initiation and Turbine Trip using the Hard Card - Controller Failure

SETUP INSTRUCTIONS

SIMULATOR SETUP:

A. Initial Conditions:

IC-11

Reactor Power: 100%

Required Plant Conditions

Reactor water level approximately 150 inches following < LL2 (105).

RFPs and HPCI tripped not available.

B. Triggers

K1H12PAU, RCIC Flow Controller Auto Mode, Push, On

C. Malfunctions

Tirgger 1, ES052F, RCIC FIC EPU Failure

C. Overrides

D. Remote Function

None required

E. Special Instructions

1. Manually trip the RCIC Turbine.

2. Place HPCI Aux Oil Pump to LOCKOUT.

3. Scram the Reactor and reduce level by tripping both RFPT's.

4. Complete initial EOP operator actions.

5. After level drops below LL2 (+105"), and is beginning to recover, place

simulator in FREEZE.

6. Place Red Cap on HPCI Aux Oil Pump.

LOT-SIM-JP-016-01 Page 3 of 11 Rev. 2

Restarting RCIC after AUTO initiation and Turbine Trip using the Hard Card - Controller Failure

SAFETY CONSIDERATIONS:

1. None.

EVALUATOR NOTES: (Do not read to performer)

1. The applicable procedure section WILL be provided to the trainee.

2. Prior to the first JPM of the JPM set, provide the JPM briefing contained in NUREG-1021,

Appendix E, or similar briefing (for non-regulated exams) to the trainee(s).

3. This JPM may be performed in the Simulator on Unit 2.

Read the following to the JPM performer.

TASK CONDITIONS:

1. Both Reactor Feed Pumps have tripped and are unavailable.

2. RCIC AUTO started and has been manually tripped.

3. SBGT is running.

4. HPCI is unavailable.

INITIATING CUE:

The Unit CRS has directed you to RESET RCIC and inject water to the Reactor Vessel at

500 gpm to raise level to 170-200 inches, using the Hard Card, and inform the Unit CRS

when the required actions are complete.

LOT-SIM-JP-016-01 Page 4 of 11 Rev. 2

Restarting RCIC after AUTO initiation and Turbine Trip using the Hard Card - Controller Failure

PERFORMANCE CHECKLIST

NOTE: Sequence is assumed unless denoted in the Comments.

TIME START:

Step 1 - Obtain RCIC Hard Card S/928

RCIC Hard Card S/928, RESTARTING RCIC AFTER AUTO INITIATION AND

TURBINE TRIP (2OP-16, Section 8.7) obtained.

SAT/UNSAT

Step 2 - ENSURE THE E51-V8 (VALVE POSITION) AND E51-V8 (MOTOR OPERATOR) ARE

CLOSED.

E51-V8 (Turbine Trip & Throttle Vlv) is placed in the close position for an

additional 5 seconds after closed indication (red light out, green light on).

SAT/UNSAT

Step 3 - PLACE RCIC FLOW CONTROL IN MANUAL (M) AND ADJUST OUTPUT TO 0%.

E51-FIC-R601, RCIC Flow Control placed in MANUAL (depresses M pushbutton

and green manual light illuminates) with 0% output (slide bar moved to the left

until the orange needle lowers to 0% output indication).

SAT/UNSAT

Step 4 - JOG OPEN E51-V8 UNTIL THE TURBINE SPEED IS CONTROLLED BY THE

GOVERNOR

E51-V8 is jogged open (control switch placed in open until green light goes out)

and turbine speed is indicated on E51-C002-2.

- CRITICAL STEP** SAT/UNSAT

Step 5 - FULLY OPEN E51-V8

E51-V8 is full open by placing control switch in the open position until the red

light is on.

- CRITICAL STEP** SAT/UNSAT

LOT-SIM-JP-016-01 Page 5 of 11 Rev. 2

Restarting RCIC after AUTO initiation and Turbine Trip using the Hard Card - Controller Failure

Step 6 - SLOWLY RAISE TURBINE SPEED UNTIL FLOW RATE OF AT LEAST 120 GPM

Turbine speed raised (slide bar moved to the right) to obtain flow rate of at least

120 gpm as indicated on the flow controller.

SAT/UNSAT

Step 7 - ENSURE E51-F019 IS CLOSED WITH FLOW GREATER THAN 80 GPM

E51-F019 verified closed (green light lit, red light off).

SAT/UNSAT

- Begin Alternate Path **

NOTE: When the flow controller is placed in AUTO, the Flow Indicating Controller (FIC)

CPU will fail, as indicated by the red FAIL light on the controller. The capacitor in

the FIC will continually discharge to cause flow to lower, unless the output controller

demand is raised to recharge the capacitor.

Step 8 - WHEN SYSTEM CONDITIONS ARE STABLE, THEN ADJUST SETPOINT, AND

TRANSFER RCIC FLOW CONTROL TO AUTO (A).

Adjusts setpoint using up or down arrows to obtain desired setpoint and then

depresses the A pushbutton and observes the green auto light illuminates.

- CRITICAL STEP** SAT/UNSAT

NOTE: Performer should diagnose failure of RCIC flow controller and raise the controller

output demand as necessary to recharge the FIC capacitor and raise flow.

Step 9 - Diagnose failure of RCIC flow controller, E51-R601, and raise controller output to

inject at the desired flow rate.

Identifies red fail light illuminated and controller does not function in auto.

Raise controller output (slide bar moved to the right) to inject at a flow rate of up

to 500 gpm, to raise Reactor water level toward 170 - 200 inches.

- CRITICAL STEP** SAT/UNSAT

LOT-SIM-JP-016-01 Page 6 of 11 Rev. 2

Restarting RCIC after AUTO initiation and Turbine Trip using the Hard Card - Controller Failure

Step 10 - ENSURE THE FOLLOWING:

BAROMETRIC CNDSR VACUUM PUMP HAS STARTED

SBGT STARTED (2OP-10) - part of initial conditions

SGT-V8 AND SGT-V9 ARE OPEN

Conditions verified or verbalized as part of initial conditions.

SAT/UNSAT

TERMINATING CUE: When RCIC has been reset and manually started and is injecting to the

RPV at approximately 500 gpm, this JPM is complete.

TIME COMPLETED:

NOTE: Comments required for any step evaluated as UNSAT.

COLLECT AND CONTROL ALL JPM EXAM MATERIALS FOR EXAM SECURITY.

Step Critical / Not Critical Reason

1 Not Critical Administrative

2 Not Critical Verification

3 Not Critical Not necessary to inject

4 Critical Necessary to inject

5 Critical Necessary to inject

6 Not Critical Not necessary to inject

7 Not Critical Verification

8 Critical Necessary to inject

9 Critical Necessary to inject

10 Not Critical Verification

LOT-SIM-JP-016-01 Page 7 of 11 Rev. 2

Restarting RCIC after AUTO initiation and Turbine Trip using the Hard Card - Controller Failure

WORK PRACTICES:

Comments are required for any step evaluated as UNSAT

A. CORE 4 SAT/ UNSAT/ NE

1. Task Preview / Pre-Job Briefs

2. Take-A-Minute / Two Minute Rule

3. Correct Component Verification (CCV), Validate

Assumptions

4. Procedure and Work Instruction Use and Adherence

(PU&A)

B. Communications (proper content, repeat backs, 3 step SAT/ UNSAT/ NE

communications, etc.)

C. STAR (Use of Stop, Think, Act, Review) SAT/ UNSAT/ NE

D. Peer Checking (if performer requests or discusses peer checking) SAT/ UNSAT/ NE

E. Proper Equipment Use (observe starting limitations, throttle valve SAT/ UNSAT/ NE

closures, etc.)

F. Safety Compliance (use of PPE, knowledge of safety equipment, SAT/ UNSAT/ NE

etc.)

G. Electrical Safety And Arc Flash Protection Compliance (refer to SAT/ UNSAT/ NE

SAF-NGGC-2175, as applicable)

H. Security Compliance (controlled area entry and exit, key control, SAT/ UNSAT/ NE

etc.)

I. Proper Tool Use (proper tool for the job, calibration dates, etc.) SAT/ UNSAT/ NE

J. Radiation Protection (ALARA, understanding and use of RWP, SAT/ UNSAT/ NE

frisking, etc.)

LOT-SIM-JP-016-01 Page 8 of 11 Rev. 2

Restarting RCIC after AUTO initiation and Turbine Trip using the Hard Card - Controller Failure

REVISION SUMMARY

2 Revised to new JPM Template

Changed to correct procedure section

Changed to match hard card verbiage

Changed SCO to CRS

Added Critical Step table

Corrected step numeration

1 Revised to new JPM Template, Revision 3.

Changed RCIC Flow Controller failure to HPU failure.

Updated to current Hard Card.

LOT-SIM-JP-016-01 Page 9 of 11 Rev. 2

Restarting RCIC after AUTO initiation and Turbine Trip using the Hard Card - Controller Failure

Validation Time: 10 Minutes (approximate).

Time Taken: ____ Minutes

APPLICABLE METHOD OF TESTING

Performance: Simulate Actual X Unit: 2

Setting: In-Plant Simulator X Admin

Time Critical: Yes No X Time Limit N/A

Alternate Path: Yes X No

EVALUATION

Performer:

JPM: Pass Fail

Remedial Training Required: Yes No

Comments:

Comments reviewed with Performer

Evaluator Signature: Date:

LOT-SIM-JP-016-01 Page 10 of 11 Rev. 2

TASK CONDITIONS:

1. Both Reactor Feed Pumps have tripped and are unavailable.

2. RCIC AUTO started and has been manually tripped.

3. SBGT is running.

4. HPCI is unavailable.

INITIATING CUE:

The Unit CRS has directed you to RESET RCIC and inject water to the Reactor Vessel at

500 gpm to raise level to 170-200 inches, using the Hard Card, and inform the Unit CRS

when the required actions are complete.

Page 11 of 11

DUKE ENERGY

BRUNSWICK TRAINING SECTION

LESSON TITLE: TURBINE OVERSPEED TRIP TEST

(JPM F RO / ISRO / USRO)

LESSON NUMBER: LOT-SIM-JP-26.0-02

REVISION NO: 0

Phil Capehart 03/13/17

PREPARER / DATE

Daniel Hulgin 03/13/17

TECHNICAL REVIEWER / DATE

Trey Bunnel 05/05/17

Rob Lax 05/05/17

VALIDATOR / DATE

Craig Oliver 05/24/17

LINE SUPERVISOR / DATE

Ed Rau 05/24/17

TRAINING SUPERVISION APPROVAL / DATE

LOT-SIM-JP-26.0-02 Page 1 of 10 Rev.0

RELATED TASKS:

245012B101 Shutdown The Main Turbine Per OP-26

K/A REFERENCE AND IMPORTANCE RATING:

241000 REACTOR/TURBINE PRESSURE REGULATING SYSTEM

K1.20 Knowledge of the physical connection and/or cause-effect relationships between

REACTOR/TURBINE PRESSURE REGULATING SYSTEM and the following:

Turbine Trip

RO 3.4 / SRO 3.5

REFERENCES:

0PT-40.2.6

TOOLS AND EQUIPMENT:

None

SAFETY FUNCTION (from NUREG 1123, Rev. 2, Supp. 1):

3 - Reactor Pressure Control

SETUP INSTRUCTIONS

IC 11

LOT-SIM-JP-26.0-02 Page 2 of 10 Rev.0

SAFETY CONSIDERATIONS:

1. None.

EVALUATOR NOTES: (Do not read to performer)

1. The applicable procedure section WILL be provided to the trainee.

2. Prior to the first JPM of the JPM set, provide the JPM briefing contained in NUREG-1021,

Appendix E, or similar briefing (for non-regulated exams) to the trainee(s).

3. This JPM is tp be performed on the Unit 2 Simulator.

Read the following to the JPM performer.

TASK CONDITIONS:

1. The Turbine is on line operating at ~ 100 MWe

2. 0PT-40.2.6, Turbine Overspeed Trip Test is currently in progress

3. All prerequisites have been verified by another operator

4. Section 6.0, Steps 1 through 8 have already been accomplished by another operator

5. The Load Dispatcher has been notified of impending grid separation

INITIATING CUE:

You are directed by the Unit CRS to perform 0PT-40.2.6, Turbine Overspeed Trip Test,

starting at Section 6.0, Step 9

LOT-SIM-JP-26.0-02 Page 3 of 10 Rev.0

PERFORMANCE CHECKLIST

NOTE: Sequence is assumed unless otherwise indicated, comments required for any step evaluated as UNSAT.

Step 1 - Obtain a current revision pre-marked version of 0PT-40.2.6, Turbine Overspeed Trip

Test.

Current Revision of 0PT-40.2.6 obtained and verified if applicable.

SAT/UNSAT

TIME START: ___________

NOTE:

MVD-DV3 (Mn Stm Lead After CV-3 Drn) operates with the limit switch position of

the CV-1/CV-2 drain valves and the position can be confirmed with the indicating

light on Panel XU-3.

CAUTION:

Operation at less than 33% turbine load and less than 25" Hg vacuum (greater than

5" Hga backpressure) can cause damage to the last stage buckets and should be

avoided.

Step 2 - Open the following drain valves located on Panel XU-3:

VALVE SAT UNSAT

MS-V46/47/48/49 (Mn Stm Ln Before SV Drns)

MVD-CV (Main SV & CV Above Seat Drn)

MVD-CV2 (Mn Stm Lead After CV-1 Drn)

MVD-CV4 (Mn Stm Lead After CV-2 Drn)

Places Valve switches in the open position. Green light extinguishes and red light

illuminates. (MVD-CV, CV2, and CV4 are throttle valves) (When MVD-CV2 and

CV4 are opened the MVD-DV3 will auto open, green light extinguishes and red

light illuminates

- CRITICAL STEP** SAT/UNSAT

Step 3 - Start the Motor Suction Pump.

Starts Motor Suction Pump by depressing Motor Suction Pump start pushbutton.

- CRITICAL STEP** SAT/UNSAT

LOT-SIM-JP-26.0-02 Page 4 of 10 Rev.0

Step 4 - Start the Turning Gear Oil Pump.

Starts Turning Gear Oil Pump by depressing Turning Gear Oil Pump start

pushbutton.

- CRITICAL STEP** SAT/UNSAT

CAUTION:

If the bypass valve does NOT open, tripping the main turbine may result in a main

turbine trip without bypass valves with resultant high reactor pressure and APRM

upscale alarms or trips.

Step 5 - Test operation of OG-PS-110 and OG-PS-111 (Low Condenser Vacuum Switches)

pressure set control and bypass valves, by performing the following:

a) Depress Bypass Valve Opening Jack Increase push button to throttle open a

bypass valve to 12% to 18%.

Bypass Valve Opening Jack Increase push button depressed to throttle open a

bypass valve to 12% to 18%.

SAT/UNSAT

Step 6 - Test operation of OG-PS-110 and OG-PS-111 (Low Condenser Vacuum Switches)

pressure set control and bypass valves, by performing the following:

b) Depress Bypass Valve Opening Jack Decrease push button to fully close the

bypass valve.

Bypass Valve Opening Jack Decrease push button depressed to fully close the

bypass valve.

SAT/UNSAT

Step 7 - Notify Load Dispatcher of impending grid separation.

Provided as an initial condition.

SAT/UNSAT

LOT-SIM-JP-26.0-02 Page 5 of 10 Rev.0

Step 8 - Depress Emergency Trip System Trip push button.

Emergency Trip System Trip push button depressed.

- CRITICAL STEP** SAT/UNSAT

Step 9 - Confirm the following:

All four main stop valves go full CLOSED SAT UNSAT

All four control valves go full CLOSED

All four intercept valves go CLOSED

All four intermediate stop valves go CLOSED

Bypass valves throttle open to maintain reactor pressure

constant at 928 psig

All components operate as described above

SAT/UNSAT

- Begin Alternate Path **

EVALUATOR NOTE: 230 KV PCB 29B fails to open in the following step.

EVALUATOR NOTE: If applicant reports unexpected PCB indications, examiner should ask

their recommended action, and concur with that action.

Step 10 - WHEN generator MWe decreases to zero, THEN ensure both generator output

breakers, Generator 2 to Bus 2A 230 KV PCB 29A and Generator 2 to Bus 2B 230

KV PCB 29B, are OPEN.

PCB 29A verified to open, red light off, green light on, UA-13 (1-7) in alarm

PCB 29B is opened by taking control switch to the trip position and observing

green light on, red light off, UA-13 (1-8) in alarm.

- CRITICAL STEP** SAT/UNSAT

TERMINATING CUE: When 230 KV PCB 29A and 29B are open this JPM is complete.

Another operator will continue the task from here.

TIME COMPLETED: _____________

COLLECT AND CONTROL ALL JPM EXAM MATERIALS FOR EXAM SECURITY.

LOT-SIM-JP-26.0-02 Page 6 of 10 Rev.0

Step Critical / Not Critical Reason

1 Not Critical Administrative

2 Critical Necessary for PT completion

3 Critical Necessary for PT completion

4 Critical Necessary for PT completion

5 Not Critical Not necessary for PT completion

6 Not Critical Not necessary for PT completion

7 Not Critical Communication

8 Critical Necessary for PT completion

9 Not Critical Verification

10 Critical Necessary for failed auto action

REVISION SUMMARY

0 New JPM Initial Revision

(Provide sufficient detail for reviewers and evaluators to understand the scope of any

technical and/or administrative changes).

LOT-SIM-JP-26.0-02 Page 7 of 10 Rev.0

WORK PRACTICES:

Comments are required for any step evaluated as UNSAT

A. CORE 4 SAT/ UNSAT/ NE

1. Task Preview / Pre-Job Briefs

2. Take-A-Minute

3. Correct Component Verification (CCV), Validate

Assumptions

4. Procedure and Work Instruction Use and Adherence

(PU&A)

B. Communications (proper content, repeat backs, 3 step SAT/ UNSAT/ NE

communications, etc.)

C. STAR (Use of Stop, Think, Act, Review) SAT/ UNSAT/ NE

D. Peer Checking (if performer requests or discusses peer checking) SAT/ UNSAT/ NE

E. Proper Equipment Use (observe starting limitations, throttle valve SAT/ UNSAT/ NE

closures, etc.)

F. Safety Compliance (use of PPE, knowledge of safety equipment, SAT/ UNSAT/ NE

etc.)

G. Electrical Safety And Arc Flash Protection Compliance (refer to SAT/ UNSAT/ NE

AD-HS-ALL-0110, as applicable)

H. Security Compliance (controlled area entry and exit, key control, SAT/ UNSAT/ NE

etc.)

I. Proper Tool Use (proper tool for the job, calibration dates, etc.) SAT/ UNSAT/ NE

J. Radiation Protection (ALARA, understanding and use of RWP, SAT/ UNSAT/ NE

frisking, etc.)

Comments:

LOT-SIM-JP-26.0-02 Page 8 of 10 Rev.0

Validation Time: 10 Minutes (approximate).

Time Taken: ____ Minutes

APPLICABLE METHOD OF TESTING

Performance: Simulate Actual X Unit: 2

Setting: In-Plant Simulator X Admin

Time Critical: Yes No X Time Limit N/A

Alternate Path: Yes X No

EVALUATION

Performer:

JPM: Pass Fail

Remedial Training Required: Yes No

Comments:

Comments reviewed with Performer

Evaluator Signature: Date:

LOT-SIM-JP-26.0-02 Page 9 of 10 Rev.0

TASK CONDITIONS:

1. The Turbine is on line operating at ~ 100 MWe

2. 0PT-40.2.6, Turbine Overspeed Trip Test is currently in progress

3. All prerequisites have been verified by another operator

4. Section 6.0, Steps 1 through 8 have already been accomplished by another operator

5. The Load Dispatcher has been notified of impending grid separation

INITIATING CUE:

You are directed by the Unit CRS to perform 0PT-40.2.6, Turbine Overspeed Trip Test,

starting at Section 6.0, Step 9

Page 10 of 10

DUKE ENERGY

BRUNSWICK TRAINING SECTION

LESSON TITLE: Rod Worth Minimizer Functional Test - Failure To Enforce Blocks

(JPM G RO / ISRO / USRO)

LESSON NUMBER: LOT-SIM-JP-07.1-03

REVISION NO: 3

Phil Capehart 03/13/17

PREPARER / DATE

Daniel Hulgin 03/13/17

TECHNICAL REVIEWER / DATE

Trey Bunnel 05/05/17

Rob Lax 05/05/17

VALIDATOR / DATE

Craig Oliver 05/24/17

LINE SUPERVISOR / DATE

Ed Rau 05/24/17

TRAINING SUPERVISION APPROVAL / DATE

LOT-SIM-JP-07.1-03 Page 1 of 11 Rev.3

Rod Worth Minimizer Functional Test - Failure To Enforce Blocks

RELATED TASKS:

201001B201, Conduct Rod Worth Minimizer Operability Test Per PT-01.6.2

K/A REFERENCE AND IMPORTANCE RATING:

201006 A3.04 3.5/3.4

Ability to monitor automatic operations of the Rod Worth Minimizer System (RWM)

including control rod movement blocks

REFERENCES:

0PT-01.6.2

0GP-01

0GP-10, Sequence A2

TOOLS AND EQUIPMENT:

None

SAFETY FUNCTION (from NUREG 1123, Rev. 2, Supp. 1):

7 - Instrumentation

SETUP INSTRUCTIONS

Startup Simulator in IC-02

Clear scram buffer at RWM computer display (back panel - place keylock switch to Inop,

press Etc. until scram data option appears, press scram data, then delete data)

Ensure RWM Computer Display and Operator Display in Operate (Operate Mode

displayed in RWM OD Header)

Assign RD042F, Insert Withdraw Rod Block Failure to TRG 1

Assign TRG1 to initiate when RWM is taken to the TEST position with a 2 second time

delay.

LOT-SIM-JP-07.1-03 Page 2 of 11 Rev.3

Rod Worth Minimizer Functional Test - Failure To Enforce Blocks

SAFETY CONSIDERATIONS:

1. None.

EVALUATOR NOTES: (Do not read to performer)

1. The applicable procedure section WILL be provided to the trainee.

2. Prior to the first JPM of the JPM set, provide the JPM briefing contained in NUREG-1021,

Appendix E, or similar briefing (for non-regulated exams) to the trainee(s).

3. Provide examinee with copy of 0PT-01.6.2 complete up to Section 6.3, RWM Functional Test.

Ensure a copy of GP-10, sequence A2 and GP-01 is available.

4. Critical Step Basis

a) Prevents Task Completion

b) May Result in Equipment Damage

c) Affects Public Health and Safety

d) Could Result in Personal Injury

Read the following to the JPM performer.

TASK CONDITIONS:

1. Unit Two startup is planned following a forced outage

2. GP-01, Prestartup Checklist is being performed and is complete up to the step to perform

0PT-01.6.2, Rod Worth Minimizer System Operability Test.

3. 0PT-01.6.2, Rod Worth Minimizer Operability Test has been completed to Section 7.3,

RWM Functional Test

4. GP-10, sequence A2 has been selected in RWM for startup

INITIATING CUE:

You are directed by the Unit CRS to perform the RWM Functional Test per 0PT-01.6.2,

Section 7.3, RWM Functional Test.

Inform the Unit CRS when the RWM Functional Test is complete.

LOT-SIM-JP-07.1-03 Page 3 of 11 Rev.3

Rod Worth Minimizer Functional Test - Failure To Enforce Blocks

PERFORMANCE CHECKLIST

NOTE: Sequence is assumed unless otherwise indicated, comments required for any step evaluated as UNSAT.

TIME START: ___________

Step 1 - Confirm the Reactor Mode Switch in START-HOT STBY.

Verifies that the Reactor Mode Switch handle is in-line with the START-& HOT

S/B position.

SAT/UNSAT

Step 2 - Ensure rod select power ON and confirm RWM Operator Display indicates INSERT

and WITHDRAW blocks.

Verifies Rod select power switch is in the On position and INSERT and

WITHDRAW blocks are indicated on RWM Operator display.

- CRITICAL STEP ** SAT/UNSAT*

Step 3 - Select a Step 01 rod per Rod Sequence Checkoff Sheet and withdraw the rod to

Position 04.

Obtains 0GP-10 Attachment 2A for Rod Sequence A2 and depresses one of the

Step 01 rods on the Rod Select Matrix.

Withdraws the rod by placing the Rod Movement Control Switch to the Notch Out

position and confirms rod moves to position 02. Repeats after the rod has settled

to notch out rod to position 04.

- CRITICAL STEP ** SAT/UNSAT*

STEP 1 ROD selected #___________

Step 4 - Confirm the following indications:

No INSERT or WITHDRAW blocks are indicated on RWM.

WITHDRAW PERMISSIVE light is on.

The selected rod is indicated at Position 04 on the RWM Operator Display

Confirms no Insert or Withdraw blocks are indicated on RWM.

Confirms Withdraw permissive light is on

Confirms selected rod is indicated at Position 04 on the RWM Operator

Display

SAT/UNSAT*

LOT-SIM-JP-07.1-03 Page 4 of 11 Rev.3

Rod Worth Minimizer Functional Test - Failure To Enforce Blocks

Step 5 - Select a rod from any Rod Sequence Checkoff Sheet step other than Step 01.

A rod (other than a GP-10 Step 01 rod) is selected by depressing the appropriate

rod on the rod select matrix.

- CRITICAL STEP ** SAT/UNSAT*

ROD Selected #___________

Step 6 - Confirm a Select Error (SE) and a Withdraw Block (WB) are indicated on the RWM

Operator Display.

Confirms Select Error (SE) and Withdraw Block (WB) are indicated on the RWM

Operator Display for the selected rod.

SAT/UNSAT*

Step 7 - Select the Step 01 rod at Position 04.

The Step 01 rod at Position 04 is selected by depressing the appropriate rod on

the rod select matrix. Confirms RWM indicates the selected rod and four rod

display shows the rod at position 04.

- CRITICAL STEP ** SAT/UNSAT*

STEP 1 ROD Selected #___________

Step 8 -Insert selected rod to position 00.

The Step 01 rod at Position 04 is inserted to position 00 by placing the Rod

Movement Control Switch to the In position and confirms rod moves to position

00 and then releases the Rod Movement Control Switch.

- CRITICAL STEP ** SAT/UNSAT*

NOTE: Verify Trigger 1 initiates when RWM is taken to TEST.

Step 9 - On RTGB Panel H12-P603, place the RWM Operator Display keylock switch in

TEST.

Obtains key #38 from the key locker and rotates clockwise the RWM Operator

Display keylock switch on RTGB Panel H12-P603 to the Test position.

- CRITICAL STEP ** SAT/UNSAT*

LOT-SIM-JP-07.1-03 Page 5 of 11 Rev.3

Rod Worth Minimizer Functional Test - Failure To Enforce Blocks

Step 10 - Press the Etc softkey on the Operator Display until the Rod Test selection appears.

Etc key is depressed until Rod Test selection appears.

SAT/UNSAT*

Step 11 - Press the Rod Test softkey on the Operator Display.

Rod Test softkey on the Operator Display is pressed.

- CRITICAL STEP ** SAT/UNSAT*

Step 12 - Select a Step 13 rod per Rod Sequence Checkoff Sheet.

A Step 13 rod per GP-10 is selected by depressing the appropriate rod on the

rod select matrix.

- CRITICAL STEP ** SAT/UNSAT*

STEP 13 ROD Selected #___________

Step 13 -Withdraw selected rod to Position 04.

Withdraws the selected rod by placing the Rod Movement Control Switch to the

Notch Out position and confirms rod moves to position 02. Repeats after the rod

has settled to notch out rod to position 04.

- CRITICAL STEP ** SAT/UNSAT*

Step 14 - On RTGB Panel H12-P603, place the RWM Operator Display keylock switch in

OPERATE.

RWM Operator Display keylock switch is rotated counter-clockwise to the

Operate position.

- CRITICAL STEP ** SAT/UNSAT*

- Begin Alternate Path **

NOTE: The withdraw permissive light will be lit even though RWM displays a Withdraw Block.

The examinee may determine RWM is not operating properly at this point.

PROMPT: If informed as CRS that RWM is not functioning at this point, direct examinee to

continue actions of the PT until a step in the PT is unsatisfactory

LOT-SIM-JP-07.1-03 Page 6 of 11 Rev.3

Rod Worth Minimizer Functional Test - Failure To Enforce Blocks

Step 15 - Confirm the following:

Withdraw block (WB) is indicated on the Operator Display.

Withdraw error (WE) is indicated on the Operator Display identifying the Step 13

rod at Position 04.

Latched step is Step 01.

OPERATE mode is indicated on the Operator Display.

Confirms withdraw block (WB) is indicated on the Operator Display.

Confirms withdraw error is indicated on the Operator Display identifying the

Step 13 rod at Position 04.

Confirms latched step is Step 01.

Confirms Operate mode is indicated on the Operator Display.

SAT/UNSAT*

NOTE: The withdraw permissive light will be lit after the rod in the next step is selected. RWM

display shows withdraw block and select error, but allows the rod to be withdrawn due

to the malfunction in the setup.

Step 16 - Select any other control rod.

A different control rod is selected by depressing the appropriate rod on the rod

select matrix.

- CRITICAL STEP ** SAT/UNSAT*

ROD Selected #___________

NOTE: The operator may determine the rod can be withdrawn by observing withdraw

permissive light being lit without actually attempting to withdraw the rod.

NOTE: The critical step in Step 17 is determining the selected rod can be withdrawn which

makes the PT Unsat.

PROMPT: When informed test is unsatisfactory, as Unit CRS direct examinee to ensure all

control rods are fully inserted.

LOT-SIM-JP-07.1-03 Page 7 of 11 Rev.3

Rod Worth Minimizer Functional Test - Failure To Enforce Blocks

Step 17 - Confirm the following

A-05 5-2, Rod Block RWM/RMCS Sys Trouble ALARMS.

Select Error (SE) is indicated on the Operator Display.

The selected control rod can NOT be withdrawn

Confirmed Rod Block RWM/RMCS Sys Trouble (A-05 5-2) alarms.

Confirmed select error (SE) is indicated on the Operator Display.

Determines the selected rod can be withdrawn and that the test is

unsatisfactory (**CRITICAL STEP)

- CRITICAL STEP ** SAT/UNSAT*

Step 18 - Inform Unit CRS that test is found to be unsatisfactory.

Unit CRS informed that test is found to be unsatisfactory.

SAT/UNSAT*

Step 19 - Insert control rod withdrawn (from Step 17 of this JPM).

Control rod is inserted using the Rod Movement Control switch by placing it in

the IN position until the control rod is at Position 00.

- CRITICAL STEP ** SAT/UNSAT*

ROD from Step 17 Selected #___________

Step 20 - Select the Step 13 rod at Position 04 and insert it to Position 00.

Control rod is inserted using the Rod Movement Control switch by placing it in

the IN position until the control rod is at Position 00.

- CRITICAL STEP ** SAT/UNSAT*

STEP 13 ROD Selected #___________

PROMPT: When all rods are inserted, inform examinee that maintenance has been contacted

for RWM repairs and the JPM is complete.

TERMINATING CUE: When the RWM functional test is determined to be unsatisfactory, and

all rods are fully inserted, this JPM is complete

TIME COMPLETED: _____________

COLLECT AND CONTROL ALL JPM EXAM MATERIALS FOR EXAM SECURITY.

LOT-SIM-JP-07.1-03 Page 8 of 11 Rev.3

Rod Worth Minimizer Functional Test - Failure To Enforce Blocks

Step Critical / Not Critical Reason

1 Not Critical Verifying condition exists

2 Critical Must turn on rod select power to be able to do the PT.

3 Critical Must select a rod to perform the PT.

4 Not Critical Verifying indications.

5 Critical Must select a rod to verify withdraw block.

6 Not Critical Verifying indications.

7 Critical Must select the rod to insert it

8 Critical The rod must be inserted for the PT

9 Critical RWM must be placed in test for the PT

10 Not Critical The next step is critical but not how they get there.

11 Critical Rod Test must be selected to perform the PT

12 Critical Must select a rod to perform the PT.

13 Critical The rod must be withdrawn to perform the PT

14 Critical RWM must be placed in operate to perform PT

15 Not Critical Verifying indications

16 Critical A rod has to be selected for the PT

17 Critical Determines that the PT is UNSAT due to being able to

move a control rod

18 Not Critical Information step

19 Critical Inserting the control rods to prevent reactivity concerns.

20 Critical Inserting the control rods to prevent reactivity concerns.

REVISION SUMMARY

3 Updated to current JPM template.

Updated to current revision of PT.

2 Modified to perform actions of PT-01.6.2 only (GP-01 no longer directs

placing mode switch to shutdown if PT is unsatisfactory).

1 Updated to current revision of 0GP-01.

LOT-SIM-JP-07.1-03 Page 9 of 11 Rev.3

Rod Worth Minimizer Functional Test - Failure To Enforce Blocks

Validation Time: 15 Minutes (approximate).

Time Taken: ____ Minutes

APPLICABLE METHOD OF TESTING

Performance: Simulate Actual X Unit: 2

Setting: In-Plant Simulator X Admin

Time Critical: Yes No X Time Limit N/A

Alternate Path: Yes X No

EVALUATION

Performer:

JPM: Pass Fail

Remedial Training Required: Yes No

Comments:

Evaluator Signature: Date:

LOT-SIM-JP-07.1-03 Page 10 of 11 Rev.3

TASK CONDITIONS:

1. Unit Two startup is planned following a forced outage

2. GP-01, Prestartup Checklist is being performed and is complete up to the step to perform

0PT-01.6.2, Rod Worth Minimizer System Operability Test.

3. 0PT-01.6.2, Rod Worth Minimizer Operability Test has been completed to Section 7.3,

RWM Functional Test

4. GP-10, sequence A2 has been selected in RWM for startup

INITIATING CUE:

You are directed by the Unit CRS to perform the RWM Functional Test per 0PT-01.6.2,

Section 7.3, RWM Functional Test.

Inform the Unit CRS when the RWM Functional Test is complete.

Page 11 of 11

DUKE ENERGY

BRUNSWICK TRAINING SECTION

LESSON TITLE: SBGT System Operations to Reduce Humidity

(JPM H RO Only)

LESSON NUMBER: LOT-SIM-JP-010-01

REVISION NO: 1

Phil Capehart 03/13/17

PREPARER / DATE

Daniel Hulgin 03/13/17

TECHNICAL REVIEWER / DATE

Trey Bunnel 05/05/17

Rob Lax 05/05/17

VALIDATOR / DATE

Craig Oliver 05/24/17

LINE SUPERVISOR / DATE

Ed Rau 05/24/17

TRAINING SUPERVISION APPROVAL / DATE

LOT-SIM-JP-010-01 Page 1 of 9 Rev. 1

RELATED TASKS:

261003B101, Perform A Control Room Manual Startup Of SBGT Per OP-10

261006B101, Secure The SBGT System Per OP-10

K/A REFERENCE AND IMPORTANCE RATING:

288000 A4.01 3.1/2.9

Ability to manually operate and or monitor in the control room: Start and stop fans

REFERENCES:

2OP-10

TOOLS AND EQUIPMENT:

None

SAFETY FUNCTION (from NUREG 1123, Rev. 2, Supp. 1):

9 - Radioactivity Release (Plant Ventilation Systems)

SETUP INSTRUCTIONS

IC Any IC

Rx. Pwr. Any

Core Age Any

LOT-SIM-JP-010-01 Page 2 of 9 Rev. 1

SAFETY CONSIDERATIONS:

1. None.

EVALUATOR NOTES: (Do not read to performer)

1. The applicable procedure section WILL be provided to the trainee.

2. Prior to the first JPM of the JPM set, provide the JPM briefing contained in NUREG-1021,

Appendix E, or similar briefing (for non-regulated exams) to the trainee(s).

3. Critical Step Basis

a) Prevents Task Completion

b) May Result in Equipment Damage

c) Affects Public Health and Safety

d) Could Result in Personal Injury

Read the following to the JPM performer.

TASK CONDITIONS:

1. The AO has reported 2A SBGT relative humidity at 72%.

2. SBGT System is in standby IAW 2OP-10, Section 6.1.1.

3. No painting has been done in the last 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months in the reactor building 80 west, 50 west or

20 south elevations.

4. No welding has been done in the reactor building in the last hour.

5. No ISFSI activities in the reactor building are in progress.

INITIATING CUE:

You are directed by the Unit CRS to perform 2OP-10, Section 6.3.1, SBGT System Operation

to Reduce Humidity, to reduce SBGT A relative humidity to <70%.

Inform the Unit CRS when relative humidity has been reduced to <70% and the SBGT System

has been secured and placed in standby alignment.

LOT-SIM-JP-010-01 Page 3 of 9 Rev. 1

PERFORMANCE CHECKLIST

NOTE: Sequence is assumed unless otherwise indicated, comments required for any step evaluated as UNSAT.

Step 1 - Perform take a minute at job site prior to beginning task.

Examinee should cover the following questions, as deemed necessary.

What are the hazards in the area? What PPE is required? Tools/PPE inspected

prior to use? Energy sources secured/isolated? Is Clearance/Tag Out

sufficient? What's the worst that can happen? Any ALARA concerns? Will I

affect plant status? HU Tools needed?

SAT/UNSAT

TIME START: ___________

Step 2 - Place SBGT A control switch to ON.

SBGT A control switch rotated clockwise two positions to the ON position.

- CRITICAL STEP** SAT/UNSAT

Step 2a - Observes SBGT A Red Fan On light is ON.

Observes SBGT A Red Fan On light illuminated.

SAT/UNSAT

Step 2b - Observes SBGT A Red Htr On light is ON.

Observes SBGT A Red Htr On light illuminated.

SAT/UNSAT

Step 2c - Observes SBGT A Red Pref light is OFF.

Observes SBGT A Red Pref light extinguished.

SAT/UNSAT

Step 2d - Observes on Panel XU-51, SBGT System flow raises to greater than or equal to

3000 scfm as indicated by VA-FI-3150-1 (SBGT A Flow).

Observes SBGT A VA-FI-3150-1 (SBGT A Flow) indicating needle rises to >3000

scfm.

SAT/UNSAT

LOT-SIM-JP-010-01 Page 4 of 9 Rev. 1

PROMPT: If requested, as the AO report that ALL 2OP-10, Attachment 1 local indications for

SBGT A are normal.

Step 3 - Monitor SBGT System operation in accordance with Attachment 1.

Verifies the following parameters on XU-51 panel:

SBGT A Flow, VA-FI-3150-1, indicates >3000 scfm.

SBGT A inlet temperature, VA-TI-3022, is ambient temperature.

SBGT A outlet temperature, VA-TI-3023, is <125°F.

Request an AO to monitor the rest of the parameters locally.

SAT/UNSAT

PROMPT: After 2A SBGT System has been verified to be operating properly inform examinee

that relative humidity is 65%.

Step 4 - IF relative humidity does NOT lower to less than 70% within 20 minutes, THEN

declare the system INOPERABLE.

Marks the step as N/A.

SAT/UNSAT*

Step 5a - Place 2A SBGT control switch to PREF and ensure the associated red PREF lamp

is ON.

Rotates 2A SBGT control switch counter-clockwise two positions to the PREF

position and observes the PREF red lamp illuminates.

- CRITICAL STEP ** SAT/UNSAT*

Step 5b - Depress 2A SBGT PUSH OFF push button and ensure the associated green PUSH

OFF indicating lamp is on.

2A SBGT PUSH OFF push button is depressed (a click is heard) and the PUSH

OFF light illuminates.

- CRITICAL STEP ** SAT/UNSAT*

LOT-SIM-JP-010-01 Page 5 of 9 Rev. 1

Step 5c - Momentarily place 2A SBGT control switch in RESET and release, allowing it to

return to PREF.

Rotates 2A SBGT control switch counter-clockwise one position to reset, switch

is released and it spring returns to the PREF position.

- CRITICAL STEP ** SAT/UNSAT*

Step 5d - Ensure the following:

SBGT A control switch in PREF

Green PUSH OFF light is ON

Red PREF light is ON

Control switch is verified in PREF, Green PUSH OFF is verified illuminated, and

red PREF light is verified illuminated.

SAT/UNSAT*

Step 6 - Notifies the CRS that SBGT A is in standby alignment and relative humidity is 65%.

CRS acknowledges the report.

SAT/UNSAT*

TERMINATING CUE: When SBGT A is <70% humidity and the system is in its standby

alignment, this JPM is complete.

TIME COMPLETED: _____________

COLLECT AND CONTROL ALL JPM EXAM MATERIALS FOR EXAM SECURITY.

LOT-SIM-JP-010-01 Page 6 of 9 Rev. 1

Step Critical / Not Critical Reason

1 Not Critical Administrative

2 Critical This step starts the SBGT Fan.

2a-d Not Critical Monitoring that the appropriate indications occur.

3 Not Critical Monitoring that the appropriate indications occur.

4 Not Critical Step is Not Applicable.

5a Critical This step shuts down the SBGT Fan

5b Critical This is placing the system back in a standby alignment.

5c Critical This is placing the system back in a standby alignment.

5d Not Critical Monitoring that the appropriate indications occur.

REVISION SUMMARY

1 Revised to current JPM template format.

Added Critical step Basis.

LOT-SIM-JP-010-01 Page 7 of 9 Rev. 1

Validation Time: 10 Minutes (approximate).

Time Taken: ____ Minutes

APPLICABLE METHOD OF TESTING

Performance: Simulate Actual X Unit: 2

Setting: In-Plant Simulator X Admin

Time Critical: Yes No X Time Limit N/A

Alternate Path: Yes No X

EVALUATION

Performer:

JPM: Pass Fail

Remedial Training Required: Yes No

Comments:

Evaluator Signature: Date:

LOT-SIM-JP-010-01 Page 8 of 9 Rev. 1

TASK CONDITIONS:

1. The AO has reported 2A SBGT relative humidity at 72%.

2. SBGT System is in standby IAW 2OP-10, Section 6.1.1.

3. No painting has been done in the last 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months in the reactor building 80 west, 50 west or

20 south elevations.

4. No welding has been done in the reactor building in the last hour.

5. No ISFSI activities in the reactor building are in progress.

INITIATING CUE:

You are directed by the Unit CRS to perform 2OP-10, Section 6.3.1, SBGT System Operation

to Reduce Humidity, to reduce SBGT A relative humidity to <70%.

Inform the Unit CRS when relative humidity has been reduced to <70% and the SBGT System

has been secured and placed in standby alignment.

Page 9 of 9

DUKE ENERGY

BRUNSWICK TRAINING SECTION

LESSON TITLE: Transfer of Recirc VFD-CONT-UPS-A(B) from Inverter Operation to

Maintenance Bypass

(JPM I RO / ISRO / USRO)

LESSON NUMBER: AOT-OJT-JP-VFD-06

REVISION NO: 0

Phil Capehart 03/13/17

PREPARER / DATE

Daniel Hulgin 03/13/17

TECHNICAL REVIEWER / DATE

Hunter Morris 05/09/17

Andrew Stoltz 05/09/17

VALIDATOR / DATE

Craig Oliver 05/24/17

LINE SUPERVISOR / DATE

Ed Rau 05/24/17

TRAINING SUPERVISION APPROVAL / DATE

AOT-OJT-JP-VFD-06 Page 1 of 10 Rev.0

RELATED TASKS:

202017B104 Transfer the Reactor Recirc VFD UPS from Inverter Operations to

Maintenance Bypass Switch per 1(2)OP-02

K/A REFERENCE AND IMPORTANCE RATING:

226001 A.C. Electrical Distribution

K3 Knowledge of the effect that a loss or malfunction of the A.C. ELECTRICAL

DISTRIBUTION will have on the following: (CFR: 41.7 / 45.4)

04 Uninterruptible power supply

RO 3.1 SRO3.3

REFERENCES:

1OP-02 Reactor Recirculation System Operating Procedure

TOOLS AND EQUIPMENT:

None

SAFETY FUNCTION (from NUREG 1123, Rev. 2, Supp. 1):

6 - Electrical

SETUP INSTRUCTIONS

None

AOT-OJT-JP-VFD-06 Page 2 of 10 Rev.0

SAFETY CONSIDERATIONS:

1. Notify SM/CRS of JPM performance prior to commencing In-plant JPM.

2. Determine actual radiological conditions and potentially contaminated areas to achieve ALARA.

3. Ensure all electrical safety requirements are observed.

4. Review Work Practices section prior to conduct of the JPM.

5. DO NOT OPERATE any plant equipment during performance of this JPM.

EVALUATOR NOTES: (Do not read to performer)

1. The applicable procedure section WILL be provided to the trainee.

2. If this is the first JPM of the JPM set, read the JPM briefing contained NUREG 1021, Appendix

E, or similar to the trainee.

Read the following to the JPM performer.

TASK CONDITIONS:

1. 1-VFD-CONT-UPS-A is currently operating in accordance with 1OP-02, Section 6.1.4.

2. In preparation for a maintenance activity, the 1-VFD-CONT-UPS-A inverter must be

realigned with UPS loads powered through the Maintenance Bypass Switch.

INITIATING CUE:

You are to perform 1OP-02, Section 6.3.14, Transfer of Recirc VFD-CONT-UPS-A(B) from

Inverter Operation to Maintenance Bypass and inform the Main Control Room when

complete.

AOT-OJT-JP-VFD-06 Page 3 of 10 Rev.0

PERFORMANCE CHECKLIST

NOTE: Sequence is assumed unless otherwise indicated, comments required for any step evaluated as UNSAT.

TIME START: ___________

Step 1 - Obtain a current revision of 1OP-2, Section 6.3.14.

Current Revision of 1OP-2, Section 6.3.14 obtained.

SAT/UNSAT

Step 2 - Confirm Recirc VFD-CONT-UPS-A(B) is operating in accordance with Section 6.1.4.

Condition is met per the initial conditions.

SAT/UNSAT

Step 3 - Confirm plant conditions require removing VFD-CONT-UPS-A(B) inverter from

service and powering UPS loads through the Maintenance Bypass switch.

Confirmed in initial conditions.

SAT/UNSAT

Step 4 - Record VFD-CONT-UPS-A(B).

Records VFD-CONT-UPS-A .

SAT/UNSAT

NOTE: This section is applicable to only the VFD-CONT-UPS-A(B).

Step 5 - Confirm the Maintenance Bypass Available light, located on the UPS back panel, is

ON.

Confirms Maintenance Bypass Available light is illuminated.

SAT/UNSAT

Step 6 - Place the Maint Bypass switch, in UTILITY.

Maint Bypass switch, rotated to the UTILITY position.

- CRITICAL STEP** SAT/UNSAT

AOT-OJT-JP-VFD-06 Page 4 of 10 Rev.0

Step 7 - Confirm NO Recirc VFD or RFCS control alarms due to the UPS transfer.

Contacts the MCR and verifies no VFD control alarms are present.

SAT/UNSAT

Step 8 - Place the UPS Output breaker, located on the UPS back panel, in OFF.

UPS Output breaker is placed in the OFF position.

- CRITICAL STEP** SAT/UNSAT

Step 9 - Place the UPS Input breaker, located on the UPS back panel, in OFF.

UPS Input breaker is placed in the OFF position.

- CRITICAL STEP** SAT/UNSAT

Step 10 - Depress the UPS Off/Bypass button, located on the UPS front panel, twice to shut

down the UPS.

The UPS Off/Bypass Button is depressed 2 times.

- CRITICAL STEP** SAT/UNSAT

Step 11 - Confirm 1-A-06, 1-5 (1-A-07, 1-6), Recirc VFD PDC UPS A(B) Fault alarm is ON.

Contacts the MCR and verifies Recirc VFD PDC UPS A(B) Fault alarm is ON.

SAT/UNSAT

TERMINATING CUE: When 1OP-02, Section 6.3.14 is complete, this JPM may be terminated.

TIME COMPLETED: _____________

COLLECT AND CONTROL ALL JPM EXAM MATERIALS FOR EXAM SECURITY.

AOT-OJT-JP-VFD-06 Page 5 of 10 Rev.0

Step Critical / Not Critical Reason

1 Not Critical Administrative

2 Not Critical Verification

3 Not Critical Verification

4 Not Critical Administrative

5 Not Critical Verification

6 Critical Necessary to transfer inverter operation

7 Not Critical Communication/Verification

8 Critical Necessary to transfer inverter operation

9 Critical Necessary to transfer inverter operation

10 Critical Necessary to transfer inverter operation

11 Not Critical Communication/Verification

AOT-OJT-JP-VFD-06 Page 6 of 10 Rev.0

WORK PRACTICES:

Comments are required for any step evaluated as UNSAT

A. CORE 4 SAT/ UNSAT/ NE

1. Task Preview / Pre-Job Briefs

2. Take-A-Minute

3. Correct Component Verification (CCV), Validate

Assumptions

4. Procedure and Work Instruction Use and Adherence

(PU&A)

B. Communications (proper content, repeat backs, 3 step SAT/ UNSAT/ NE

communications, etc.)

C. STAR (Use of Stop, Think, Act, Review) SAT/ UNSAT/ NE

D. Peer Checking (if performer requests or discusses peer checking) SAT/ UNSAT/ NE

E. Proper Equipment Use (observe starting limitations, throttle valve SAT/ UNSAT/ NE

closures, etc.)

F. Safety Compliance (use of PPE, knowledge of safety equipment, SAT/ UNSAT/ NE

etc.)

G. Electrical Safety And Arc Flash Protection Compliance (refer to SAT/ UNSAT/ NE

AD-HS-ALL-0110, as applicable)

H. Security Compliance (controlled area entry and exit, key control, SAT/ UNSAT/ NE

etc.)

I. Proper Tool Use (proper tool for the job, calibration dates, etc.) SAT/ UNSAT/ NE

J. Radiation Protection (ALARA, understanding and use of RWP, SAT/ UNSAT/ NE

frisking, etc.)

Comments:

AOT-OJT-JP-VFD-06 Page 7 of 10 Rev.0

REVISION SUMMARY

0 Initial Revision-New JPM.

(Provide sufficient detail for reviewers and evaluators to understand the scope of any

technical and/or administrative changes).

AOT-OJT-JP-VFD-06 Page 8 of 10 Rev.0

Validation Time: 20 Minutes (approximate).

Time Taken: ____ Minutes

APPLICABLE METHOD OF TESTING

Performance: Simulate Actual X Unit: 1

Setting: In-Plant X Simulator Admin

Time Critical: Yes No Time Limit N/A

Alternate Path: Yes No X

EVALUATION

Performer:

JPM: Pass Fail

Remedial Training Required: Yes No

Comments:

Comments reviewed with Performer

Evaluator Signature: Date:

AOT-OJT-JP-VFD-06 Page 9 of 10 Rev.0

TASK CONDITIONS:

1. 1-VFD-CONT-UPS-A is currently operating in accordance with 1OP-02, Section 6.1.4.

2. In preparation for a maintenance activity, the 1-VFD-CONT-UPS-A inverter must be

realigned with UPS loads powered through the Maintenance Bypass Switch.

INITIATING CUE:

You are to perform 1OP-02, Section 6.3.14, Transfer of Recirc VFD-CONT-UPS-A(B) from

Inverter Operation to Maintenance Bypass and inform the Main Control Room when complete

Page 10 of 10

DUKE ENERGY

BRUNSWICK TRAINING SECTION

LESSON TITLE: Restoring Seal Purge Flow with Pump Running - Seal Leakage

Abnormal (Unit 1)

(JPM J RO / ISRO)

LESSON NUMBER: AOT-OJT-JP-002-A03

REVISION NO: 6

Phil Capehart 03/13/17

PREPARER / DATE

Daniel Hulgin 03/13/17

TECHNICAL REVIEWER / DATE

Hunter Morris 05/09/17

Andrew Stoltz 05/09/17

VALIDATOR / DATE

Craig Oliver 05/24/17

LINE SUPERVISOR / DATE

Ed Rau 05/24/17

TRAINING SUPERVISION APPROVAL / DATE

AOT-OJT-JP-002-A03 Page 1 of 12 Rev.6

RELATED TASKS:

202602B104 Restore Reactor Recirculation Pump Seal Purge Flow With Pump

Running per 1(2)OP-02

K/A REFERENCE AND IMPORTANCE RATING:

202001 Recirculation System

A4 Ability to manually operate and/or monitor in the control room: (CFR: 41.7 / 45.5

to 45.8)

10 Seal flow: Plant-Specific

RO 2.8 / SRO 2.8

REFERENCES:

1OP-02 Reactor Recirculation System Operating Procedure

TOOLS AND EQUIPMENT:

None

SAFETY FUNCTION (from NUREG 1123, Rev. 2, Supp. 1):

Safety Function 1, Reactivity Control

SETUP INSTRUCTIONS

Prior to reading the cue: Ensure the blank spots in the task conditions, and initiating cue

are filled in with for the appropriate RR Pump (1A/1B).

AOT-OJT-JP-002-A03 Page 2 of 12 Rev.6

SAFETY CONSIDERATIONS:

1. Notify SM/CRS of JPM performance prior to commencing In-plant JPM.

2. Determine actual radiological conditions and potentially contaminated areas to achieve

ALARA.

3. Ensure all electrical safety requirements are observed.

4. Review Work Practices section prior to conduct of the JPM.

5. DO NOT OPERATE any plant equipment during performance of this JPM.

EVALUATOR NOTES: (Do not read to performer)

1. The applicable procedure section WILL be provided to the trainee.

2. Prior to the first JPM of the JPM set, provide the JPM briefing contained in NUREG-1021,

Appendix E, or similar briefing (for non-regulated exams) to the trainee(s).

Read the following to the JPM performer.

TASK CONDITIONS:

1. Both Reactor Recirc Pumps are in service.

2. Seal purge flow has been interrupted to the Reactor Recirculation Pump Seals.

3. Indication of abnormal seal leakage is present (upper).

4. All applicable prerequisites have been met.

5. Additional qualified personnel are available to assist

6. The CRD System is in operation.

7. The Recirc Pump Seal Injection Flow Controller is operable.

8. Seal No. 1 inlet temperature is 175°F

INITIATING CUE:

You are directed by the Reactor Operator to:

Restore seal purge flow to the Reactor Recirculation Pump Seals IAW 1OP-02, section

6.3.8

Inform the control room when those actions are complete.

AOT-OJT-JP-002-A03 Page 3 of 12 Rev.6

PERFORMANCE CHECKLIST

NOTE: Sequence is assumed unless otherwise indicated, comments required for any step evaluated as UNSAT.

TIME START: ___________

Step 1 - Obtain a current revision of 1OP-02, Section 6.3.8

Current revision of 1OP-02, Section 6.3.8 obtained.

SAT/UNSAT

Step 2 - (6.3.8 Step 1) Confirm recirculation pump upper seal leakage is abnormal.

Upper seal leakage confirmed as abnormal (given in task conditions).

SAT/UNSAT

Step 3 - (6.3.8 Step 2) Ensure all applicable prerequisites as listed in Section 5.0 are met.

All applicable prerequisites confirmed as met (given in task conditions).

SAT/UNSAT

NOTE:

B32-TR-R601 Point 12(24) - (Pump A(B) No. 1 Seal Cavity Inlet) is located on Panel H12-

P614.

CAUTION:

If upper seal leakage exceeds the alarm point (0.5 gpm) and seal injection flow is lost,

the seals may become overheated unless action is taken to restore seal purge flow as

soon as possible.

If cooling water to the recirculation pump seal coolers is interrupted during a loss of seal

injection, seal damage may occur if the the seal staging valve is NOT CLOSED and the

recirculation pump shut down within 90 seconds. Specific guidance is given in: 1APP-A-

06 (1-4), Pump A Seal Closed Clg Wtr Flow Lo and 1APP-A-07 (6-5), Pump B Seal

Closed Clg Wtr Flow Lo.

AOT-OJT-JP-002-A03 Page 4 of 12 Rev.6

Step 4 - (6.3.8 Step 3a-c) IF Seal No. 1 inlet temperature is less than 170°F, THEN restore

seal purge flow as soon as possible, within 5 minutes OR before B32-TR-R601 Point

12(24) - Pump A(B) No. 1 Seal Cavity Inlet exceeds 170°F, by performing the

following:

a) Ensure the CRD System in operation

b) Ensure 1-B32-V22(V30) (Seal Injection Vlv) is OPEN.

c) Ensure seal purge flow is 3 to 5 gpm as indicated on local indicator 1-B32-FI-

1839(1842) [RCR Pmp 1A(B) Seal Inject Flow Indicator].

Confirms inlet temperature is greater than 170°F (given in task conditions) marks

step N/A and does not perform step.

SAT/UNSAT

CAUTION:

If injection flow can NOT be restored within a reasonable time as judged by the rate of

temperature rise and seal temperature approaches 200°F, the recirculation pumps will be shut

down and isolated as directed by Step 5.

Step 5 - (6.3.8 Step 4a) IF Seal No. 1 inlet temperature is greater than 170°F but less than

200°F, THEN restore seal purge as follows: a. Ensure 1-B32-V45(V47) (Seal

Injection Flow Controller Upstream Isolation Valve) is CLOSED.

1-B32-V45(V47) (Seal Injection Flow Controller Upstream Isolation Valve) is

closed by turning the handwheel in the clockwise direction until full resistance is

obtained.

- CRITICAL STEP** SAT/UNSAT

Step 6 - (6.3.8 Step 4b) IF Seal No. 1 inlet temperature is greater than 170°F but less than

200°F, THEN restore seal purge as follows: b. Ensure 1-B32-V43(V44) ( Seal

Injection Flow Controller Bypass Valve) is CLOSED.

1-B32-V43(V44) ( Seal Injection Flow Controller Bypass Valve) is verified to be

closed by turning the handwheel in the clockwise direction to verify full resistance

on the handwheel.

SAT/UNSAT

PROMPT: When contacted as MCR, state the 1-B32-V22(V30) (Seal Injection Vlv) is OPEN.

Step 7 - (6.3.8 Step 4c) IF Seal No. 1 inlet temperature is greater than 170°F but less than

200°F, THEN restore seal purge as follows: c. Ensure 1-B32-V22(V30) (Seal

Injection Vlv) is OPEN.

Contacts control room to verify 1-B32-V22(V30) (Seal Injection Vlv) is OPEN.

SAT/UNSAT

AOT-OJT-JP-002-A03 Page 5 of 12 Rev.6

PROMPT: When contacted as MCR, state the CRD System is in operation. May not contact

since given in initial conditions.

Step 8 - (6.3.8 Step 4d) IF Seal No. 1 inlet temperature is greater than 170°F but less than

200°F, THEN restore seal purge as follows: d. Ensure the CRD System in operation.

Contacts control room to verify CRD System in operation .

SAT/UNSAT

EVALUATOR NOTE: Recirculation Pump seal temperatures are monitored by recorder B32-

R601 on Panel H12-P614: Point 12(24) - Pump A(B) Seal No. 1 Inlet (T-2)..

PROMPT: If asked (and after the 1-B32-V45(V47) is throttled open) , inform applicant that

temperature is dropping 0.2º F every 15 seconds.

PROMPT: Several minutes after the 1-B32-V45(V47) is throttled open inform student that all

seal temperatures are normal.

Step 9 - (6.3.8 Step 4e) IF Seal No. 1 inlet temperature is greater than 170°F but less than

200°F, THEN restore seal purge as follows: e. WHILE monitoring Recirculation

Pump seal temperatures, throttle open either of the following valves so that B32-TR-

R601 Point 12(24) - Pump A(B) No. 1 Seal Cavity Inlet does NOT lower more than

5°F per minute or 50°F per hour:

IF flow controller is OPERABLE, THEN slowly throttle OPEN 1-B32-V45(V47) (Seal

Injection Flow Controller Upstream Isolation Valve)

or

IF flow controller is NOT OPERABLE, THEN slowly throttle OPEN 1-B32-V43(V44)

(Seal Injection Flow Controller Bypass Valve).

1-B32-V45(V47) (Seal Injection Flow Controller Upstream Isolation Valve) is

turned in the counter clockwise direction to throttle the valve OPEN.

- CRITICAL STEP** SAT/UNSAT

AOT-OJT-JP-002-A03 Page 6 of 12 Rev.6

Step 10 - (6.3.8 Step 4f) IF Seal No. 1 inlet temperature is greater than 170°F but less than

200°F, THEN restore seal purge as follows: f. WHEN seal temperatures are normal,

THEN perform either of the following:

IF flow controller is OPERABLE, THEN fully open 1-B32-V45(V47) (Seal Injection

Flow Controller Upstream Isolation Valve).

IF flow controller is NOT OPERABLE, THEN throttle 1-B32-V43(V44) (Seal Injection

Flow Controller Bypass Valve) until seal injection flow is 3 to 5 gpm as indicated on 1-

B32-FI-1839(1842) [RCR Pmp 2A(B) Seal Inject Flow Indicator] at the flow controller.

1-B32-V45(V47) (Seal Injection Flow Controller Upstream Isolation Valve) is

turned in the counter clockwise direction until full resistance is obtained.

- CRITICAL STEP** SAT/UNSAT

PROMPT: If asked, indicate to the student that the flow indicator reads 4 gpm.

Step 11 - (6.3.8 Step 4g) IF Seal No. 1 inlet temperature is greater than 170°F but less than

200°F, THEN restore seal purge as follows: g. Ensure seal injection flow is 3 to 5

gpm as indicated on local indicator 1-B32-FI-1839(1842) [RCR Pmp 1A(B) Seal Inject

Flow Indicator].

Flow verified to indicate 3 to 5 gpm on B32-FI-1839 (1842).

SAT/UNSAT

Step 12 - Inform Control Room that seal purge flow has been restored.

Control Room informed seal purge is restored.

SAT/UNSAT

TERMINATING CUE: When seal purge has been restored (B32-V45(47) is fully open) this

JPM is complete.

TIME COMPLETED: _____________

COLLECT AND CONTROL ALL JPM EXAM MATERIALS FOR EXAM SECURITY.

AOT-OJT-JP-002-A03 Page 7 of 12 Rev.6

Step Critical / Not Critical Reason

1 Not Critical Administrative

2 Not Critical Verification

3 Not Critical Verification

4 Not Critical Verification

5 Critical Necessary to restore seal purge

6 Not Critical Verification

7 Not Critical Verification

8 Not Critical Verification

9 Critical Necessary to restore seal purge

10 Critical Necessary to restore seal purge

11 Not Critical Verification

12 Not Critical Communication

AOT-OJT-JP-002-A03 Page 8 of 12 Rev.6

WORK PRACTICES:

Comments are required for any step evaluated as UNSAT

A. CORE 4 SAT/ UNSAT/ NE

1. Task Preview / Pre-Job Briefs

2. Take-A-Minute

3. Correct Component Verification (CCV), Validate

Assumptions

4. Procedure and Work Instruction Use and Adherence

(PU&A)

B. Communications (proper content, repeat backs, 3 step SAT/ UNSAT/ NE

communications, etc.)

C. STAR (Use of Stop, Think, Act, Review) SAT/ UNSAT/ NE

D. Peer Checking (if performer requests or discusses peer checking) SAT/ UNSAT/ NE

E. Proper Equipment Use (observe starting limitations, throttle valve SAT/ UNSAT/ NE

closures, etc.)

F. Safety Compliance (use of PPE, knowledge of safety equipment, SAT/ UNSAT/ NE

etc.)

G. Electrical Safety And Arc Flash Protection Compliance (refer to SAT/ UNSAT/ NE

AD-HS-ALL-0110, as applicable)

H. Security Compliance (controlled area entry and exit, key control, SAT/ UNSAT/ NE

etc.)

I. Proper Tool Use (proper tool for the job, calibration dates, etc.) SAT/ UNSAT/ NE

J. Radiation Protection (ALARA, understanding and use of RWP, SAT/ UNSAT/ NE

frisking, etc.)

Comments:

AOT-OJT-JP-002-A03 Page 9 of 12 Rev.6

REVISION SUMMARY

6 Revised to meet new format.

Changed procedure section to 6.3.8

5 Minor Revision Changes is all that was listed for this revision.

(Provide sufficient detail for reviewers and evaluators to understand the scope of any

technical and/or administrative changes).

AOT-OJT-JP-002-A03 Page 10 of 12 Rev.6

Validation Time: 15 Minutes (approximate).

Time Taken: ____ Minutes

APPLICABLE METHOD OF TESTING

Performance: Simulate X Actual Unit: 1

Setting: In-Plant X Simulator Admin

Time Critical: Yes No X Time Limit N/A

Alternate Path: Yes X No

EVALUATION

Performer:

JPM: Pass Fail

Remedial Training Required: Yes No

Comments:

Comments reviewed with Performer

Evaluator Signature: Date:

AOT-OJT-JP-002-A03 Page 11 of 12 Rev.6

TASK CONDITIONS:

1. Both Reactor Recirc Pumps are in service.

2. Seal purge flow has been interrupted to the Reactor Recirculation Pump Seals.

3. Indication of abnormal seal leakage is present.

4. All applicable prerequisites have been met.

5. Additional qualified personnel are available to assist

6. The CRD System is in operation.

7. The Recirc Pump Seal Injection Flow Controller is operable.

8. Seal No. 1 inlet temperature is 175°F

INITIATING CUE:

You are directed by the Reactor Operator to:

Restore seal purge flow to the Reactor Recirculation Pump Seals IAW 1OP-02, section

6.3.8

Inform the control room when those actions are complete

Page 12 of 12

DUKE ENERGY

BRUNSWICK TRAINING SECTION

LESSON TITLE: Restoring Seal Purge Flow with Pump Running - Seal Leakage

Abnormal (Unit 2)

LESSON NUMBER: AOT-OJT-JP-002-A03

REVISION NO: 6

Phil Capehart 03/13/17

PREPARER / DATE

Daniel Hulgin 03/13/17

TECHNICAL REVIEWER / DATE

Hunter Morris 05/09/17

Andrew Stoltz 05/09/17

VALIDATOR / DATE

Craig Oliver 05/24/17

LINE SUPERVISOR / DATE

Ed Rau 05/24/17

TRAINING SUPERVISION APPROVAL / DATE

AOT-OJT-JP-002-A03 Page 1 of 12 Rev.6

RELATED TASKS:

202602B104 Restore Reactor Recirculation Pump Seal Purge Flow With Pump

Running per 1(2)OP-02

K/A REFERENCE AND IMPORTANCE RATING:

202001 Recirculation System

A4 Ability to manually operate and/or monitor in the control room: (CFR: 41.7 / 45.5

to 45.8)

10 Seal flow: Plant-Specific

RO 2.8 / SRO 2.8

REFERENCES:

2OP-02 Reactor Recirculation System Operating Procedure

TOOLS AND EQUIPMENT:

None

SAFETY FUNCTION (from NUREG 1123, Rev. 2, Supp. 1):

Safety Function 1, Reactivity Control

SETUP INSTRUCTIONS

Prior to reading the cue: Ensure the blank spots in the task conditions, and initiating cue

are filled in with for the appropriate RR Pump (2A/2B).

AOT-OJT-JP-002-A03 Page 2 of 12 Rev.6

SAFETY CONSIDERATIONS:

1. Notify SM/CRS of JPM performance prior to commencing In-plant JPM.

2. Determine actual radiological conditions and potentially contaminated areas to achieve

ALARA.

3. Ensure all electrical safety requirements are observed.

4. Review Work Practices section prior to conduct of the JPM.

5. DO NOT OPERATE any plant equipment during performance of this JPM.

EVALUATOR NOTES: (Do not read to performer)

1. The applicable procedure section WILL be provided to the trainee.

2. Prior to the first JPM of the JPM set, provide the JPM briefing contained in NUREG-1021,

Appendix E, or similar briefing (for non-regulated exams) to the trainee(s).

Read the following to the JPM performer.

TASK CONDITIONS:

1. Both Reactor Recirc Pumps are in service.

2. Seal purge flow has been interrupted to the Reactor Recirculation Pump Seals.

3. Indication of abnormal seal leakage is present.

4. All applicable prerequisites have been met.

5. Additional qualified personnel are available to assist

6. The CRD System is in operation.

7. The Recirc Pump Seal Injection Flow Controller is operable.

8. Seal No. 1 inlet temperature is 175°F

INITIATING CUE:

You are directed by the Reactor Operator to:

Restore seal purge flow to the Reactor Recirculation Pump Seals IAW 2OP-02, section

6.3.8

Inform the control room when those actions are complete.

AOT-OJT-JP-002-A03 Page 3 of 12 Rev.6

PERFORMANCE CHECKLIST

NOTE: Sequence is assumed unless otherwise indicated, comments required for any step evaluated as UNSAT.

TIME START: ___________

Step 1 - Obtain a current revision of 2OP-02, Section 6.3.8

Current revision of 2OP-02, Section 6.3.8 obtained.

SAT/UNSAT

Step 2 - (6.3.8 Step 1) Ensure recirculation pump upper seal leakage is abnormal.

Upper seal leakage confirmed as abnormal (given in task conditions).

SAT/UNSAT

Step 3 - (6.3.8 Step 2) Ensure all applicable prerequisites as listed in Section 5.0 are met.

All applicable prerequisites confirmed as met (given in task conditions).

SAT/UNSAT

NOTE:

Pump A(B) Seal No. 1 Inlet temperature is monitored by recorder B32-R601, Point 12(24) on

Panel H12-P614.

CAUTION:

If upper seal leakage exceeds the alarm point (0.5 gpm) and seal injection flow is lost,

the seals may become overheated unless action is taken to restore seal purge flow as

soon as possible.

If cooling water to the recirculation pump seal coolers is interrupted during a loss of seal

injection, seal damage may occur if the the seal staging valve is NOT CLOSED and the

recirculation pump shut down within 90 seconds. Specific guidance is given in: 2APP-A-

06 (1-4), Pump A Seal Closed Clg Wtr Flow Lo and 2APP-A-07 (6-5), Pump B Seal

Closed Clg Wtr Flow Lo.

AOT-OJT-JP-002-A03 Page 4 of 12 Rev.6

Step 4 - (6.3.8 Step 3a-c) IF Seal No. 1 inlet temperature is less than 170°F, THEN restore

seal purge flow as soon as possible, within 5 minutes or before Pump A(B) Seal No.

1 Inlet temperature exceeds 170°F, by performing the following:

a) Ensure the CRD System in operation

b) Ensure 2-B32-V22(V30) (Seal Injection Vlv) is OPEN.

c) Ensure seal purge flow is 3 to 5 gpm as indicated on local indicator 2-B32-FI-

1839(1842) [RCR Pmp 1A(B) Seal Inject Flow Indicator].

Confirms inlet temperature is greater than 170°F (given in task conditions) marks

step N/A and does not perform step.

SAT/UNSAT

CAUTION:

If injection flow can NOT be restored within a reasonable time as judged by the rate of

temperature rise and seal temperature approaches 200°F, the recirculation pumps will be shut

down and isolated as directed by Step 5.

Step 5 - (6.3.8 Step 4a) IF Seal No. 1 inlet temperature is greater than 170°F but less than

200°F, THEN restore seal purge as follows: a. Ensure 2-B32-V45(V47) (Seal

Injection Flow Controller Upstream Isolation Valve) is CLOSED.

2-B32-V45(V47) (Seal Injection Flow Controller Upstream Isolation Valve) is

closed by turning the handwheel in the clockwise direction until full resistance is

obtained.

- CRITICAL STEP** SAT/UNSAT

Step 6 - (6.3.8 Step 4b) IF Seal No. 1 inlet temperature is greater than 170°F but less than

200°F, THEN restore seal purge as follows: b. Ensure 2-B32-V43(V44) ( Seal

Injection Flow Controller Bypass Valve) is CLOSED.

2-B32-V43(V44) ( Seal Injection Flow Controller Bypass Valve) is verified to be

closed by turning the handwheel in the clockwise direction to verify full resistance

on the handwheel.

SAT/UNSAT

PROMPT: When contacted as MCR, state the 1-B32-V22(V30) (Seal Injection Vlv) is OPEN.

Step 7 - (6.3.8 Step 4c) IF Seal No. 1 inlet temperature is greater than 170°F but less than

200°F, THEN restore seal purge as follows: c. Ensure 2-B32-V22(V30) (Seal

Injection Vlv) is OPEN.

Contacts control room to verify 2-B32-V22(V30) (Seal Injection Vlv) is OPEN.

SAT/UNSAT

AOT-OJT-JP-002-A03 Page 5 of 12 Rev.6

PROMPT: When contacted as MCR, state the CRD System is in operation.

Step 8 - (6.3.8 Step 4d) IF Seal No. 1 inlet temperature is greater than 170°F but less than

200°F, THEN restore seal purge as follows: d. Ensure the CRD System in operation.

Contacts control room to verify CRD System in operation .

SAT/UNSAT

EVALUATOR NOTE: Recirculation Pump seal temperatures are monitored by recorder B32-

R601 on Panel H12-P614: Point 12(24) - Pump A(B) Seal No. 1 Inlet (T-2)..

PROMPT: If asked (and after the 2-B32-V45(V47) is throttled open) , inform applicant that

temperature is dropping 0.2º F every 15 seconds.

PROMPT: Several minutes after the 2-B32-V45(V47) is throttled open inform student that all

seal temperatures are normal.

Step 9 - (6.3.8 Step 4e) IF Seal No. 1 inlet temperature is greater than 170°F but less than

200°F, THEN restore seal purge as follows: e. WHILE monitoring Recirculation

Pump seal temperatures, throttle open either of the following valves so that Pump

A(B) Seal No. 1 Inlet temperature does NOT lower more than 5°F per minute or 50°F

per hour:

IF flow controller is OPERABLE, THEN throttle open 2-B32-V45(V47) (Seal

Injection Flow Controller Upstream Isolation Valve)

or

IF flow controller is NOT OPERABLE, THEN throttle open 2-B32-V43(V44) (Seal

Injection Flow Controller Bypass Valve).

2-B32-V45(V47) (Seal Injection Flow Controller Upstream Isolation Valve) is

turned in the counter clockwise direction to throttle the valve OPEN.

- CRITICAL STEP** SAT/UNSAT

AOT-OJT-JP-002-A03 Page 6 of 12 Rev.6

Step 10 - (6.3.8 Step 4f) IF Seal No. 1 inlet temperature is greater than 170°F but less than

200°F, THEN restore seal purge as follows: f. WHEN seal temperatures are normal,

THEN perform either of the following:

IF flow controller is OPERABLE, THEN fully open 2-B32-V45(V47) (Seal Injection

Flow Controller Upstream Isolation Valve).

IF flow controller is NOT OPERABLE, THEN throttle 2-B32-V43(V44) (Seal Injection

Flow Controller Bypass Valve) until seal injection flow is 3 to 5 gpm as indicated on 2-

B32-FI-1839(1842) [RCR Pmp 2A(B) Seal Inject Flow Indicator] at the flow controller.

2-B32-V45(V47) (Seal Injection Flow Controller Upstream Isolation Valve) is

turned in the counter clockwise direction until full resistance is obtained.

- CRITICAL STEP** SAT/UNSAT

PROMPT: If asked, indicate to the student that the flow indicator reads 4 gpm.

Step 11 - (6.3.8 Step 4g) IF Seal No. 1 inlet temperature is greater than 170°F but less than

200°F, THEN restore seal purge as follows: g. Ensure seal purge flow is 3 to 5 gpm

as indicated on local indicator 2-B32-FI-1839(1842) [RCR Pmp 2A(B) Seal Inject

Flow Indicator].

Flow verified to indicate 3 to 5 gpm on B32-FI-1839 (1842).

SAT/UNSAT

Step 12 - Inform Control Room that seal purge flow has been restored.

Control Room informed seal purge is restored.

SAT/UNSAT

TERMINATING CUE: When seal purge has been restored (B32-V45(47) is fully open) this

JPM is complete.

TIME COMPLETED: _____________

COLLECT AND CONTROL ALL JPM EXAM MATERIALS FOR EXAM SECURITY.

AOT-OJT-JP-002-A03 Page 7 of 12 Rev.6

Step Critical / Not Critical Reason

1 Not Critical Administrative

2 Not Critical Verification

3 Not Critical Verification

4 Not Critical Verification

5 Critical Necessary to restore seal purge

6 Not Critical Verification

7 Not Critical Verification

8 Not Critical Verification

9 Critical Necessary to restore seal purge

10 Critical Necessary to restore seal purge

11 Not Critical Verification

12 Not Critical Communication

AOT-OJT-JP-002-A03 Page 8 of 12 Rev.6

WORK PRACTICES:

Comments are required for any step evaluated as UNSAT

A. CORE 4 SAT/ UNSAT/ NE

1. Task Preview / Pre-Job Briefs

2. Take-A-Minute

3. Correct Component Verification (CCV), Validate

Assumptions

4. Procedure and Work Instruction Use and Adherence

(PU&A)

B. Communications (proper content, repeat backs, 3 step SAT/ UNSAT/ NE

communications, etc.)

C. STAR (Use of Stop, Think, Act, Review) SAT/ UNSAT/ NE

D. Peer Checking (if performer requests or discusses peer checking) SAT/ UNSAT/ NE

E. Proper Equipment Use (observe starting limitations, throttle valve SAT/ UNSAT/ NE

closures, etc.)

F. Safety Compliance (use of PPE, knowledge of safety equipment, SAT/ UNSAT/ NE

etc.)

G. Electrical Safety And Arc Flash Protection Compliance (refer to SAT/ UNSAT/ NE

AD-HS-ALL-0110, as applicable)

H. Security Compliance (controlled area entry and exit, key control, SAT/ UNSAT/ NE

etc.)

I. Proper Tool Use (proper tool for the job, calibration dates, etc.) SAT/ UNSAT/ NE

J. Radiation Protection (ALARA, understanding and use of RWP, SAT/ UNSAT/ NE

frisking, etc.)

Comments:

AOT-OJT-JP-002-A03 Page 9 of 12 Rev.6

REVISION SUMMARY

6 Revised to meet new format.

Changed procedure section to 6.3.8

5 Minor Revision Changes is all that was listed for this revision.

(Provide sufficient detail for reviewers and evaluators to understand the scope of any

technical and/or administrative changes).

AOT-OJT-JP-002-A03 Page 10 of 12 Rev.6

Validation Time: 15 Minutes (approximate).

Time Taken: ____ Minutes

APPLICABLE METHOD OF TESTING

Performance: Simulate X Actual Unit: 2

Setting: In-Plant X Simulator Admin

Time Critical: Yes No X Time Limit N/A

Alternate Path: Yes X No

EVALUATION

Performer:

JPM: Pass Fail

Remedial Training Required: Yes No

Comments:

Comments reviewed with Performer

Evaluator Signature: Date:

AOT-OJT-JP-002-A03 Page 11 of 12 Rev.6

TASK CONDITIONS:

1. Both Reactor Recirc Pumps are in service.

2. Seal purge flow has been interrupted to the Reactor Recirculation Pump Seals.

3. Indication of abnormal seal leakage is present.

4. All applicable prerequisites have been met.

5. Additional qualified personnel are available to assist

6. The CRD System is in operation.

7. The Recirc Pump Seal Injection Flow Controller is operable.

8. Seal No. 1 inlet temperature is 175°F

INITIATING CUE:

You are directed by the Reactor Operator to:

Restore seal purge flow to the Reactor Recirculation Pump Seals IAW 2OP-02, section

6.3.8

Inform the control room when those actions are complete

Page 12 of 12

DUKE ENERGY

BRUNSWICK TRAINING SECTION

LESSON TITLE: Setting Service Air Dryer Sweep Value to Zero

(JPM K RO / ISRO / USRO)

LESSON NUMBER: AOT-OJT-JP-300-K02

REVISION NO: 0

Phil Capehart 03/13/17

PREPARER / DATE

Daniel Hulgin 03/13/17

TECHNICAL REVIEWER / DATE

Hunter Morris 05/09/17

Andrew Stoltz 05/09/17

VALIDATOR / DATE

Craig Oliver 05/24/17

LINE SUPERVISOR / DATE

Ed Rau 05/24/17

TRAINING SUPERVISION APPROVAL / DATE

AOT-OJT-JP-300-K02 Page 1 of 13 Rev.0

RELATED TASKS:

200504B504 Perform Emergency Actions Associated with a Pneumatic (Air/Nitrogen)

System Failure per 0AOP-20

K/A REFERENCE AND IMPORTANCE RATING:

Gen 2.1.30 4.4 / 4.0

Ability to locate and operate components, including local controls.

300000 A2.01 2.9/2.8

Ability to (a) predict the impacts of air dryer and filter malfunctions on the Instrument Air

System and (b) based on those predictions, use procedures to correct, control, or mitigate

the consequences of those abnormal operations

REFERENCES:

0AOP-20.0 Pneumatic (Air/Nitrogen) System Failures

TOOLS AND EQUIPMENT:

None

SAFETY FUNCTION (from NUREG 1123, Rev. 2, Supp. 1):

8 - Plant Service Systems (300000 - Instrument Air)

SETUP INSTRUCTIONS

None

AOT-OJT-JP-300-K02 Page 2 of 13 Rev.0

SAFETY CONSIDERATIONS:

1. Notify SM/CRS of JPM performance prior to commencing In-plant JPM.

2. Determine actual radiological conditions and potentially contaminated areas to achieve

ALARA.

3. Ensure all electrical safety requirements are observed.

4. Review Work Practices section prior to conduct of the JPM.

5. DO NOT OPERATE any plant equipment during performance of this JPM.

EVALUATOR NOTES: (Do not read to performer)

1. The applicable procedure section WILL be provided to the trainee.

2. Prior to the first JPM of the JPM set, provide the JPM briefing contained in NUREG-

1021, Appendix E, or similar briefing (for non-regulated exams) to the trainee(s).

Read the following to the JPM performer.

TASK CONDITIONS:

1. A loss of pneumatics has occurred.

2. 0AOP-20.0 is being executed.

INITIATING CUE:

You are directed by the CRS to:

Perform 0AOP-20.0, Pneumatic (Air/Nitrogen) System Failures, Attachment 1, Setting Service

Air Dryer(s) Maximum Sweep Value To Zero, on 1B Air Dryer.

Inform the CRS when the required actions are complete.

AOT-OJT-JP-300-K02 Page 3 of 13 Rev.0

PERFORMANCE CHECKLIST

NOTE: Sequence is assumed unless otherwise indicated, comments required for any step evaluated as UNSAT.

TIME START: ___________

Step 1 - Obtain a current revision of 0AOP-20.0, Attachment 1.

Current revision of 0AOP-20.0, Attachment 1 obtained.

SAT/UNSAT

NOTE:

DIP switch #9 is located inside the Dryer Control System display cabinet. DIP switch #9 is the

second switch from the bottom, located between the door and circuit board. DIP switch is in

the on position when the switch is switched away from the circuit board.

Step 2 - Identify applicable Dryer Control System display cabinet by circling below:

1-SA-1A-AIR-DRY PNL

1-SA-1B-AIR-DRY PNL

2-SA-2A-AIR-DRY PNL

1-SA-1B-AIR-DRY PNL is circled.

SAT/UNSAT

EVALUATOR NOTE: The cabinet is not locked, the use of anything (i.e. screwdriver, a key,

etc) will turn the key mechanism to allow the cabinet door to open.

PROMPT: When the performer is going to open the cabinet, give them the pictures, as

needed, of the inside of the cabinet to demonstrate operation of the Dip Switch.

Step 3 - Place DIP SWITCH #9 to ON.

DIP SWITCH #9 is placed to ON by moving the switch away from the circuit

board.

- CRITICAL STEP** SAT/UNSAT

AOT-OJT-JP-300-K02 Page 4 of 13 Rev.0

Step 4 - Depress Mode (F1) key until the CONFIGURE page is displayed.

Mode (F1) key is depressed until the CONFIGURE page is displayed.

SAT/UNSAT

Step 5 - Depress Page (F2) key until CONFIGURE PAGE 2 of 2 is displayed.

Page (F2) key is depressed until CONFIGURE PAGE 2 of 2 is displayed.

SAT/UNSAT

Step 6 - Depress ENTER (F5).

ENTER (F5) key is depressed.

SAT/UNSAT

NOTE:

Values are adjusted by using the +(F3) and -(F4) keys.

Step 7 - Adjust MAXIMUM SWEEP VALUE to 0 (zero) with the +(F3) and -(F4) keys.

MAXIMUM SWEEP VALUE adjusted to zero (from 90) by depressing repeatedly

the -(F4) key until 0 is displayed.

- CRITICAL STEP** SAT/UNSAT

NOTE:

New values are accepted by pressing ENTER (F5) key or rejected by pressing the

ESC (F6) key.

Step 8 - Depress ENTER (F5) key.

ENTER (F5) key is depressed.

- CRITICAL STEP** SAT/UNSAT

AOT-OJT-JP-300-K02 Page 5 of 13 Rev.0

NOTE:

DIP switch is in the off position when the switch is switched toward the circuit board.

Step 9 - Place DIP SWITCH #9 to OFF.

DIP SWITCH #9 is placed to OFF by moving the switch toward the circuit board.

- CRITICAL STEP** SAT/UNSAT

Step 10 - Inform CRS that the maximum sweep value has been set to zero for Service Air

Dryer 1B IAW 0AOP-20.0.

CRS informed that the maximum sweep value has been set to zero for Service

Air Dryer 1B IAW 0AOP-20.0.

SAT/UNSAT

TERMINATING CUE: When 0AOP-20.0, Attachment 1, Setting Service Air Dryer(s) Maximum

Sweep Value to Zero, actions are completed, this JPM is complete.

TIME COMPLETED: _____________

COLLECT AND CONTROL ALL JPM EXAM MATERIALS FOR EXAM SECURITY.

Step Critical / Not Critical Reason

1 Not Critical Administrative

2 Not Critical Administrative

3 Critical Necessary for sweep adjustment

4 Not Critical GUI manipulation

5 Not Critical GUI manipulation

6 Not Critical GUI manipulation

7 Critical Necessary for sweep adjustment

8 Critical Necessary for sweep adjustment

9 Critical Necessary for sweep adjustment

10 Not Critical Communication

AOT-OJT-JP-300-K02 Page 6 of 13 Rev.0

WORK PRACTICES:

Comments are required for any step evaluated as UNSAT

A. CORE 4 SAT/ UNSAT/ NE

1. Task Preview / Pre-Job Briefs

2. Take-A-Minute

3. Correct Component Verification (CCV), Validate

Assumptions

4. Procedure and Work Instruction Use and Adherence

(PU&A)

B. Communications (proper content, repeat backs, 3 step SAT/ UNSAT/ NE

communications, etc.)

C. STAR (Use of Stop, Think, Act, Review) SAT/ UNSAT/ NE

D. Peer Checking (if performer requests or discusses peer checking) SAT/ UNSAT/ NE

E. Proper Equipment Use (observe starting limitations, throttle valve SAT/ UNSAT/ NE

closures, etc.)

F. Safety Compliance (use of PPE, knowledge of safety equipment, SAT/ UNSAT/ NE

etc.)

G. Electrical Safety And Arc Flash Protection Compliance (refer to SAT/ UNSAT/ NE

AD-HS-ALL-0110, as applicable)

H. Security Compliance (controlled area entry and exit, key control, SAT/ UNSAT/ NE

etc.)

I. Proper Tool Use (proper tool for the job, calibration dates, etc.) SAT/ UNSAT/ NE

J. Radiation Protection (ALARA, understanding and use of RWP, SAT/ UNSAT/ NE

frisking, etc.)

Comments:

AOT-OJT-JP-300-K02 Page 7 of 13 Rev.0

REVISION SUMMARY

0 Initial Revision, new JPM modified from AOT-OJT-JP-300-K01 Rev 1.

(Provide sufficient detail for reviewers and evaluators to understand the scope of any

technical and/or administrative changes).

AOT-OJT-JP-300-K02 Page 8 of 13 Rev.0

Validation Time: 12 Minutes (approximate).

Time Taken: ____ Minutes

APPLICABLE METHOD OF TESTING

Performance: Simulate X Actual Unit: 1

Setting: In-Plant X Simulator Admin

Time Critical: Yes No X Time Limit N/A

Alternate Path: Yes No X

EVALUATION

Performer:

JPM: Pass Fail

Remedial Training Required: Yes No

Comments:

Comments reviewed with Performer

Evaluator Signature: Date:

AOT-OJT-JP-300-K02 Page 9 of 13 Rev.0

Page 10 of 13

Page 11 of 13

Page 12 of 13

TASK CONDITIONS:

1. A loss of pneumatics has occurred.

2. 0AOP-20.0 is being executed.

INITIATING CUE:

You are directed by the CRS to:

Perform 0AOP-20.0, Pneumatic (Air/Nitrogen) System Failures, Attachment 1, Setting Service

Air Dryer(s) Maximum Sweep Value To Zero, on 1B Air Dryer.

Inform the CRS when the required actions are complete.

Page 13 of 13

DUKE ENERGY

BRUNSWICK TRAINING SECTION

LESSON TITLE: Evaluate Jet Pump Performance Per 0PT-13.1

LESSON NUMBER: LOT-ADM-JP-002-02

REVISION NO: 2

Phil Capehart 03/13/17

PREPARER / DATE

Daniel Hulgin 03/13/17

TECHNICAL REVIEWER / DATE

Brian West 04/18/17

Michael Long 05/05/17

VALIDATOR / DATE

Craig Oliver 05/24/17

LINE SUPERVISOR / DATE

Ed Rau 05/24/17

TRAINING SUPERVISION APPROVAL / DATE

LOT-ADM-JP-002-02 Page 1 of 37 Rev.2

RELATED TASKS:

202001B201, Perform Reactor Recirculation Jet Pump Operability Test Per PT-13.1

K/A REFERENCE AND IMPORTANCE RATING:

GEN 2.1.33 3.4/4.0

REFERENCES:

0PT-13.1

2OP-02

TOOLS AND EQUIPMENT:

Calculator

ADMINISTRATIVE CATEGORY (from NUREG 1123, Rev. 2, Supp. 1):

Generic 2.1 - Conduct Of Operations

SETUP INSTRUCTIONS

None-Admin

LOT-ADM-JP-002-02 Page 2 of 37 Rev.2

SAFETY CONSIDERATIONS:

1. None

EVALUATOR NOTES: (Do not read to performer)

1. The applicable procedure section WILL be provided to the trainee.

2. Prior to the first JPM of the JPM set, provide the JPM briefing contained in NUREG-1021,

Appendix E, or similar briefing (for non-regulated exams) to the trainee(s).

Read the following to the JPM performer.

TASK CONDITIONS:

1. Unit Two is operating at 100% power .

2. All recirculation loop flow and differential pressure indicators are operable.

3. Recirc/Jet Pump readings are as indicated in the provided attachment.

INITIATING CUE:

(ALL) You are directed by the Unit CRS to perform 0PT-13.1, Reactor Recirculation Jet

Pump Operability, using the data provided. Determine if the surveillance test is

completed SAT or UNSAT. Inform the Unit CRS of the results.

SURVEILLANCE

SAT UNSAT

LOT-ADM-JP-002-02 Page 3 of 37 Rev.2

SRO ONLY

The following is read ONLY after completion of the task on

page 3.

Read the following to the JPM performer.

TASK CONDITIONS:

1. Unit Two is operating at 100% power .

2. All recirculation loop flow and differential pressure indicators are operable.

3. Recirc/Jet Pump readings are as indicated in the provided attachment.

INITIATING CUE:

(SRO) Determine what actions (if any) are required based on the given conditions.

LOT-ADM-JP-002-02 Page 4 of 37 Rev.2

PERFORMANCE CHECKLIST

NOTE: Sequence is assumed unless otherwise indicated, comments required for any step evaluated as UNSAT.

TIME START: ___________

NOTE: The following steps require evaluation of curves located in 2OP-02, Attachments 4

through 17.

Step 1 - Record time of test and reactor power level.

Records current time and 100% power.

SAT/UNSAT

NOTE: The readings in steps 2 through 5 are digital readings and should not vary.

Step 2 - Obtain Recirculation Pump A Calculated Speed, Panel on P603.

Recirculation Pump A Calculated Speed determined to be 82%.

- CRITICAL STEP** SAT/UNSAT

Step 3 - Obtain Recirculation Pump B Calculated Speed, Panel on P603.

Recirculation Pump B Calculated Speed determined to be 82%.

- CRITICAL STEP** SAT/UNSAT

Step 4 - Obtain Recirculation Pump A flow on B32-FR-R614.

Recirculation Pump A flow on B32-FR-R614 determined to be 47,000 gpm.

SAT/UNSAT

Step 5 - Obtain Recirculation Pump B flow on B32-FR-R614.

Recirculation Pump B flow on B32-FR-R614 determined to be 47,000 gpm.

SAT/UNSAT

LOT-ADM-JP-002-02 Page 5 of 37 Rev.2

NOTE: The readings in steps 6 and 7 may vary slightly from student to student. Reading

should be within 1x106 lbm/hr of listed values.

Step 6 - Obtain Jet Pump Loop A flow from Flow Indicator B21-FI-R611A.

Determines Jet Pump Loop A flow is 38x106 lbm/hr (+/- 1x106 lbm/hr)

- CRITICAL STEP** SAT/UNSAT

Step 7 - Obtain Jet Pump Loop B flow from Flow Indicator B21-FI-R611B.

Determines Jet Pump Loop B flow is 38x106 lbm/hr (+/- 1x106 lbm/hr)

- CRITICAL STEP** SAT/UNSAT

Step 8 - Record the current revision number of 2OP-02, Reactor Recirculation System

Operating Procedure.

Current revision (170) of 2OP-02 recorded.

SAT/UNSAT

NOTE: The readings in step 9, 10 & 11 may vary slightly from student to student. Reading

should be within 1% of listed values.

Step 9 - Record individual jet pump % psid.

Records the following values (+/- 1%):

JP 1 @ 31% JP 11 @ 37%

JP 2 @ 31% JP 12 @ 36%

JP 3 @ 40% JP 13 @ 35%

JP 4 @ 33% JP 14 @ 36%

JP 5 @ 40% JP 15 @ 40%

JP 6 @ 35% JP 16 @ 41%

JP 7 @ 32% JP 17 @ 37%

JP 8 @ 32% JP 18 @ 34%

JP 9 @ 34% JP 19 @ 34%

JP 10 @ 32% JP 20 @ 37%

- CRITICAL STEP** SAT/UNSAT

LOT-ADM-JP-002-02 Page 6 of 37 Rev.2

Step 10 - Determine Loop A average % psid.

Loop A average % psid is 34.0% psid (acceptable range 33.0% - 35.0%).

- CRITICAL STEP** SAT/UNSAT

Step 11 - Determine Loop B average % psid.

Loop B average % psid is 36.7% psid (acceptable range 35.7% - 37.7%).

- CRITICAL STEP** SAT/UNSAT

Step 12 - Compare the % psid for each jet pump and calculated average jet pump% psid for

each loop with the established curves.

Determines Jet Pump #3 is UNSAT.

- CRITICAL STEP** SAT/UNSAT

Step 13 - Notify CRS that PT-13.1, Jet Pump Performance is completed UNSAT due to Jet

Pump #3 being out of range and Recirc Loop B.

Determines Jet Pump #3 and Recirc Loop B readings are 87 UNSAT.

SAT/UNSAT

TERMINATING CUE: When examinee has evaluated jet pump operability per 0PT-13.1 this

JPM is complete.

NOTE: SROs will be given the SRO only CUE upon completion of Step 13.

TIME COMPLETED: _____________

COLLECT AND CONTROL ALL JPM EXAM MATERIALS FOR EXAM SECURITY.

LOT-ADM-JP-002-02 Page 7 of 37 Rev.2

NOTE: This portion of the JPM is based on the presumption that the SRO determined the

surveillance was unsat with the jet pump #3 inop. If SRO did not determine that the

jet pump was inop, provide this additional cue: Assuming the surveillance was

unsat due to an inop jet pump, determine what actions (if any) are required.

Step 14 (SRO ONLY) -Determine appropriate Tech Spec actions.

Determines Condition A of TS 3.4.2 is entered with a required action and

completion time of MODE 3 in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ..

- CRITICAL STEP** SAT/UNSAT

TERMINATING CUE: When examinee has determined the required action, this JPM is

complete.

TIME COMPLETED: _____________

COLLECT AND CONTROL ALL JPM EXAM MATERIALS FOR EXAM SECURITY.

Step Critical / Not Critical Reason

1 Not Critical Not necessary to determine if surveillance is SAT

2 Critical Necessary to determine if surveillance is SAT

3 Critical Necessary to determine if surveillance is SAT

4 Not Critical Transposition of digital number from gauge

5 Not Critical Transposition of digital number from gauge

6 Critical Necessary to determine if surveillance is SAT

7 Critical Necessary to determine if surveillance is SAT

8 Not Critical Administrative

9 Critical Necessary to determine if surveillance is SAT

10 Critical Necessary to determine if surveillance is SAT

11 Critical Necessary to determine if surveillance is SAT

12 Critical Necessary to determine if surveillance is SAT

13 Not Critical Communication

14 Critical TS required action

LOT-ADM-JP-002-02 Page 8 of 37 Rev.2

WORK PRACTICES:

Comments are required for any step evaluated as UNSAT

A. CORE 4 SAT/ UNSAT/ NE

1. Task Preview / Pre-Job Briefs

2. Take-A-Minute

3. Correct Component Verification (CCV), Validate

Assumptions

4. Procedure and Work Instruction Use and Adherence

(PU&A)

B. Communications (proper content, repeat backs, 3 step SAT/ UNSAT/ NE

communications, etc.)

C. STAR (Use of Stop, Think, Act, Review) SAT/ UNSAT/ NE

D. Peer Checking (if performer requests or discusses peer checking) SAT/ UNSAT/ NE

E. Proper Equipment Use (observe starting limitations, throttle valve SAT/ UNSAT/ NE

closures, etc.)

F. Safety Compliance (use of PPE, knowledge of safety equipment, SAT/ UNSAT/ NE

etc.)

G. Electrical Safety And Arc Flash Protection Compliance (refer to SAT/ UNSAT/ NE

AD-HS-ALL-0110, as applicable)

H. Security Compliance (controlled area entry and exit, key control, SAT/ UNSAT/ NE

etc.)

I. Proper Tool Use (proper tool for the job, calibration dates, etc.) SAT/ UNSAT/ NE

J. Radiation Protection (ALARA, understanding and use of RWP, SAT/ UNSAT/ NE

frisking, etc.)

Comments:

LOT-ADM-JP-002-02 Page 9 of 37 Rev.2

REVISION SUMMARY

2 Step 1 is now in alignment with PT

Step 9 is now a CT, necessary to complete JPM

Added KEY.

Added picture for RR speed

1 Formatting changes to match the JPM template, revision 3.

Validated using 0PT-13.1 Reactor Recirculation Jet Pump Operability

revision 44 and 2OP-02 Reactor Recirculation System Operating

Procedure revision 161.

Added attachment that includes photos to enable being performed in

classroom.

Added Duke Energy Progress image to cover page.

Updated work practices to current plant expectations.

Removed Step 1 which was obtaining the procedure (it is given to

them).

0 Was accidentally shredded

(Provide sufficient detail for reviewers and evaluators to understand the scope of any

technical and/or administrative changes).

LOT-ADM-JP-002-02 Page 10 of 37 Rev.2

- - - - EXAM KEY**********

DO NOT DISTRIBUTE

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LOT-ADM-JP-002-02 Page 28 of 37 Rev.2

Validation Time: 30 Minutes (approximate).

Time Taken: ____ Minutes

APPLICABLE METHOD OF TESTING

Performance: Simulate Actual X Unit: N/A

Setting: In-Plant Simulator Admin X

Time Critical: Yes No X Time Limit N/A

Alternate Path: Yes No X

EVALUATION

Performer:

JPM: Pass Fail

Remedial Training Required: Yes No

Comments:

Comments reviewed with Performer

Evaluator Signature: Date:

LOT-ADM-JP-002-02 Page 29 of 37 Rev.2

Page 30 of 37

Page 31 of 37

Page 32 of 37

Page 33 of 37

Page 34 of 37

Page 35 of 37

TASK CONDITIONS:

1. Unit Two is operating at 100% power .

2. All recirculation loop flow and differential pressure indicators are operable.

3. Recirc/Jet Pump readings are as indicated in the provided attachment.

INITIATING CUE:

You are directed by the Unit CRS to perform 0PT-13.1, Reactor Recirculation Jet Pump

Operability, using the data provided. Determine if the surveillance test is completed SAT

or UNSAT. Inform the Unit CRS of the results.

SURVEILLANCE

SAT UNSAT

Page 36 of 37

SRO ONLY

TASK CONDITIONS:

1. Unit Two is operating at 100% power .

2. All recirculation loop flow and differential pressure indicators are operable.

3. Recirc/Jet Pump readings are as indicated in the provided attachment.

INITIATING CUE:

(SRO) Determine what actions (if any) are required based on the given conditions.

Page 37 of 37

DUKE ENERGY

BRUNSWICK TRAINING SECTION

LESSON TITLE: DC Ground Calculation

LESSON NUMBER: AOT-ADM-JP-051-07

REVISION NO: 0

Phil Capehart 03/13/17

PREPARER / DATE

Daniel Hulgin 03/13/17

TECHNICAL REVIEWER / DATE

Shawn Zander 04/18/17

David Rutland 04/18/17

VALIDATOR / DATE

Craig Oliver 05/24/17

LINE SUPERVISOR / DATE

Ed Rau 05/24/17

TRAINING SUPERVISION APPROVAL / DATE

AOT-ADM-JP-051-07 Page 1 of 10 Rev.0

RELATED TASKS:

263613B104 Perform DC Ground Isolation For Bus P, N, And P/N Per 1(2)OP-51

K/A REFERENCE AND IMPORTANCE RATING:

263000 A4.04 3.0/3.2

Ability to manually operate and/or monitor in the control room - ground detection circuit.

REFERENCES:

2OP-51 DC Electrical System Operating Procedure:

Section 6.3.1 DC Ground Isolation For Bus P, N, and PN

Attachment 4 Data Sheet for Battery Ground Detection.

AI-115 125/250 VDC System Ground Correction Guidelines

TOOLS AND EQUIPMENT:

Calculator

ADMINISTRATIVE CATEGORY (from NUREG 1123, Rev. 2, Supp. 1):

Generic 2.1 - Conduct Of Operations

SETUP INSTRUCTIONS

N/A Admin JPM

AOT-ADM-JP-051-07 Page 2 of 10 Rev.0

SAFETY CONSIDERATIONS:

1. None.

EVALUATOR NOTES: (Do not read to performer)

1. The applicable procedure section WILL be provided to the trainee.

2. Prior to the first JPM of the JPM set, provide the JPM briefing contained in NUREG-1021,

Appendix E, or similar briefing (for non-regulated exams) to the trainee(s).

Read the following to the JPM performer.

TASK CONDITIONS:

1. The Control Room has received annunciation of grounds.

2. 2OP-51, DC ELECTRICAL SYSTEM OPERATING PROCEDURE, Section 6.3.1,DC

Ground Isolation For Bus P, N, and PN, is complete through step 6.3.1.14.

3. Another operator has determined the following:

Switchboard P BUS PN BUS N BUS

Switchboard 2A 1.8 mA 0.08 mA 2.2 mA

Switchboard 2B 1.7 mA 0.12 mA 1.8 mA

4. Battery chargers 2A-1, 2A-2, 2B-1 and 2B-2 are ALL in FLOAT

INITIATING CUE:

You are directed by the CRS to:

Continue performance of 2OP-51, Section 6.3.1 by performing the calculations to

determine the total resistance to ground for 125/250 VDC Battery Switchboard 2A and

125/250 VDC Battery Switchboard 2B.

Determine the Action Level for the grounds based on the given conditions.

Switchboard 2A Action Level Switchboard 2B Action Level

AOT-ADM-JP-051-07 Page 3 of 10 Rev.0

PERFORMANCE CHECKLIST

NOTE: Sequence is assumed unless otherwise indicated, comments required for any step evaluated as UNSAT.

Step 1 - Obtain current revision of 2OP-51 Section 6.3.1 and Attachment 4.

Current revision of 2OP-51 Section 6.3.1and Attachment 4 obtained

SAT/UNSAT

TIME START: ___________

NOTE: Candidate may choose to record voltages and perform the calculations in any order.

Step 2 - Record voltage for Battery Chargers as appropriate on attachment 4.

Voltage for each charger is recorded as 135VDC on attachment 4

SAT/UNSAT

Step 3 - Perform calculation for Switchboard 2A on attachment 4.

Switchboard 2A resistance is calculated as 17.5 K (+/-.5K)

- CRITICAL STEP** SAT/UNSAT

Step 4 - Perform calculation for Switchboard 2B on attachment 4.

Switchboard 2A resistance is calculated as 27.1 K (+/-.5K)

- CRITICAL STEP** SAT/UNSAT

Step 5 - Determine appropriate actions for Switchboard 2A.

Determines Switchboard 2A resistance is < 25 K, and this meets the

requirement for Action Level 1 IAW 0AI-115.

- CRITICAL STEP** SAT/UNSAT

Step 5 - Determine appropriate actions for Switchboard 2B.

Determines Switchboard 2A resistance is >25 K, and this meets the

requirement for Action Level 0 IAW 0AI-115..

- CRITICAL STEP** SAT/UNSAT

AOT-ADM-JP-051-07 Page 4 of 10 Rev.0

TERMINATING CUE: Required performance information is included in the given conditions.

Determine grounds and determine action levels.

TIME COMPLETED: _____________

COLLECT AND CONTROL ALL JPM EXAM MATERIALS FOR EXAM SECURITY.

Step Critical / Not Critical Reason

1 Not Critical Administrative

2 Not Critical Not critical- due to not being the final calculation.

3 Critical Ground determination is critical

4 Critical Ground determination is critical

5 Critical Action level is critical.

6 Critical Action level is critical.

AOT-ADM-JP-051-07 Page 5 of 10 Rev.0

WORK PRACTICES:

Comments are required for any step evaluated as UNSAT

A. CORE 4 SAT/ UNSAT/ NE

1. Task Preview / Pre-Job Briefs

2. Take-A-Minute

3. Correct Component Verification (CCV), Validate

Assumptions

4. Procedure and Work Instruction Use and Adherence

(PU&A)

B. Communications (proper content, repeat backs, 3 step SAT/ UNSAT/ NE

communications, etc.)

C. STAR (Use of Stop, Think, Act, Review) SAT/ UNSAT/ NE

D. Peer Checking (if performer requests or discusses peer checking) SAT/ UNSAT/ NE

E. Proper Equipment Use (observe starting limitations, throttle valve SAT/ UNSAT/ NE

closures, etc.)

F. Safety Compliance (use of PPE, knowledge of safety equipment, SAT/ UNSAT/ NE

etc.)

G. Electrical Safety And Arc Flash Protection Compliance (refer to SAT/ UNSAT/ NE

AD-HS-ALL-0110, as applicable)

H. Security Compliance (controlled area entry and exit, key control, SAT/ UNSAT/ NE

etc.)

I. Proper Tool Use (proper tool for the job, calibration dates, etc.) SAT/ UNSAT/ NE

J. Radiation Protection (ALARA, understanding and use of RWP, SAT/ UNSAT/ NE

frisking, etc.)

Comments:

AOT-ADM-JP-051-07 Page 6 of 10 Rev.0

REVISION SUMMARY

0 JPM Modified from AOT-ADM-JP-051-05 Rev3.

(Provide sufficient detail for reviewers and evaluators to understand the scope of any

technical and/or administrative changes).

AOT-ADM-JP-051-07 Page 7 of 10 Rev.0

AOT-ADM-JP-051-07 Page 8 of 10 Rev.0

Validation Time: 10 Minutes (approximate).

Time Taken: ____ Minutes

APPLICABLE METHOD OF TESTING

Performance: Simulate Actual X Unit: N/A

Setting: In-Plant Simulator Admin X

Time Critical: Yes No X Time Limit N/A

Alternate Path: Yes No X

EVALUATION

Performer:

JPM: Pass Fail

Remedial Training Required: Yes No

Comments:

Comments reviewed with Performer

Evaluator Signature: Date:

AOT-ADM-JP-051-07 Page 9 of 10 Rev.0

TASK CONDITIONS:

1. The Control Room has received annunciation of grounds.

2. 2OP-51, DC ELECTRICAL SYSTEM OPERATING PROCEDURE, Section 6.3.1,DC

Ground Isolation For Bus P, N, and PN, is complete through step 6.3.1.14.

3. Another operator has determined the following:

Switchboard P BUS PN BUS N BUS

Switchboard 2A 1.8 mA 0.08 mA 2.2 mA

Switchboard 2B 1.7 mA 0.12 mA 1.8 mA

4. Battery chargers 2A-1, 2A-2, 2B-1 and 2B-2 are ALL in FLOAT

INITIATING CUE:

You are directed by the CRS to:

Continue performance of 2OP-51, Section 6.3.1 by performing the calculations to

determine the total resistance to ground for 125/250 VDC Battery Switchboard 2A and

125/250 VDC Battery Switchboard 2B.

Determine the Action Level for the grounds based on the given conditions.

Switchboard 2A Action Level Switchboard 2B Action Level

Page 10 of 10

DUKE ENERGY

BRUNSWICK TRAINING SECTION

LESSON TITLE: Determine If Electrical Loading Is Within The Limits

(SRO ONLY)

LESSON NUMBER: LOT-SIM-JP-201-D08

REVISION NO: 0

Phil Capehart 03/13/17

PREPARER / DATE

Daniel Hulgin 03/13/17

TECHNICAL REVIEWER / DATE

Mike Long 05/05/17

John Carol 05/05/17

VALIDATOR / DATE

Craig Oliver 05/24/17

LINE SUPERVISOR / DATE

Ed Rau 05/24/17

TRAINING SUPERVISION APPROVAL / DATE

LOT-SIM-JP-201-D08 Page 1 of 11 Rev.0

RELATED TASKS:

341224B102 Determine actions required for Limiting Conditions for Operation per 0OI-

01.01, Technical Specifications, and the TRM

K/A REFERENCE AND IMPORTANCE RATING:

262001 A2.10 Ability to (a) predict the impacts of the following on the A.C. ELECTRICAL

DISTRIBUTION ; and (b) based on those predictions, use procedures to

correct, control, or mitigate the consequences of those abnormal conditions

or operations: Exceeding current limitations. (CFR: 41.5 / 45.6)

2.9/3.4

REFERENCES:

2OI-03.2, Reactor Operator Daily Surveillance Report

Unit Two Technical Specifications

TOOLS AND EQUIPMENT:

Classroom or U2 simulator

Calculator

SAFETY FUNCTION (from NUREG 1123, Rev. 2, Supp. 1):

Safety Function 6, Electrical (A.C. Electrical Distribution)

SETUP INSTRUCTIONS

If setting up for simulator:

IC: IC-13

Rx. Pwr: 100%

Core Age: MOC

2B RHR Pump/2B RHRSW booster pump running in torus cooling, 3 condensate pumps

running, 4CWIPs running. Both NSW pumps running.

OR

Ensure applicable ammeters are reading as follows: 1700 amps for C, 1800 amps for D,

and Common B 150 amps.

LOT-SIM-JP-201-D08 Page 2 of 11 Rev.0

SAFETY CONSIDERATIONS:

1. None

EVALUATOR NOTES: (Do not read to performer)

1. The applicable procedure section WILL be provided to the trainee.

2. Prior to the first JPM of the JPM set, provide the JPM briefing contained in NUREG-1021,

Appendix E, or similar briefing (for non-regulated exams) to the trainee(s).

3. This JPM may be performed on Unit 2 simulator or classroom as selected by the evaluator.

4. Critical Step Basis

a) Prevents Task Completion

b) May Result in Equipment Damage

c) Affects Public Health and Safety

d) Could Result in Personal Injury

Read the following to the JPM performer.

TASK CONDITIONS:

1. You are a Unit Two Reactor Operator.

2. The fourth Circulating Water Intake Pump has been started on Unit Two IAW 2OP-

29.0.

3. Buses Common A and B are being supplied by their respective units.

4. Unit Two is in MODE 1

5. The Process Computer is unavailable.

INITIATING CUE:

You are directed by the Unit CRS to determine if electrical loading is within the limits

established in 2OI-03.2, Reactor Operator Daily Surveillance Report (RODSR), and report all

required actions (if any) for Unit Two.

LOT-SIM-JP-201-D08 Page 3 of 11 Rev.0

PERFORMANCE CHECKLIST

NOTE: Sequence is assumed unless otherwise indicated, comments required for any step evaluated as UNSAT.

Step 1 - Obtain current revision of 2OI-03.2.

Current revision of 2OI-03.2 obtained.

SAT/UNSAT

TIME START: ___________

NOTE: Steps can be performed out of given sequence.

Step 2 - Determine applicable loading limit IAW RODSR.

Determines Item No.16, Unit 2 Dayshift, is applicable with a total allowed

amperage from Buses 2C, 2D, and Common B required to be 3550 amps.

- CRITICAL STEP** SAT/UNSAT

Step 3 - Determine applicable instrumentation IAW Note S.

Determines correct ammeters for checking bus amps are on XU-2.

SAT/UNSAT

Step 4 - Obtain amperage for Buses 2C.

Determines Bus 2C amperage is 1700 amps (+/- 25 amps).

- CRITICAL STEP** SAT/UNSAT

Step 5 - Obtain amperage for Bus 2D.

Determines Bus 2D amperage is 1800 amps (+/- 25 amps).

- CRITICAL STEP** SAT/UNSAT

LOT-SIM-JP-201-D08 Page 4 of 11 Rev.0

Step 6 - Obtain amperage for Bus Common B .

Determines Bus Common B amperage is 150 amps (+/- 25 amps).

- CRITICAL STEP** SAT/UNSAT

Step 7 - Calculate total amperes for Buses 2C, 2D, and Common B.

Determines total amperes for Buses 2C, 2D, and Common B is 3650 amps (+/-

50 amps) e.g. 1700a+1800a+150a=3650a

- CRITICAL STEP** SAT/UNSAT

Step 8 - Determine if total amperage has exceeded allowed limit.

Determines total amperes for Buses 2C, 2D, and Common B at 3650 amps (+/-

50 amps) is greater than allowed limit of 3550 amps.

- CRITICAL STEP** SAT/UNSAT

Step 9 - Determine status of offsite sources IAW Note T.

Determines both off site power sources are declared inoperable.

SAT/UNSAT

Step 10 - Determine all applicable action and completion time for exceeding the allowable load

limit IAW Unit Two Tech Specs.

Determines LCO 3.8.1 Condition C and E actions are required.

- CRITICAL STEP** SAT/UNSAT

TERMINATING CUE: Required performance information is included in the given conditions.

Determine if electrical loading is within the limits and report the required

actions Unit 2.

TIME COMPLETED: _____________

LOT-SIM-JP-201-D08 Page 5 of 11 Rev.0

COLLECT AND CONTROL ALL JPM EXAM MATERIALS FOR EXAM SECURITY.

Step Critical / Not Critical Reason

1 Not Critical Administrative

2 Critical Load limit necessary for completion

3 Not Critical Note not necessary to be referenced

4 Critical Necessary for total amperage calculation

5 Critical Necessary for total amperage calculation

6 Critical Necessary for total amperage calculation

7 Critical Total amperage needed for comparison with allowed limit

8 Critical Comparison necessary for required action

9 Not Critical Note not necessary to be referenced

10 Critical TS required actions are necessary

LOT-SIM-JP-201-D08 Page 6 of 11 Rev.0

WORK PRACTICES:

Comments are required for any step evaluated as UNSAT

A. CORE 4 SAT/ UNSAT/ NE

1. Task Preview / Pre-Job Briefs

2. Take-A-Minute

3. Correct Component Verification (CCV), Validate

Assumptions

4. Procedure and Work Instruction Use and Adherence

(PU&A)

B. Communications (proper content, repeat backs, 3 step SAT/ UNSAT/ NE

communications, etc.)

C. STAR (Use of Stop, Think, Act, Review) SAT/ UNSAT/ NE

D. Peer Checking (if performer requests or discusses peer checking) SAT/ UNSAT/ NE

E. Proper Equipment Use (observe starting limitations, throttle valve SAT/ UNSAT/ NE

closures, etc.)

F. Safety Compliance (use of PPE, knowledge of safety equipment, SAT/ UNSAT/ NE

etc.)

G. Electrical Safety And Arc Flash Protection Compliance (refer to SAT/ UNSAT/ NE

AD-HS-ALL-0110, as applicable)

H. Security Compliance (controlled area entry and exit, key control, SAT/ UNSAT/ NE

etc.)

I. Proper Tool Use (proper tool for the job, calibration dates, etc.) SAT/ UNSAT/ NE

J. Radiation Protection (ALARA, understanding and use of RWP, SAT/ UNSAT/ NE

frisking, etc.)

Comments:

LOT-SIM-JP-201-D08 Page 7 of 11 Rev.0

REVISION SUMMARY

0 Original JPM, modified from LOT-SIM-JP-201-D07

(Provide sufficient detail for reviewers and evaluators to understand the scope of any

technical and/or administrative changes).

LOT-SIM-JP-201-D08 Page 8 of 11 Rev.0

Validation Time: 15 Minutes (approximate).

Time Taken: ____ Minutes

APPLICABLE METHOD OF TESTING

Performance: Simulate X Actual Unit: 2

Setting: In-Plant Simulator X Admin

Time Critical: Yes No X Time Limit N/A

Alternate Path: Yes No X

EVALUATION

Performer:

JPM: Pass Fail

Remedial Training Required: Yes No

Comments:

Comments reviewed with Performer

Evaluator Signature: Date:

LOT-SIM-JP-201-D08 Page 9 of 11 Rev.0

TASK CONDITIONS:

1. You are a Unit Two Reactor Operator.

2. The fourth Circulating Water Intake Pump has been started on Unit Two IAW 2OP-

29.0.

3. Buses Common A and B are being supplied by their respective units.

4. Unit Two is in MODE 1

5. The Process Computer is unavailable.

INITIATING CUE:

You are directed by the Unit CRS to determine if electrical loading is within the limits

established in 2OI-03.2, Reactor Operator Daily Surveillance Report (RODSR), and report all

required actions (if any) for Unit Two.

Page 10 of 11

Page 11 of 11

DUKE ENERGY

BRUNSWICK TRAINING SECTION

LESSON TITLE: Develop a Clearance Boundary - 2A TBCCW Pump

LESSON NUMBER: LOT-ADM-JP-201-E05

REVISION NO: 0

Phil Capehart 03/13/17

PREPARER / DATE

Daniel Hulgin 03/13/17

TECHNICAL REVIEWER / DATE

Shawn Zander 04/18/17

David Rutland 04/18/17

VALIDATOR / DATE

Craig Oliver 05/24/17

LINE SUPERVISOR / DATE

Ed Rau 05/24/17

TRAINING SUPERVISION APPROVAL / DATE

LOT-ADM-JP-201-E05 Page 1 of 11 Rev.0

RELATED TASKS:

299020B301

Develop a Clearance Per AD-OP-ALL-0200, Clearance and Tagging

K/A REFERENCE AND IMPORTANCE RATING:

2.2.13 (4.1/4.3)

Knowledge of tagging and clearance procedures

REFERENCES:

AD-OP-ALL-0200

2OP-44 Turbine Building Closed Cooling Water System Operating Procedure

D-02033-SH0001A

TOOLS AND EQUIPMENT:

None

SAFETY FUNCTION (from NUREG 1123, Rev. 2, Supp. 1):

Admin - Equipment Control

SETUP INSTRUCTIONS

(Specify, as applicable)

LOT-ADM-JP-201-E05 Page 2 of 11 Rev.0

SAFETY CONSIDERATIONS:

1. None

EVALUATOR NOTES: (Do not read to performer)

1. The applicable procedure section WILL be provided to the trainee.

2. Prior to the first JPM of the JPM set, provide the JPM briefing contained in NUREG-1021,

Appendix E, or similar briefing (for non-regulated exams) to the trainee(s).

Read the following to the JPM performer.

TASK CONDITIONS:

1. You are an operator in the Work Control Center. eSOMS is off-line. No historical

clearances are available for review.

2. A clearance has been requested by maintenance to place the TBCCW Pump 2A under

clearance for pump packing replacement.

3. The TBCCW Pumps 2B and 2C are in service on Unit Two.

4. Hanging the clearance will not result in any radiation dose.

5. The next available serial number is 17-0020.

6. Barrels are staged for collection of any drainage.

INITIATING CUE:

You are directed to propose a Clearance Boundary for TBCCW Pump 2A by completing

Attachment 21 page 2 of AD-OP-ALL-0200, Clearance and Tagging. Clearance removal will be

developed by another operator.

LOT-ADM-JP-201-E05 Page 3 of 11 Rev.0

- - - - EXAM KEY DO NOT DISTRIBUTE*******************************

- - - - EXAM KEY DO NOT DISTRIBUTE*******************************

LOT-ADM-JP-201-E05 Page 4 of 11 Rev.0

PERFORMANCE CHECKLIST

NOTE: Sequence is assumed unless otherwise indicated, comments required for any step evaluated as UNSAT.

NOTE: The examiner should provide a copy AD-OP-ALL-0200 and two blank copies of

Attachment 21 page 2 of AD-OP-ALL-0200 to the examinee.

NOTE: The examiner should provide a copy of the required print (D-02033-SH0001A) and

0OP-44 to the applicant.

TIME START: ___________

NOTE: CITs can have position OFF or In-Place / HUNG

Step 1 - Identify control switch for TBCCW Pump 2A should be placed to OFF.

Determine 2A Control Switch CS-423 should be placed to OFF.

SAT/UNSAT

Step 2 - Identify breaker 2-2TJ-MF1-52 on MCC-2TJ should be DANGER tagged to OFF.

Determine 2-2TJ-MF1-52 on MCC-2TJ RED/CIT tagged OFF.

- CRITICAL STEP** SAT/UNSAT

NOTE: Sequence of suction or discharge valve closing is not critical so long as the pump

motor is de-energized.

Step 3 - Identify TBCCW Pump 2A Discharge Valve, 2-TCC-V11, should be DANGER tagged

closed.

Determine 2-TCC-V11 should be RED tagged closed.

- CRITICAL STEP** SAT/UNSAT

Step 4 - Identify TBCCW Pump 2A Suction Valve, 2-TCC-V5, should be DANGER tagged

closed.

Determine 2-TCC-V5 should be RED tagged closed.

- CRITICAL STEP** SAT/UNSAT

LOT-ADM-JP-201-E05 Page 5 of 11 Rev.0

NOTE: Sequence of drain or vent valve opening is not critical.

NOTE: May note in details tab that drains are to be routed to barrels or suitable collection.

Step 5 - Identify TBCCW Pump 2A Casing Drain Valve, 2-TCC-V254, should be open.

Determine 2-TCC-V254 should be open.

- CRITICAL STEP** SAT/UNSAT

Step 6 - Identify TBCCW Pump 2A Vent Valve, 2-TCC-V251, should be open.

Determine 2-TCC-V251 should be open.

- CRITICAL STEP** SAT/UNSAT

NOTE: IV is not critical for CIT.

Step 7 - Identifies that Independent Verification is required.

Determine verification required for clearance steps.

SAT/UNSAT

Step 8 - Submit proposed boundary to WCC SRO.

Proposed boundary submitted to WCC SRO.

SAT/UNSAT

TERMINATING CUE: When the clearance boundary has been submitted, this JPM is

complete.

TIME COMPLETED: _____________

COLLECT AND CONTROL ALL JPM EXAM MATERIALS FOR EXAM SECURITY.

LOT-ADM-JP-201-E05 Page 6 of 11 Rev.0

Step Critical / Not Critical Reason

1 Not Critical Not an isolation boundary

2 Critical Isolation boundary

3 Critical Isolation boundary

4 Critical Isolation boundary

5 Critical Necessary for energy release

6 Critical Necessary for energy release

7 Not Critical Administrative

8 Not Critical Administrative

LOT-ADM-JP-201-E05 Page 7 of 11 Rev.0

WORK PRACTICES:

Comments are required for any step evaluated as UNSAT

A. CORE 4 SAT/ UNSAT/ NE

1. Task Preview / Pre-Job Briefs

2. Take-A-Minute

3. Correct Component Verification (CCV), Validate

Assumptions

4. Procedure and Work Instruction Use and Adherence

(PU&A)

B. Communications (proper content, repeat backs, 3 step SAT/ UNSAT/ NE

communications, etc.)

C. STAR (Use of Stop, Think, Act, Review) SAT/ UNSAT/ NE

D. Peer Checking (if performer requests or discusses peer checking) SAT/ UNSAT/ NE

E. Proper Equipment Use (observe starting limitations, throttle valve SAT/ UNSAT/ NE

closures, etc.)

F. Safety Compliance (use of PPE, knowledge of safety equipment, SAT/ UNSAT/ NE

etc.)

G. Electrical Safety And Arc Flash Protection Compliance (refer to SAT/ UNSAT/ NE

AD-HS-ALL-0110, as applicable)

H. Security Compliance (controlled area entry and exit, key control, SAT/ UNSAT/ NE

etc.)

I. Proper Tool Use (proper tool for the job, calibration dates, etc.) SAT/ UNSAT/ NE

J. Radiation Protection (ALARA, understanding and use of RWP, SAT/ UNSAT/ NE

frisking, etc.)

Comments:

LOT-ADM-JP-201-E05 Page 8 of 11 Rev.0

REVISION SUMMARY

0 Initial Revision - New JPM Modified from LOT-ADM-JP-201-E04

(Provide sufficient detail for reviewers and evaluators to understand the scope of any

technical and/or administrative changes).

LOT-ADM-JP-201-E05 Page 9 of 11 Rev.0

Validation Time: 30 Minutes (approximate).

Time Taken: ____ Minutes

APPLICABLE METHOD OF TESTING

Performance: Simulate Actual X Unit: 2

Setting: In-Plant Simulator Admin X

Time Critical: Yes No X Time Limit N/A

Alternate Path: Yes No X

EVALUATION

Performer:

JPM: Pass Fail

Remedial Training Required: Yes No

Comments:

Comments reviewed with Performer

Evaluator Signature: Date:

LOT-ADM-JP-201-E05 Page 10 of 11 Rev.0

TASK CONDITIONS:

1. You are an operator in the Work Control Center. eSOMS is off-line. No historical

clearances are available for review.

2. A clearance has been requested by maintenance to place the TBCCW Pump 2A under

clearance for pump packing replacement.

3. The TBCCW Pumps 2B and 2C are in service on Unit Two.

4. Hanging the clearance will not result in any radiation dose.

5. The next available serial number is 17-0020.

6. Barrels are staged for collection of any drainage.

INITIATING CUE:

You are directed to propose a Clearance Boundary for TBCCW Pump 2A by completing

Attachment 21 page 2 of AD-OP-ALL-0200, Clearance and Tagging. Clearance removal will be

developed by another operator.

Page 11 of 11

DUKE ENERGY

BRUNSWICK TRAINING SECTION

LESSON TITLE: Determine Post Maintenance Testing Requirements

LESSON NUMBER: LOT-OJT-JP-201-E-05

REVISION NO: 0

Phil Capehart 03/13/17

PREPARER / DATE

Daniel Hulgin 03/13/17

TECHNICAL REVIEWER / DATE

Brian West 04/18/17

M Long 05/05/17

VALIDATOR / DATE

Craig Oliver 05/24/17

LINE SUPERVISOR / DATE

Ed Rau 05/24/17

TRAINING SUPERVISION APPROVAL / DATE

LOT-OJT-JP-201-E-05 Page 1 of 10 Rev.0

RELATED TASKS:

342013B302 Determine PMT Requirements Following Maintenance Activities per 0PLP-

20 and AD-WC-ALL-0250

K/A REFERENCE AND IMPORTANCE RATING:

Generic 2.2.21 Knowledge of pre- and post-maintenance operability requirements.

RO 2.9 SRO 4.1

REFERENCES:

0PLP-20, Post-Maintenance Testing Program

1OP-21, Reactor Building Closed Cooling Water System Operating Procedure

TOOLS AND EQUIPMENT:

None

SAFETY FUNCTION (from NUREG 1123, Rev. 2, Supp. 1):

3 - Equipment Control

SETUP INSTRUCTIONS

None

LOT-OJT-JP-201-E-05 Page 2 of 10 Rev.0

SAFETY CONSIDERATIONS:

1. None.

EVALUATOR NOTES: (Do not read to performer)

1. For Licensed personnel, provide memory stick with POM documents and access to non-network

computer.

2. If this is the first JPM of the JPM set, read the JPM briefing contained NUREG 1021, Appendix E,

or similar to the trainee.

3. This JPM may be administered in the simulator, control room, or classroom setting.

Read the following to the JPM performer.

TASK CONDITIONS:

1. 1-RCC-V1, FP HX 1A Outlet Valve, has been removed from the system, and a

replacement valve has been installed.

INITIATING CUE:

You are directed to determine the Post Maintenance Testing Requirements for

1-RCC-V1, FP HX 1A Outlet Valve, maintenance.

List the post maintenance testing requirements for the valve only:

LOT-OJT-JP-201-E-05 Page 3 of 10 Rev.0

PERFORMANCE CHECKLIST

NOTE: Sequence is not essential to completing the task, comments required for any step evaluated as UNSAT.

TIME START: ___________

Step 1 - Obtain a copy of 0PLP-20.

Obtains a copy of 0PLP-20.

SAT/UNSAT

Step 2 - Identifies that 1-RCC-V1 is a manual valve and goes to attachment 19.

References attachment 19.

SAT/UNSAT

Step 3 - Identifies from Attachment 19 that 1-RCC-V1 was replaced and condition A is

applicable.

Identifies that valve was replaced.

SAT/UNSAT

Step 4 - Identifies that Post maintenance Tests 1, 2, and 5 are required.

Identifies that the following tests are required:

During the tests, visually observe the valve to verify proper operation, positive

isolation, and that no packing or external leakage exists.(*CRITICAL)

Exercise (stroke) check. (*CRITICAL)

Seat leakage test (if limits are specified). (*not Critical as limits were not

specified in cue).

- CRITICAL STEP** SAT/UNSAT

LOT-OJT-JP-201-E-05 Page 4 of 10 Rev.0

Step 5 - Identifies that Post maintenance Test 3 is also required (since 1-RCC-V1 is a locked

throttled valve).

Identifies that the following tests are required:

For locked in position throttle valves, perform a flow verification check.

.

- CRITICAL STEP** SAT/UNSAT

TERMINATING CUE: Termination criteria in cue: Determine adequacy of PMT, and list PMT

requirements.

TIME COMPLETED: _____________

COLLECT AND CONTROL ALL JPM EXAM MATERIALS FOR EXAM SECURITY.

Step Critical / Not Critical Reason

1 Not Critical Administrative

2 Not Critical Not necessary to complete performance.

3 Not Critical Not necessary to complete performance.

4 Critical Necessary to complete performance identified in cue.

5 Critical Necessary to complete performance identified in cue.

LOT-OJT-JP-201-E-05 Page 5 of 10 Rev.0

- - - - EXAM KEY DO NOT DISTRIBUTE***********************

- - - - EXAM KEY DO NOT DISTRIBUTE***********************

LOT-OJT-JP-201-E-05 Page 6 of 10 Rev.0

WORK PRACTICES:

Comments are required for any step evaluated as UNSAT

A. CORE 4 SAT/ UNSAT/ NE

1. Task Preview / Pre-Job Briefs

2. Take-A-Minute

3. Correct Component Verification (CCV), Validate

Assumptions

4. Procedure and Work Instruction Use and Adherence

(PU&A)

B. Communications (proper content, repeat backs, 3 step SAT/ UNSAT/ NE

communications, etc.)

C. STAR (Use of Stop, Think, Act, Review) SAT/ UNSAT/ NE

D. Peer Checking (if performer requests or discusses peer checking) SAT/ UNSAT/ NE

E. Proper Equipment Use (observe starting limitations, throttle valve SAT/ UNSAT/ NE

closures, etc.)

F. Safety Compliance (use of PPE, knowledge of safety equipment, SAT/ UNSAT/ NE

etc.)

G. Electrical Safety And Arc Flash Protection Compliance (refer to SAT/ UNSAT/ NE

AD-HS-ALL-0110, as applicable)

H. Security Compliance (controlled area entry and exit, key control, SAT/ UNSAT/ NE

etc.)

I. Proper Tool Use (proper tool for the job, calibration dates, etc.) SAT/ UNSAT/ NE

J. Radiation Protection (ALARA, understanding and use of RWP, SAT/ UNSAT/ NE

frisking, etc.)

Comments:

LOT-OJT-JP-201-E-05 Page 7 of 10 Rev.0

REVISION SUMMARY

0 Initial Revision.

(Provide sufficient detail for reviewers and evaluators to understand the scope of any

technical and/or administrative changes).

LOT-OJT-JP-201-E-05 Page 8 of 10 Rev.0

Validation Time: 10 Minutes (approximate).

Time Taken: ____ Minutes

APPLICABLE METHOD OF TESTING

Performance: Simulate Actual X Unit: N/A

Setting: In-Plant Simulator Admin X

Time Critical: Yes No X Time Limit N/A

Alternate Path: Yes No X

EVALUATION

Performer:

JPM: Pass Fail

Remedial Training Required: Yes No

Comments:

Comments reviewed with Performer

Evaluator Signature: Date:

LOT-OJT-JP-201-E-05 Page 9 of 10 Rev.0

TASK CONDITIONS:

1. 1-RCC-V1, FP HX 1A Outlet Valve, has been removed from the system, and a

replacement valve has been installed.

INITIATING CUE:

You are directed to determine the Post Maintenance Testing Requirements for

1-RCC-V1, FP HX 1A Outlet Valve, maintenance.

List the post maintenance testing requirements for the valve only:

Page 10 of 10

DUKE ENERGY

BRUNSWICK TRAINING SECTION

LESSON TITLE: Determine Protective Action Recommendation (EP/PAR)

LESSON NUMBER: SOT-ADM-JP-301-A21

REVISION NO: 0

Phil Capehart 03/13/17

PREPARER / DATE

Daniel Hulgin 03/13/17

TECHNICAL REVIEWER / DATE

Brian West 04/18/17

Mike Long 05/05/17

VALIDATOR / DATE

Craig Oliver 05/24/17

LINE SUPERVISOR / DATE

Ed Rau 05/24/17

TRAINING SUPERVISION APPROVAL / DATE

SOT-ADM-JP-301-A21 Page 1 of 12 Rev.0

RELATED TASKS:

344236B502 Direct Emergency Response As Site Emergency Coordinator Following

Declaration Of A General Emergency per PEP-2.1.1.

344005B102 Recommend Protective Actions To States And Counties per PEP-2.6.28.

K/A REFERENCE AND IMPORTANCE RATING:

Generic 2.4.44 Knowledge of emergency plan protective action recommendations. (CFR:

41.10 / 41.12 / 43.5 / 45.11)

RO 2.4 SRO 4.4

REFERENCES:

0PEP-02.6.21,Emergency Communicator

0PEP-02.6.28, Off-Site Protective Action Recommendations

0PEP-02.1, Brunswick Nuclear Plant Initial Emergency Actions

TOOLS AND EQUIPMENT:

None

SAFETY FUNCTION (from NUREG 1123, Rev. 2, Supp. 1):

4 - Emergency Plan

SETUP INSTRUCTIONS

None

SOT-ADM-JP-301-A21 Page 2 of 12 Rev.0

SAFETY CONSIDERATIONS:

1. None

EVALUATOR NOTES: (Do not read to performer)

1. For Licensed personnel, provide memory stick with POM documents and access to non-network

computer. Provide attached ENF Form

2. If this is the first JPM of the JPM set, read the JPM briefing contained NUREG 1021, Appendix E,

or similar to the trainee.

3. This JPM may be administered in the simulator, control room, or classroom setting

- Ensure all Applicants have access to Plant references prior to proceeding**

Read the following to the JPM performer.

TASK CONDITIONS:

1. This is a DRILL: It is now 1300 on Thursday, July 27th 2017.

2. You are the Site Emergency Coordinator during a plant emergency.

3. The Emergency Operations Facility is not yet fully staffed.

4. You have just declared a General Emergency (EAL RG1.2) based on the following conditions:

a. Unisolable steam line break with a failure of the MSIVs to isolate after an automatic

isolation.

b. Emergency Depressurization has been performed

c. As of this time, an HP Dose Assessment has indicated > 5000 mrem thyroid CEDE at

the Site Area Boundary with the release originating from the Unit 2 Turbine Building

5. As of this time, the Control Room Emergency Coordinator has the appropriate Offsite Agencies on

the line. They are aware of the emergency and are awaiting formal reporting.

6. As of this time, the following meteorological conditions exist:

a. Wind Direction: 150o

b. Wind Speed: 10 mph

c. No precipitation forecast

d. Stability Class: C

INITIATING CUE:

You are to complete the Emergency Notification Form required following the given conditions

above.

This JPM is TIME CRITICAL.

SOT-ADM-JP-301-A21 Page 3 of 12 Rev.0

PERFORMANCE CHECKLIST

NOTE: Sequence is not essential to completing this task, comments required for any step evaluated as UNSAT.

TIME START: ___________

Step 1 - 0PEP-02.6.21, Attachment 2, ENF Line #1.

Marks DRILL.

- CRITICAL STEP** SAT/UNSAT

Step 2 - 0PEP-02.6.21, Attachment 2, ENF Line #2.

Verifies BRUNSWICK is pre-filled in

SAT/UNSAT

Step 3 - 0PEP-02.6.21, Attachment 2, ENF Line #3.

Verifies GENERAL EMERGENCY pre filled in

SAT/UNSAT

Step 4 - 0PEP-02.6.21, Attachment 2, ENF Line #4 (Ref 0PEP-02.1).

Verifies EAL RG1.2. (Not critical-pre filled in)

Marks Declaration Date 07/27/2017 1300. (**CRITICAL STEP)

Verifies Description Dose Assessment using actual meteorology indicates

doses > 1000 mrem TEDE or 5000 mrem thyroid CDE at or beyond the SITE

BOUNDARY. (Not critical-pre filled in)

- CRITICAL STEP** SAT/UNSAT

Step 5 - 0PEP-02.6.21, Attachment 2, ENF Line #5.

Marks Release IS OCCURRING.

- CRITICAL STEP** SAT/UNSAT

SOT-ADM-JP-301-A21 Page 4 of 12 Rev.0

Step 6 - 0PEP-02.6.21, Attachment 2, ENF Line #6 (Ref 0PEP-02.6.28, Attachment 2).

Marks Evacuate F, G, H, J.

Marks Shelter A, B, E.

Marks Consider the use of KI.

- CRITICAL STEP** SAT/UNSAT

Step 7 - 0PEP-02.6.21, Attachment 2, ENF Lines #7 through 11.

Use of these lines is not required for Initial Notifications. Post JPM

questioning is required if any of these items are completed.

SAT/UNSAT

Step 8 - 0PEP-02.6.21, Attachment 2, ENF Line #12.

This line may contain any applicant provided information.

N/A

Step 9 - 0PEP-02.6.21, Attachment 2, ENF Line #13.

Marks Applicant signature in Approved By line.

Marks SEC (Site Area Coordinator) as Title.

Marks Date/Time (referenced off given Date/Time).

TIME designated must be within 15 minutes of JPM start for successful

completion.

- CRITICAL STEP** SAT/UNSAT

Step 10 - 0PEP-02.6.21, Attachment 2, ENF Lines #14 and 15.

These lines may be left blank.

SAT/UNSAT

TERMINATING CUE: Completion of Emergency Notification Form .

TIME COMPLETED: _____________

COLLECT AND CONTROL ALL JPM EXAM MATERIALS FOR EXAM SECURITY.

SOT-ADM-JP-301-A21 Page 5 of 12 Rev.0

Step Critical / Not Critical Reason

1 Critical Required for SAT completion of ENF 2 Not Critical Pre-filled on ENF 3 Not Critical Pre-filled on ENF 4 Critical Required for SAT completion of ENF 5 Critical Required for SAT completion of ENF 6 Critical Required for SAT completion of ENF 7 Not Critical Not Required for SAT completion of ENF 8 Not Critical Not Required for SAT completion of ENF 9 Critical Required for SAT completion of ENF 10 Not Critical Not Required for SAT completion of ENF

SOT-ADM-JP-301-A21 Page 6 of 12 Rev.0

- - - - EXAM KEY****************

DO NOT DISTRIBUTE

- - - - EXAM KEY****************

DO NOT DISTRIBUTE

SOT-ADM-JP-301-A21 Page 7 of 12 Rev.0

WORK PRACTICES:

Comments are required for any step evaluated as UNSAT

A. CORE 4 SAT/ UNSAT/ NE

1. Task Preview / Pre-Job Briefs

2. Take-A-Minute

3. Correct Component Verification (CCV), Validate

Assumptions

4. Procedure and Work Instruction Use and Adherence

(PU&A)

B. Communications (proper content, repeat backs, 3 step SAT/ UNSAT/ NE

communications, etc.)

C. STAR (Use of Stop, Think, Act, Review) SAT/ UNSAT/ NE

D. Peer Checking (if performer requests or discusses peer checking) SAT/ UNSAT/ NE

E. Proper Equipment Use (observe starting limitations, throttle valve SAT/ UNSAT/ NE

closures, etc.)

F. Safety Compliance (use of PPE, knowledge of safety equipment, SAT/ UNSAT/ NE

etc.)

G. Electrical Safety And Arc Flash Protection Compliance (refer to SAT/ UNSAT/ NE

AD-HS-ALL-0110, as applicable)

H. Security Compliance (controlled area entry and exit, key control, SAT/ UNSAT/ NE

etc.)

I. Proper Tool Use (proper tool for the job, calibration dates, etc.) SAT/ UNSAT/ NE

J. Radiation Protection (ALARA, understanding and use of RWP, SAT/ UNSAT/ NE

frisking, etc.)

Comments:

SOT-ADM-JP-301-A21 Page 8 of 12 Rev.0

REVISION SUMMARY

0 Initial Revision.

(Provide sufficient detail for reviewers and evaluators to understand the scope of any

technical and/or administrative changes).

SOT-ADM-JP-301-A21 Page 9 of 12 Rev.0

Validation Time: 12 Minutes (approximate).

Time Taken: ____ Minutes

APPLICABLE METHOD OF TESTING

Performance: Simulate Actual X Unit: N/A

Setting: In-Plant Simulator Admin X

Time Critical: Yes No X Time Limit 15 min

Alternate Path: Yes No X

EVALUATION

Performer:

JPM: Pass Fail

Remedial Training Required: Yes No

Comments:

Comments reviewed with Performer

Evaluator Signature: Date:

SOT-ADM-JP-301-A21 Page 10 of 12 Rev.0

This JPM is TIME CRITICAL.

TASK CONDITIONS:

1. This is a DRILL: It is now 1300 on Thursday, July 27th 2017.

2. You are the Site Emergency Coordinator during a plant emergency.

3. The Emergency Operations Facility is not yet fully staffed.

4. You have just declared a General Emergency (EAL RG1.2) based on the following conditions:

a. Unisolable steam line break with a failure of the MSIVs to isolate after an automatic

isolation.

b. Emergency Depressurization has been performed

c. As of this time, an HP Dose Assessment has indicated > 5000 mrem thyroid CEDE at

the Site Area Boundary with the release originating from the Unit 2 Turbine Building

5. As of this time, the Control Room Emergency Coordinator has the appropriate Offsite Agencies on

the line. They are aware of the emergency and are awaiting formal reporting.

6. As of this time, the following meteorological conditions exist:

a. Wind Direction: 150o

b. Wind Speed: 10 mph

c. No precipitation forecast

d. Stability Class: C

INITIATING CUE:

You are to complete the Emergency Notification Form required following the given conditions

above.

This JPM is TIME CRITICAL.

Page 11 of 12

Page 12 of 12

DUKE ENERGY

BRUNSWICK TRAINING SECTION