Text

Draft Operating Test (Section a, Section B, Section C) (Folder 2)
	ML18088A662
Person / Time
Site:	Limerick
Issue date:	03/27/2018
From:	Byers T; Exelon Generation Co
To:	Brian Fuller; Operations Branch I
Shared Package
ML17138A091	List: IR 05000352/2017302; ML17151A980; ML18038B410; ML18038B436; ML18067A416; ML18067A417; ML18067A430; ML18079A546; ML18079A812; ML18088A662; ML18088A664;
References
	U01956
	Download: ML18088A662 (376)
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J .=- Exelon Generation LIMERICK GENERATING STATION JOB PERFORMANCE MEASURE ERP CLASSIFICATION AND REPORTING (TIME CRITICAL)

JPM Number: LOJPM3101 REVISION NUMBER: 001 DATE: - - - -

Developed By:

Instructor Date Validated By:

SME or Instructor Date Reviewed By:

Operations Representative Date Reviewed By:

EP Representative Date Approved By:

Training Department Date LOJPM3101 Rev001.doc SRRS: 3D.105 Page 1 of 14 (When used for operator initial or continuing training)

I,=Exelon Generation Note: This LGS format satisfies the TQ-JA-150 Format I. JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation.

Prior to JPM usage, revalidate JPM using steps 9 through 13 below.

1. Task description and number, JPM description and number are identified.

2. Knowledge and Abilities (KIA) references are included.

3. Performance location specified. (in-plant, control room, simulator, or other)

4. Initial setup conditions are identified.

5. Initiating cues (and terminating cues if required) are properly identified.

6. Task standards identified and verified by SME review.

7. Critical steps meet the criteria for critical steps and are identified with an asterisk

(*).

8. If an alternate path is used, the task standard contains criteria for successful completion.

9. Verify the procedure(s) referenced by this JPM reflects the current revision:

Procedure EP-AA-1008 Addendum 3 Rev: 002 Procedure EP-MA-114-100-F-01 Rev: P Procedure EP-AA-112-100-F-01 Rev: _...........,._

Y Procedure EP-AA-111-F-11 Rev:_....a..A~

Procedure---------- Rev: _ __

10. Verify cues both verbal and visual are free of conflict.

11. Verify performance time is accurate

12. If the JPM cannot be performed as written with proper responses, then revise the JPM.

13. When JPM is initially validated, sign and date JPM cover page.

Subsequent validations, sign and date below:

SME / Instructor Date SME / Instructor Date SME / Instructor Date LOJPM3101 Rev001.doc SRRS: 3D.105 Page 2 of 14 (When used for operator initial or continuing training)

j .=Exelon Generation II. RECORD OF TEMPORARY CHANGES:

A. Approval of Pen & Ink Changes will be by the ILT or LORT Lead Instructor with OTM concurrence B. All Pen & Ink Changes are to be tracked in ILTor LOR Program Action Tracking for Next Revision C. All Pen & Ink Changes shall be in accordance with TQ-AA-223 Temp Date of Purpose of Change ILT/LORT Action Revision Change# Change Approval Tracking Date Ill. REVISION HISTORY:

A. If a Revision affects a Task Performance from VISION Terminal Performance Objectives then the revision must also be made in the VISION database.

B. The description of the Revision should adequately indicate how the training content of the Revision has changed.

C. The description of the Revision should also include previous format reference and number and previous template used (i.e. for conversion to LLOJPM format).

D. For Revision 000, put reason for writing this JPM and for all subsequent revisions, annotate the changes that were made or incorporated.

Revision # Date of Description of Revision and Affect on Training Content Number Revision This JPM supersedes LLOJPM0101 Rev002. Revised to new template 09/26/16 000 and to align with latest procedure revision.

Rev001 Revised to incorporate minor procedural and JPM changes 09/19/17

Date of Revision - refers to date revision was released for approval LOJPM3101 Rev001.doc SRRS: 3D.105 Page 3 of 14 (When used for operator initial or continuing training)

I,=' Exelon Generation IV. TASK STANDARD:

1. Site Area Emergency is declared within 15 minutes of the candidate beginning the classification.

2. Notification form completed and provided to Shift Communicator within 15 minutes of declaring the Site Area Emergency.

V. SIMULATOR SETUP D Use existing IC Met Data rgj Insert the following Met Data values:

RZZ002 MET Data Wind Direction (0-360) DEG AZIMUTH Target Value= 312.5 RZZ003 MET Data Wind Speed (0-100) MPH Target Value= 5.7 LOJPM3101 Rev001.doc SRRS: 3D.105 Page 4 of 14 (When used for operator initial or continuing training)

[F Exelon Generation VI. INITIAL CONDITIONS:

The following station events and conditions exist on Unit 1:

1. Reactor power 100% in OPCON 1

2. A tornado with winds of 200 mph caused damage to the Unit 1 Reactor Enclosure, and structural failure of the Unit 1 Spent Fuel Pool (SFP).

3. The Unit 1 SFP wall has a large hole, approximately 5' above the fuel assemblies, and the water has drained from the Unit 1 Spent Fuel Pool to Radwaste.

4. The remaining Unit 1 SFP water is boiling, with the steam escaping the refuel floor through a breach.

5. Control Room ventilation has automatically placed itself in a radiation isolation flowpath, with the 'OA' CREFAS fan running.

6. Health Physics dose assessment team reports that the projected offsite dose using computer dose model is as follows:

150 mRem TEDE.

COE Thyroid is expected to reach 380 mRem.

7. The Unit 1 and Unit 2 SFPs are separated.

8. Ll-053-200A reads 4.5' down slow.

9. Ll-053-2008 reads 23.5' steady.

1O. Refuel Floor has been isolated with SBGT in service

11. North Stack Radiation is 2.20 E+04 µCi/sec VII. INITIATING CUES: This Task is Time Critical This JPM will start when you tell the evaluator that you are aware of task conditions and are ready to begin.

No prior classifications or notifications have been made. You are required to make the highest classification based on the given plant conditions and make subsequent call outs.

All communications should indicate a drill.

LOJPM3101 Rev001.doc SRRS: 3D.105 Page 5 of 14 (When used for operator initial or continuing training)

I;~ Exelon Generation Information for Evaluator's Use:

Any UNSAT requires written comments on respective step.

Denotes critical steps Number any comments in the "Comment Number" column on the following pages. Then annotate that comment in the "Comments" section. The comment section should be used to document: the reason that a step is marked as unsatisfactory, marginal performance relating to management expectations, or problems the examinee had while performing the JPM.

Comments relating to procedural or equipment issues should be entered and tracked using the site's appropriate tracking system.

Some operations that are performed from outside the control room may require multiple steps.

These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed.

The JPM Start Time clock starts when the candidate acknowledges the initiating cue.

LOJPM3101 Rev001.doc SRRS: 3D.105 Page 6 of 14 (When used for operator initial or continuing training)

I,F Exelon Generation VIII. PERFORMANCE CHECKLIST:

JPM Start Time: _ _ __

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NOTE TO EVALUATOR//DRIVER:

IF JPM is NOT conducted in Simulator: Provide a screen shot of "Meteorological 15 Minute Average Point Data".

1. REFER to the appropriate N/A N/A LGS EAL Matrix

2. Call for Shift Communicator Shift Communicator called to report to to report to MCR MCR

3. Identify the operating MODE Matrix obtained:

for the affected Unit(s) prior to the abnormal condition, IZI HOT and obtain appropriate 0COLD Matrix.

4. Review the initiating Use EAL Matrix to classify event N/A conditions applicable to the operating MODE.

5. DECLARE the event Event Declared:

0 UNUSUAL EVENT DALERT fZI SITE AREA EMERGENCY 0GENERALEMERGENCY Declared within 15 minutes of the JPM START TIME:

DECLARATION TIME:

LOJPM3101 Rev001.doc SRRS: 3D.105 Page 7 of 14 (When used for operator initial or continuing training)

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NOTE: Candidate may choose, in step 6, Scenario 3: Actual event report to facility alternate location, which is acceptable.

6. Direct Shift Communicator to Everbridge activation:

activate the ERO or make

~ Scenario 1: Actual event report to management only facility notifications D Scenario 2: Management notification only D Scenario 3: Actual event report to facility alternate location

7. Complete the Event At the completion of the JPM the NIA Notification form Event Notification Form will be evaluated against the JPM standard located below.

8. Direct Shift Communicator to Shift Communicator notified to make perform state and local notifications within 15 minutes of notifications DECLARATION TIME.

Declaration Time:

Notification Initiated Time:

NOTE: the expectation is notification is initiated within 9 (nine)minutes of declaration time. Notification times between 9-15 minutes constitutes a pass with comment.

CUE: When form has been completed and Shift Communicator informed to process form: N/A N/A "You have met the termination criteria for this JPM" NOTE: The following steps are performed by the evaluator following the student providing the Notification form to the evaluator.

LOJPM3101 Rev001.doc SRRS: 3D.105 Page 8 of 14 (When used for operator initial or continuing training)

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EP-MA-114-100-F-01, STATE/LOCAL EVENT NOTIFICATION FORM

9. UTILITY MESSAGE NO. "1" or equivalent entered

10. VERIFIED WITH NIA N/A

11. EMERGENCY DIRECTOR Signature entered APPROVAL

12. CALL STATUS: Call Status marked iZ! THIS IS A DRILL

13. AFFECTED STATION: Affected Station marked for iZ! LIMERICK

14. AFFECTED UNIT(S): Unit(s) marked IZI ONE OTWO

15. CLASSIFICATION: Classification marked 0 UNUSUAL EVENT 0ALERT iZ! SITE AREA EMERGENCY 0GENERALEMERGENCY

16. DECLARED AT: Time entered Date entered

17. THIS REPRESENTS A/AN: This Represents marked iZ! INITIAL DECLARATION 0 ESCALATION 0 NO CHANGE

18. EMERGENCY ACTION "RS1" entered Threshold 2.a.

LEVEL (EAL) NUMBER:

LOJPM3101 Rev001.doc SRRS: 3D.105 Page 9 of 14 (When used for operator initial or continuing training)

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19. A BRIEF NON-TECHNICAL ~ A- Abnormal Rad Levels/

DESCRIPTION OF THE Radiological Effluent EVENT:

D B- Fission Product Barrier Degradation D C- System Malfunction D D- Hazards and Other Conditions Affecting Plant Safety D E- Independent Spent Fuel Storage Installation Malfunction D F- Cold Shutdown/Refueling System Malfunctions

20. RADIOLOGICAL RELEASE Release Status marked STATUS:

0 NO RELEASE

~AIRBORNE D LIQUID 0 RELEASE TERMINATED

21. METEOROLOGY DATA: Simulator Values match displayed Tower 1 175' using 15 minute average values:

Wind Direction: 312.5 (degrees)

Wind Speed: 5.7 (MPH)

CUE: Provide MET Attachment Attachment Values :

only if in location other than Wind Direction: 312.5 (degrees) simulator Wind Speed: 5.7 (MPH)

22. PROTECTIVE ACTION PAR Recommendation marked RECOMMENDATION

~ NOT Applicable (a orb):

D PAR Recommendation LOJPM3101 Rev001.doc SRRS: 3D.105 Page 10 of 14 (When used for operator initial or continuing training)

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23. CONCLUSION Conclusion marked

~ THIS IS A DRILL (Critical that at least one of the two status blocks on the page is marked correctly and no contradictory info is marked. If contradictory info is marked, then the incorrect step is UNSAT. If one block is blank and the other is correct, then the blank block is N/A)

JPM Stop Time: _ __

LOJPM3101 Rev001.doc SRRS: 3D.105 Page 11 of 14 (When used for operator initial or continuing training)

I,= Exelon Generation JPM

SUMMARY

Operator's Name: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __....;.

Job

Title:

D SEO D SM D SRO D RO D STA/IA D EO D OTHER JPM

Title:

ERP CLASSIFICATION AND REPORTING (TIME CRITICAL)

JPM Number: LOJPM3101 Revision Number: 001 Task Number and

Title:

TP03440070302, Classify Emergency Events Requiring Emergency Plan Implementation KIA Number and Importance: Generic 2.4.41 Importance 4.6 Safety Function (1-9) NIA .

Ad min Category (A 1-4) A4 (Emergency Plan)

Level of Difficulty (1-5) .:,

Suggested Testing Environment: Simulator Alternate Path:0 Yes~ No SRO Only:~ Yes D No Time Critical: ~ Yes D No Reference(s):

EP-AA-1008 Addendum 3, LGS EMERGENCY ACTION LEVELS FOR LGS, Rev. 002 EP-MA-114-100-F-01, STATE/LOCAL EVENT NOTIFICATION FORM, Rev. P EP-AA-112-1 OO-F-01, SHIFT EMERGENCY DIRECTOR CHECKLIST, Rev Y EP-AA-111-F-11, Limerick PAR Flowchart, Rev. A Actual Testing Environment: D Simulator D Control Room D In-Plant D Other Testing Method: D Simulate ~ Perform Estimated Time to Complete: 27 minutes Actual Time Used: minutes EVALUATION

SUMMARY

Were all the Critical Elements performed satisfactorily? D Yes D No The operator's performance was evaluated against standards contained within this JPM and has been determined to be: D Satisfactory D Unsatisfactory Comments:

Evaluator's Name: - - - - - - - - - - - - - - - - - (Print)

Evaluator's Signature: _ _ _ _ _ _ _ _ _ _ _ _ _ __ Date: ---

LOJPM3101 Rev001.doc SRRS: 3D.105 Page 12 of 14 (When used for operator initial or continuing training)

~

_,,_. Exelon Generation LIMERICK GENERATING STATION JOB PERFORMANCE MEASURE INDIVIDUAL BRIEFING SHEET INITIAL CONDITIONS:

The following station events and conditions exist on Unit 1:

1. Reactor power 100% in OPCON 1

2. A tornado with winds of 200 mph caused damage to the Unit 1 Reactor Enclosure, and structural failure of the Unit 1 Spent Fuel Pool (SFP).

3. The Unit 1 SFP wall has a large hole, approximately 5' above the fuel assemblies, and the water has drained from the Unit 1 Spent Fuel Pool to Radwaste.

4. The remaining Unit 1 SFP water is boiling, with the steam escaping the refuel floor through a breach.

5. Control Room ventilation has automatically placed itself in a radiation isolation flowpath, with the 'OA' CREFAS fan running.

6. Health Physics dose assessment team reports that the projected offsite dose using computer dose model is as follows:

150 mRem TEDE.

COE Thyroid is expected to reach 380 mRem.

7. The Unit 1 and Unit 2 SFPs are separated.

8. Ll-053-200A reads 4.5' down slow.

9. Ll-053-2008 reads 23.5' steady.

10. Refuel Floor has been isolated with SBGT in service

11. North Stack Radiation is 2.20 E+04 µCi/sec INITIATING CUES: This Task is Time Critical This JPM will start when you tell the evaluator that you are aware of task conditions and are ready to begin.

No prior classifications or notifications have been made. You are required to make the highest classification based on the given plant conditions and make subsequent call outs. All communications should indicate a drill.

Page 13 of 14

.,,:., < Exelon Generation 917METEOROLOGICAL 15 MINUTE AVERAGE POINT DATA PIO SENSOR DESCRIPTION VALUE EU T1DTULFA T1.SP.U TOWER 1 270 FT WIND SPEED 6.3 MPH T1SPIFA T1.SP.I TOWER 1 175 FT WIND SPEED 5.7 MPH T T12SPLFA T1.SP.L TOWER 1 30 FT WIND SPEED 4.6 MPH 0 T1DRUFA T1.DR.U TOWER 1 270 FT WIND DIRECTION 314.5 DEG AZ w T1DRIFA T1.DR.I TOWER 1 175 FT WIND DIRECTION 312.5 DEG AZ T1DRLFA T1.DR.L TOWER 1 30 FT WIND DIRECTION 311.1 DEG AZ E

T1DTULFA T1.DT.U-L TOWER 1 266 - 26 FT DEL TA TEMP -0.3 DEG F R T1DTILFA T1.DT.I-L TOWER 1 171 - 26 FT DELTA TEMP 0.4 DEG F T1ATLFA T1.AT.L TOWER 1 26 FT AMBIENT TEMP 85.2 DEGF 1

T1DPLFA T1.DP.L TOWER 1 26 FT DEW POINT 45.00 DEG F T1RNFA T1.RN TOWER 1 PRECIPITATION 0.1 INCHES T2DTULFA T2.SP.U TOWER 2 304 FT WIND SPEED 6.1 MPH T2SPIFA T2.SP.I TOWER 2 159 FT WIND SPEED 5.5 MPH T

T22SPLFA T2.SP.L TOWER 2 30 FT WIND SPEED 4.1 MPH 0 T2DRUFA T2.DR.U TOWER 2 304 FT WIND DIRECTION 321.4 DEG AZ w T2DRIFA T2.DR.I TOWER 2 159 FT WIND DIRECTION 320.5 DEG AZ E T2DRLFA T2.DR.L TOWER 2 30 FT WIND DIRECTION 318.9 DEG AZ R T2DTULFA T2.DT.U-L TOWER 2 304 - 26 FT DEL TA TEMP -0.4 DEGF T2DTILFA T2.DT.I-L TOWER 2 155 - 26 FT DEL TA TEMP 0.6 DEGF 2 T2ATLFA T2.AT.L TOWER 2 26 FT AMBIEWNT TEMP 85.0 DEG F T2DPLFA T2.DP.L TOWER 2 26 FT DEW POINT 44.81 DEG F Page 14 of 14

I; Exelon Generation LIMERICK GENERATING STATION JOB PERFORMANCE MEASURE EVALUATE OVERTIME WORK REQUEST (RO)

JPM Number: LOJPM6704 REVISION NUMBER: 001 DATE: - - - -

Developed By:

Instructor Date Validated By:

SME or Instructor Date Reviewed By:

Operations Representative Date Reviewed By: NIA NIA EP Representative Date Approved By:

Training Department Date LOJPM6704 Rev001.doc SRRS: 3D.105 Page 1 of 9 (When used for operator initial or continuing training)

1.= Exelon Generation Note: This LGS format satisfies the TQ-JA-150 Format I. JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation.

Prior to JPM usage, revalidate JPM using steps 9 through 13 below.

1. Task description and number, JPM description and number are identified.

2. Knowledge and Abilities (KIA) references are included.

3. Performance location specified. (in-plant, control room, simulator, or other)

4. Initial setup conditions are identified.

5. Initiating cues (and terminating cues if required) are properly identified.

6. Task standards identified and verified by SME review.

7. Critical steps meet the criteria for critical steps and are identified with an asterisk

(*).

8. If an alternate path is used, the task standard contains criteria for successful completion.

9. Verify the procedure(s) referenced by this JPM reflects the current revision:

Procedure LS-AA-119 Rev: 12 Procedure Rev: _ __

Procedure Rev: - - -

Rev: _ __

Procedure----------

Procedure Rev:

10. Verify cues both verbal and visual are free of conflict.

11. Verify performance time is accurate

12. If the JPM cannot be performed as written with proper responses, then revise the JPM.

13. When JPM is initially validated, sign and date JPM cover page.

Subsequent validations, sign and date below:

SME / Instructor Date SME / Instructor Date SME / Instructor Date LOJPM6704 Rev001.doc SRRS: 3D.105 Page 2 of 9 (When used for operator initial or continuing training)

I,:-:-' Exelon Generation II. RECORD OF TEMPORARY CHANGES:

A. Approval of Pen & Ink Changes will be by the ILT or LORT Lead Instructor with OTM concurrence B. All Pen & Ink Changes are to be tracked in ILTor LOR Program Action Tracking for Next Revision C. All Pen & Ink Changes shall be in accordance with TQ-AA-223 Temp Date of Purpose of Change ILT/LORT Action Revision Change# Change Approval Tracking Date Ill. REVISION HISTORY:

A. If a Revision affects a Task Performance from VISION Terminal Performance Objectives then the revision must also be made in the VISION database.

B. The description of the Revision should adequately indicate how the training content of the Revision has changed.

C. The description of the Revision should also include previous format reference and number and previous template used (i.e. for conversion to LLOJPM format).

D. For Revision 000, put reason for writing this JPM and for all subsequent revisions, annotate the changes that were made or incorporated.

Revision # Date of Description of Revision and Affect on Training Content Number Revision 000 This JPM replaces 2012 RO JPM A-1.1, Rev. 3. Revised to new 09/11/14 template and to align with latest procedure revision.

Rev001 Revised to change status of time off between shifts and align with new 09/28/17 JPM standard

Date of Revision - refers to date revision was released for approval LOJPM6704 Rev001.doc SRRS: 3D.105 Page 3 of 9 (When used for operator initial or continuing training)

[ ; Exelon Generation IV. TASK STANDARD:

Review the work hour history and determines that overtime request will result in exceeding 10 CFR 26 Work Hour Limits.

V. INITIAL CONDITIONS:

1. You were on vacation from 9/1 to 9/22.

2. Shift supervision has presented you with the below proposed schedule.

3. Additionally shift supervision has proposed a 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months overtime shift:

Sunday 10/07 0600-1800.

Sunday Monday Tuesday Wednesday Thursday Friday Saturday 9/23 9/24 9/25 9/26 9/27 9/28 9/29 1200-1800 0600-1800 0600-1800 0600-1400 0600-1400 0600-1400 0600-1400 Sunday Monday Tuesday Wednesday Thursday Friday Saturday 9/30 10/1 10/2 10/3 10/4 10/5 10/6 0600-1500 0600-2100 OFF OFF 0600-1800 0800-1200 0600-2100 VI. INITIATING CUE:

Using the schedule provided:

1. Determine if your proposed work schedule meets work hour requirements, if not, list any and ALL restrictions that apply.

2. Determine if you can work the entire requested shift (Sunday 10/7 0600-1800), if not, list any and ALL restrictions that apply.

3. Document your conclusion on the Individual Briefing Sheet.

LOJPM6704 Rev001.doc SRRS: 3D.105 Page 4 of 9 (When used for operator initial or continuing training)

I,F Exelon Generation Information for Evaluator's Use:

Any UNSAT requires written comments on respective step.

Denotes critical steps Number any comments in the "Comment Number" column on the following pages. Then annotate that comment in the "Comments" section. The comment section should be used to document: the reason that a step is marked as unsatisfactory, marginal performance relating to management expectations, or problems the examinee had while performing the JPM.

Comments relating to procedural or equipment issues should be entered and tracked using the site's appropriate tracking system.

Some operations that are performed from outside the control room may require multiple steps.

These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed.

The JPM Start Time clock starts when the candidate acknowledges the initiating cue.

LOJPM6704 Rev001.doc SRRS: 3D.105 Page 5 of 9 (When used for operator initial or continuing training)

1.= Exelon Generation VII. PERFORMANCE CHECKLIST:

JPM Start Time - - - - -

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1. Provide to candidate, a copy of:

N/A

Individual Briefing Sheet

2. Candidate obtains LS-AA-119, Candidate obtains and Fatigue Management and Work reviews LS-AA-119, Fatigue Hour Limits. Management and Work Hour Limits.

CUE: Provide copy of LS-AA-119, Fatigue Management and Work Hour Limits, when candidate demonstrates ability to obtain procedure.

3. [5.1.1] 10 CFR 26 Work Hour Limits. Candidate determines that (The following limit applies he/she cannot work the regardless of unit status) requested shift on Sunday because At least a 10-hour break between successive work periods, or an 8-

The required 10 hour1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months hour break when a break of less break between work then 10-hours is necessary to periods will not be met accommodate a crew's scheduled transition between work schedules or shifts.

4. [5.1.1] 10 CFR 26 Work Hour Limits. Candidate determines that he/she cannot work the full (The following limit applies requested shift on Sunday regardless of unit status) because No more than 26 work hours in any

The additional hours will 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months period. result in exceeding 26 hours3.009259e-4 days 0.00722 hours 4.298942e-5 weeks 9.893e-6 months in any 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months period.

LOJPM6704 Rev001.doc SRRS: 3D.105 Page 6 of 9 (When used for operator initial or continuing training)

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5. [5.1.1] 10 CFR 26 Work Hour Limits. Candidate determines that (The following limit applies previously worked schedule violation occurred due to not regardless of unit status) having a 34 hour3.935185e-4 days 0.00944 hours 5.621693e-5 weeks 1.2937e-5 months break in a 9 A 34 hour3.935185e-4 days 0.00944 hours 5.621693e-5 weeks 1.2937e-5 months break in any 9 day period day period.

(this limit may be incorporated into minimum days off requirements)

The period [9/23 -10/01]

did not have a 34 hour3.935185e-4 days 0.00944 hours 5.621693e-5 weeks 1.2937e-5 months break CUE: You have met the termination criteria for this JPM JPM Completion Time _ _ _ __

LOJPM6704 Rev001.doc SRRS: 3D.105 Page 7 of 9 (When used for operator initial or continuing training)

I,:""Exelon Generation JPM

SUMMARY

Operator's Name: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _____

Job

Title:

D SED D SM D SRO D RO D STA/IA D EO D OTHER JPM

Title:

EVALUATE OVERTIME WORK REQUEST (RO)

JPM Number: LOJP6704 Revision Number: 001 Task Number and

Title:

3420160302 Apply Administrative Procedure Requirements for Work Controls KIA Number and Importance: G2.1.5 RO 2.9 SRO 3.9 Safety Function (1-9) N/A Admin Category (A1-4) _1____

Level of Difficulty (1-5) -1..

Suggested Testing Environment: Classroom Alternate Path: D Yes ~ No SRO Only: D Yes ~ No Time Critical: D Yes ~ No Reference(s): NUREG 1123, Rev. 2 Supp. 1 LS-AA-119, Fatigue Management And Work Hour Limits, Rev. 12 Actual Testing Environment: D Simulator D Control Room D In-Plant D Other Testing Method: D Simulate ~ Perform Estimated Time to Complete: 25 minutes Actual Time Used: ____ minutes EVALUATION

SUMMARY

Were all the Critical Elements performed satisfactorily? D Yes D No The operator's performance was evaluated against standards contained within this JPM and has been determined to be: D Satisfactory D Unsatisfactory Comments:

Evaluator's Name: - - - - - - - - - - - - - - - - - (Print)

Evaluator's Signature: _ _ _ _ _ _ _ _ _ _ _ _ _ __ Date: ------

LOJPM6704 Rev001.doc SRRS: 3D.105 Page 8 of 9 (When used for operator initial or continuing training)

.-.:* Exelon Generation LIMERICK GENERATING STATION JOB PERFORMANCE MEASURE INDIVIDUAL BRIEFING SHEET INITIAL CONDITIONS:

5. You were on vacation from 9/1 to 9/22.

6. Shift supervision has presented you with the below proposed schedule.

7. Additionally shift supervision has proposed a 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months overtime shift:

Sunday 10/07 0600-1800.

Sunday Monday Tuesday Wednesday Thursday Friday Saturday 9/23 9/24 9/25 9/26 9/27 9/28 9/29 1200-1800 0600-1800 0600-1800 0600-1400 0600-1400 0600-1400 0600-1400 Sunday Monday Tuesday Wednesday Thursday Friday Saturday 9/30 10/1 10/2 10/3 10/4 10/5 10/6 0600-1500 0600-2100 OFF OFF 0600-1800 0800-1200 0600-2100 INITIATING CUE:

Using the schedule provided:

1. Determine if your proposed work schedule meets work hour requirements, if not, list any and ALL restrictions that apply.

2. Determine if you can work the entire requested shift (Sunday 10/7 0600-1800), if not, list any and ALL restrictions that apply.

3. Document your conclusion below.

ANSWER: - - - - - - - - - - - - - - - - - - - - - - - - - -

Page 9 of 9

I=" Exelon Generation LIMERICK GENERATING STATION JOB PERFORMANCE MEASURE REVIEW DRYWELL FLOOR DRAIN SUMP/EQUIPMENT DRAIN TANK LOGS AND DETERMINE COMPLIANCE WITH TS 3.4.3.2 JPM Number: LOJPM6708 REVISION NUMBER: 002 DATE: _ __

Developed By:

Instructor Date Validated By:

SME or Instructor Date Reviewed By:

Operations Representative Date Reviewed By:

EP Representative Date Approved By:

Training Department Date LOJPM6708 Rev002.doc SRRS: 3D.105 Page 1 of 9 (When used for operator initial or continuing training)

IF Exelon Generation Note: This LGS format satisfies the TQ-JA-150 Format I. JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation.

Prior to JPM usage, revalidate JPM using steps 9 through 13 below.

1. Task description and number, JPM description and number are identified.

2. Knowledge and Abilities (KIA) references are included.

3. Performance location specified. (in-plant, control room, simulator, or other)

4. Initial setup conditions are identified.

5. Initiating cues (and terminating cues if required) are properly identified.

6. Task standards identified and verified by SME review.

7. Critical steps meet the criteria for critical steps and are identified with an asterisk

(*}.

8. If an alternate path is used, the task standard contains criteria for successful completion.

9. Verify the procedure(s) referenced by this JPM reflects the current revision:

Procedure ST-6-107-596-1 Rev: --=-------

28 Procedure_ _ _ _ _ _ _ _ _ __ Rev: _ __

Procedure---------- Rev: _ __

Procedure Rev:

Rev:

Procedure---------- ---

10. Verify cues both verbal and visual are free of conflict.

11. Verify performance time is accurate

12. If the JPM cannot be performed as written with proper responses, then revise the JPM.

13. When JPM is initially validated, sign and date JPM cover page.

Subsequent validations, sign and date below:

SME / Instructor Date SME / Instructor Date SME / Instructor Date LOJPM6708 Rev002.doc SRRS: 3D.105 Page 2 of 9 (When used for operator initial or continuing training)

I=' Exelon Generation II. RECORD OF TEMPORARY CHANGES:

A Approval of Pen & Ink Changes will be by the ILTor LORT Lead Instructor with OTM concurrence B. All Pen & Ink Changes are to be tracked in ILT or LOR Program Action Tracking for Next Revision C. All Pen & Ink Changes shall be in accordance with TQ-AA-223 Temp Date of Purpose of Change ILT/LORT Action Revision Change# Change Approval Tracking Date Ill. REVISION HISTORY:

A If a Revision affects a Task Performance from VISION Terminal Performance Objectives then the revision must also be made in the VISION database.

B. The description of the Revision should adequately indicate how the training content of the Revision has changed.

C. The description of the Revision should also include previous format reference and number and previous template used (i.e. for conversion to LLOJPM format).

D. For Revision 000, put reason for writing this JPM and for all subsequent revisions, annotate the changes that were made or incorporated.

Revision # Date of Description of Revision and Affect on Training Content Number Revision Rev001 Revised to new template and to align with latest procedure revision. 06/22/16 Rev002 Revised to incorporate both RO and SRO requirements 9/21/17

Date of Revision - refers to date revision was released for approval LOJPM6708 Rev002.doc SRRS: 3D.105 Page 3 of 9 (When used for operator initial or continuing training)

I~ Exelon Generation IV. TASK STANDARD:

Review the data for Drywell Floor and Equipment Drain Tanks, determine that >2 gpm increase in leakage over a 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period was exceeded on day 5, and identification of a math error on day 2. Also, Tech Spec 3.4.3.2 referenced for UNIDENTIFIED LEAKAGE.

Additionally, SRO identifies per T.S. 3.4.3.2, source of leakage be identified or to be in Hot SID within next 12 hrs.

V. SIMULATOR SETUP N/A VI. INITIAL CONDITIONS:

1. Unit 1 is in OPCON 1

2. Unit 1 has been at 100% power for 179 days

3. FQRSH-61-112 is Operable VII. INITIATING CUE:

Shift Supervision directs you to perform a peer check review for a completed ST-6-107-596-1, "Drywell Floor Drain Sump/Equipment Drain Tank Surveillance Log/OPCON 1, 2, 3". Perform this review, document discrepancies, and Tech Spec concerns, if any.

In addition, SROs identify all Tech Spec actions that apply for the condition, if any.

LOJPM6708 Rev002.doc SRRS: 3D.105 Page 4 of 9 (When used for operator initial or continuing training)

I~ Exelon Generation Information for Evaluator's Use:

Any UNSAT requires written comments on respective step.

Denotes critical steps Number any comments in the "Comment Number" column on the following pages. Then annotate that comment in the "Comments" section. The comment section should be used to document: the reason that a step is marked as unsatisfactory, marginal performance relating to management expectations, or problems the examinee had while performing the JPM.

Comments relating to procedural or equipment issues should be entered and tracked using the site's appropriate tracking system.

Some operations that are performed from outside the control room may require multiple steps.

These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed.

The JPM Start Time clock starts when the candidate acknowledges the initiating cue.

LOJPM6708 Rev002.doc SRRS: 3D.105 Page 5 of 9 (When used for operator initial or continuing training)

I; Exelon Generation VIII. PERFORMANCE CHECKLIST:

JPM Start Time I- 0:::

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1. Provide candidate with the following:

Individual Briefing Sheet NIA

Completed ST-6-107-596-1, "Drywell Floor Drain Sump/

Equipment Drain Tank Surveillance Log/OPCON 1, 2, 3"

Unit 1 Tech Specs

Calculator

2. Candidate reviews ST-6-107-596-1 NIA for compliance

3. (Step 4.1.3) Candidate notes that Fl FQRSH-61-112, (points 3 and 4 Hi 115, FLOOR, FL, and Fl alarm setpoints) have been 135, EQUIP, FL, are determined available and Fl-61-115, OPERABLE FLOOR, FL, and Fl- 61-135, EQUIP, FL, are OPERABLE, therefore floor and equipment totalizer readings are available.

EVALUATORS NOTE: A math error has occurred on Attachment 2, Day 2. The candidate should identify the error however it will not change the outcome of the test and has no effect on actual drywell leakage.

4. (Attachment 2, Day 2 Log) Applicant verifies Total Total Leakrate is calculated by Leakrate calculations are for all Total Leakrate entries adding together each of the recorded values on Attachment 2, Table 1 (Fl-61-115 Floor and Fl (Candidate notes math error 135 Equip) AND recorded as Total Day 2 Total Leakrate 1.3 gpm Leakrate (gpm) on Attachment 2, vice 2. 3 gpm)

Table 1 LOJPM6708 Rev002.doc SRRS: 3D.105 Page 6 of 9 (When used for operator initial or continuing training)

IF Exelon Generation I- tt:

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EVALUATORS NOTE:

Roleplay as unit supervisor and acknowledge applicant report.

5. (Attachment 2, Day 5 Log) Candidate identifies on Day 5 that the 0800 floor drain Perform the following at 08:00, 16:00, reading is now 3.9 gpm.

AND 00:00:

This is an increase of >2 gpm over the last 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

IF Total Leakrate is.::: 25 gpm, Applicant notes this should AND Fl-61-115 is.::: 5 gpm not have been marked SAT.

AND Fl-61-115 increase is,:::2 gpm from previous 00:00 reading THEN ENTER SAT OTHERWISE ENTER UNSAT on Candidate notes that they Attachment 2, Table 1, would notify SSV as Tech AND NOTIFY SSV Spec actions may be required

6. Tech Spec 3.4.3.2 Reactor coolant Candidate references TS

system leakage referenced. 3.4.3.2.f Reactor coolant system leakage shall be limited to 2 gpm increase in UNIDENTIFIED LEAKAGE over 24 - hour period EVALUATORS NOTE: This is the termination point for RO's.

The remaining portion of this JPM is "SRO Only"

7. SRO determines required action for SRO identifies per TS 3.4.3.2 Tech Spec 3.4.3.2 UNIDENTIFIED action e. The source of

LEAKAGE leakage must be identified within 4hrs. or be in HOT SHUTDOWN within next 12 hrs.

CUE: You have met the termination criteria for this JPM JPM Completion Time _ _ _ __

LOJPM6708 Rev002.doc SRRS: 3D.105 Page 7 of 9 (When used for operator initial or continuing training)

I,=:"' Exelon Generation JPM

SUMMARY

Operator's Name: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Job

Title:

D SEO D SM D SRO D RO D STA/IA D EO D OTHER JPM

Title:

Review Drywell Floor Drain Sump/Equipment Drain Tank Logs and Determine Compliance with TS 3.4.3.2 JPM Number: LOJPM6708 Revision Number: 002 Task Number and

Title:

2990150101 Perform and Review Weekly Surveillance Logs KIA Number and Importance: Generic 2.2.12 3.7/4.1 Safety Function (1-9) NIA Admin Category (A1-4)--=2-Level of Difficulty (1-5) __3__

Suggested Testing Environment: Simulator/Classroom Alternate Path:0 Yes [8J No SRO Only: D Yes [8J No Time Critical: D Yes [8J No Reference(s): NUREG 1123, Rev. 2 Supp. 1 ST-6-107-596-1, Drywell Floor Drain Sump/Equipment Drain Tank Surveillance Log/OPCON 1,2,3, Rev. 28 LGS Unit 1 TS 3.4.3.2 Actual Testing Environment: D Simulator D Control Room D In-Plant D Other Testing Method: D Simulate [8J Perform Estimated Time to Complete: 25 minutes Actual Time Used: minutes EVALUATION

SUMMARY

Were all the Critical Elements performed satisfactorily? D Yes D No The operator's performance was evaluated against standards contained within this JPM and has been determined to be: D Satisfactory D Unsatisfactory Comments:

Evaluator's Name: - - - - - - - - - - - - - - - - - (Print)

Evaluator's Signature: _ _ _ _ _ _ _ _ _ _ _ _ _ __ Date: - - - - - -

LOJPM6708 Rev002.doc SRRS: 30.105 Page 8 of 9 (When used for operator initial or continuing training)

__.. Exelon Generation LIMERICK GENERATING STATION JOB PERFORMANCE MEASURE INDIVIDUAL BRIEFING SHEET INITIAL CONDITIONS:

1. Unit 1 is in OPCON 1

2. Unit 1 has been at 100% power for 179 days INITIATING CUE:

Shift Supervision directs you to perform a peer check review for a completed ST-6-107-596-1, "Drywell Floor Drain Sump/Equipment Drain Tank Surveillance Log/OPCON 1, 2, 3". Perform this review, document discrepancies, and Tech Spec concerns, if any.

In addition, SROs identify all Tech Spec actions that apply for the condition, if any.

Document discrepancies, and Tech Spec concerns, if any.

Page 9 of 9

I,= Exelon Generation LIMERICK GENERATING STATION JOB PERFORMANCE MEASURE ADMINISTRATIVE ACTIONS FOR A THERMAL LIMIT VIOLATION JPM Number: LOJPM6714 REVISION NUMBER: 001 DATE: - - - -

Developed By:

Instructor Date Validated By:

SME or Instructor Date Reviewed By:

Operations Representative Date Reviewed By: NIA NIA EP Representative Date Approved By:

Training Department Date LOJPM6714 Rev001.doc SRRS: 3D.105 Page 1 of 13 (When used for operator initial or continuing training)

I,="" Exelon Generation Note: This LGS format satisfies the TQ-JA-150 Format I. JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation.

Prior to JPM usage, revalidate JPM using steps 9 through 13 below.

1. Task description and number, JPM description and number are identified.

2. Knowledge and Abilities (KIA) references are included.

3. Performance location specified. (in-plant, control room, simulator, or other)

4. Initial setup conditions are identified.

5. Initiating cues (and terminating cues if required) are properly identified.

6. Task standards identified and verified by SME review.

7. Critical steps meet the criteria for critical steps and are identified with an asterisk

(*).

8. If an alternate path is used, the task standard contains criteria for successful completion.

9. Verify the procedure(s) referenced by this JPM reflects the current revision:

Procedure GP-5 Appendix 2 Rev: -

Procedure GP-14 Rev: ~ 8--

Procedure NF-AB-705 Rev: ----'"-'1O"----

Procedure Rev: _ __

Procedure

Rev: - - -

10. Verify cues both verbal and visual are free of conflict.

11. Verify performance time is accurate

12. If the JPM cannot be performed as written with proper responses, then revise the JPM.

13. When JPM is initially validated, sign and date JPM cover page.

Subsequent validations, sign and date below:

SME / Instructor Date SME / Instructor Date SME / Instructor Date LOJPM6714 Rev001.doc SRRS: 3D.105 Page 2 of 13 (When used for operator initial or continuing training)

I ='"" Exelon Generation II. RECORD OF TEMPORARY CHANGES:

A. Approval of Pen & Ink Changes will be by the ILTor LORT Lead Instructor with OTM concurrence B. All Pen & Ink Changes are to be tracked in ILTor LOR Program Action Tracking for Next Revision C. All Pen & Ink Changes shall be in accordance with TQ-AA-223 Temp Date of Purpose of Change ILT/LORT Action Revision Change# Change Approval Tracking Date Ill. REVISION HISTORY:

A. If a Revision affects a Task Performance from VISION Terminal Performance Objectives then the revision must also be made in the VISION database.

B. The description of the Revision should adequately indicate how the training content of the Revision has changed.

C. The description of the Revision should also include previous format reference and number and previous template used (i.e. for conversion to LLOJPM format).

D. For Revision 000, put reason for writing this JPM and for all subsequent revisions, annotate the changes that were made or incorporated.

Revision # Date of Description of Revision and Affect on Training Content Number Revision 000 This JPM replaces LLOJPM0714 Rev. 1. Revised to new template and 8/01/14 aligned using MFLCPR for Thermal Limit vs using FLLLP.

Rev001 JPM revised to new JPM template and procedure revision 10/24/16

Date of Revision - refers to date revision was released for approval LOJPM6714 Rev001.doc SRRS: 3D.105 Page 3 of 13 (When used for operator initial or continuing training)

I,::!" Exelon Generation IV. TASK STANDARD:

Candidate identifies MFLCPR is greater than 1.0 and a power reduction is required, using Control Rods only, in accordance with the Reactor Maneuvering Shutdown Instructions (RMSI), and GP-5, Appendix 2, until MFLCPR is less than 1.0 Additionally, SRO identifies per T.S. 3.2.3.b, corrective actions (Control Rods insertion per GP-14) must be taken within 15 minutes to restore MCPR to within required limit within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or Thermal Power reduced to < 25% of rated thermal power within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

V. INITIAL CONDITIONS:

1. Reactor power is currently stable at - 99.8%.

2. During the previous shift, Reactor Engineering and Ops Management had authorized a Reactor power ascension using Control Rods and Recirc flow.

3. Reactor power was raised per GP-5, Appendix 2, from 90% following a Control Rod pattern adjustment.

4. Shift turnover has been completed, all required log entries have been completed and you have assumed shift duties.

5. The latest official 30 Monicore Periodic Log (P1) has been run to assess the recent Reactor power ascension with the following:

The Plant Process Computer (PPG) is OPERABLE

30 Monicore (3DM) is OPERABLE

No Plant Monitoring System (PPG) or software testing is in progress.

The P-1 edit is not known to be invalid.

EOC-RPT system is operable

Turbine Bypass system is operable LOJPM6714 Rev001.doc SRRS: 3D.105 Page 4 of 13 (When used for operator initial or continuing training)

I;:::!"" Exelon General ion VI. INITIATING CUE:

You are directed to review the official 30 Monicore Periodic Log (P1 ), and perform the following:

1. Verify Reactor Core Limits have been maintained during the recent power ascension AND if any Reactor Core Limit is NOT in compliance:

a) Identify parameter(s), and enter the appropriate procedure(s) b) Identify required action( s) for the entered procedure( s)

Information for Evaluator's Use:

Any UNSAT requires written comments on respective step.

Denotes critical steps Number any comments in the "Comment Number" column on the following pages. Then annotate that comment in the "Comments" section. The comment section should be used to document: the reason that a step is marked as unsatisfactory, marginal performance relating to management expectations, or problems the examinee had while performing the JPM.

Comments relating to procedural or equipment issues should be entered and tracked using the site's appropriate tracking system.

Some operations that are performed from outside the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed.

The JPM Start Time clock starts when the candidate acknowledges the initiating cue.

LOJPM6714 Rev001.doc SRRS: 3D.105 Page 5 of 13 (When used for operator initial or continuing training)

I.=" Exelon Generation VII. PERFORMANCE CHECKLIST:

JPM Start Time-----

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NOTE: The 30 Monicore Periodic Log (P1) identifies MFLCPR greater than 1.0. MFLCPR is a Thermal Limit as specified in Tech Specs. GP-5, Appendix 2 references GP-14, Resolution of Thermal Limit Violations, to restore any Thermal Limit or FLLLP to less than the maximum valve listed in GP-14, Attachment 1. Also the candidate may request NF-AB-705, 30 Monicore-Troubleshooting for computer data validation.

1. Provide the candidate with the following: N/A

Individual Briefing Sheet

30 Monicore Periodic Log (P1 ).

2. Candidate reviews the 30 Monicore Candidate observes MFLCPR Periodic Log (P1) to verify core limits has exceeded the limit (Thermal Limits and FLLLP are specified in GP-5.

acceptable).

(All other core parameters are within their specified limits).

3. Candidate communicates the Candidate states the following condition of the core as indicated on concerning the condition of the 30 Monicore Periodic Log (P1 ). the core:

The core MFLCPR has exceeded the specified limit.

CUE: If requested, provide candidate (All other core parameters are with GP-5, Appendix 2.

within their specified limits).

4. Candidate determines GP-14 must Candidate reviews GP-14 be entered and references GP-14, prerequisites and "NOTES" Resolution of Thermal Limit prior to step 3.1 of GP-14.

Violations CUE: When requested, ensure available GP-14, Resolution of Thermal Limit Violations LOJPM6714 Rev001.doc SRRS: 3D.105 Page 6 of 13 (When used for operator initial or continuing training)

I=' Exelon Generation I- c:::

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5. (GP-14 3.1) Immediately notify Shift Immediately inform the Management and Reactor following for the MFLCPR Engineering of any thermal limit OR violation:

FLLLP violation.

Shift Management

Reactor Engineers

6. (GP-14 3.2) IF MFLCPR violation Candidate determines a

occurs REDUCE Reactor power Reactor power reduction is using Control Rods only using RMSI required with Control Rods AND GP-5 Appendix 2. only, using RMSI AND GP-5 Appendix 2 concurrently until core Thermal Limits and FLLLP are less than 1.000 NOTE: This is the termination point for RO's only CUE: (RO's only) - You have met the termination criteria for this JPM The remaining portion of this JPM is "SRO's only' Provide the SRO, with a copy of the following:

1. NF-AB-705, 30 Monicore-Troubleshooting

2. TECH SPECS, Unit 1

7. (GP-14 3.5) Examine P-1 containing SRO candidate determines thermal limit violation for Core power, Flow, Control unexplained changes using NF-AB- Rod pattern and LPRMs are 705 for computer data validation consistent at power level and P-1 appears to be valid CUE: Provide the SRO, copy of NF-AB-705, 30 Monicore-Troubleshooting

8. (GP-14 Note) Reference Tech Spec Determine (from P-1) MCPR 3.2.3.b to verify MCPR ~ MCPR = 1.383 and MCPRLIM =

limit adjusted by MCPR(P) and 1.390 MCPR(F) provided EOC-RPT 1.383 is < 1.390 requiring system and Turbine Bypass system action to be taken operable LOJPM6714 Rev001.doc SRRS: 3D.105 Page 7 of 13 (When used for operator initial or continuing training)

I,::"' Exelon Generation I- c:::

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9. (Tech Spec) Reference Tech Spec Tech Spec 3.2.3.b, states

3.2.3.b With MCPR < MCPR LIMIT corrective actions (Control corrective actions must be taken Rods inserted per GP-14) within 15 minutes to restore MCPR must be taken within 15 to within required limit within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months minutes to restore MCPR to or reduce Thermal Power to < 25% within required limit within 2 of rated thermal power within the hours or Thermal Power next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . reduced to < 25% of rated thermal power within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

CUE: You have met the termination criteria for this JPM JPM Completion Time _ _ _ __

LOJPM6714 Rev001.doc SRRS: 3D.105 Page 8 of 13 (When used for operator initial or continuing training)

I=' Exelon Generation JPM

SUMMARY

Operator's Name: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ____..;.

Job

Title:

D SEO D SM D SRO D RO D STA/IA D EO D OTHER JPM

Title:

ADMINISTRATIVE ACTIONS FOR A THERMAL LIMIT VIOLATION JPM Number: LOJPM6714 Revision Number: 001 Task Number and

Title:

2830010101 Use Plant Computer 2953010101 Actions for GP-5, Intentional Power Drop KIA Number and Importance: 295014 AA2.04 4.1 / 4.4 Generic 2.1.7 4.4 / 4.7 Safety Function (1-9) N/A Admin Category (A1-4) _1........__

Level of Difficulty (1-5) _L Suggested Testing Environment: Classroom Alternate Path:0 Yes ~ No SRO Only: D Yes ~ No Time Critical: D Yes ~ No Reference(s): GP-5, Appendix 2, Rx Maneuvering Without Shutdown, Rev 97 GP-14, Resolution of Thermal Limit Violations, Rev 08 NF-AB-705, 30 Monicore-Troubleshooting Rev 10 Tech Specs, Unit 1 Actual Testing Environment: D Simulator D Control Room D In-Plant D Other Testing Method: D Simulate ~ Perform Estimated Time to Complete: 30 minutes Actual Time Used: minutes EVALUATION

SUMMARY

Were all the Critical Elements performed satisfactorily? D Yes D No The operator's performance was evaluated against standards contained within this JPM and has been determined to be: D Satisfactory D Unsatisfactory Comments:

Evaluator's N a m e : - - - - - - - - - - - - - - - - - (Print)

Evaluator's Signature: _ _ _ _ _ _ _ _ _ _ _ _ _ __ Date: ---

LOJPM6714 Rev001.doc SRRS: 3D.105 Page 9 of 13 (When used for operator initial or continuing training)

__.. Exelon Generation LIMERICK GENERATING STATION JOB PERFORMANCE MEASURE INDIVIDUAL BRIEFING SHEET INITIAL CONDITIONS:

1. Reactor power is currently stable at - 99.8%.

2. During the previous shift, Reactor Engineering and Ops Management had authorized a Reactor power ascension using Control Rods and Recirc flow.

3. Reactor power was raised per GP-5, Appendix 2, from 90% following a Control Rod pattern adjustment.

4. Shift turnover has been completed, all required log entries have been completed and you have assumed shift duties.

5. The latest official 30 Monicore Periodic Log (P1) has been run to assess the recent Reactor power ascension with the following:

The Plant Process Computer (PPC) is OPERABLE

30 Monicore (3DM) is OPERABLE

No Plant Monitoring System (PMS) or software testing is in progress.

The P-1 edit is not known to be invalid.

EOC-RPT system is operable

Turbine Bypass system is operable INITIATING CUE STATEMENT:

You are directed to review the official 30 Monicore Periodic Log (P1 ), and perform the following:

1. Verify Reactor Core Limits have been maintained during the recent power ascension AND if any Reactor Core Limit is NOT in compliance:

c) Identify parameter(s), and enter the appropriate procedure(s) d) Identify required action(s) for the entered procedure(s)

Page 10 of 13

~* Exelon Generation LIMERICK GENERATING STATION JOB PERFORMANCE MEASURE INDIVIDUAL BRIEFING SHEET Document Required A c t i o n s : - - - - - - - - - - - - - - - - - - - -

Page 11 of 13

~

-~

Exelon Generation 1 PAGE 1 LIMERICK-1 CYCLE 17 SEQUENCE NO 8 CORE PARAMETERS 3DM V6.59.06/Pl1El0 18-DEC-2017 14:30 CALCULATED POWER MWT 3507.5 PERIODIC LOG 18-DEC-2017 14:30 PRINTED POWER MWE 11 75. 6 AUTOMATIC CASE ID FMLD1171218143010 FLOW MLB/HR 99.636 CALC RESULTS RESTART FMLD1171218123056 FPAPDR 0.864 LPRM SHAPE - FULL CORE SUBC BTU/LB 20.12 Keff 1.0083 PR PSia 1058.33 XE WORTH % -2.21 LOAD LINE

SUMMARY

CORE MWD/sT 19903.6 XE/RATED 0.991 CORE POWER 99.8%

CYCLE MWD/sT 1505.2 AVE VF 0.459 CORE FLOW 99.6%

MCPR 1.383 FLLLP 0.884 LOAD LINE 100.0%

ALTERNATE INPUT : LGl DLO TBSIS RPTIS PRIS OPTB.INP CORRECTION FACTORS: MFLCPR= 1.001 MFLPD= 0.999 MAPRAT= 1.000 ZBB= 1.76 ft OPTION: ARTS 2 LOOPS ON MANUAL FLOW MCPRLIM= 1.390 FCBB= N/A MOST LIMITING LOCATIONS (NON-SYMMETRIC)

MFLCPR LOC MFLPD LOC MAPRAT LOC PCMARG LOC 1.005 43-16 0.863 47 4 0.736 47 4 0.025 15 4 1.001 45-18 0.848 41 4 0.723 41 4 0.023 43 4 0.954 41-14 0.847 51 4 0. 712 43 4 0.019 47 4 0.947 47-20 0.843 49 4 0. 712 45 4 -0.050 49 4 0.937 45-16 0.839 41 4 0. 711 45 4 -0.052 47 4 0.897 31-28 0.837 43 4 0.709 47 4 -0.140 39 4 0.894 27-30 0.837 45 4 0.706 43 4 -0.167 37 4 0.878 41-12 0.835 45 4 0.705 49 4 -0.209 43 4 0.876 49-20 0.829 41 4 0.702 45 4 -0.235 41 4

0. 871 31-24 0.827 45 4 0.698 47 4 -0.412 45 4 SEQ. A-2 C=MFLCPR D=MFLPD M=MAPRAT P=PCMARG *=MULTIPLE CORE AVE AXIAL NOTCH REL PW LOC 0.178 25 00 0.387 24 59 02 0.522 23 L 04 0.633 22 55 06 0.705 21 51 08 0.763 20 L 10 0.795 19 47 00 12 0.812 18 43 p 14 0.906 17 L 16 0.931 16 39 12 12 18 0.972 15 35 20 1.008 14 L 22 1.034 13 31 00 00 24 1.079 12 27 26 1.130 11 L 28 1.167 10 23 12 12 30 1. 299 09 19

32 1. 385 08 L 34 1. 454 07 15 00 C 36 1.526 06 11 38 1.592 05 L 40 1.603 04 <-

07 42 1. 498 03 03 44 1.193 02 L L L L L L L 46 0.430 01 02 06 10 14 18 22 26 30 34 38 42 46 50 54 58 CORE AVERAGE RADIAL POWER DISTRIBUTION RING # 1 2 3 4 5 6 7 8 REL PW 1.334 1.356 1.262 1.225 1.222 1.292 1.007 0.418 Page 12 of 13

.-- Exelon Generation 1 PAGE 2 LIMERICK-1 CYCLE 17 INSTRUMENT READINGS/STATUS SEQUENCE NO 8 CALIBRATED LPRM READINGS 18-DEC-2017 14:30 CALCULATED 18-DEC-2017 14:30 PRINTED 57D 16.7 0.0 21.8 20.6 CASE ID FMLD1171218143010 C 17.4 27.1 28.6 23.2 LPRM SHAPE - FULL CORE B 16.6 31.8 33.4 24.7 A 13.6 32.0 34.7 22.8 # OF TIPS NOT SCANNED: 9 49D 17.1 24.7 27.3 23.8 26.1 22.7 FAILED SENSORS:

C 19.6 37.0 40.1 35.1 37.7 30.2 LPRM ( 8 SIGNALS FAILED)

B 20.4 0.0 52.3 45.4 51. 8 37.7 817C 1649B 2425D 2457D A 18.7P 66.0 66.0 56.1 68.5 44.7 3209B 3233A 4809D 5641D LPRM ( 0 PANACEA REJECTED) 41D 25.0 28.1 31. 8 30.3 31. 4 25.5 0.0 OTHER SENSORS O TOTAL)

C 34.7 39.7 37.4 41. 0 37.5 38.3 23.0 SUB RODS B 44.4 52.9 47.3 51.1 48.4 51.8 24.9 NONE A 57.8 66.9 55.3 61.8 58.1 70.1 22.2 T TIP RUN RECOMMENDED 33D 25.3 26.4 31.3 29.5 30.1 23.8 21. 7 C MFLCPR LOCATION C 36.6 36.3 42.3 43.2 40.6 34.3 27.9 M MAPRAT LOCATION B 47.8 46.9 53.9 55.7 51. 6 44.4 32.6 D MFLPD LOCATION A 61.6 54.7 64.6 0.0 62.0 53.8 34.3 p PCMARG LOCATION

MULTIPLE LIMIT 25D 25.1 29.0 0.0 30.8 31.1 27.1 21.2 C 36.1 40.0 37.7 42.2 36.9 39.7 27.2 B 47.1 52.2 47.3 53.8 46.6 52.4 31.7 A 59.0 63.6 53.3 63.6 54.3* 67.5 31.9 17D 22.6 26.1 29.1 27.2 28.2C 24.6 16.5 C 0.0 39.1 39.9 37.3 39.4 36.9 17.4 B 34.6 52.0 51.6 47.3 53.0 49.6 16.5 A 39.1 67.9 63.0 54.0 64.7 65.0 13.8 09D 22.5 25.8 25.3 25.1 0.0 C 29.3 37.1 37.2 34.6 19.7 B 35.3 48.1 0.0 44.5 20.6 A 39.5 59.5 64.0 56.8 19.0 08 16 24 32 40 48 56 CORE

SUMMARY

INER 1.054 CORE POWER 99.8% CALC SUB FLOW 96 .2% DP MEAS PSI 14.890 CORE FLOW 99.6% OPER SUB FLOW -1.0% DP CALC PSI 20.181 LOAD LINE 100.0% FLOW BASIS MEAS FEEDWTR FLOW MLB/HR 15.30 APRM CALIBRATION 1 2 3 4 READING 99.3 99.5 99.6 99.6 AGAF 1.005 1.003 1.002 1.002 APRM - %CTP -0.5 -0.3 -0.2 -0.2 TIP RUNS RECOMMENDED STRINGS: NONE DRIVE FLOW MLB/HR 32.47 FEEDWTR TEMP Deg F 431.8 CORE AVG VOID FRACTION 0.459 Page 13 of 13

1 z Exelon Generation LIMERICK GENERATING STATION JOB PERFORMANCE MEASURE AREA RAD MONITOR(s) FAIL DOWNSCALE JPM Number: LOJPM6718 REVISION NUMBER: 000 DATE: - - - -

Developed By:

Instructor Date Validated By:

SME or Instructor Date Reviewed By:

Operations Representative Date Reviewed By:

EP Representative Date Approved By:

Training Department Date LOJPM6718 RevOOO.doc SRRS: 3D.105 Page 1 of 12 (When used for operator initial or continuing training)

I? Exelon Generation Note: This LGS format satisfies the TQ-JA-150 Format I. JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation.

Prior to JPM usage, revalidate JPM using steps 9 through 13 below.

1. Task description and number, JPM description and number are identified.

2. Knowledge and Abilities (KIA) references are included.

3. Performance location specified. (in-plant, control room, simulator, or other)

4. Initial setup conditions are identified.

5. Initiating cues (and terminating cues if required) are properly identified.

6. Task standards identified and verified by SME review.

7. Critical steps meet the criteria for critical steps and are identified with an asterisk

(*).

8. If an alternate path is used, the task standard contains criteria for successful completion.

9. Verify the procedure(s) referenced by this JPM reflects the current revision:

Procedure S27 .1.A Rev: 21 Procedure S27.10.A Rev: 9 Procedure ARC-MCR-109 A-5 Rev: 2 Procedure Tech S12ecs Unit 1 Rev:

Procedure Rev:

10. Verify cues both verbal and visual are free of conflict.

11. Verify performance time is accurate

12. If the JPM cannot be performed as written with proper responses, then revise the JPM.

13. When JPM is initially validated, sign and date JPM cover page.

Subsequent validations, sign and date below:

SME / Instructor Date SME / Instructor Date SME / Instructor Date LOJPM6718 RevOOO.doc SRRS: 3D.105 Page 2 of 12 (When used for operator initial or continuing training)

[.::"'Exelon Generation II. RECORD OF TEMPORARY CHANGES:

A. Approval of Pen & Ink Changes will be by the ILTor LORT Lead Instructor with OTM concurrence B. All Pen & Ink Changes are to be tracked in ILT or LOR Program Action Tracking for Next Revision C. All Pen & Ink Changes shall be in accordance with TQ-AA-223 Temp Date of Purpose of Change ILT/LORT Action Revision Change# Change Approval Tracking Date Ill. REVISION HISTORY:

A. If a Revision affects a Task Performance from VISION Terminal Performance Objectives then the revision must also be made in the VISION database.

B. The description of the Revision should adequately indicate how the training content of the Revision has changed.

C. The description of the Revision should also include previous format reference and number and previous template used (i.e. for conversion to LLOJPM format).

D. For Revision 000, put reason for writing this JPM and for all subsequent revisions, annotate the changes that were made or incorporated.

Revision # Date of Description of Revision and Affect on Training Content Number Revision 000 This JPM is New 8/01/17

Date of Revision - refers to date revision was released for approval LOJPM6718 RevOOO.doc SRRS: 3D.105 Page 3 of 12 (When used for operator initial or continuing training)

I;=;- Exelon Generation IV. TASK STANDARD:

1. On the Individual Briefing Sheet, only the following downscale ARMs listed, including location and actions required:

Channel Location Action Radwaste Cask T-103 / SAMP referenced 9

Loading Area 22 Elev Have HP install a potable ARM in the vicinity of the 217' inoperable monitor.

Candidate may determine to reference S27.1.A step 4.3, or as a minimum:

(Plan to include)

1) Place affected ARMs in "ZERO" position at Aux Equipment Room.

30 Steam Separator Area Criticality ARMs 15, Elev 352' Inform HP to perform ST-0-027-640-1 Candidate may determine to reference S27.1.A step 4.3, or as a minimum:

33 Pool Plug Laydown (Plan to include)

Area 11 Elev 352'

1) Place affected ARMs in "ZERO" position at Aux Equipment Room.

2. For SRO, Tech Spec action(s) 3.3.7 a) Tech Spec 3.3.7.1.b b) With one or more radiation monitoring channels inoperable, take action 71 requirements:

(a) If fuel movement on-going install portable continuous monitor with the same alarm setpoint in vicinity of installed monitor.

(b) If no fuel movement on-going perform surveys of monitored area with portable monitoring instrumentation at least once per 24 hrs.

LOJPM6718 RevOOO.doc SRRS: 3D.105 Page 4 of 12 (When used for operator initial or continuing training)

I,="" Exelon Generation V. SIMULATOR SETUP N/A VI. INITIAL CONDITIONS:

1. Unit 1 is at 100% power.

2. MCR received the following alarm:

ARC-MCR-109 A-5, Area Rad Monitors Downscale

3. No maintenance activities are currently being performed VII. INITIATING CUE:

Shift Supervision directs you to identify which channel(s), channel number and location are in the downscale condition, and the action(s) required for the given condition.

In addition, SROs identify all Tech Spec actions that apply for the condition, if any.

Information for Evaluator's Use:

Any UNSAT requires written comments on respective step.

Denotes critical steps Number any comments in the "Comment Number" column on the following pages. Then annotate that comment in the "Comments" section. The comment section should be used to document: the reason that a step is marked as unsatisfactory, marginal performance relating to management expectations, or problems the examinee had while performing the JPM.

Comments relating to procedural or equipment issues should be entered and tracked using the site's appropriate tracking system.

Some operations that are performed from outside the control room may require multiple steps.

These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed.

The JPM Start Time clock starts when the candidate acknowledges the initiating cue.

LOJPM6718 RevOOO.doc SRRS: 3D.105 Page 5 of 12 (When used for operator initial or continuing training)

I;: Exelon Generation VIII. PERFORMANCE CHECKLIST:

JPM Start Time I- 0:::

I- Zw ELEMENT STANDARD I- <

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Oz (J

Lead Evaluator (or designee) Notes: Provide Candidate with the following:

Individual Briefing Sheet, including Attachment #1

ARC-MCR-109 A-5, 1 AREA RAD MONITORS DOWNSCALE

S27.1 O.A, Guidance for Addressing Area Radiation Monitor Alarms, and

S27.1.A, Operation Of The Area Radiation Monitoring System

Unit 1 Tech Specs (SROs only)

1. [ARC-MCR-109 A-5] Candidate verifies channel 9, Verify at Recorder RR-M 1-1 R600 30 and 33 from recorder are which channel(s) (1-35) is in a below downscale setpoint of downscale condition. .02 mr/hr.

2. [ARC-MCR-109 A-5] ACK Alarm" key at Recorder At Recorder RR-M 1-1 R600 press RR-M 1-1 R600 pressed and "ACK Alarm" key AND reset annunciator reset.

annunciator

3. [ARC-MCR-109 A-5] Candidate obtains S27.1 O.A, Obtain current revision of S27.10.A, Guidance for Addressing Guidance for Addressing Area Area Radiation Monitor Radiation Monitor Alarms Alarms

4. [ARC-MCR-109 A-5] Direct HP to perform ST

IF two or more Fuel Pool criticality 027-640-1 monitors are inoperable (channels 30, 31, 33), THEN have HP perform ST-0-027-640-1

5. [S27.10.A 4.2]

IF a high radiation alarm occurs, AND Radiation Protection has N/A determined the alarm to be false THEN USE Attachment 1.

LOJPM6718 RevOOO.doc SRRS: 30.105 Page 6 of 12 (When used for operator initial or continuing training)

I;;-Exelon Generation I- et::

I- Zw ELEMENT STANDARD I- <C W CD

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(.)

6. [S27 .1 O.A 4.3] No maintenance activities IF downscale alarm occurs that is currently being performed per known to be caused by maintenance Initial Conditions activities, THEN CONSIDER defeating the alarm per S27 .1.A, Operation Of The Area Radiation Monitoring System, procedure.

7. [S27 .1 O.A 4.3] Candidate references IF other downscale alarm occurs, S27 .10 .A Attachment 2 THEN USE Attachment 2.

8. [S27.10.A Att #2] Candidate directs to place

"T-103" SAMP-2 ARMS ARM channel 9, in zero Channels: 1, 2, 8, 9, 10, 11, 21, 22 For either Unit 1 or 2 9a. [S27.10.A Att #2] Candidate directs HP to

"T-103" SAMP-2 ARMS ARM install a portable ARM in the Channels: 1, 2, 8, 9, 10, 11, 21, 22 vicinity of channel 9 For either Unit 1 or 2 (Radwaste Cask Loading Area 22 Elev 217')

9b. [S27.10.A Att #2] Candidate directs to place

Criticality ARM channel in zero:

RIS 30-M1-*K600

30, (Steam Separator Area 15, Elev 352')

RIS 31-M1-*K600

33, (Pool Plug Laydown

RIS 33-M1-*K600 Area 11 Elev 352')

10. [S27.10.A 4.6] Candidate obtains S27.1.A, REFER to S27 .1.A, Operation Of Operation Of The Area The Area Radiation Monitoring Radiation Monitoring System, System, to defeat the downscale procedure.

alarm for the ARM that was placed in zero.

LOJPM6718 RevOOO.doc SRRS: 3D.105 Page 7 of 12 (When used for operator initial or continuing training)

I,FExelon Generation I- 0:::

I- ZW ELEMENT STANDARD I- <( Wm

<( u, :E :E u, z :E ::J

J Oz

(.)

Lead Evaluator (or designee) Notes This is the termination point for RO's.

The remaining portion of this JPM is "SRO Only"

11. Reference Tech Spec 3.3.7.1 for Tech Spec 3.3.7.1.b

Spent Pool Criticality Monitors With one or more radiation monitoring channels inoperable, take action 71 requirements:

If fuel movement on-going install portable continuous monitor with the same alarm setpoint in vicinity of installed monitor If no fuel movement on-going perform surveys of monitored area with portable monitoring instrumentation at least once per 24 hrs.

CUE: You have met the termination criteria for this JPM JPM Completion Time _ _ _ __

LOJPM6718 RevOOO.doc SRRS: 3D.105 Page 8 of 12 (When used for operator initial or continuing training)

I,=" Exelon Generation NRC Answer Summary Page As a minimum the following conditions should be referenced for the downscale ARMs Channel Location Action Radwaste Cask T-103 / SAMP referenced 9 Loading Area 22 Elev Have HP install a potable ARM in the vicinity of the 217' inoperable monitor.

Candidate may determine to reference S27.1.A step 4.3, or as a minimum:

(Plan to include)

1) Place affected ARMs in "ZERO" position at Aux Equipment Room.

Criticality ARMs 30 Steam Separator Area 15, Elev 352' Inform HP to perform ST-0-027-640-1 Candidate may determine to reference S27.1.A step 4.3, or as a minimum:

33 Pool Plug Laydown (Plan to include)

Area 11 Elev 352'

1) Place affected ARMs in "ZERO" position at Aux Equipment Room.

12. For SRO, Tech Spec action(s) 3.3.7 a) Tech Spec 3.3.7.1.b b) With one or more radiation monitoring channels inoperable, take action 71 requirements:

(a) If fuel movement on-going install portable continuous monitor with the same alarm setpoint in vicinity of installed monitor.

(b) If no fuel movement on-going perform surveys of monitored area with portable monitoring instrumentation at least once per 24 hrs.

LOJPM6718 RevOOO.doc SRRS: 3D.105 Page 9 of 12 (When used for operator initial or continuing training)

I ~ Exelon Generation JPM

SUMMARY

Operator's Name: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ______;,

Job

Title:

D SEO D SM D SRO D RO D STA/IA D EO D OTHER JPM

Title:

AREA RAD MONITOR(s) FAIL DOWNSCALE JPM Number: LOJPM6718 Revision Number: 000 Task Number and

Title:

2990090301 Apply Radiation and Contamination Safety Procedures KIA Number and Importance: Generic 2.3.15 2.9/3.1 Safety Function (1-9) _ _

Ad min Category (A 1-4) _3____ (Radiation Controls)

Level of Difficulty (1-5) _3_ _

Suggested Testing Environment: Classroom Alternate Path:0 Yes D No SRO Only: D Yes ~ No Time Critical: D Yes ~ No Reference(s): S27.1.A, Operation Of The Area Radiation Monitoring System, Rev 21 S27.1 O.A, Guidance for Addressing Area Radiation Monitor Alarms, Rev 9 ARC-MCR-109 A-5, 1 AREA RAD MONITORS DOWNSCALE, Rev 2 Unit 1 Tech Specs Actual Testing Environment: D Simulator D Control Room D In-Plant D Other Testing Method: D Simulate ~ Perform Estimated Time to Complete: 15 minutes Actual Time Used: minutes EVALUATION

SUMMARY

Were all the Critical Elements performed satisfactorily? D Yes D No The operator's performance was evaluated against standards contained within this JPM and has been determined to be: D Satisfactory D Unsatisfactory Comments:

Evaluator's Name: - - - - - - - - - - - - - - - - - (Print)

Evaluator's Signature: _ _ _ _ _ _ _ _ _ _ _ _ _ __ Date: ------

LOJPM6718 RevOOO.doc SRRS: 30.105 Page10of12 (When used for operator initial or continuing training)

~

Exelon Generation LIMERICK GENERATING STATION JOB PERFORMANCE MEASURE INDIVIDUAL BRIEFING SHEET INITIAL CONDITIONS:

1. Unit 1 is at 100% power.

2. MCR received the following alarm:

ARC-MCR-109 A-5, Area Rad Monitors Downscale

3. Attachment #1 contains ARM current and last burst readings from recorder RR-M1-1R600

4. No maintenance activities are currently being performed INITIATING CUE:

Shift Supervision directs you to identify which channel(s), channel number and location are in the downscale condition, and the action(s) required for the given condition.

In addition, SROs identify all Tech Spec actions that apply for the condition, if any.

I Channel Location Action SROs, identify all Tech Spec actions that apply for the above condition, if any.

Page 11 of 12

~ Exelon Generation ATTACHMENT 1 Recorder RR-M1-1 R600 last burst AND current values:

Reading from Readings Channel last burst print following MCR (mR/hr) alarm (mR/hr) 1 4.22 4.52 2 5.74 4.91 3 8.02 8.76 4 3.25 2.95 5 4.51 5.27 6 6.28 6.54 7 12.76 11.99 8 3.91 3.83 9 2.10 0.01 10 6.77 7.07 11 2.14 2.23 12 0.90 0.79 13 6.75 6.57 14 25.87 24.93 15 13.45 14.32 16 3.29 3.45 17 5.98 5.74 18 10.02 10.52 19 13.04 13.42 20 7.93 8.13 21 8.32 8.54 22 7.58 7.74 23 6.19 6.26 24 5.74 5.31 25 3.05 3.41 26 4.81 4.80 27 7.77 7.21 28 8.18 8.16 29 2.22 2.41 30 1.23 0.00 31 2.57 2.61 32 2.14 2.01 33 1.27 0.01 34 1.23 1.41 35 2.41 2.19 Page 12 of 12

I,=Exelon Generation LIMERICK GENERATING STATION JOB PERFORMANCE MEASURE DETERMINATION OF ADEQUATE SHIFT STAFFING (SRO)

JPM Number: LOJPM6725 REVISION NUMBER: 001 DATE: ----

Developed By:

Instructor Date Validated By:

SME or Instructor Date Reviewed By:

Operations Representative Date Reviewed By: N/A N/A EP Representative Date Approved By:

Training Department Date LOJPM6725 Rev001.doc SRRS: 30.105 Page 1 of 9 (When used for operator initial or continuing training)

I; Exelon Generation Note: This LGS format satisfies the TQ-JA-150 Format I. JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation.

Prior to JPM usage, revalidate JPM using steps 9 through 13 below.

1. Task description and number, JPM description and number are identified.

2. Knowledge and Abilities (KIA) references are included.

3. Performance location specified. (in-plant, control room, simulator, or other)

4. Initial setup conditions are identified.

5. Initiating cues (and terminating cues if required) are properly identified.

6. Task standards identified and verified by SME review.

7. Critical steps meet the criteria for critical steps and are identified with an asterisk

(*).

8. If an alternate path is used, the task standard contains criteria for successful completion.

9. Verify the procedure(s) referenced by this JPM reflects the current revision:

Procedure OP-LG-101-111 Procedure U/1 Tech Spec Table 6.2.2-1 Rev: 6 Rev: __N=A-=---

Procedure U/2 Tech Spec Table 6.2.2-1 Rev: -~-

NA Procedure Rev:

Rev: _ __

Procedure

10. Verify cues both verbal and visual are free of conflict.

11. Verify performance time is accurate

12. If the JPM cannot be performed as written with proper responses, then revise the JPM.

13. When JPM is initially validated, sign and date JPM cover page.

Subsequent validations, sign and date below:

SME / Instructor Date SME / Instructor Date SME / Instructor Date LOJPM6725 Rev001.doc SRRS: 3D.105 Page 2 of 9 (When used for operator initial or continuing training)

I~ Exelon Generation II. RECORD OF TEMPORARY CHANGES:

A. Approval of Pen & Ink Changes will be by the ILTor LORT Lead Instructor with OTM concurrence B. All Pen & Ink Changes are to be tracked in ILT or LOR Program Action Tracking for Next Revision C. All Pen & Ink Changes shall be in accordance with TQ-AA-223 Temp Date of Purpose of Change ILT/LORT Action Revision Change# Change Approval Tracking Date Ill. REVISION HISTORY:

A. If a Revision affects a Task Performance from VISION Terminal Performance Objectives then the revision must also be made in the VISION database.

B. The description of the Revision should adequately indicate how the training content of the Revision has changed.

C. The description of the Revision should also include previous format reference and number and previous template used (i.e. for conversion to LLOJPM format).

D. For Revision 000, put reason for writing this JPM and for all subsequent revisions, annotate the changes that were made or incorporated.

Revision # Date of Description of Revision and Affect on Training Content Number Revision 000 This JPM is new. 11/12/14 Rev001 Revised to incorporate JPM and procedural revisions 9/15/17

Date of Revision - refers to date revision was released for approval LOJPM6725 Rev001.doc SRRS: 3D.105 Page 3 of 9 (When used for operator initial or continuing training)

I,::;:"Exelon Generation IV. SIMULATOR SETUP INSTRUCTIONS Simulator - NIA V. TASK STANDARD:

1. Determine that the SM must take immediate action to ensure that the STA position is filled within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months

2. Determine that one of the following must occur:

a. The Unit 2 CRS assumes responsibility for both Units, or

b. The Floor Supervisor assumes the role of Unit 1 CRS VI. INITIAL CONDITIONS:

1. Both Units are in OPCON 1

2. A total of 4 SROs have the 1800-0600 shift, as follows:

a. Shift Manager

b. Unit 1 CRS (the only qualified STA)

c. Unit 2 CRS

d. Floor Supervisor

3. At 2000, the Unit 1 CRS suffers a stomach illness and is driven home VII. INITIATING CUE:

Evaluate how the sudden absence of the Unit 1 CRS impacts the Tech Spec shift staffing requirements; determine the required actions. Document your findings on the Cue Sheet.

LOJPM6725 Rev001.doc SRRS: 3D.105 Page 4 of 9 (When used for operator initial or continuing training)

I? Exelon Generation Information for Evaluator's Use:

Any UNSAT requires written comments on respective step.

Denotes critical steps Number any comments in the "Comment Number" column on the following pages. Then annotate that comment in the "Comments" section. The comment section should be used to document: the reason that a step is marked as unsatisfactory, marginal performance relating to management expectations, or problems the examinee had while performing the JPM.

Comments relating to procedural or equipment issues should be entered and tracked using the site's appropriate tracking system.

Some operations that are performed from outside the control room may require multiple steps.

These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed.

The JPM Start Time clock starts when the candidate acknowledges the initiating cue.

LOJPM6725 Rev001.doc SRRS: 30.105 Page 5 of 9 (When used for operator initial or continuing training)

1-=- Exelon Generation VIII. PERFORMANCE CHECKLIST:

JPM Start T i m e - - - - -

I- 0:::

I- ZW ELEMENT STANDARD I- <C w ca

<C U) :a; :a; U) z::, :a; ::,

Oz 0

Lead Evaluator (or designee) Notes: Provide Candidate with the following:

Individual Briefing Sheet

OP-LG-101-111, Shift Staffing Requirements, when requested

Unit 1 Tech Specs, if requested

Unit 2 Tech Specs, if requested Examinee may elect to perform the following Elements in the order he/she chooses.

1. Review OP-LG-101-111 and/or Tech Candidate reviews OP-LG-Specs for SRO shift staffing 101-111 and/or Tech Specs requirements. to determine the minimum number of SROs required to satisfy staffing requirements, as follows:

1 Shift Manager

2 SROs

1 STA (who can be any one of the SROs who is qualified as such)

2. Determine the action required in Per the "Table Notations" of

response to the absence of a Tech Spec Table 6.2.2-1, the qualified STA. SM must immediately take action to ensure that the STA position is filled within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

LOJPM6725 Rev001.doc SRRS: 3D.105 Page 6 of 9 (When used for operator initial or continuing training)

I ~ ExelonGeneration

~ et:

~ Zw ELEMENT STANDARD ~

<(

U)

Wm U) z ::E ::E

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Oz 0

3. Determine the action required in Determines that one of the

response to the absence of the Unit following must occur in order 1 CRS. to fill the Unit 1 CRS position:

Unit 2 CRS assumes responsibility for both Units, or

Floor Supervisor assumes the role of Unit 1 CRS CUE: "You have met the termination criteria for this JPM."

JPM Completion Time-----

LOJPM6725 Rev001.doc SRRS: 30.105 Page 7 of 9 (When used for operator initial or continuing training)

1-==-Exelon Generation JPM

SUMMARY

Operator's Name: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _____

Job

Title:

D SEO D SM D SRO D RO D STA/IA D EO D OTHER JPM

Title:

Determination of Adequate Shift Staffing (SRO)

JPM Number: LOJPM6725 Revision Number: 001 Task Number and

Title:

3420140302 Manage the Shift Team 3430160302 Assure Adequate Personnel Coverage For All Plant Conditions In Accordance With Overtime Policy KIA Number and Importance: G 2.1.5 2.9 / 3.9 Level of Difficulty (1-5) .....L Safety Function (1-9) _ _

Admin Category (A1-4) ______ 1_

Suggested Testing Environment: Classroom Alternate Path:0 Yes IZ! No SRO Only: 1Z! Yes D No Time Critical: D Yes IZI No Reference(s): OP-LG-101-111, Shift Staffing Requirements, Rev 006 Technical Specifications, Section 6.2.2 for Unit 1 and Unit 2 Actual Testing Environment: D Simulator D Control Room D In-Plant D Other Testing Method: D Simulate 1Z1 Perform Estimated Time to Complete: ~ minutes Actual Time Used: minutes EVALUATION

SUMMARY

Were all the Critical Elements performed satisfactorily? D Yes D No The operator's performance was evaluated against standards contained within this JPM and has been determined to be: D Satisfactory D Unsatisfactory Comments:

Evaluator's Name: - - - - - - - - - - - - - - - - - (Print)

Evaluator's Signature: _ _ _ _ _ _ _ _ _ _ _ _ _ __ Date: ------

LOJPM6725 Rev001.doc SRRS: 3D.105 Page 8 of 9 (When used for operator initial or continuing training)

__... Exelon Generation LIMERICK GENERATING STATION JOB PERFORMANCE MEASURE INDIVIDUAL BRIEFING SHEET INITIAL CONDITIONS:

1. Both Units are in OPCON 1

2. A total of 4 SROs have the 1800-0600 shift, as follows:

a. Shift Manager

b. Unit 1 CRS (the only one who is qualified STA)

c. Unit 2 CRS

d. Floor Supervisor

3. At 2000, the Unit 1 CRS suffers a stomach illness and is driven home INITIATING CUE:

Evaluate how the sudden absence of the Unit 1 CRS impacts the Tech Spec shift staffing requirements; determine the required actions. Document your findings on this Cue Sheet.

Page 9 of 9

_,_, Exelon Generation.

LIMERICK GENERATING STATION JOB PERFORMANCE MEASURE AUTHORIZE A REACTOR MANEUVERING SHUTDOWN INSTRUCTION (RMSI) FOLLOWING A ROD PATTERN ADJUSTMENT JPM Number: LOJPM6727 REVISION NUMBER: 002 DATE: _ __

Developed By:

Instructor Date Validated By:

SME or Instructor Date Reviewed By:

Operations Representative Date Reviewed By:

EP Representative Date Approved By:

Training Department Date LOJPM6727 Rev002.doc SRRS: 3D.105 Page 1 of 9 (When used for operator initial or continuing training)

Exelon Generation, Note: This LGS format satisfies the TQ-JA-150 Format I. JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation.

Prior to JPM usage, revalidate JPM using steps 9 through 13 below.

1. Task description and number, JPM description and number are identified.

2. Knowledge and Abilities (KIA) references are included.

3. Performance location specified. (in-plant, control room, simulator, or other)

4. Initial setup conditions are identified.

5. Initiating cues (and terminating cues if required) are properly identified.

6. Task standards identified and verified by SME review.

7. Critical steps meet the criteria for critical steps and are identified with an asterisk

(*).

8. If an alternate path is used, the task standard contains criteria for successful completion.

9. Verify the procedure(s) referenced by this JPM reflects the current revision:

Procedure NF-LG-721-1005 Rev: 3 Procedure NF-LG-721-1005-F-01 Procedure NF-AB-720-F-1 Rev: 0 Rev: -----1__

Procedure---------- Rev: _ __

Procedure Rev:

10. Verify cues both verbal and visual are free of conflict.

11. Verify performance time is accurate

12. If the JPM cannot be performed as written with proper responses, then revise the JPM.

13. When JPM is initially validated, sign and date JPM cover page.

Subsequent validations, sign and date below:

SME / Instructor Date SME / Instructor Date SME / Instructor Date LOJPM6727 Rev002.doc SRRS: 3D.105 Page 2 of 9 (When used for operator initial or continuing training)

- a.-'

~ , Exelon Generation II. RECORD OF TEMPORARY CHANGES:

A Approval of Pen & Ink Changes will be by the ILTor LORT Lead Instructor with OTM concurrence B. All Pen & Ink Changes are to be tracked in ILTor LOR Program Action Tracking for Next Revision C. All Pen & Ink Changes shall be in accordance with TQ-AA-223 Temp Date of Purpose of Change ILT/LORT Action Revision Change# Change Approval Tracking Date Ill. REVISION HISTORY:

A If a Revision affects a Task Performance from VISION Terminal Performance Objectives then the revision must also be made in the VISION database.

B. The description of the Revision should adequately indicate how the training content of the Revision has changed.

C. The description of the Revision should also include previous format reference and number and previous template used (i.e. for conversion to LLOJPM format).

D. For Revision 000, put reason for writing this JPM and for all subsequent revisions, annotate the changes that were made or incorporated.

Revision # Date of Description of Revision and Affect on Training Content Number Revision This JPM was originally on the 2008 NRC Exam as SRO A 1-1. It has 11/10/14 000 been reformatted and modified to add an incorrect rod and a lower than acceptable core flow rate.

Rev001 Revised for Use 06/06/15 Rev002 Revised due to procedure revisions 9/17/17

Date of Revision - refers to date revision was released for approval LOJPM6727 Rev002.doc SRRS: 30.105 Page 3 of 9 (When used for operator initial or continuing training)

,__ Exelon Generation IV. INSTRUCTIONS

1. Handouts required to be included with this JPM:

a. 30 MONICORE PREDICTOR

b. NF-LG-721-1005-F-01 Reactor Maneuvering Shutdown Instructions (RMSI)

c. NF-LG-721-1005, Reactor Maneuvering Shutdown Instructions Preparation Guideline V. TASK STANDARD:

The applicant should determine that the SRO should NOT authorize the Reactor Maneuvering Shutdown Instructions because of the following;

1. RMSI Flow Reduction Target is less than 60 Mlbm/hr, the limit established in NF-LG-721-1005.

2. Control Rod ID 30-25 is incorrect, the Control Rod ID should be 30-23.

VI. INITIAL CONDITIONS:

1. A rod pattern adjustment has just been completed.

2. The Reactor Engineer has handed you a new Reactor Maneuvering Shutdown Instruction (RMSI). The RMSI has been prepared and verified on 1ard of December 2017 by qualified reactor engineers, John Doe and Jim Miller.

3. The Reactor Engineer has also handed you the 30 MONICORE PREDICTOR results that have been used to develop the RMSI.

VII. INITIATING CUE:

You are directed to review the provided documents and sign for SRO AUTHORIZATION. If there are discrepancies that prevent your authorization of the RMSI, cite each of them on Cue Sheet.

LOJPM6727 Rev002.doc SRRS: 3D.105 Page 4 of 9 (When used for operator initial or continuing training)

~*

Exelon Generation.

Information for Evaluator's Use:

Any UNSAT requires written comments on respective step.

Denotes critical steps Number any comments in the "Comment Number" column on the following pages. Then annotate that comment in the "Comments" section. The comment section should be used to document: the reason that a step is marked as unsatisfactory, marginal performance relating to management expectations, or problems the examinee had while performing the JPM.

Comments relating to procedural or equipment issues should be entered and tracked using the site's appropriate tracking system.

Some operations that are performed from outside the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed.

The JPM Start Time clock starts when the candidate acknowledges the initiating cue.

LOJPM6727 Rev002.doc SRRS: 3D.105 Page 5 of 9 (When used for operator initial or continuing training)

_,,,_ Exelon Generation ANSWER KEY - DO NOT HAND-OUT TO CANDIDATE

==

Description:==

A rod pattern adjustment has just been completed. The Reactor Engineer has brought the new Reactor Maneuvering Shutdown Instructions (RMSI) to the control room and requested that the Shift Manager/CRS authorize (or activate) the new instructions. There is an incorrect rod on the sheet (30-23 should be 30-25). Additionally, core flow value of 58 Mlbm/hr is lower than allowed by NF-LG-721-1005 step 6.1.2.

JPM is designed to test the ability to determine that a new RMSI rod insertion sheet has been submitted for SRO approval with errors. The candidate will be provided the RMSI package and a 20 Monicore Predictor that shows one of the rods in the RMSI listed is incorrect and that core flow reduction value is lower than allowed.

The SRO signoff is on the RMSI cover sheet. The candidate may be cued as to the location to sign, as RE's are usually asked and will show the SRO where to sign.

Must be provided with the scanned P-1 predictor showing the rod pattern.

Fill out NF-LG-721-1005-F-01 with the Reactor Engineer signoff Fill in Shutdown Sequence ID LG1C17SD-01.0 RE/QNE 2nd Verifier Step Rod ID Target 1 30-31 00 2 14-47 00 3 46-15 00 4 46-47 00 5 14-15 00 6 30-39 00 7 30-25 00 (incorrect rod - should be 30-23) 8 38-31 00 9 22-31 00 10 14-39 00 11 46-23 00 12 46-39 00 13 14-23 00 NA remaining blanks on rod sheet place NA in each column.

Cue is that a rod pattern exchange took place and the RE has provided the new RMSI for SRO approval signoff on page 1.

Candidate should identify the step 7 rod is incorrect.

Candidate should also identify that core flow value is lower than allowed by procedure.

LOJPM6727 Rev002.doc SRRS: 3D.105 Page 6 of 9 (When used for operator initial or continuing training)

~*** Exelon Generation VIII. PERFORMANCE CHECKLIST:

JPM Start Time - - - - -

I- 0::

I- ZW ELEMENT STANDARD I- <( Wm

<( U)

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, :::E ::::,

Oz 0

1. Review the following: Candidate reviews RMSI, NF-LG-721-1005 and P-1.

RMSI

NF-LG-721-1005

P-1 Predictor Log CUE: Provide the following to the candidate:

Individual Briefing Sheet

RMSI (NF-LG-721-1005-F-01)

NF-LG- 721-1005

P-1 Predictor Log, to candidate .

2. Determine from the RMSI that Identify from the P-1 edit that Control Rod 30-25 is a mis-identified control rod 30-25 should be control rod. 30-23.

3. Determine from the RMSI that core Identify from NF-LG 721-1005 flow is less than 60 Mlbm/hr. incorrect core flow value.

4. SRO determines that RMSI is SRO lists errors on CUE incorrect. sheet and does not sign off RMSI due to the errors.

CUE: You have met the termination criteria for this JPM JPM Completion Time _ _ _ __

LOJPM6727 Rev002.doc SRRS: 3D.105 Page 7 of 9 (When used for operator initial or continuing training)

~

__.,. Exelon Generation.

JPM

SUMMARY

Operator's Name: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ___..;.

Job

Title:

D SEO D SM D SRO D RO D STA/IA D EO D OTHER JPM

Title:

AUTHORIZE A REACTOR MANEUVERING SHUTDOWN INSTRUCTION (RMSI) FOLLOWING A ROD PATIERN ADJUSTMENT JPM Number: LOJPM6727 Revision Number: 002 Task Number and

Title:

3420030302, Review Results of Completed Surveillance Tests KIA Number and Importance: G 2.1.37 4.3/4.6 Level of Difficulty (1-5) ..1.....

Safety Function (1-9) NIA Ad min Category (A 1-4) _1__

Suggested Testing Environment: Simulator/Classroom Alternate Path:0 Yes ~ No SRO Only:~ Yes D No Time Critical: D Yes ~ No Reference(s): NF-LG-721-1005-F-01, Reactor Maneuvering Shutdown Instructions, Rev 0 NF-LG-721-1005, Reactor Maneuvering Shutdown Instructions Preparation Guideline, Rev 3 Actual Testing Environment: D Simulator D Control Room D In-Plant D Other Testing Method: D Simulate ~ Perform Estimated Time to Complete: 15 minutes Actual Time Used: minutes EVALUATION

SUMMARY

Were all the Critical Elements performed satisfactorily? D Yes D No The operator's performance was evaluated against standards contained within this JPM and has been determined to be: D Satisfactory D Unsatisfactory Comments:

Evaluator's Name: - - - - - - - - - - - - - - - - - (Print)

Evaluator's Signature: _ _ _ _ _ _ _ _ _ _ _ _ _ __ Date: ---

LOJPM6727 Rev002.doc SRRS: 3D.105 Page 8 of 9 (When used for operator initial or continuing training)

,_.. Exelon Generation LIMERICK GENERATING STATION JOB PERFORMANCE MEASURE INDIVIDUAL BRIEFING SHEET INITIAL CONDITIONS:

1. A rod pattern adjustment has just been completed.

2. The Reactor Engineer has handed you a new Reactor Maneuvering Shutdown Instruction (RMSI). The RMSI has been prepared and verified on 1ard of December 2017 by qualified reactor engineers, John Doe and Jim Miller.

3. The Reactor Engineer has also handed you the 30 MONICORE PREDICTOR results that have been used to develop the RMSI.

INITIATING CUE:

You are directed to review the provided documents and sign for SRO AUTHORIZATION. If there are discrepancies that prevent your authorization of the RMSI, cite each of them on Cue Sheet.

ANSWER Key:

1. RMSI is APPROVED

2. RMSI Not APPROVED: State the reason(s) for disapproval below:

SRRS: 3D.105 Page 9 of 9 (When used for operator initial or continuing training)

PAGE 1 Predictor 1 of 1 LIMERICK - 1 30 MONICORE TRAINING only CORE PARAMETERS 3DM V6.58.15/Pll.9 18-DEC-2017 14:54 CALCULATED PREDICTOR LOG 18-DEC-2017 14:54 PRINTED POWER MWT 1554.8 CASE ID FSFF1121817145401 FLOW MLB/HR 58.000 CALC RESULTS RESTART FMLS1121817143107 FPAPDR 1.052 FIT - FULL CORE SUBC BTU/LB 22.63 Keff 1.0061 PR PSia 1056.10 XE WORTH% -2.19 LOAD LINE

SUMMARY

CORE MWD/sT 18457.9 XE/RATED 1. 092 CORE POWER 44.2%

CYCLE MWD/sT 5387.1 AVE VF 0.484 CORE FLOW 58.0%

MCPR 2.533 FLLLP 0.548 LOAD LINE 63.0%

D EXP MWD/sT 260.0 CORRECTION FACTORS: MFLCPR= 1.250 MFLPD= 1.000 MAPRAT= 1.000 ZBB= 1.80 ft OPTION: ARTS 2 LOOPS ON MANUAL FLOW MCPRLIM= 1.370 FCBB= N/A MOST LIMITING LOCATIONS (NON-SYMMETRIC)

MFLCPR LOC MFLPD LOC MAPRAT LOC PCMARG LOC 0.679 21-16 0.465 17 4 0.326 21 5 ***** 17 4 0.679 15-22 0.465 19 4 0.326 17 4 ***** 21 5 0.668 17-20 0.460 21 4 0.323 13 5 ***** 13 5 0.668 19-18 0.460 19 4 0.323 19 4 ***** 19 4 0.628 17-16 0.458 17 4 0.311 15 4 ***** 21 4

0. 626 15-18 0.456 15 4 0.310 11 4 ***** 15 4 0.626 23-14 0.456 21 4 0.309 15 4 ***** 15 4 0.578 13-24 0.428 15 4 0.291 21 4 ***** 17 4 0.556 13-20 0.411 21 4 0.286 23 4 ***** 13 5 0.553 19-14 0.409 15 4 0.682 15 5 ***** 25 5 C=MFLCPR D=MFLPD M=MAPRAT P=PCMARG *=MULTIPLE CORE AVE AXIAL NOTCH REL PW LOC 0.120 25 00 0.247 24 59 02 0.382 23 L 04 0.505 22 55 06 0.600 21 51 08 0.673 20 L 10 0.738 19 47 00 08 00 12 0.791 18 43 14 0.891 17 L 16 0.938 16 39 00 08 00 08 00 18 1.005 15 35 20 1.135 14 L 22 1. 184 13 31 08 00 00 00 08 24 1. 244 12 27 26 1.302 11 L 28 1.329 10 23 00 08 00 08 00 30 1.392 09 19

32 1. 44 7 08 L 34 1. 484 07 15 00

08 00 36 1.517 06 11 38 1. 557 05 L 40 1.544 04 <-

07 42 1.422 03 03 44 1. 141 02 L L L L L L L 46 0.414 01 02 06 10 14 18 22 26 30 34 38 42 4 6 50 54 58 CORE AVERAGE RADIAL POWER DISTRIBUTION RING # 1 2 3 4 5 6 7 8 REL PW 1. 288 1.273 1.188 1.172 1. 219 1.257 1.044 0.472

I,::ff!!r' Exelon Generation LIMERICK GENERATING STATION JOB PERFORMANCE MEASURE SECURE UNIT 1 HPCI FOLLOWING FULL FLOW FUNCTIONAL TEST JPM Number: LOJPM3020 REVISION NUMBER: 002 DATE: _ __

Developed By:

Instructor Date Validated By:

SME or Instructor Date Reviewed By:

Operations Representative Date Reviewed By:

EP Representative Date Approved By:

Training Department Date LOJPM3020 Rev002.doc SRRS: 3D.105 Page 1 of 10 (When used for operator initial or continuing training)

I=' Exelon Generation Note: This LGS format satisfies the TQ-JA-150 Format I. JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation.

Prior to JPM usage, revalidate JPM using steps 9 through 13 below.

1. Task description and number, JPM description and number are identified.

2. Knowledge and Abilities (KIA) references are included.

3. Performance location specified. (in-plant, control room, simulator, or other)

4. Initial setup conditions are identified.

5. Initiating cues (and terminating cues if required) are properly identified.

6. Task standards identified and verified by SME review.

7. Critical steps meet the criteria for critical steps and are identified with an asterisk

(*).

8. If an alternate path is used, the task standard contains criteria for successful completion.

9. Verify the procedure(s) referenced by this JPM reflects the current revision:

Procedure S55.1.D Rev: 46 Procedure---------- Rev: ---

Procedure Rev: - - -

Procedure

Rev: - - -

Procedure

Rev: - - -

10. Verify cues both verbal and visual are free of conflict.

11. Verify performance time is accurate.

12. If the JPM cannot be performed as written with proper responses, then revise the JPM.

13. When JPM is initially validated, sign and date JPM cover page.

Subsequent validations, sign and date below:

SME / Instructor Date SME / Instructor Date SME / Instructor Date LOJPM3020 Rev002.doc SRRS: 3D.105 Page 2 of 10 (When used for operator initial or continuing training)

I:' Exelon Generation II. RECORD OF TEMPORARY CHANGES:

A. Approval of Pen & Ink Changes will be by the ILT or LORT Lead Instructor with OTM concurrence.

B. All Pen & Ink Changes are to be tracked in ILT or LOR Program Action Tracking for Next Revision.

C. All Pen & Ink Changes shall be in accordance with TQ-AA-223.

Temp Date of Purpose of Change ILT/LORT Action Revision Change# Change Approval Tracking Date Ill. REVISION HISTORY:

A. If a Revision affects a Task Performance from VISION Terminal Performance Objectives then the revision must also be made in the VISION database.

B. The description of the Revision should adequately indicate how the training content of the Revision has changed.

C. The description of the Revision should also include previous format reference and number and previous template used (i.e. for conversion to LLOJPM format).

D. For Revision 000, put reason for writing this JPM and for all subsequent revisions, annotate the changes that were made or incorporated.

Revision # Date of Description of Revision and Affect on Training Content Number Revision 000 This JPM replaces LLOJPM0020 Rev. 6. Revised to new template and 9/17/14 to align with latest procedure revision.

001 JPM revised to new JPM format and procedure changes 9/3/16 002 JPM revised to new procedure changes 8/14/17

Date of Revision - refers to date revision was released for approval LOJPM3020 Rev002.doc SRRS: 3D.105 Page 3 of 10 (When used for operator initial or continuing training)

[.=-Exelon Generation IV. SIMULATOR SETUP INSTRUCTIONS:

1. Reset simulator to IC-3, or another IC if JPM was validated in the respective IC.

NOTE: It is okay to use a similar IC to the IC listed above, provided the IC actually used is verified to be compatible with this and other JPMs that are scheduled to be run concurrently ..

2. Ensure marked-up to section 4.5 'System Restoration' copy of S55.1.D, HPCI System Full Flow Functional Test available with HPCI in full flow test, CST-to-CST, with 120 psig > Rx pressure, and flow controller in AUTO set at 5600 gpm.

3. Place RHR system in Suppression Pool Cooling V. TASK STANDARD:

HPCI shutdown, per section 4.5, of S55.1.D, HPCI System Full Flow Functional Test.

VI. INITIAL CONDITIONS:

1. Unit 1 is at 100% power.

2. Unit 1 HPCI is operating in full flow test per S55.1.D.

3. RHR is in Suppression Pool Cooling

4. ST-6-060-390-1, Suppression Pool Temperature Check, is currently being performed by another operator.

VII. INITIATING CUE:

You are directed by Shift Supervision to shutdown Unit 1 HPCI, per S55.1.D.

LOJPM3020 Rev002.doc SRRS: 3D.105 Page 4 of 10 (When used for operator initial or continuing training)

I.FExelon Generation Information for Evaluator's Use:

Any UNSAT requires written comments on respective step.

Denotes critical steps Number any comments in the "Comment Number" column on the following pages. Then annotate that comment in the "Comments" section. The comment section should be used to document: the reason that a step is marked as unsatisfactory, marginal performance relating to management expectations, or problems the examinee had while performing the JPM.

Comments relating to procedural or equipment issues should be entered and tracked using the site's appropriate tracking system.

Some operations that are performed from outside the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed.

The JPM Start Time clock starts when the candidate acknowledges the initiating cue.

LOJPM3020 Rev002.doc SRRS: 3D.105 Page 5 of 10 (When used for operator initial or continuing training)

I,=Exelon Generation VIII. PERFORMANCE CHECKLIST:

JPM Start Time - - - - -

I- 0::

I- Zw

ELEMENT STANDARD I- <(

u, Wm

<(

u, z :E :E

, :E ::,

Oz 0

Lead Evaluator (or designee) Notes: Provide candidate with the following:

Individual Briefing Sheet, and

M/U copy, to section 4.5, of S55.1.D, HPCI System Full Flow Functional Test

1. Obtain copy of S55.1.D, HPCI S55.1.D, HPCI System Full System Full Flow Functional Test Flow Functional Test reviewed to section 4.5, System Restoration CUE: Ensure copy of S55.1.D, HPCI System Full Flow Functional Test available marked-up to section 4.5, System Restoration

2. [$55.1.D 4.5.1] FIC-55-1 R600 placed in ENSURE FC-55-*R600 in MANUAL.

"MANUAL".

3. [$55.1.D 4.5.2] Speed lowered using FIC

WHEN test is complete, THEN 1R600 by depressing the LOWER FC-55-*R600 until speed as "CLOSE" pushbutton in indicated on Sl-56-*61 is nominal MANUAL until Sl-56-161 2,250 rpm. indicates 2200 to 2300 RPM.

4. [$55.1.D 4.5.3] IF HV-55-*F071, "HPCI/RCIC Flush N/A Line to Suppression Pool" (TEST OUTBOARD), was opened to establish flow path to Suppression Pool, THEN CLOSE HV-55-*F071, TEST OUTBOARD.

5. {$55.1.D 4.5.4] HV-55-1 FOOS control switch CLOSE HV-55-*F008, "HPCI Test taken to CLOSE.

Loop Shutoff (TEST ISOL).

LOJPM3020 Rev002.doc SRRS: 3D.105 Page 6 of 10 (When used for operator initial or continuing training)

I=' Exelon Generation I- et:

I- ZW I- <( Wal

ELEMENT STANDARD <( en :E :E en z

, :E :::,

Oz 0

6. [S55.1.D 4.5.5] HV-55-1 F001 control switch Simultaneously CLOSE HV taken to close

F001,"HPCI Steam Supply" (INLET)

AND

6a. [S55.1.D 4.5.5] TURBINE TRIP pushbutton DEPRESS AND HOLD "Turbine depressed until HV-55-*F001, Trip" (TURBINE TRIP) pushbutton INLET, is fully closed.

until HV-55-*F001, INLET, is fully closed.

7. [S55. 1.D 4. 5. 6] TURBINE TRIP pushbutton WHEN HV-55-*F001, INLET, is fully released when HV-55-1 F001 closed, THEN RELEASE TURBINE is full closed.

TRIP pushbutton.

8. [S55.1.D 4.5. 7] When Sl-56-161 is between 0 WHEN Sl-56-*61, "HPCI Turbine and 1 ,200 rpm, 1OP213 AUX Speed" (S), is less than 1,200 rpm, OIL PUMP verified ON.

THEN VERIFY *OP213, "Auxiliary Oil Pump" (AUX OIL PUMP) is running.

9. [S55.1.D 4.5.8] FV-56-112 (STOP), OPEN.

VERIFY FV-56-*12, "HPCI Turbine Stop Valve" (STOP), open.

10. [S55.1.D 4.5.9] FV-56-112 remains open MONITOR position of FV-56-*12 while *OP213, AUX OIL while *OP213, AUX OIL PUMP, is PUMP, is running.

running.

11. [S55.1.D 4.5.10] HV-55-1 F012 CLOSED.

VERIFY HV-55-*F012, MIN FLOW, closed.

12. [S55.1.D 4.5.11] HV-55-1F041 CLOSED.

ENSURE HV-55-*F041, "HPCI Pump Suction from Suppression Pool" (SUPP POOL SUCTION) is closed.

LOJPM3020 Rev002.doc SRRS: 30.105 Page 7 of 10 (When used for operator initial or continuing training)

I,= Exelon Generation I-"

I- Zw I- <( Wal

ELEMENT STANDARD <( en z :E :E en ::::, :E::::,

Oz 0

13. [S55.1.D 4.5.11] HV-55-1F042 OPEN.

ENSURE HV-55-*F042 "HPCI Pump Suction from Suppression Pool" (SUPP POOL SUCTION) is open.

14.[S55.1.D 4.5.11] HV-55-1F028 OPEN.

ENSURE HV-55-*F028, "HPCI Steam Drain Line Isolation" Valve (TRAP INBOARD), is open.

15.[S55.1.D 4.5.11] HV-55-1 F029 OPEN.

ENSURE HV-55-*F029, "HPCI Steam Drain Line Isolation" (OUTBOARD TO COND), is open.

16.[S55.1.D 4.5.11] HV-55-1 F011 CLOSED.

ENSURE HV-55-*F011, "HPCI/RCIC Test Return to CST" (CONDENSATE RETURN), is closed.

17.[S55.1.D 4.5.11] HV-55-1F004 OPEN.

ENSURE HV-55-*F004, "HPCI Pump Suction" (COND TK SUCTION) is open.

18.[S55.1.D 4.5.11] HV-55-1 FOOS CLOSED ENSURE HV-55-*FOOB, "HPCI TEST Loop Shutoff (TEST ISOL), is closed.

CUE: You have met the termination criteria for this JPM JPM Completion Time _ _ _ __

LOJPM3020 Rev002.doc SRRS: 3D.105 Page 8 of 10 (When used for operator initial or continuing training)

I..:Er Exelon Generation JPM

SUMMARY

Operator's Name: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Job

Title:

D SEO D SM D SRO D RO D STA/IA D EO D OTHER JPM

Title:

SECURE UNIT 1 HPCI FOLLOWING FULL FLOW FUNCTIONAL TEST JPM Number: LOJPM3020 Revision Number: 002 Task Number and

Title:

2060030101 Shutdown HPCI System Following Automatic or Manual Initiation KIA Number and Importance: 206000 A4.04 3.7 / 3.7 Safety Function (1-9) 4 (Heat Removal from Core)

Admin Category (A1-4) N/A Level of Difficulty (1-5) ~

Suggested Testing Environment: Simulator Alternate Path: D Yes 1:8'.1 No SRO Only: D Yes 1:8'.1 No Time Critical: D Yes 1:8'.1 No Reference(s): S55.1.D, HPCI System Full Flow Functional Test, Rev.46 Actual Testing Environment: 1:8'.1 Simulator D Control Room D In-Plant D Other Testing Method: D Simulate 1:8'.1 Perform Estimated Time to Complete: 30 minutes Actual Time Used: minutes EVALUATION

SUMMARY

Were all the Critical Elements performed satisfactorily? D Yes D No The operator's performance was evaluated against standards contained within this JPM and has been determined to be: D Satisfactory D Unsatisfactory Comments:

Evaluator's Name: - - - - - - - - - - - - - - - - - (Print)

Evaluator's Signature: _ _ _ _ _ _ _ _ _ _ _ _ __ Date: _ _ _ _ __

LOJPM3020 Rev002.doc SRRS: 30.105 Page 9 of 10 (When used for operator initial or continuing training)

__.. Exelon Generation LIMERICK GENERATING STATION JOB PERFORMANCE MEASURE INDIVIDUAL BRIEFING SHEET INITIAL CONDITIONS:

1. Unit 1 is at 100% power.

2. Unit 1 HPCI is operating in full flow test per S55.1.D.

3. RHR is in Suppression Pool Cooling

4. ST-6-060-390-1, Suppression Pool Temperature Check, is currently being performed by another operator.

INITIATING CUE:

You are directed by Shift Supervision to shutdown Unit 1 HPCI, per S55.1.D.

Page 10 of 10

I=" Exelon Generation LIMERICK GENERATING STATION JOB PERFORMANCE MEASURE PERFORM A GROUP Ill NSSSS ISOLATION RESET JPM NUMBER: LOJPM3037 REVISION NUMBER: 004 DATE:

Developed By:

Instructor Date Validated By:

SME or Instructor Date Reviewed By:

Operations Representative Date Reviewed By:

EP Representative Date Approved By:

Training Department Date LOJPM3037 Rev004.doc SRRS: 3D.105 Page 1 of 10 (When used for operator initial or continuing training)

I:"" Exelon Generation I. JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation.

Prior to JPM usage, revalidate JPM using steps 9 through 13 below.

1. Task description and number, JPM description and number are identified.

2. Knowledge and Abilities (KIA) references are included.

3. Performance location specified. (in-plant, control room, simulator, or other)

4. Initial setup conditions are identified.

5. Initiating cues (and terminating cues if required) are properly identified.

6. Task standards identified and verified by SME review.

7. Critical steps meet the criteria for critical steps and are identified with an asterisk

(*).

8. If an alternate path is used, the task standard contains criteria for successful completion.

9. Verify the procedure(s) referenced by this JPM reflects the current revision:

Procedure GP-8 U/1 Rev: . . .;1. . ;:;.8__

Procedure GP-8. 1 U/1 Rev: - 16- -

Procedure Rev: - - -

Rev: _ __

Procedure Procedure

Rev: - - -

10. Verify cues both verbal and visual are free of conflict.

11. Verify performance time is accurate

12. If the JPM cannot be performed as written with proper responses, then revise the JPM.

13. When JPM is initially validated, sign and date JPM cover page.

Subsequent validations, sign and date below:

SME / Instructor Date SME / Instructor Date SME / Instructor Date LOJPM3037 Rev004.doc SRRS: 3D.105 Page 2 of 10 (When used for operator initial or continuing training)

I,=Exelon Generation II. RECORD OF TEMPORARY CHANGES:

A. Approval of Pen & Ink Changes will be by the ILT or LORT Lead Instructor with OTM concurrence B. All Pen & Ink Changes are to be tracked in ILT or LOR Program Action Tracking for Next Revision C. All Pen & Ink Changes shall be in accordance with TQ-AA-223 Temp Date of Purpose of Change ILT/LORT Action Revision Change# Change Approval Tracking Date Ill. REVISION HISTORY:

A. If a Revision affects a Task Performance from VISION Terminal Performance Objectives then the revision must also be made in the VISION database.

B. The description of the Revision should adequately indicate how the training content of the Revision has changed.

C. The description of the Revision should also include previous format reference and number and previous template used (i.e. for conversion to LLOJPM format).

D. For Revision 000, put reason for writing this JPM and for all subsequent revisions, annotate the changes that were made or incorporated.

Revision # Date of Description of Revision and Affect on Training Content Number Revision This JPM replaces LLOJPM0037 Rev. 4. The purpose of this revision 10/8/13 000 is to reformat with the new JPM template and to ensure agreement with latest procedure revision.

001 Minor editorial and typo fixes and to ensure agreement with latest 10/27/14 procedure revision.

002 Note: Rev 002 had no description of revision 003 Minor editorial changes and updated for the deletion of GP-8.3 U/1 10/03/16 Rev004 Added noun names to CAC Valves 9/27/17

Date of Revision - refers to date revision was released for approval LOJPM3037 Rev004.doc SRRS: 3D.105 Page 3 of 10 (When used for operator initial or continuing training)

1--=-Exelon Generation IV. SIMULATOR SETUP INSTRUCTIONS:

1. Reset simulator to IC-3, or another IC if JPM was validated in the respective IC.

NOTE: It is okay to use a similar IC to the IC listed above, provided the IC actually used is verified to be compatible with this and other JPMs that are scheduled to be run concurrently.

2. Insert Malt MNS158A, MNS1588, RWCU INBD AND OUTBD ISOLATION SIGNALS

3. Clear Malt MNS158A, MNS1588

4. Verify PPG displays indicate Group Ill isolation command= YES V. TASK STANDARD STATEMENT:

S32 A and D pushbuttons depressed with all Blue and Green reset switches in CLOSE as indicated by PPG indicating Group Ill isolation command= NO.

VI. INITIAL CONDITIONS:

1. Reactor Water Cleanup isolated due to a spurious RWCU differential flow signal.

2. The instrument problem has been corrected.

VII. INITIATING CUE STATEMENT (Describe the task clearly):

The CRS has directed you to reset the Unit 1 Group Ill isolation.

LOJPM3037 Rev004.doc SRRS: 3D.105 Page 4 of 10 (When used for operator initial or continuing training)

I: ' Exelon Generation Information for Evaluator's Use:

Any UNSAT requires written comments on respective step.

Denotes critical steps Number any comments in the "Comment Number" column on the following pages. Then annotate that comment in the "Comments" section. The comment section should be used to document: the reason that a step is marked as unsatisfactory, marginal performance relating to management expectations, or problems the examinee had while performing the JPM. Comments relating to procedural or equipment issues should be entered and tracked using the site's appropriate tracking system.

Some operations that are performed from outside the control room may require multiple steps.

These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed.

The JPM Start Time clock starts when the candidate acknowledges the initiating cue.

LOJPM3037 Rev004.doc SRRS: 3D.105 Page 5 of 10 (When used for operator initial or continuing training)

I;~ Exelon Generation VIII. PERFORMANCE CHECKLIST:

JPM Start Time-----

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1. Obtain current revision of GP-8 and Current revision of GP-8 U/1 GP-8.1 U/1. and GP-8.1 U/1 obtained.

CUE: Provide candidate with a copy of GP-8 and GP-8.1.)

2. Using GP-8 U/1 and/or GP-8.1 U/1 Determine R1 reset is determine all isolation signals are required (Signal J) and clear and an R1 reset is required. isolation signals are clear EVALUATORS NOTE: The sequence of placing Blue and Green switches to CLOSE is not critical.

(GP-8 U/1, 1.1.1.1) HV-41-1 F084 switch in

3. PLACE HV-41-1F084, "Main Steam" CLOSE position.

DRAIN SAMPLE INBOARD to "CLOSE".

4. PLACE HV-51-1F040, "'A' RHR HV-51-1 F040 switch in Drain to RNV outboard lsol. Viv. CLOSE position.

(OUTBOARD)", to "CLOSE"

5. PLACE HV-51-1F079A, "A RHR HV-51-1 F079A switch in Heat Exchanger" (SAMPLE CLOSE position.

INBOARD), to "CLOSE".

6. PLACE HV-51-1F079B, "B RHR HV-51-1F079B switch in Heat Exchanger" (SAMPLE CLOSE position.

INBOARD), to "CLOSE".

7. PLACE SV-57-133, "Cont Atmos SV-57-133 switch in CLOSE Sample" (ISOLA), to "CLOSE". position.

8. PLACE SV-57-183, 191 "Cont SV-57-183, 191 switch in Atmos Sample" (ISOLA), to CLOSE position.

"CLOSE".

LOJPM3037 Rev004.doc SRRS: 3D.105 Page 6 of 10 (When used for operator initial or continuing training)

I,:' Exelon Generation I- a::

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9. PLACE SV-57-132, 134, 150, "Cont SV-57-132, 134, 150 switch in Atmos Sample" (ISOL B}, to CLOSE position.

"CLOSE".

10. PLACE SV-57-181, "Cont Atmos SV-57-181 switch in CLOSE Sample" (ISOL B), to "CLOSE". position.

11. PLACE HV-41-1F085, "Main HV 1 F085 switch in Steam" (DRAIN SAMPLE CLOSE position.

OUTBOARD), to "CLOSE".

12. PLACE HV-51-1F080A, "A RHR HV-51-1F080A switch in Heat Exchanger" (SAMPLE CLOSE position.

OUTBOARD), to "CLOSE".

13. PLACE HV-51-1F080B, "A RHR HV-51-1 FOBOB switch in Heat Exchanger" (SAMPLE CLOSE position.

OUTBOARD}, to "CLOSE".

14. PLACE HS-57-187, "Atmosphere HS-57-187 switch in CLOSE Sample" (SUPP POOL ISOL). to position.

"CLOSE".

15. PLACE HS-57-153 "Atmosphere HS-57-153 switch in CLOSE Sample" (DRYWELL ISOL), to position.

"CLOSE".

16. PLACE HV-43-1F019, "Recirc HV-43-1 F019 switch in Sample" (INBOARD), to "CLOSE". CLOSE position.

17. PLACE HV-43-1F020, Recirc HV-43-1 F020 switch in Sample" (OUTBOARD), to CLOSE position.

"CLOSE".

(GP-8 U/1, 1.1.1.2) B21-S32A and B21-S32D pushbuttons depressed.

18. PRESS B21-S32A AND B21-S32D.

LOJPM3037 Rev004.doc SRRS: 3D.105 Page 7 of 10 (When used for operator initial or continuing training)

1-~ Exelon Generation I- a::

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19. Verify Group Ill isolation reset per Group Ill isolation signal not PPC. present on PPC screen "Containment lsol Valve Status".

CUE: You have met the termination criteria for this JPM JPM Completion Time _ _ _ __

LOJPM3037 Rev004.doc SRRS: 3D.105 Page 8 of 10 (When used for operator initial or continuing training)

I=' Exelon Generation JPM

SUMMARY

Operator's Name: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Job

Title:

D SEO D SM D SRO D RO D STA/IA D EO D OTHER JPM

Title:

PERFORM A GROUP Ill NSSSS ISOLATION RESET JPM Number: LOJPM3037 Revision Number: 004 Task Number and

Title:

2040080401, Place RWCU System Back in Service Following a Group Ill Isolation KIA Number and Importance: 223002 A4.03 3.6/3.5 Safety Function (1-9) 5 (Containment Integrity)

Admin Category (A1-4) N/A Level of Difficulty (1-5) 3 Suggested Testing Environment: Simulator Alternate Path:0 Yes [8J No SRO Only: D Yes [8J No Time Critical: D Yes [8J No Reference(s): GP-8 U/1 Rev. 18 GP-8.1 U/1 Rev. 16 Actual Testing Environment: [8J Simulator D Control Room D In-Plant D Other Testing Method: D Simulate [8J Perform Estimated Time to Complete: 15 minutes Actual Time Used: minutes EVALUATION

SUMMARY

Were all the Critical Elements performed satisfactorily? D Yes D No The operator's performance was evaluated against standards contained within this JPM and has been determined to be: D Satisfactory D Unsatisfactory Comments:

Evaluator's Name: - - - - - - - - - - - - - - - - - (Print)

Evaluator's Signature: _ _ _ _ _ _ _ _ _ _ _ _ _ __ Date:

LOJPM3037 Rev004.doc SRRS: 30.105 Page 9 of 10 (When used for operator initial or continuing training)

! Exelon Generation LIMERICK GENERATING STATION JOB PERFORMANCE MEASURE INDIVIDUAL BRIEFING SHEET INITIAL CONDITIONS:

1. Reactor Water Cleanup isolated due to a spurious RWCU differential flow signal.

2. The instrument problem has been corrected.

INITIATING CUE STATEMENT:

The CRS has directed you to reset the Unit 1 Group Ill isolation.

Page 10 of 10

I~ Exelon Generation LIMERICK GENERATING STATION JOB PERFORMANCE MEASURE RESETTING A 42% RECIRCULATION SYSTEM RUNBACK JPM Number: LOJPM3119 REVISION NUMBER: 000 DATE: - - - -

Developed By:

Instructor Date Validated By:

SME or Instructor Date Reviewed By:

Operations Representative Date Reviewed By: NIA NIA EP Representative Date Approved By:

Training Department Date LOJPM3119 RevOOO.doc SRRS: 3D.105 Page 1 of 11 (When used for operator initial or continuing training)

I=' Exelon Generation Note: This LGS format satisfies the TQ-JA-150 Format I. JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation.

Prior to JPM usage, revalidate JPM using steps 9 through 13 below.

1. Task description and number, JPM description and number are identified.

2. Knowledge and Abilities (KIA) references are included.

3. Performance location specified. (in-plant, control room, simulator, or other)

4. Initial setup conditions are identified.

5. Initiating cues (and terminating cues if required) are properly identified.

6. Task standards identified and verified by SME review.

7. Critical steps meet the criteria for critical steps and are identified with an asterisk

(*}.

8. If an alternate path is used, the task standard contains criteria for successful completion.

9. Verify the procedure(s) referenced by this JPM reflects the current revision:

Procedure S43.0.B Rev: ........_

27 __

Procedure ARC MCR 111 A-5 Procedure ARC MCR 112 A-5 Rev: 1 Rev: - ' - - -

Procedure Rev: _ __

Procedure

Rev: - - -

10. Verify cues both verbal and visual are free of conflict.

11. Verify performance time is accurate

12. If the JPM cannot be performed as written with proper responses, then revise the JPM.

13. When JPM is initially validated, sign and date JPM cover page.

Subsequent validations, sign and date below:

SME / Instructor Date SME / Instructor Date SME / Instructor Date LOJPM3119 RevOOO.doc SRRS: 3D.105 Page 2 of 11 (When used for operator initial or continuing training)

I , :Exelon Generation II. RECORD OF TEMPORARY CHANGES:

A. Approval of Pen & Ink Changes will be by the ILTor LORT Lead Instructor with OTM concurrence B. All Pen & Ink Changes are to be tracked in ILT or LOR Program Action Tracking for Next Revision C. All Pen & Ink Changes shall be in accordance with TQ-AA-223 Temp Date of Purpose of Change ILT/LORT Action Revision Change# Change Approval Tracking Date Ill. REVISION HISTORY:

A. If a Revision affects a Task Performance from VISION Terminal Performance Objectives then the revision must also be made in the VISION database.

B. The description of the Revision should adequately indicate how the training content of the Revision has changed.

C. The description of the Revision should also include previous format reference and number and previous template used (i.e. for conversion to LLOJPM format).

D. For Revision 000, put reason for writing this JPM and for all subsequent revisions, annotate the changes that were made or incorporated.

Revision # Date of Description of Revision and Affect on Training Content Number Revision This New JPM resets the 42% recirc runback with alternate path of 8/1/17 000 loss of Recirc Pump cooling added.

Date of Revision - refers to date revision was released for approval LOJPM3119 RevOOO.doc SRRS: 30.105 Page 3 of 11 (When used for operator initial or continuing training)

I,FExelon Generation IV. SIMULATOR SETUP INSTRUCTIONS:

1. Reset simulator to IC-3, or another IC if JPM was validated in the respective IC.

NOTE: It is okay to use a similar IC to the IC listed above, provided the IC actually used is verified to be compatible with this and other JPMs that are scheduled to be run concurrently.

2. Insert Malfunction MRR505A with a deactivation time of 30 seconds.

3. Insert Malfunction MRR506A with a deactivation time of 30 seconds.

4. Ensure Rx power is < 75%

5. Insert the following.

r Timer Pause DeleteA/1 J 11111 [I Pending LOJPM3119 RevOOO.doc SRRS: 3D.105 Page 4 of 11 (When used for operator initial or continuing training)

Ir Exelon Generation favorites Iriggers Tri er# Trigger Text Operators 1 RROSPBRBRST Arithmetic:

2

Multiplication 3 I Division 4 + Addtion 5 - Subtraction 6

Relational:

7

> Greater than 8

>* Greater than 9 or equal 10 < Less than 11 <= Less than or 12 equal 13 == Equal to 14 != Not equal to 15 Logical:

16 t.t. And 17 18 II Or

! Not 19

? Other:

Open Paren Close Paren Irigger Now l .Clear C_learAII l!,ccept V. TASK STANDARD:

Recirc Pump High Limit Runback reset and alternate DWCW loop selected for Recirc Motor Coolers.

VI. INITIAL CONDITIONS:

1. Unit 1 was at 100% power when the '1A' Condensate Pump tripped.

2. The plant received a 42% runback on both Reactor Recirculation Pumps.

3. '1A' Condensate Pump has been returned to service.

4. SS-043-105A(B), 1A(B) ASD Local/Remote Selector Switch has been verified to be in "REMOTE" at 1OC042A(B)

5. No other Recirc Pump RUNBACK conditions exist at this time.

VII. INITIATING CUE:

You are directed by Shift Supervision to reset the 42% runback on the '1A' and '1 B' Reactor Recirculation Pumps per S43.0.B and clear all system alarms.

LOJPM3119 RevOOO.doc SRRS: 3D.105 Page 5 of 11 (When used for operator initial or continuing training)

I,:'Exelon Generation Information for Evaluator's Use:

Any UNSAT requires written comments on respective step.

Denotes critical steps Number any comments in the "Comment Number" column on the following pages. Then annotate that comment in the "Comments" section. The comment section should be used to document: the reason that a step is marked as unsatisfactory, marginal performance relating to management expectations, or problems the examinee had while performing the JPM.

Comments relating to procedural or equipment issues should be entered and tracked using the site's appropriate tracking system.

Some operations that are performed from outside the control room may require multiple steps.

These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed.

The JPM Start Time clock starts when the candidate acknowledges the initiating cue.

LOJPM3119 RevOOO.doc SRRS: 3D.105 Page 6 of 11 (When used for operator initial or continuing training)

I; Exelon Generation VIII. PERFORMANCE CHECKLIST:

JPM Start Time - - - - -

I- ~

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1. Obtain a current revision of S43.0.B, Current revision of S43.0.B Resetting a Recirculation System obtained.

Runback.

CUE: Provide a current revision of S43.0.B.

2. ($43.0.B 4.1.1)

VERIFY all prerequisites satisfied. N/A CUE: If asked, say, "All Recirc Pump RUNBACK conditions have been corrected per initiating conditions"

3. ($43.0.B 4.1.2) Verified Unit 1 Recirculation VERIFY procedure being performed on System correct uniUtrain.

4. ($43.0.B 4 .. 2.1) '1A' Recirc Pump motor speed VERIFY that *A Recirc Pump motor demand is verified to be within speed demand is the same(+/- 5 rpm) +/- 5 rpm of speed indicated on as motor speed as indicated on Xl-043- Xl-043-13A on 1OC626 OR XR-

3A, "ASD *A MCR HMI" on panel 043-101A recorder at 10C602.

OC626 OR XR-043-*01A "ASD *A Speed/Demand Recorder" at panel

OC602.

5. ($43.0.B 4.2.2) '1 B' Recirc Pump motor speed VERIFY that *B Recirc Pump motor demand is verified to be within speed is the same(+/- 5 rpm) as motor +/- 5 rpm of speed indicated on speed as indicated on Xl-043-*38, "ASD Xl-043-138 on 1OC626 OR XR-

B MCR HMI" on panel *OC626 043-1 01 B recorder at 1OC602.

OR XR-043-*01 B "ASD *B Speed/Demand Recorder" at panel

OC602.

LOJPM3119 RevOOO.doc SRRS: 3D.105 Page 7 of 11 (When used for operator initial or continuing training)

I:' Exelon Generation I- 0:::

I- Zw I- <( Wal ELEMENT STANDARD <( UJ :E :E UJ z

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EVALUATORS NOTE: Alternate Path will begin when PB-043-106, ASD Runback Reset is depressed. DWCW flow to the 'A' and 'B' Recirc pumps will be reduced initiating the 'Recirc Pump Winding Cooler Lo Flow' alarm (MCR-ARC 111/112 RECIRC A-5). The operator will verify the DWCW low flow condition and place the alternate DWCW loop is service per the ARC.

6. ($43.0.B 4.2.3) PB-043-106 "ASD Runback

PRESS AND RELEASE PB-043-*06 Reset" depressed and released.

"ASD Runback Reset" at panel *OC602.

7. ($43.0.B 4.2.4) HIGH AND LOW LIMIT lights VERIFY HIGH AND LOW LIMIT verified extinguished for 'A' and runback indication for both pumps light 'B' pumps on 10C602.

not lit at panel *OC602.

8. ($43.0.B 4.2.5) 111 C-4and 112C-4 VERIFY the following annunciators annunciators cleared.

clear:

ARC-MCR-*11 C4, *A RECIRC FLOW LIMIT

ARC-MCR-*12 C4, *B RECIRC FLOW LIMIT

9. ($43.0.B 4.2.6) PB-043-107 A depressed twice PRESS PB-043-*07A, "*A ASD Fault to clear alarms.

Reset" pushbutton two times to clear any applicable alarms.

10.($43.0.B 4.2. 7) PB-043-1078 depressed twice to clear alarms.

PRESS PB-043-*078, "*B ASD Fault Reset" pushbutton two times to clear any applicable alarms.

11. Respond to annunciators 111 /112 Acknowledge annunciators RECIRC A-5 1A/B Recirc Pump Motor 111/112 RECIRC A-5, and Winding Cooling Water Lo Flow reference ARCs for alarms

12. (111 REC/RC A-5/112 CLEANUPA-5) Flow to Recirc Pumps A and B, Verify low flow using Fl-87-157 A/B, on using Fl-87-157A/B, indicates 10C681 low LOJPM3119 RevOOO.doc SRRS: 3D.105 Page 8 of 11 (When used for operator initial or continuing training)

I,,;:;- Exelon Generation I- er:::

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13. (111 REC/RC A-5) Alternate Loop DWCW (Loop B)

Put alternate Drywell Chilled Water placed in service, HSS-087-loop into service by placing HSS-087- 151 placed in Loop B 151 in Loop A (Loop B) as required.

14. (112 CLEANUP A-5) Alternate Loop DWCW (Loop B)

Put alternate Drywell Chilled Water loop placed in service, HSS-087-150 placed in Loop B into service by placing HSS-087-150 in Loop A (Loop B) as required

15. (111 REC/RC A-51112 CLEANUP A-5) Candidate references S43.0.D Monitor motor winding temperatures per to monitor Recirc Pump Motor Winding temperatures.

S43.0.D CUE: You have met the termination criteria for this JPM JPM Completion Time LOJPM3119 RevOOO.doc SRRS: 3D.105 Page 9 of 11 (When used for operator initial or continuing training)

I-=' Exelon Generation JPM

SUMMARY

Operator's Name: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __..:.

Job

Title:

D SEO D SM D SRO D RO D STA/IA D EO D OTHER JPM

Title:

RESETIING A 42% RECIRCULATION SYSTEM RUNBACK JPM Number: LOJPM3911 Revision Number: 000 Task Number and

Title:

2020070401 Reset a Recirc System Runback KIA Number and Importance: 202001 A3.04 3.2/3.1 Safety Function (1-9) 1 (Reactivity Control)

Admin Category (A1-4) N/A Level of Difficulty (1-5) _3__

Suggested Testing Environment: Simulator Alternate Path: lS'.I Yes D No SRO Only: D Yes lS'.I No Time Critical: D Yes lS'.I No Reference(s): S43.0.B, Resetting a Recirculation System Runback, Rev. 27.

ARC-MCR-111 A-5 1A Recirc Pump Motor Winding Cooling Water Lo Flow, Rev 1 ARC-MCR-112 A-5 1B Recirc Pump Motor Winding Cooling Water Lo Flow, Rev 1 Actual Testing Environment: 1SJ Simulator D Control Room D In-Plant D Other Testing Method: D Simulate lS'.I Perform Estimated Time to Complete: 15 minutes Actual Time Used: minutes EVALUATION

SUMMARY

Were all the Critical Elements performed satisfactorily? D Yes D No The operator's performance was evaluated against standards contained within this JPM and has been determined to be: D Satisfactory D Unsatisfactory Comments:

Evaluator's N a m e : - - - - - - - - - - - - - - - - - (Print)

Evaluator's Signature: _ _ _ _ _ _ _ _ _ _ _ _ _ __ Date: ----

LOJPM3119 RevOOO.doc SRRS: 3D.105 Page 10 of 11 (When used for operator initial or continuing training)

,,,:,.* Exelon Generation LIMERICK GENERATING STATION JOB PERFORMANCE MEASURE INDIVIDUAL BRIEFING SHEET INITIAL CONDITIONS:

1. Unit 1 was at 100% power when the '1A' Condensate Pump tripped.

2. The plant received a 42% runback on both Reactor Recirculation Pumps.

3. '1A' Condensate Pump has been returned to service.

4. SS-043-105A(B), 1A(B) ASD Local/Remote Selector Switch has been verified to be in "REMOTE" at 1OC042A(B)

5. No other Recirc Pump RUNBACK conditions exist at this time.

INITIATING CUE:

You are directed by Shift Supervision to reset the 42% runback on the '1A' and '1 B' Reactor Recirculation Pumps per S43.0.B and clear all system alarms.

Page 11 of 11

I=" Exelon Generation LIMERICK GENERATING STATION JOB PERFORMANCE MEASURE PLACING ALTERNATE RECW PUMP IN SERVICE JPM Number: LOJPM3129 REVISION NUMBER: 003 DATE: - - - - -

Developed By:

Instructor Date Validated By:

SME or Instructor Date Reviewed By:

Operations Representative Date Reviewed By:

EP Representative Date Approved By:

Training Department Date LOJPM3129 Rev003.doc SRRS: 3D.105 Page 1 of 11 (When used for operator initial or continuing training)

I.="" Exelon Generation Note: This LGS format satisfies the TQ-JA-150 Format I. JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation.

Prior to JPM usage, revalidate JPM using steps 9 through 13 below.

1. Task description and number, JPM description and number are identified.

2. Knowledge and Abilities (KIA) references are included.

3. Performance location specified. (in-plant, control room, simulator, or other)

4. Initial setup conditions are identified.

5. Initiating cues (and terminating cues if required) are properly identified.

6. Task standards identified and verified by SME review.

7. Critical steps meet the criteria for critical steps and are identified with an asterisk

(*).

8. If an alternate path is used, the task standard contains criteria for successful completion.

9. Verify the procedure(s) referenced by this JPM reflects the current revision:

Procedure S13.6.A Rev: 10 Procedure ARC MCR 118 H-3 Rev: ~--

1 Procedure---------- Rev: _ __

Procedure - - - - - - - - - - Rev: _ __

Procedure Rev:

10.

Verify cues both verbal and visual are free of conflict.

11. Verify performance time is accurate

12. If the JPM cannot be performed as written with proper responses, then revise the JPM.

13. When JPM is initially validated, sign and date JPM cover page.

Subsequent validations, sign and date below:

SME / Instructor Date SME / Instructor Date SME / Instructor Date LOJPM3129 Rev003.doc SRRS: 3D.105 Page 2 of 11 (When used for operator initial or continuing training)

I ,F Exelon Generation II. RECORD OF TEMPORARY CHANGES:

A. Approval of Pen & Ink Changes will be by the ILT or LORT Lead Instructor with OTM concurrence B. All Pen & Ink Changes are to be tracked in ILT or LOR Program Action Tracking for Next Revision C. All Pen & Ink Changes shall be in accordance with TQ-AA-223 Temp Date of Purpose of Change ILT/LORT Action Revision Change# Change Approval Tracking Date Ill. REVISION HISTORY:

A. If a Revision affects a Task Performance from VISION Terminal Performance Objectives then the revision must also be made in the VISION database.

B. The description of the Revision should adequately indicate how the training content of the Revision has changed.

C. The description of the Revision should also include previous format reference and number and previous template used (i.e. for conversion to LLOJPM format).

D. For Revision 000, put reason for writing this JPM and for all subsequent revisions, annotate the changes that were made or incorporated.

Revision # Date of Description of Revision and Affect on Training Content Number Revision This JPM replaces LLOJPM0129 Rev. 6. Revised to new template and 11/13/13 000 to align with latest procedure revision. Made final JPM step for securina '1 B' RECW Pumo critical.

001 Minor format changes. 12/23/14 002 Revised to new JPM template and procedure revision 10/19/16 003 Minor format changes. 8/21/17

Date of Revision - refers to date revision was released for approval LOJPM3129 Rev003.doc SRRS: 3D.105 Page 3 of 11 (When used for operator initial or continuing training)

I,:' Exelon Generation IV. SIMULATOR SETUP INSTRUCTIONS:

1. Reset simulator to IC-3, or another IC if JPM was validated in the respective IC.

NOTE: It is okay to use a similar IC to the IC listed above, provided the IC actually used is verified to be compatible with this and other JPMs that are scheduled to be run concurrently.

2. INSERT the following malfunctions on Trigger_ltl_when '1A' RECW pump is secured.

a. DELETE Pl-13-108 Override when '1A' RECW pump is RESTARTED (instructor station P&ID can be used to determine pump status).

r Timer Pause Pending

Annunciator Summary r Timer Pause Delete All Pending LOJPM3129 Rev003.doc SRRS: 3D.105 Page 4 of 11 (When used for operator initial or continuing training)

I: ' Exelon Generation r a :* O~talm 1 ZCC,00 AIJ~ic:

2 I M~~i°'

3 I DhW)

~

Mtoo 5

I

Sl.tJIJw 6

R~~

7 0

> Gr~eftlm V. TASK STANDARD:

'8' RECW Pump shutdown and 'A' RECW Pump restarted.

VI. INITIAL CONDITIONS:

1. The '1A' RECW Pump is in service, the '18' RECW Pump is in "AUTO"

2. The '1A' RECW Pump is to be removed from service to support scheduled maintenance to repack the pump

3. '18' RECW pump is ready for start with the following conditions:

a. 13-10018, "RECW Pump Suction" and 13-10058, "RECW Pump Discharge" are open

b. Pump has been successfully vented, and 13-10038 "RECW Pump Vent" is closed

c. Pump oil level is in the green band

d. The EO is standing by to support swapping RECW Pumps VII. INITIATING CUE:

Shift Supervision directs you to start the '18' RECW pump and to remove the '1A' RECW pump from service per S13.6.A, Placing Alternate RECW Pump in Service.

LOJPM3129 Rev003.doc SRRS: 3D.105 Page 5 of 11 (When used for operator initial or continuing training)

j .F ExelonGeneration Information for Evaluator's Use:

Any UNSAT requires written comments on respective step.

Denotes critical steps Number any comments in the "Comment Number" column on the following pages. Then annotate that comment in the "Comments" section. The comment section should be used to document: the reason that a step is marked as unsatisfactory, marginal performance relating to management expectations, or problems the examinee had while performing the JPM.

Comments relating to procedural or equipment issues should be entered and tracked using the site's appropriate tracking system.

Some operations that are performed from outside the control room may require multiple steps.

These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed.

The JPM Start Time clock starts when the candidate acknowledges the initiating cue.

LOJPM3129 Rev003.doc SRRS: 3D.105 Page 6 of 11 (When used for operator initial or continuing training)

I? Exelon Generation VIII. PERFORMANCE CHECKLIST:

JPM Start Time -----

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1. OBTAIN current revision of S13.6.A, N/A Placing Alternate RECW Pump in Service.

2. (S13.6.A, 4.1) VERIFY all N/A prerequisites satisfied.

Provided in Initiating Cue

3. (S13.6.A, 4.2) VERIFY procedure Verify on Unit 1 being performed on correct unit.

4. (S13.6.A, 4.3) VERIFY standby 13- N/A 10018, "RECW Pump Suction Provided in Initiating Cue Valve," open.

5. (S13.6.A, 4.4) VERIFY standby 13- NIA 10058, "RECW Pump Discharge Provided in Initiating Cue Valve," open.

6a. (S13.6.A, 4.5) OPEN standby N/A 13-10038, "RECW Pump Vent,"

Provided in Initiating Cue until a steady stream is observed.

6b. (S13.6.A, 4.6) WHEN a steady, N/A solid stream of water flows, THEN Provided in Initiating Cue CLOSE vent.

7. (S13.6.A, 4.7) ENSURE standby N/A 18P210, "Rx Encl Pump" (PUMP) oil Provided in Initiating Cue level is in green band.

8. (S13.6.A, 4.8) START standby HS-13-1038 ("18" RECW 18P210, "Rx Encl Pump" (PUMP) pump Handswitch) is taken to

START.

AND PERFORM the following:

LOJPM3129 Rev003.doc SRRS: 3D.105 Page 7 of 11 (When used for operator initial or continuing training)

I; Exelon Generation I- 0::

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8a. VERIFY Pl-13-1068, "RECW Pump "1 B" RECW pump discharge Disch," is 160 to 180 psig. pressure verified.

CUE: The EO reports that "1 B" RECW pump discharge pressure is 175 psig.

8b. VERIFY no excessive vibration OR "1 B" RECW pump is verified noise at pump/motor. to not have excessive vibration or noise.

CUE: The EO reports that no excessive vibration or noise is noted for "1 B" RECWpump.

9. (S13.6.A, 4.9) STOP desired 1AP210, HS-13-103A ("1A" RECW "RECW Pump" (Pump). pump Handswitch) is taken to

"STOP" NOTE TO EVALUATOR AND DRIVER: Alternate path begins with next step. Trigger #1 automatically actuates when '1A' RECW Pump is secured to initiate RECW discharge pressure decreasing to 80 psig

10. RESPOND to "REAC ENCL Alarm reported to CRS COOLING WATER HTX OUT LO PRESS" alarm.

11. REFERENCE ARC-MCR 118 H -3 ARC for 118 H-3 "REAC "REAC ENCL COOLING WATER ENCL COOLING WATER HTX OUT LO PRESS" HTX OUT LO PRESS referenced.

LOJPM3129 Rev003.doc SRRS: 3D.105 Page 8 of 11 (When used for operator initial or continuing training)

=-

Exelon Generation ELEMENT STANDARD I-

<(

en

12. VERIFY low RECW Supply pressure RECW low supply pressure using Pl-13-108 at 1OC655. (80 psig) verified at Pl-13-108 at 10C655.

IF EO at RECW pump is contacted:

CUE: '1 B' RECW Pump discharge pressure has dropped to 80 psig, and the pump is making excessive noise."

IF CRS is contacted:

CUE: The CRS directs you to take the required action to restore RECW and place any degraded equipment in a safe condition.

EVALUTOR NOTE: The candidate may enter ON-113 for loss of RECW due to the low pressure condition. If this procedure is followed, step 2.6 will lead candidate back into S13.6.A to place the alternate pump in service.

NOTE TO EVALUATOR AND DRIVER:

When'1A' RECW pump is restarted, the Pl-13-108 "RECW Supply Pressure" indication override is removed.

13. START 1AP210, "RECW Pump" HS-13-103A ("1A" RECW

(PUMP) pump Handswitch) is taken to START.

14. STOP 1BP210, "RECW Pump" HS-13-1038 ("18" RECW

(PUMP) pump Handswitch) is taken to "STOP"

15. VERIFY "RECW Pump Disch," is RECW Pump Disch," is 160 to 180 psig on Pl-13-108 on 175 psig. and 118 H -3, REAC 1OC655 and 118 H -3, REAC ENCL ENCL clear.

COOLING WATER HTX OUT LO PRESS is clear.

CUE: You have met the termination criteria for this JPM JPM Completion Time _ _ _ __

LOJPM3129 Rev003.doc SRRS: 30.105 Page 9 of 11 (When used for operator initial or continuing training)

I,FExelon Generation JPM

SUMMARY

Operator's Name: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ___..;.

Job

Title:

D SEO D SM D SRO D RO D STNIA D EO D OTHER JPM

Title:

PLACING ALTERNATE RECW PUMP IN SERVICE JPM Number: LOJPM3129 Revision Number: 003 Task Number and

Title:

TP0-2080030101, Place Alternate RECW Pump in Service KIA Number and Importance: 400000 A2.01 3.3/3.4 Safety Function (1-9) 8 (Plant Service System)

Admin Category (A1-4) NIA Level of Difficulty (1-5) ...L Suggested Testing Environment: Simulator Alternate Path:~ Yes D No SRO Only: D Yes~ No Time Critical: D Yes~ No Reference(s): S13.6.A, Placing Alternate RECW Pump in Service, Rev.10 Actual Testing Environment: ~ Simulator D Control Room D In-Plant D Other Testing Method: D Simulate ~ Perform Estimated Time to Complete: 15 minutes Actual Time Used: minutes EVALUATION

SUMMARY

Were all the Critical Elements performed satisfactorily? D Yes D No The operator's performance was evaluated against standards contained within this JPM and has been determined to be: D Satisfactory D Unsatisfactory Comments:

Evaluator's Name: - - - - - - - - - - - - - - - - - (Print)

Evaluator's Signature: _ _ _ _ _ _ _ _ _ _ _ _ _ __ Date: ---

LOJPM3129 Rev003.doc SRRS: 3D.105 Page 10 of 11 (When used for operator initial or continuing training)

=r--- Exelon Generation LIMERICK GENERATING STATION JOB PERFORMANCE MEASURE INDIVIDUAL BRIEFING SHEET INITIAL CONDITIONS:

1. The '1A' RECW Pump is in service, the '18' RECW Pump is in "AUTO"

2. The '1A' RECW Pump is to be removed from service to support scheduled maintenance to repack the pump

3. '18' RECW pump is ready for start with the following conditions:

a. 13-10018, "RECW Pump Suction" and 13-10058, "RECW Pump Discharge" are open

b. Pump has been successfully vented, and 13-10038 "RECW Pump Vent" is closed

c. Pump oil level is in the green band

d. The EO is standing by to support swapping RECW Pumps INITIATING CUE:

Shift Supervision directs you to start the '18' RECW pump and to remove the '1A' RECW pump from service per S13.6.A, Placing Alternate RECW Pump in Service.

Page 11 of 11

1-= Exelon Generation LIMERICK GENERATING STATION JOB PERFORMANCE MEASURE EHC PUMP OPERABILITY TEST JPM Number: LOJPM3140 REVISION NUMBER: 000 DATE: - - - -

Developed By:

Instructor Date Validated By:

SME or Instructor Date Reviewed By:

Operations Representative Date Reviewed By: N/A N/A EP Representative Date Approved By:

Training Department Date LOJPM3140 RevOOO.doc SRRS: 3D.105 Page 1 of 13 (When used for operator initial or continuing training)

j ,='Exelon Generation Note: This LGS format satisfies the TQ-JA-150 Format I. JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation.

Prior to JPM usage, revalidate JPM using steps 9 through 13 below.

1. Task description and number, JPM description and number are identified.

2. Knowledge and Abilities (KIA) references are included.

3. Performance location specified. (in-plant, control room, simulator, or other)

4. Initial setup conditions are identified.

5. Initiating cues (and terminating cues if required) are properly identified.

6. Task standards identified and verified by SME review.

7. Critical steps meet the criteria for critical steps and are identified with an asterisk

(*}.

8. If an alternate path is used, the task standard contains criteria for successful completion.

9. Verify the procedure(s) referenced by this JPM reflects the current revision:

Procedure RT-6-031-320-1 Rev: ~--

27 Procedure ARC-MCR-107 G-2 Rev: - - ' - -

Procedure ARC-MCR-107 H-2 Procedure OT-102 Rev: 3 Rev: -=---

27 Procedure Rev: _ __

10. Verify cues both verbal and visual are free of conflict.

11. Verify performance time is accurate

12. If the JPM cannot be performed as written with proper responses, then revise the JPM.

13. When JPM is initially validated, sign and date JPM cover page.

Subsequent validations, sign and date below:

SME / Instructor Date SME / Instructor Date SME / Instructor Date LOJPM3140 RevOOO.doc SRRS: 3D.105 Page 2 of 13 (When used for operator initial or continuing training)

j $ Exelon Generation II. RECORD OF TEMPORARY CHANGES:

A. Approval of Pen & Ink Changes will be by the ILT or LORT Lead Instructor with OTM concurrence B. All Pen & Ink Changes are to be tracked in ILT or LOR Program Action Tracking for Next Revision C. All Pen & Ink Changes shall be in accordance with TQ-AA-223 Temp Date of Purpose of Change ILT/LORT Action Revision Change# Change Approval Tracking Date Ill. REVISION HISTORY:

A. If a Revision affects a Task Performance from VISION Terminal Performance Objectives then the revision must also be made in the VISION database.

B. The description of the Revision should adequately indicate how the training content of the Revision has changed.

C. The description of the Revision should also include previous format reference and number and previous template used (i.e. for conversion to LLOJPM format).

D. For Revision 000, put reason for writing this JPM and for all subsequent revisions, annotate the changes that were made or incorporated.

Revision # Date of Description of Revision and Affect on Training Content Number Revision 000 This is a new JPM 8/1/17

Date of Revision - refers to date revision was released for approval LOJPM3140 RevOOO.doc SRRS: 3D.105 Page 3 of 13 (When used for operator initial or continuing training)

I:' Exelon Generation IV. TASK STANDARD:

'1A' EHC Pump tested, upon securing '1A' EHC the operator responds to rising reactor pressure, entering OT-102, Reactor High Pressure and reduces reactor power to clear the High Pressure alarm. Investigation reveals the TSV #3 has failed closed causing the reactor high pressure. Operator further reduces reactor power to 88% as directed by OT-102.

V. SIMULATOR SETUP

1. Reset simulator to IC-3, or another IC if JPM was validated in the respective IC.

NOTE: It is acceptable to use a similar IC to the IC listed above, provided the IC actually used is verified to be compatible with this and other JPMs that are scheduled to be run concurrently.

2. Ensure 1A EHC Pump in service

3. Build the following - manual trigger #1 to start the '1 B' EHC Pump, and automatic trigger #2 to close the #3 TSV in 20 seconds after the '1A' EHC Pump is secured.

TRIGGER/ MALFUNCTION /

(o TIME EVENT DESCRIPTION

1 Manual Starts '1 B' EHC Pump (local start)

2 '1A' EHC Pump HS to STOP Auto/ ZDl81 (1239)

Initiates #3 TSV to close (20 sec T/D)

-~,':'* ~-~-x_ r

.Eavorites Iriggers Trigger# Trigger Text Operators:

1 Arithmetic:

2 20181(1239) .. Multiplication 3 / Division 4 + Addition 5

Subtraction 6

Relational:

7 8

> Greater then 9

>- Greater than or equal 10 < Less than

<

Less than or 12 equal 13 == Equ81 to 14 !- Not equal to 15 Logical:

16 8.8. And 17 II Or

! Not Other:

Open Paren Clo#e Paren t;lear _J Cjear AH Accept LOJPM3140 RevOOO.doc SRRS: 3D.105 Page 4 of 13 (When used for operator initial or continuing training)

I,£"" Exelon Generation SIMULATOR SETUP cont'd r Timer Pause VI. INITIAL CONDITIONS:

1. 1AP113, '1A' EHC Pump is running.

2. 1BP113, '1 B' EHC Pump is available.

3. An EO is located at the EHC Power Unit.

4. SSV permission has been given to start test.

5. U1 RO permission has been given to start test.

VII. INITIATING CUE:

Shift Supervision directs you perform RT-6-031-320-1, Unit 1 EHC Pump Operability/

Performance Check.

LOJPM3140 RevOOO.doc SRRS: 3D.105 Page 5 of 13 (When used for operator initial or continuing training)

I*::=-' Exelon Generation Information for Evaluator's Use:

Any UNSAT requires written comments on respective step.

Denotes critical steps Number any comments in the "Comment Number" column on the following pages. Then annotate that comment in the "Comments" section. The comment section should be used to document: the reason that a step is marked as unsatisfactory, marginal performance relating to management expectations, or problems the examinee had while performing the JPM.

Comments relating to procedural or equipment issues should be entered and tracked using the site's appropriate tracking system.

Some operations that are performed from outside the control room may require multiple steps.

These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed.

The JPM Start Time clock starts when the candidate acknowledges the initiating cue.

LOJPM3140 RevOOO.doc SRRS: 30.105 Page 6 of 13 (When used for operator initial or continuing training)

I=- Exelon Generation VIII. PERFORMANCE CHECKLIST:

JPM Start Time - - - - -

I- 0:::

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1. Obtain current revision of RT-6-031- Candidate obtains copy of 320-1, EHC Pump Operability/ RT-6-031-320-1 Performance Check.

CUE: Candidate is given a copy of RT-6-031-320-1 when knowledge of the correct location of procedure is demonstrated.

2. (RT-6-031-320-1 4.1.1) Prerequisites verified VERIFY all prerequisites of RT 031-320-1, section 2.0 are satisfied.

3. (RT-6-031-320-1 4.1.2) Unit 1 verified VERIFY procedure being performed on unit 1.

4. (RT-6-031-320-1 4.2.1) Permission provided in initial OBTAIN SSV permission to start conditions test.

5. (RT-6-031-320-1 4.2.2) Permission provided in initial OBTAIN PRO/RO permission to conditions start test.

6. (RT-6-031-320-1 4.2.3) Candidate determines section

IF pump 1BP113 is currently 4.3 is to be performed first running, THEN PERFORM Section 4.4 before Section 4.3.

7. (RT-6-031-320-1 4.2.4) Candidate circles 1AP113 CIRCLE running pump LOJPM3140 RevOOO.doc SRRS: 3D.105 Page 7 of 13 (When used for operator initial or continuing training)

I=' Exelon Generation I- 0::

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8. (RT-6-031-320-1 4.3) N/A RECORD the following on Attach #1 Ba. (RT-6-031-320-1 4.3.1) Value of - 1600 psig 1AP113 discharge pressure from recorded Pl-19-122, EHC PUMP DISCH PX, at panel 1OC653.

8b. (RT-6-031-320-1 4.3.2) Value of 1590 psig recorded 1AP113 discharge pressure from EHC Pumps HMI (Xl-031-104 on 10-C998) (330-T1-217).

CUE: EO reports Xl-031-104 PT3-A pressure of 1590 psig 8c. (RT-6-031-320-1 4.3.3) Value of 1575 psig recorded 1AP113 discharge pressure from PI-M2-181, MANIFOLD PRESSURE, at EHC Power Unit (330-T1-217).

CUE: EO reports PI-M2-181 pressure of 1575 psig

9. (RT-6-031-320-1 4.3.4) Candidate determines ENSURE 1AP113 discharge pressure is within band pressure from 1500 to 1700 psig using S31.0.A, EHC Pump Pressure Compensator Adjustment, as required AND ENTER a note in the Additional Action/Test Comments section to annotate any adjustments.

LOJPM3140 RevOOO.doc SRRS: 3D.105 Page 8 of 13 (When used for operator initial or continuing training)

I;:- Exelon Generation I- 0:::

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10. (RT-6-031-320-1 4.3.5) Candidate records discharge RECORD the following in flow of 25 GPM and Casing Attachment 1 for 1AP113: Drain Flow of 0.8 GPM.

- Pump discharge flow

- Pump casing drain flow Candidate records motor

- Pump motor current current of -40 amps CUE: EO reports Pump discharge flow (FM1-A) 25 GPM and Pump casing drain flow (FM2-A) 0.8 GPM Lead Evaluator (or designee) Notes:

Manual Trigger #1 simulates start of '1 B' EHC Pump from the field Auto Trigger #2 initiates TSV #3 closes (T/D) when '1A' EHC Pump taken to STOP.

11. (RT-6-031-320-1 4.3.6) 1BP113 verified to be in ENSURE pump control switch for "AUTO" 1BP113, EHC PUMP B, in "AUTO."

12. (RT-6-031-320-1 4.3. 7) Candidate requests EO to PRESS HS-M2-1 HFPMB PS-M2- perform step 4.3.7 to verify 1103 Solenoid Test Valve Switch 1BP113 is running pushbutton, at EHC Power Unit, AND VERIFY 1BP113 starts.

CUE: Driver Trigger #1 to start '1 B' EHC PUMP following repeat back of direction to start the '1 B' EHC Pump.

13. (RT-6-031-320-1 4.3.8) 105 H-2, EHC HYO FLUID VERIFY EHC HYO FLUID STANDBY PUMP RUNNING STANDBY PUMP RUNNING annunciator acknowledged annunciator alarms, at panel 105 MAIN TURB.

LOJPM3140 RevOOO.doc SRRS: 3D.105 Page 9 of 13 (When used for operator initial or continuing training)

I$ Exelon Generation I- a::

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14. (RT-6-031-320-1 4.3.9) 1BP113 placed in "RUN"

PLACE EHC PUMP B, 1BP113 handswitch to "RUN," at panel 10C653.

15. (RT-6-031-320-1 4.3.10) Annunciator reset and cleared VERIFY EHC HYO FLUID STANDBY PUMP RUNNING annunciator clears, at panel 105 MAIN TURB.

16. (RT-6-031-320-1 4. 3. 11) Candidate determines that IF section 4.4 was performed first section 4 .4 not performed and THEN ENTER NIA in initials blanks continues in section 4.3.

of steps 4.3.12 AND 4.3.13 AND GO TO Section 4.5, Otherwise, CONTINUE.

CUE: 3 minutes of Pump Operation has occurred.

17. (RT-6-031-320-1 4.3.12) 1AP113 HS placed in "STOP"

PLACE EHC PUMP A handswitch to "STOP," at panel 10C653, AND VERIFY pump stops.

18. (RT-6-031-320-1 4.3.13) 1AP113 HS placed in "AUTO"

PLACE EHC PUMP A handswitch in "AUTO."

Lead Evaluator (or designee) Notes: Alternate Path begins with the next step.

19. Respond to annunciator 107 G-2, Candidate responds to ARC-REACTOR HI PRESS and 107 H-2, MCR 107 G-2, REACTOR HI REACTOR HI/LO LEVEL PRESS

20. (ARC-MGR 107 G-2) Candidate verifies high Candidate verifies high pressure on reactor pressure and enters Pl-42-1 R605 on 1OC603 OT-102, Reactor High Pressure LOJPM3140 RevOOO.doc SRRS: 3D.105 Page 10 of 13 (When used for operator initial or continuing training)

1,5 Exelon Generation I- et::

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21. (OT-102 2.1) Candidate reduces Reactor

Candidate references OT-102, power in accordance with GP-Reactor High Pressure and 5, Steady State Operations, performs Immediate Operator AND Reactor Maneuvering Actions Shutdown Instructions to maintain Reactor pressure less than 1053 psig.

22. (OT-102 2.2) Candidate controls reactor CONTROL Reactor pressure Below pressure below 1053 psig.

1053 psig with bypass valves using the jack, OR by reducing pressure set.

23. Identify cause of reactor pressure Candidate identifies #3 TSV increase closure has failed closed

24. (OT-102 3. 1) Candidate references OT-DIRECT performance of appropriate 102, Attachment #2 Attachment based on cause of the pressure rise.

25. (OT-102 Att#2) Reactor power reduced to

IF a control valve OR stop valve <88% power in accordance closure caused the pressure rise with GP-5, Steady State THEN REDUCE Rx power to <88% Operations, AND Reactor Maneuvering Shutdown Instructions CUE: You have met the termination criteria for this JPM JPM Completion Time _ _ _ __

LOJPM3140 RevOOO.doc SRRS: 3D.105 Page 11 of 13 (When used for operator initial or continuing training)

I; Exelon Generation JPM

SUMMARY

Operator's Name: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _~

Job

Title:

D SEO D SM D SRO D RO D STA/IA D EO D OTHER JPM

Title:

EHC PUMP OPERABILITY TEST JPM Number: LOJPM3140 Revision Number: 000 Task Number and

Title:

2480040101 Operate EHC Pumps KIA Number and Importance: 241000 RO 3.5/ SRO 3.4 Safety Function (1-9) _3_ (Reactor Pressure Control)

Admin Category (A1-4) NIA Level of Difficulty (1-5) 3 Suggested Testing Environment: Simulator Alternate Path:[8'.I Yes D No SRO Only: D Yes [8J No Time Critical: D Yes [8J No Reference(s): RT-6-031-320-1, EHC Pump Operability/Performance Check, Rev 027 ARC-MCR-107 G-2, Reactor High Pressure, Rev 4 ARC-MCR-107 H-2, Reactor Hi/Lo Level, Rev 3 OT-102, Reactor High Pressure Rev 027 Actual Testing Environment: [8J Simulator D Control Room D In-Plant D Other Testing Method: D Simulate [8J Perform Estimated Time to Complete: 15 minutes Actual Time Used: minutes EVALUATION

SUMMARY

Were all the Critical Elements performed satisfactorily? D Yes D No The operator's performance was evaluated against standards contained within this JPM and has been determined to be: D Satisfactory D Unsatisfactory Comments:

Evaluator's N a m e : - - - - - - - - - - - - - - - - - (Print)

Evaluator's Signature: _ _ _ _ _ _ _ _ _ _ _ _ _ __ Date:

LOJPM3140 RevOOO.doc SRRS: 3D.105 Page 12 of 13 (When used for operator initial or continuing training)

..=:., Exelon Generation LIMERICK GENERATING STATION JOB PERFORMANCE MEASURE INDIVIDUAL BRIEFING SHEET INITIAL CONDITIONS:

1. 1AP113, '1A' EHC Pump is running.

2. 1BP113, '1 B' EHC Pump is available.

3. An EO is located at the EHC Power Unit.

4. SSV permission has been given to start test.

5. U1 RO permission has been given to start test.

INITIATING CUE:

Shift Supervision directs you perform RT-6-031-320-1, Unit 1 EHC Pump Operability/

Performance Check.

Page 13 of 13

I_.-:- Exelon Generation LIMERICK GENERATING STATION JOB PERFORMANCE MEASURE STANDBY GAS TREATMENT SYSTEM TRAIN SWAP JPM Number: LOJPM3514 REVISION NUMBER: 000 DATE: - - - -

Developed By:

Instructor Date Validated By:

SME or Instructor Date Reviewed By:

Operations Representative Date Reviewed By:

EP Representative Date Approved By:

Training Department Date LOJPM3514 RevOOO.doc SRRS: 30.105 Page 1 of 10 (When used for operator initial or continuing training)

[~Exelon Generation Note: This LGS format satisfies the TQ-JA-150 Format I. JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation.

Prior to JPM usage, revalidate JPM using steps 9 through 13 below.

1. Task description and number, JPM description and number are identified.

2. Knowledge and Abilities (KIA) references are included.

3. Performance location specified. (in-plant, control room, simulator, or other)

4. Initial setup conditions are identified.

5. Initiating cues (and terminating cues if required) are properly identified.

6. Task standards identified and verified by SME review.

7. Critical steps meet the criteria for critical steps and are identified with an asterisk

(*).

8. If an alternate path is used, the task standard contains criteria for successful completion.

9. Verify the procedure(s) referenced by this JPM reflects the current revision:

Procedure S76.8.C Rev: 7 Procedure Rev:

Procedure Rev:

10. Verify cues both verbal and visual are free of conflict.

11. Verify performance time is accurate

12. If the JPM cannot be performed as written with proper responses, then revise the JPM.

13. When JPM is initially validated, sign and date JPM cover page.

Subsequent validations, sign and date below:

SME / Instructor Date SME / Instructor Date SME / Instructor Date LOJPM3514 RevOOO.doc SRRS: 3D.105 Page 2 of 10 (When used for operator initial or continuing training)

[="Exelon Generation II. RECORD OF TEMPORARY CHANGES:

A. Approval of Pen & Ink Changes will be by the ILT or LORT Lead Instructor with OTM concurrence B. All Pen & Ink Changes are to be tracked in ILTor LOR Program Action Tracking for Next Revision C. All Pen & Ink Changes shall be in accordance with TQ-AA-223 Temp Date of Purpose of Change ILT/LORT Action Revision Change# Change Approval Tracking Date Ill. REVISION HISTORY:

A. If a Revision affects a Task Performance from VISION Terminal Performance Objectives then the revision must also be made in the VISION database.

B. The description of the Revision should adequately indicate how the training content of the Revision has changed.

C. The description of the Revision should also include previous format reference and number and previous template used (i.e. for conversion to LLOJPM format).

D. For Revision 000, put reason for writing this JPM and for all subsequent revisions, annotate the changes that were made or incorporated.

Revision # Date of Description of Revision and Affect on Training Content Number Revision 000 This is a new JPM 08/01/17

Date of Revision - refers to date revision was released for approval LOJPM3514 RevOOO.doc SRRS: 3D.105 Page 3 of 10 (When used for operator initial or continuing training)

1.= Exelon Generation.

IV. TASK STANDARD:

'B' SGTS Filter Train in service and 'A' SGTS Filter Train out of service.

V. SIMULATOR SETUP

1. Reset simulator to IC-3, or another IC if JPM was validated in the respective IC.

NOTE: It is okay to use a similar IC to the IC listed above, provided the IC actually used is verified to be compatible with this and other JPMs that are scheduled to be run concurrently.

2. Insert a Refuel Floor Secondary Containment Manual Isolation as follows:

a. Perform the following:

b. PLACE HS-76-181A and HS-76-1818 to ISOL

c. DEPRESS and RELEASE HS-76-181A and HS-76-1818 PB

3. Ensure "A" SGTS in service with "A" Fan OAV163, running through the "A" filter train (HV-076-11A AND HV-076-012A open)

4. Ensure "B" SGTS, OBV163, in STBY (NOT running)

5. Place HS-076-0138 in AUTO (HV-076-011 BAND HV-076-0128, NOT open).

6. Reset alarms.

LOJPM3514 RevOOO.doc SRRS: 3D.105 Page 4 of 10 (When used for operator initial or continuing training)

I,:ii?' Exelon Generation VI. INITIAL CONDITIONS:

1. A Refuel Floor Secondary Containment Isolation has been initiated

2. "A" SGTS Fan and Filter Train is in service VII. INITIATING CUE:

Shift Supervision directs you to place the "B" SGTS Fan and Filter Train in service as directed by section 4.4 of S76.8.C, Swapping Of SGTS and RERS Fans With Secondary Containment Isolation Initiated.

LOJPM3514 RevOOO.doc SRRS: 30.105 Page 5 of 10 (When used for operator initial or continuing training)

I_;;;- Exelon Generation.

Information for Evaluator's Use:

Any UNSAT requires written comments on respective step.

Denotes critical steps Number any comments in the "Comment Number" column on the following pages. Then annotate that comment in the "Comments" section. The comment section should be used to document: the reason that a step is marked as unsatisfactory, marginal performance relating to management expectations, or problems the examinee had while performing the JPM.

Comments relating to procedural or equipment issues should be entered and tracked using the site's appropriate tracking system.

Some operations that are performed from outside the control room may require multiple steps.

These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed.

The JPM Start Time clock starts when the candidate acknowledges the initiating cue.

LOJPM3514 RevOOO.doc SRRS: 3D.105 Page 6 of 10 (When used for operator initial or continuing training)

I,=Exelon Generation VIII. PERFORMANCE CHECKLIST:

JPM Start Time - - - - -

I- a::

I- ZW ELEMENT STANDARD I- <C Wm

<C u, u, z:) ::E ::E

E :)

Oz 0

1. Obtain current revision of S76.8.C, Candidate locates S76.8.C, Swapping Of SGTS and RERS Fans Swapping Of SGTS and With Secondary Containment RERS Fans With Secondary Isolation Initiated. Containment Isolation Initiated.

CUE: Candidate is given a copy of S76.8.C, Swapping Of SGTS and RERS Fans With Secondary Containment Isolation Initiated.

2. Candidate references proper section Candidate references section S76.8.C to swap from the A SGTS 4.4 of S76.8.C Filter Train to the B SGTS Filter Train to the B

3. (S76. 8. C 4.4. 1) HS-076-0138 placed to the

PLACE "SGTS Filter Train "OPEN" position Handswitch," HS-076-0138 to "OPEN" position to manually start the "B" Train.

4. (S76.8.C 4.4.2) HV-076-118 and HV-076-VERIFY dampers HV-076-011 B 0128 verified OPEN AND HV-076-0128, Filter Inlet and Outlet, indicate "OPEN" at panel OOC681.

5. (S76.8.C 4.4.3) HS-076-0408 placed in

PLACE "B" SGTS Fan Handswitch," AUTO HS-076-0408, for OB-V163 to the "AUTO" position at panel OOC681.

LOJPM3514 RevOOO.doc SRRS: 3D.105 Page 7 of 10 (When used for operator initial or continuing training)

I,:' ExelonGeneration I- a:::

I- ZW ELEMENT STANDARD I- <( Wm

<( U) :::E :::E U) z::::, :::E ::::,

Oz 0

EVALUATORS NOTE: S76.8.C, Swapping Of SGTS and RERS Fans With Secondary Containment Isolation Initiated steps 4.4.5 and 4.4.7 both state "OR as directed by SSV" If requested, role-play as SSV and state to candidate "Perform the procedure as written"

6. (S76.8.C 4.4.4) "B" SGTS Fan running VERIFY "B" fan starts at panel OOC681.

7. (S76.8.C 4.4.5) HS-076-041A placed in

PLACE "A" SGTS Fan Handswitch, STANDBY HS-076-041A, for OA-V163 to the "STANDBY" position.

8. (S76.8.C 4.4.6) "A" SGTS Fan not running VERIFY "A" Fan stops at panel OOC681.

9. ($76. 8. C 4. 4. 7) HS-076-013A placed in

PLACE HS-076-013A to the "AUTO" "AUTO" position.

10. (S76.8.C 4.4.8) HV-076-011A and HV-076-VERIFY "A" SGTS Filter Train 012A verified CLOSED Dampers,"HV-076-011A AND HV-076-012A, Filter Inlet and Outlet, indicate "CLOSED" at panel OOC681.

CUE: You have met the termination criteria for this JPM JPM Completion Time _ _ _ __

LOJPM3514 RevOOO.doc SRRS: 3D.105 Page 8 of 10 (When used for operator initial or continuing training)

I? Exelon Generation JPM

SUMMARY

Operator's Name: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _~

Job

Title:

D SEO D SM D SRO D RO D STA/IA D EO D OTHER JPM

Title:

STANDBY GAS TREATMENT SYSTEM TRAIN SWAP JPM Number: LOJPM3514 Revision Number: 000 Task Number and

Title:

2610040101 Lineup and place SGTS in service KIA Number and Importance: 261000 A4.03 3.0/3.0 Safety Function (1-9) 9 (Radioactivity Release)

Admin Category (A1-4) N/A Level of Difficulty (1-5) 2.5 Suggested Testing Environment: Simulator Alternate Path:0 Yes ~ No SRO Only: D Yes ~ No Time Critical: D Yes ~ No Reference(s): S76.8.C, Swapping Of SGTS and RERS Fans With Secondary Containment Isolation Initiated, Rev 7 Actual Testing Environment: ~ Simulator D Control Room D In-Plant D Other Testing Method: D Simulate ~ Perform Estimated Time to Complete: 15 minutes Actual Time Used: minutes EVALUATION

SUMMARY

Were all the Critical Elements performed satisfactorily? D Yes D No The operator's performance was evaluated against standards contained within this JPM and has been determined to be: D Satisfactory D Unsatisfactory Comments:

Evaluator's Name: - - - - - - - - - - - - - - - - - (Print)

Evaluator's Signature: _ _ _ _ _ _ _ _ _ _ _ _ _ __ Date:

LOJPM3514 RevOOO.doc SRRS: 3D.105 Page 9 of 10 (When used for operator initial or continuing training)

~.,, Exelon Generation LIMERICK GENERATING STATION JOB PERFORMANCE MEASURE INDIVIDUAL BRIEFING SHEET INITIAL CONDITIONS:

1. A Refuel Floor Secondary Containment Isolation has been initiated

2. "A" SGTS Fan and Filter Train is in service INITIATING CUE:

Shift Supervision directs you to place the "B" SGTS Fan and Filter Train in service as directed by section 4.4 of S76.8.C, Swapping Of SGTS and RERS Fans With Secondary Containment Isolation Initiated.

Page 10 of 10

I: ' Exelon Generation LIMERICK GENERATING STATION JOB PERFORMANCE MEASURE SUPPLYING POWER TO A 480 VAC NON-SAFEGUARD LOAD CENTER FROM ITS ALTERNATE SOURCE JPM Number: LOJPM3525 REVISION NUMBER: 004 DATE: - - - -

Developed By:

Instructor Date Validated By:

SME or Instructor Date Reviewed By:

Operations Representative Date Reviewed By:

EP Representative Date Approved By:

Training Department Date LOJPM3525 Rev004.doc SRRS: 3D.105 Page 1 of 9 (When used for operator initial or continuing training)

I? Exelon Generation Note: This LGS format satisfies the TQ-JA-150 Format I. JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation.

Prior to JPM usage, revalidate JPM using steps 9 through 13 below.

1. Task description and number, JPM description and number are identified.

2. Knowledge and Abilities (KIA) references are included.

3. Performance location specified. (in-plant, control room, simulator, or other)

4. Initial setup conditions are identified.

5. Initiating cues (and terminating cues if required) are properly identified.

6. Task standards identified and verified by SME review.

7. Critical steps meet the criteria for critical steps and are identified with an asterisk

(*).

8. If an alternate path is used, the task standard contains criteria for successful completion.

9. Verify the procedure(s) referenced by this JPM reflects the current revision:

Procedure S93. 7.A Rev: 40 Procedure_ _ _ _ _ _ _ _ _ __ Rev: _ __

Procedure Rev: - - -

Procedure

Rev: - - -

Rev: _ __

Procedure----------

10. Verify cues both verbal and visual are free of conflict.

11. Verify performance time is accurate

12. If the JPM cannot be performed as written with proper responses, then revise the JPM.

13. When JPM is initially validated, sign and date JPM cover page.

Subsequent validations, sign and date below:

SME / Instructor Date SME / Instructor Date SME / Instructor Date LOJPM3525 Rev004.doc SRRS: 3D.105 Page 2 of 9 (When used for operator initial or continuing training)

j .F Exelon Generation II. RECORD OF TEMPORARY CHANGES:

A. Approval of Pen & Ink Changes will be by the ILTor LORT Lead Instructor with OTM concurrence B. All Pen & Ink Changes are to be tracked in ILT or LOR Program Action Tracking for Next Revision C. All Pen & Ink Changes shall be in accordance with TQ-AA-223 Temp Date of Purpose of Change ILT/LORT Action Revision Change# Change Approval Tracking Date Ill. REVISION HISTORY:

A. If a Revision affects a Task Performance from VISION Terminal Performance Objectives then the revision must also be made in the VISION database.

B. The description of the Revision should adequately indicate how the training content of the Revision has changed.

C. The description of the Revision should also include previous format reference and number and previous template used (i.e. for conversion to LLOJPM format).

D. For Revision 000, put reason for writing this JPM and for all subsequent revisions, annotate the changes that were made or incorporated.

Revision # Date of Description of Revision and Affect on Training Content Number Revision This JPM replaces LLOJPM0525 Rev. 3. Revised to new template 9/17/13 000 and to align with latest procedure revision. Changed cue so Operators must determine control power source (step 4.7).

001 Minor format changes. 12/23/14 002 No Data on revision 003 JPM revised to reflect new JPM format and procedure changes 10/18/16 004 Minor format changes. 8/15/17

Date of Revision - refers to date revision was released for approval LOJPM3525 Rev004.doc SRRS: 3D.105 Page 3 of 9 (When used for operator initial or continuing training)

I;;:7 Exelon Generation IV. SIMULATOR SETUP INSTRUCTIONS:

1. Reset simulator to any IC with 480 VAC Non-Safeguard power normally aligned.

2. Insert an override on Ammeter to 54 amps for 1248 480 VAC Load Center Transformer on Trigger 1 with a 3 second time delay as follows:

Show Maffunctlons

0 Show 8emotes

0 Hide Qverrldes

1 ! Show !',nnuncl&tors

0 - - - - - - - - - - - - - - '

Oven/de Summary--

Tag ID ! Description ! Podion/Target !ActualValue ! OvenideValue ! Al1Jltime ! Actime ! Oactirne ! Trig A/10210 Load Centei 124B Feeder Ammeter Indication 54 00:0003 00:00:00 00:00:00 1 r TlmerPause DeleteAII I

3. Create Trigger 1 from green indicating light on breaker 52-10322 (1148 Breaker Green Lamp ON) as follows:

NOTE: It is acceptable to use a similar IC to the IC listed above, provided the IC actually used is verified to be compatible with this and other JPMs that are scheduled to be run concurrently.

~ Event Trigger Builder o

. '. N.1 ,

I

.:J .:J I== [equal to) .:J J

11 jZEDB322G !True Trigger Variable Name Operator Value I,. . . . . . . . . . . . . . . . . .~,

accept L.........~~-~~..........1 V. TASK STANDARD:

1148 Load Center loads transferred to 1248 Load Center through Tie Breaker and then restored to 1148 Load Center.

LOJPM3525 Rev004.doc SRRS: 3D.105 Page 4 of 9 (When used for operator initial or continuing training)

[,:::;:"Exelon Generation VI. INITIAL CONDITIONS:

1. Shift Manager's Permission has been given to close 480 VAC Tie breaker.

2. Maintenance has been scheduled for the 1148 Reactor Area Load Center Transformer.

3. Load on the 1148 and 1248 Load Centers has been minimized by placing alternate trains of components in service.

4. Loads have been minimized and/or de-energized to the lowest extent practical.

5. SSVN has determined that step 4.5 of S93.7.A will NOT be performed.

VII. INITIATING CUE:

Shift Supervision has directed you to supply the 1148 Non-Safeguard Load Center from it's alternate source (1248 Load Center) beginning with step 4.6 of S93.7.A.

Information for Evaluator's Use:

Any UNSAT requires written comments on respective step.

Denotes critical steps Number any comments in the "Comment Number" column on the following pages. Then annotate that comment in the "Comments" section. The comment section should be used to document: the reason that a step is marked as unsatisfactory, marginal performance relating to management expectations, or problems the examinee had while performing the JPM.

Comments relating to procedural or equipment issues should be entered and tracked using the site's appropriate tracking system.

Some operations that are performed from outside the control room may require multiple steps.

These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed.

The JPM Start Time clock starts when the candidate acknowledges the initiating cue.

LOJPM3525 Rev004.doc SRRS: 3D.105 Page 5 of 9 (When used for operator initial or continuing training)

1.= Exelon Generation VIII. PERFORMANCE CHECKLIST:

JPM Start Time - - - - -

t- 0:::

t- ZW t- <( Wal ELEMENT STANDARD <( fl) ::E ::E fl) z

, ::E ::,

Oz 0

Lead Evaluator (or designee) Notes: Provide the following:

Individual Briefing Sheet

S93.7.A, Supplying Power To A 480VAC Non-Safeguard Load Center From Its Alternate Source (S93.7.A, 4.6) Verify 1148 Transformer to

1. IF de-energizing transformers be de-energized.

supplying Load Centers, THEN ENSURE control power for the affected load center(s) is aligned to the bus that will remain energized.

Otherwise CONTINUE to step 4.7.

CUE: If requested, 1148 Load Center Transformer will be de-energized.

(S93.7.A, 4.6.1) 1248 is circled.

2. CIRCLE the desired source AND EO is directed to select NON-MARK those not aligned N/A PREFERRED Source (1248).

CUE: If directed to select NON-PREFERRED source, report: "Control Power for the 1148-1248 Load Center has been selected to NON-PREFERRED."

(S93.7.A, 4.7) Breaker Control Switch 52-

3. PLACE Tie Breaker control switch in 10342/CS taken to "CLOSE" "CLOSE" AND HOLD OR AND held in "CLOSE" for DEPRESS Tie Breaker "CLOSE" 1148 480 Volt Load Center.

pushbutton at load center for TSC load centers 144D/244D only) AND PERFORM the following:

LOJPM3525 Rev004.doc SRRS: 3D.105 Page 6 of 9 (When used for operator initial or continuing training)

~

Exelon Generation I- 0::

I- ZW I- <( Wal ELEMENT STANDARD <( U) ::E ::E U) z::, ::E ::,

Oz 0

3a. PLACE appropriate Bus Breaker Bus Breaker 52-10322/CS

control switch to "TRIP". placed in "TRIP".

3b. WHEN Tie breaker indicates Bus Breaker 52-10342/CS closed, AND Main Breaker released.

indicates tripped, THEN RELEASE Tie Breaker control switch.

EVALUATOR NOTE: Alternate path starts here. Ammeter A 10210 for 1248 Load Center Ammeter Indication to 54 Amps should actuate on Trigger 1 (1148 Breaker open).

(S93.7.A, 4.8) Ammeter for 1248 is

4. OBSERVE ammeter associated with observed to be indicating 54 Load Center Bus which is now AMPS feeding intertied buses.

(S93.7.A, 4.9) Operator determines 54 amps

5. IF 13 KV load exceeds specified in excess of 50 amp load limit amperage values, THEN PERFORM from attachment 2.

the following:

EVALUATOR NOTE: REMOVE 1248 LOAD CENTER AMMETER OVERRIDE

5a. CLOSE opened Bus Breaker. Bus Breaker 52-10322/CS placed in "CLOSE".

CUE: You have met the termination criteria for this JPM JPM Completion Time _ _ _ __

LOJPM3525 Rev004.doc SRRS: 3D.105 Page 7 of 9 (When used for operator initial or continuing training)

I.:' Exelon Generation JPM

SUMMARY

Operator's Name: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Job

Title:

D SEO D SM D SRO D RO D STA/IA D EO D OTHER JPM

Title:

SUPPL YING POWER TO A 480 VAC NON-SAFEGUARD LOAD CENTER FROM ITS AL TERNA TE SOURCE JPM Number: LOJPM3525 Revision Number: 004 Task Number and

Title:

TP0-2623030401, Supply Power to 480 VAC Non-Safeguard Load Centers from Alternate Source KIA Number and Importance: 262001 A4.05 3.3/3.3 Safety Function (1-9) 6 (Electrical)

Admin Category (A1-4) N/A Level of Difficulty (1-5) ...1...

Suggested Testing Environment: Simulator Alternate Path:IZ] Yes D No SRO Only: D Yes IZ] No Time Critical: D Yes IZ] No Reference(s): S93.7.A, Supplying Power To A 480VAC Non-Safeguard Load Center From Its Alternate Source, Rev. 40 Actual Testing Environment: IZ] Simulator D Control Room D In-Plant D Other Testing Method: D Simulate IZ] Perform Estimated Time to Complete: 10 minutes Actual Time Used: minutes EVALUATION

SUMMARY

Were all the Critical Elements performed satisfactorily? D Yes D No The operator's performance was evaluated against standards contained within this JPM and has been determined to be: D Satisfactory D Unsatisfactory Comments:

Evaluator's Name: - - - - - - - - - - - - - - - - - (Print)

Evaluator's Signature: _ _ _ _ _ _ _ _ _ _ _ _ _ __ Date: - - -

LOJPM3525 Rev004.doc SRRS: 30.105 Page 8 of 9 (When used for operator initial or continuing training)

Exelon Generation LIMERICK GENERATING STATION JOB PERFORMANCE MEASURE INDIVIDUAL BRIEFING SHEET INITIAL CONDITIONS

1. Shift Manager's Permission has been given to close 480 VAC Tie breaker.

2. Maintenance has been scheduled for the 1148 Reactor Area Load Center Transformer.

3. Load on the 1148 and 1248 Load Centers has been minimized by placing alternate trains of components in service.

4. Loads have been minimized and/or de-energized to the lowest extent practical.

5. SSVN has determined that step 4.5 of S93.7.A will NOT be performed.

INITIATING CUE STATEMENT:

Shift Supervision has directed you to supply the 1148 Non-Safeguard Load Center from it's alternate source (1248 Load Center) beginning with step 4.6 of S93.7.A.

Page 9 of 9

Ir Exelon Generation LIMERICK GENERATING STATION JOB PERFORMANCE MEASURE START A CONDENSATE PUMP JPM Number: LOJPM3530 REVISION NUMBER: 000 DATE: - - - -

Developed By:

Instructor Date Validated By:

SME or Instructor Date Reviewed By:

Operations Representative Date Reviewed By: NIA EP Representative Date Approved By:

Training Department Date LOJPM3530 RevOOO.doc SRRS: 3D.105 Page1of10 (When used for operator initial or continuing training)

I,=' Exelon Generation Note: This LGS format satisfies the TQ-JA-150 Format I. JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation.

Prior to JPM usage, revalidate JPM using steps 9 through 13 below.

1. Task description and number, JPM description and number are identified.

2. Knowledge and Abilities (KIA) references are included.

3. Performance location specified. (in-plant, control room, simulator, or other)

4. Initial setup conditions are identified.

5. Initiating cues (and terminating cues if required) are properly identified.

6. Task standards identified and verified by SME review.

7. Critical steps meet the criteria for critical steps and are identified with an asterisk

(*).

8. If an alternate path is used, the task standard contains criteria for successful completion.

9. Verify the procedure(s) referenced by this JPM reflects the current revision:

Procedure S05.1. B Rev: -=------

21 Procedure ARC MCR 104 D-2 Rev: -=---

2 Procedure Rev: - - -

Procedure

Rev: - - -

Procedure---------- Rev: _ __

10. Verify cues both verbal and visual are free of conflict.

11 . Verify performance time is accurate

12. If the JPM cannot be performed as written with proper responses, then revise the JPM.

13. When JPM is initially validated, sign and date JPM cover page.

Subsequent validations, sign and date below:

SME / Instructor Date SME / Instructor Date SME / Instructor Date LOJPM3530 RevOOO.doc SRRS: 3D.105 Page 2 of 10 (When used for operator initial or continuing training)

1-~ Exelon Generation II. RECORD OF TEMPORARY CHANGES:

A. Approval of Pen & Ink Changes will be by the ILTor LORT Lead Instructor with OTM concurrence B. All Pen & Ink Changes are to be tracked in ILTor LOR Program Action Tracking for Next Revision C. All Pen & Ink Changes shall be in accordance with TQ-AA-223 Temp Date of Purpose of Change ILT/LORT Action Revision Change# Change Approval Tracking Date Ill. REVISION HISTORY:

A. If a Revision affects a Task Performance from VISION Terminal Performance Objectives then the revision must also be made in the VISION database.

B. The description of the Revision should adequately indicate how the training content of the Revision has changed.

C. The description of the Revision should also include previous format reference and number and previous template used (i.e. for conversion to LLOJPM format).

D. For Revision 000, put reason for writing this JPM and for all subsequent revisions, annotate the changes that were made or incorporated.

Revision # Date of Description of Revision and Affect on Training Content Number Revision This New JPM supersedes LLOJPM0520 Rev. 1. To start a 08/01/17 000 Condensate Pump and includes a hotwell level transmitter failure.

Date of Revision - refers to date revision was released for approval LOJPM3530 RevOOO.doc SRRS: 3D.105 Page 3 of 10 (When used for operator initial or continuing training)

I,= Exelon Generation IV. TASK STANDARD:

Place 3rd Condensate Pump (1C Condensate Pump) in service and Hotwell Level Controller swapped to the B Transmitter.

V. SIMULATOR SETUP

1. Reset simulator to IC-3, or another IC if JPM was validated in the respective IC.

NOTE: It is okay to use a similar IC to the IC listed above, provided the IC actually used is verified to be compatible with this and other JPMs that are scheduled to be run concurrently.

2. Ensure '1A' and '18' Condensate Pumps in service, with '1C' Condensate Pump ready to be placed in service.

3. Create Trigger tl.1._ to automatically actuate MMC0778 "Hotwell Level Controller fails low" when '1C' Condensate Pump Discharge Valve is opened (GREEN light OFF).

VI. INITIAL CONDITIONS:

1. Unit 1 is at approximately 50% power.

2. GP-2, Normal Plant Startup, is in progress

3. '1A/B' Condensate Pumps are in service.

4. '1C' Condensate Pump has been secured for greater than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

5. RO Briefed per step 2.4

6. An EO is standing by at the 1C Condensate Pump VII. INITIATING CUE:

Shift Supervision directs you, per GP-2, Normal Plant Startup, to start the '1 C' Condensate Pump, per S05.1.B, Placing Second And Third Condensate Pumps In Service.

LOJPM3530 RevOOO.doc SRRS: 3D.105 Page 4 of 10 (When used for operator initial or continuing training)

1.= Exelon Generation Information for Evaluator's Use:

Any UNSAT requires written comments on respective step.

Denotes critical steps Number any comments in the "Comment Number" column on the following pages. Then annotate that comment in the "Comments" section. The comment section should be used to document: the reason that a step is marked as unsatisfactory, marginal performance relating to management expectations, or problems the examinee had while performing the JPM.

Comments relating to procedural or equipment issues should be entered and tracked using the site's appropriate tracking system.

Some operations that are performed from outside the control room may require multiple steps.

These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed.

The JPM Start Time clock starts when the candidate acknowledges the initiating cue.

LOJPM3530 RevOOO.doc SRRS: 3D.105 Page 5 of 10 (When used for operator initial or continuing training)

I$" Exelon Generation VIII. PERFORMANCE CHECKLIST:

JPM Start Time - - - - -

t- a::

t- ZW ELEMENT STANDARD t- <( W[Q

<( u, ::IE ::IE u, z::, ::IE ::,

Oz 0

1. Obtain current revision of SOS.1.8, Candidate obtains S05.1.B, Placing Second And Third Condensate Placing Second And Third Pumps In Service. Condensate Pumps In Service.

CUE: Candidate is given a copy of SOS.1.B, Placing Second And Third Condensate Pumps In Service.

2. ($05. 1.8 4.3) HV-05-101C, Condensate Pump OPEN selected HV-05-*01A{B,C), Suction (SUCT) is verified open.

Condensate Pump Suction" (SUCT).

3. ($05. 1.8 4.4) HV-05-102C, Condensate Pump ENSURE selected HV-05-*02A{B,C), Discharge Viv (DISCH), is "Condensate Pump Discharge Viv" verified closed.

(DISCH), closed.

EVALUATORS NOTE: S05.1.B, Placing Second And Third Condensate Pumps In Service step 4.5 is performed locally at the Condensate Pump

4. ($05.1.B 4.5)

PERFORM S05.1.B section 4.5 locally N/A at Condensate pump to be started:

CUE: S05.1.B, section 4.5, is complete for the '1 C' Condensate Pump.

5. ($05.1.B 4.6) Verify FVC-05-103, ADJUST FVC-05-*03, "Condensate "Condensate Recirculation Recirculation Control Valve," by Control Valve," is throttled to adjusting FIC-06-*02, "Condensate Total maintained flow rate of 7,500 Flow" COND RECIRC (FL) controller gpm.

setpoint at panel *OC652 from 6,000 gpm to 7,500 gpm.

LOJPM3530 RevOOO.doc SRRS: 3D.105 Page 6 of 10 (When used for operator initial or continuing training)

I-=-- Exelon Generation t- 0::

t- Zw ELEMENT STANDARD t-

<(

ti)

Wm ti) z ::E ::E

> ::E ::>

Oz 0

6. (S05.1.B 4. 7.1) '1 C' Condensate Pump HS-005-

START *A{B,C)P102, "Condensate 102C taken to START.

Pump," as follows:

7. (S05.1.B 4. 7.2) After starting current has settled

WHEN starting current has decayed, HV-005-102C, "1C Cond Pp THEN OPEN HV-005-*02A{B,C), Disch Viv" (DISCH C) taken to

"*A{B,C) Cond Pp Disch Viv" (DISCH A OPEN:

{B,C):

8. (S05.1.B 4. 7.3) N/A OBSERVE the following on pump start:

EVALUATORS NOTE: Alternate Path- Hotwell Level transmitter failure activates when '1C' Condensate Pump Discharge Valve is full OPEN. Annunciator MCR 104 COND D-2, HP COND HOTWELL HI/LO LEVEL, will alarm. Candidate may identify and respond to plant condition prior to receiving Hotwell HI/LO Level alarm and may proceed directly to step 12b. In this case JPM steps not performed prior to step 12b should be marked N/A Ba. (S05.1.B 4. 7.3) Observe HV-005-102C, "1C HV-005-*02A{B,C), "*A(B,C) Cond Pp Cond Pp Disch Viv" DISCH C, Disch Viv" DISCH A{B,C), opens fully. fully opens 8b. (S05.1.B 4. 7.3) Observe '1 C' pump ammeter Pump ammeter settles out at nominal settles out at nominal current current level of other running pumps level of other running pumps.

Be. (S05. 1.B 4. 7.3) Verify 7,500 gpm recirculation FV-C-05-*03, "Condensate Recirculation flow maintained.

Control Valve" opens as required

9. (S05.1.B 4. 7.4) Computer points F1111 through MONITOR pump bearing F1125 monitored until AND motor winding temperatures on temperatures stabilized.

computer points F*111 through F*125 for 30 minutes OR until Temperature stabilize.

10. (ARC MGR 107 0-5) Candidate references Digital Respond to MCR 107 D-5 FWLCS Feedwater Level Control Monitor TROUBLE annunciator. to determine Make-Up/Reject error LOJPM3530 RevOOO.doc SRRS: 3D.105 Page 7 of 10 (When used for operator initial or continuing training)

[-=' Exelon Generation t- D::

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10a. (ARC MGR 104 0-2) ARC referenced for MCR 104 Respond to MCR 104 D-2, HP COND COND D-2, HP COND HOTWELL HI/LO LEVEL annunciator. HOTWELL HI/LO LEVEL

11. (ARC MGR 104 0-2) Makeup/reject valves verified to Verify proper operation of makeup/reject not be maintaining Hotwell level valves. between 42.25 and 50.25 inches.

12. (ARC MGR 104 0-2)

If valves are not responding to level.

Switch to alternate level transmitter as N/A follows:

12a. (ARC MGR 104 0-2) Level controllers LIC-05-101 Place level controllers LIC-05-101 AND AND LIC-05-102 placed in LIC-05-102 in MANUAL mode at MANUAL mode at 10C652.

10C652.

12b. (ARC MGR 104 0-2) Alternate level transmitter LT-05

Select alternate level transmitter (LT 101A OR LT-05 101 B) using HS-05-101, 101 B selected using HS-05-101, "LEVEL CONTROL SEL," at "LEVEL CONTROL SEL," at 1OC652. 10C652.

12c. (ARC MGR 104 0-2) LIC-05-101 AND LIC-05-102 Place LIC-05-101 AND LIC-05-102 in placed in AUTO mode, and AUTO mode, and slowly adjust setpoint setpoint slowly adjust to to desired hotwell level value. between 42.25 and 50.25 inches.

12d. (ARC MGR 104 0-2)

If valves are still not controlling level, N/A take manual control of makeup/reject level controller to maintain level between 42.25 and 50.25 inches.

CUE: You have met the termination criteria for this JPM JPM Completion Time _ _ _ __

LOJPM3530 RevOOO.doc SRRS: 3D.105 Page 8 of 10 (When used for operator initial or continuing training)

I,£5" Exelon Generation JPM

SUMMARY

Operator's Name: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Job

Title:

D SED D SM D SRO D RO D STA/IA D EO D OTHER JPM

Title:

START A CONDENSATE PUMP JPM Number: LOJPM3530 Revision Number: 000 Task Number and

Title:

2560030101 Start additional Condensate Pumps KIA Number and Importance 256000 A3.02 3.0/2.9 A4.03 3.2/3.1 Safety Function (1-9) 2 (Reactor Water Inventory)

Admin Category (A1-4) _ _

Level of Difficulty (1-5) ____3_ _

Suggested Testing Environment: Simulator Alternate Path: ~ Yes D No SRO Only: D Yes ~ No Time Critical: D Yes ~ No Reference(s): S05.1.B Placing Second And Third Condensate Pump In Service, Rev 21 ARC-MCR-104 D-2, HP Cond Hotwell Hi/Lo Level, Rev 2 Actual Testing Environment: ~ Simulator D Control Room D In-Plant D Other Testing Method: D Simulate ~ Perform Estimated Time to Complete: 15 minutes Actual Time Used: minutes EVALUATION

SUMMARY

Were all the Critical Elements performed satisfactorily? D Yes D No The operator's performance was evaluated against standards contained within this JPM and has been determined to be: D Satisfactory D Unsatisfactory Comments:

Evaluator's Name: - - - - - - - - - - - - - - - - - (Print)

Evaluator's Signature: _ _ _ _ _ _ _ _ _ _ _ _ _ __ Date: ------

LOJPM3530 RevOOO.doc SRRS: 3D.105 Page 9 of 10 (When used for operator initial or continuing training)

="' Exelon Generation LIMERICK GENERATING STATION JOB PERFORMANCE MEASURE INDIVIDUAL BRIEFING SHEET INITIAL CONDITIONS:

1. Unit 1 is at approximately 50% power.

2. GP-2, Normal Plant Startup, is in progress

3. '1A/B' Condensate Pumps are in service.

4. '1 C' Condensate Pump has been secured for greater than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

5. RO Briefed per step 2.4

6. An EO is standing by at the 1C Condensate Pump INITIATING CUE:

Shift Supervision directs you, per GP-2, Normal Plant Startup, to start the '1 C' Condensate Pump, per S05.1.B, Placing Second And Third Condensate Pumps In Service.

Page 10 of 10

1.= Exelon Generation LIMERICK GENERATING STATION JOB PERFORMANCE MEASURE INADVERTENT OPENING OF A RELIEF VALVE JPM Number: LOJPM2204 REVISION NUMBER: 003 DATE: - - - -

Developed By:

Instructor Date Validated By:

SME or Instructor Date Reviewed By:

Operations Representative Date Reviewed By:

EP Representative Date Approved By:

Training Department Date LOJPM2204 Rev003.doc SRRS: 3D.105 Page 1 of 9 (When used for operator initial or continuing training)

I=' Exelon Generation Note: This LGS format satisfies the TQ-JA-150 Format I. JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation.

Prior to JPM usage, revalidate JPM using steps 9 through 13 below.

1. Task description and number, JPM description and number are identified.

2. Knowledge and Abilities (KIA) references are included.

3. Performance location specified. (in-plant, control room, simulator, or other)

4. Initial setup conditions are identified.

5. Initiating cues (and terminating cues if required) are properly identified.

6. Task standards identified and verified by SME review.

7. Critical steps meet the criteria for critical steps and are identified with an asterisk

(*).

8. If an alternate path is used, the task standard contains criteria for successful completion.

9. Verify the procedure(s) referenced by this JPM reflects the current revision:

Procedure OT-114 Rev: 38 Procedure- - - - - - - - - - - Rev: - - -

Procedure---------- Rev: _ __

Procedure - - - - - - - - - - Rev: ---

Procedure Rev:

10. Verify cues both verbal and visual are free of conflict.

11. Verify performance time is accurate.

12. If the JPM cannot be performed as written with proper responses, then revise the JPM.

13. When JPM is initially validated, sign and date JPM cover page.

Subsequent validations, sign and date below:

SME / Instructor Date SME / Instructor Date SME / Instructor Date LOJPM2204 Rev003.doc SRRS: 3D.105 Page 2 of 9 (When used for operator initial or continuing training)

I,;:Sr" Exelon Generation II. RECORD OF TEMPORARY CHANGES:

A. Approval of Pen & Ink Changes will be by the ILTor LORT Lead Instructor with OTM concurrence.

B. All Pen & Ink Changes are to be tracked in ILTor LOR Program Action Tracking for Next Revision.

C. All Pen & Ink Changes shall be in accordance with TQ-AA-223.

Temp Date of Purpose of Change ILT/LORT Action Revision Change# Change Approval Tracking Date Ill. REVISION HISTORY:

A. If a Revision affects a Task Performance from VISION Terminal Performance Objectives then the revision must also be made in the VISION database.

B. The description of the Revision should adequately indicate how the training content of the Revision has changed.

C. The description of the Revision should also include previous format reference and number and previous template used (i.e. for conversion to LLOJPM format).

D. For Revision 000, put reason for writing this JPM and for all subsequent revisions, annotate the changes that were made or incorporated.

Revision Date of Description of Revision and Affect on Training Content Number Revision This JPM replaces LLOJPM0204 Rev. 8. Revised to new template and 10/28/14 000 to align with latest procedure revision.

001 JPM revised to incorporate changes in JPM template and OT-114 04/13/15 002 Revised to incorporate Pen and Ink Changes of #1513595-19/08 10/24/16 003 Revised to align with current revision of OT-114 10/04/17

Date of Revision - refers to date revision was released for approval LOJPM2204 Rev003.doc SRRS: 30.105 Page 3 of 9 (When used for operator initial or continuing training)

1.£""Exelon Generation IV. TASK STANDARD:

Four (4) fuses removed to close the SRV. Two (2) fuses removed from panel *OC631 and two (2) fuses removed from panel *OC628 V. INITIAL CONDITIONS:

1. LGS Unit is in OPCON 3

2. PSV-41-_F013M is confirmed stuck open VI. INITIATING CUE:

You are directed by Shift Supervision to pull fuses for PSV-41-*F013M as directed by OT-114.

Information for Evaluator's Use:

Any UNSAT requires written comments on respective step.

Denotes critical steps Number any comments in the "Comment Number" column on the following pages. Then annotate that comment in the "Comments" section. The comment section should be used to document: the reason that a step is marked as unsatisfactory, marginal performance relating to management expectations, or problems the examinee had while performing the JPM.

Comments relating to procedural or equipment issues should be entered and tracked using the site's appropriate tracking system.

Some operations that are performed from outside the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed.

The JPM Start Time clock starts when the candidate acknowledges the initiating cue.

LOJPM2204 Rev003.doc SRRS: 3D.105 Page 4 of 9 (When used for operator initial or continuing training)

I? Exelon Generation VII. PERFORMANCE CHECKLIST:

JPM Start Time - - - - -

I- 0:::

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1. Obtain current revision of OT-114 N/A CUE: Provide a copy of OT-114

2. Obtain Fuse Pullers Fuse pullers in hand NOTE: The operator can obtain fuse pullers (Electrical locker, maintenance shop, tool locker etc.)

CUE: Once operator demonstrates ability to obtain fuse pullers, say "You have obtained fuse pullers."

EVALUATORS NOTE:

Steps 3 - 6 are to be completed when performing this JPM on Unit 1.

Steps 7 -10 are to be completed when performing this JPM on Unit 2.

Steps for the Unit NOT selected for this JPM may be marked NIA even though they are marked as critical steps.

UNIT 1 ONLY Fuse 10-C628 B21C-F3M at

3. PULL Fuse 10-C628/B21C-F3M at panel 1OC628 removed panel 1OC628

-ADS Valve 821-F013M CUE: Fuse is pulled LOJPM2204 Rev003.doc SRRS: 3D.105 Page 5 of 9 (When used for operator initial or continuing training)

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UNIT 1 ONLY Fuse 10-C628/821C-F4M at

4. PULL Fuse 10-C628 B21C-F4M at panel 1OC628 removed panel 1OC628

-ADS Valve B21-F013M CUE: Fuse is pulled UNIT 1 ONLY Fuse 10-C631/B21C-F7M at panel 1OC631 removed

5. PULL Fuse 10-C631 B21C-F7M at panel 1OC631

-ADS Valve PSV-F013M CUE: Fuse is pulled UNIT 1 ONLY Fuse 10-C631/B21C-F8M at panel 1OC631 removed

6. PULL Fuse 10-C631 B21C-F8M at panel 1OC631

-ADS Valve PSV-F013M CUE: Fuse is pulled EVALUATORS NOTE:

Steps 3 - 6 are to be completed when performing this JPM on Unit 1.

Steps 7 -10 are to be completed when performing this JPM on Unit 2.

Steps for the Unit NOT selected for this JPM may be marked N/A even though they are marked as critical steps.

UNIT 2 ONLY Fuse 20-C628/B21 C-F3M at panel 20C628 removed

7. PULL Fuse 20-C628/821C-F3M at panel 20C628

-ADS Valve PSV 41-2F013M CUE: Fuse is pulled LOJPM2204 Rev003.doc SRRS: 3D.105 Page 6 of 9 (When used for operator initial or continuing training)

~

Exelon Generation t- 0:::

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UNIT 2 ONLY Fuse 20-C628/B21 C-F4M at panel 20C628 removed

8. PULL Fuse 20-C628/B21C-F4M at panel 20C628

-ADS Valve PSV 41-2F013M CUE: Fuse is pulled

UNIT 2 ONLY Fuse 20-C631/B21C-F7M at panel 20C631 removed

9. PULL Fuse 20-C631/B21C-F7M at panel 20C631

-ADS Valve PSV 41-2F013M CUE: Fuse is pulled

UNIT 2 ONLY Fuse 20-C631/B21C-F8M at panel 20C631 removed

10. PULL Fuse 20-C631/B21C-F8M at panel 20C631

-ADS Valve PSV 41-2F013M CUE: Fuse is pulled CUE: (After all four fuses have been removed), You have met the termination criteria for this JPM JPM Completion Time _ _ _ __

LOJPM2204 Rev003.doc SRRS: 3D.105 Page 7 of 9 (When used for operator initial or continuing training)

I; Exelon Generation JPM

SUMMARY

Operator's Name: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _--'-

Job

Title:

D SEO D SM D SRO D RO D STA/IA D EO D OTHER JPM

Title:

INADVERTENT OPENING OF A RELIEF VALVE JPM Number: LOJPM2204 Revision Number: 001 Task Number and

Title:

2000270501 (OT-114) Actions for Inadvertent Opening of an SRV (LO) 2990760504 Perform EO actions of OT-114 (NLO)

KIA Number and Importance: 239002 A2.03 4.1/4.1 Safety Function (1-9) 3.0 Admin Category (A1-4) N/A Level of Difficulty (1-5) ...1...

Suggested Testing Environment: In-Plant Alternate Path: D Yes ~ No SRO Only: D Yes ~ No Time Critical: D Yes ~ No Reference(s): OT-114, INADVERTENT OPENING OF A RELIEF VALVE, Rev 038 Actual Testing Environment: D Simulator D Control Room ~ In-Plant D Other Testing Method: ~ Simulate D Perform Estimated Time to Complete: 30 minutes Actual Time Used: minutes EVALUATION

SUMMARY

Were all the Critical Elements performed satisfactorily? D Yes D No The operator's performance was evaluated against standards contained within this JPM and has been determined to be: D Satisfactory D Unsatisfactory Comments:

Evaluator's Name: - - - - - - - - - - - - - - - - (Print)

Evaluator's Signature: _ _ _ _ _ _ _ _ _ _ _ _ __ Date: -----

LOJPM2204 Rev003.doc SRRS: 30.105 Page 8 of 9 (When used for operator initial or continuing training)

"' Exelon Generation LIMERICK GENERATING STATION JOB PERFORMANCE MEASURE INDIVIDUAL BRIEFING SHEET INITIAL CONDITIONS:

1. LGS Unit is in OPCON 3

2. PSV-41-_F013M is confirmed stuck open INITIATING CUE:

You are directed by Shift Supervision to pull fuses for PSV-41-*F013M on Unit# _ _ _ as directed by OT-114.

Page 9 of 9

I,,::;!r Exelon Generation LIMERICK GENERATING STATION JOB PERFORMANCE MEASURE MANUAL ISOLATION AND VENT OF THE SCRAM AIR HEADER JPM Number: LOJPM2210 REVISION NUMBER: 003 DATE: - - - -

Developed By:

Instructor Date Validated By:

SME or Instructor Date Reviewed By:

Operations Representative Date Reviewed By: N/A N/A EP Representative Date Approved By:

Training Department Date LOJPM2210 Rev003.doc SRRS: 3D.105 Page 1 of 9

{When used for operator initial or continuing training)

I= Exelon Generation Note: This LGS format satisfies the TQ-JA-150 Format I. JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation.

Prior to JPM usage, revalidate JPM using steps 9 through 13 below.

1. Task description and number, JPM description and number are identified.

2. Knowledge and Abilities (KIA) references are included.

3. Performance location specified. (in-plant, control room, simulator, or other)

4. Initial setup conditions are identified.

5. Initiating cues (and terminating cues if required) are properly identified.

6. Task standards identified and verified by SME review.

7. Critical steps meet the criteria for critical steps and are identified with an asterisk

(*).

8. If an alternate path is used, the task standard contains criteria for successful completion.

9. Verify the procedure(s) referenced by this JPM reflects the current revision:

Procedure T-216 U/1 Rev: 18 Procedure ...:..T-=-2::..;1:..;:6:......;U==/-=2'--_ _ _ _ __ Rev: -

Procedure Rev: - - -

Procedure

Rev: - - -

Rev: _ __

Procedure----------

10. Verify cues both verbal and visual are free of conflict.

11. Verify performance time is accurate

12. If the JPM cannot be performed as written with proper responses, then revise the JPM.

13. When JPM is initially validated, sign and date JPM cover page.

Subsequent validations, sign and date below:

SME / Instructor Date SME / Instructor Date SME / Instructor Date LOJPM2210 Rev003.doc SRRS: 3D.105 Page 2 of 9 (When used for operator initial or continuing training)

I =-' Exelon Generation II. RECORD OF TEMPORARY CHANGES:

A. Approval of Pen & Ink Changes will be by the ILTor LORT Lead Instructor with OTM concurrence B. All Pen & Ink Changes are to be tracked in ILT or LOR Program Action Tracking for Next Revision C. All Pen & Ink Changes shall be in accordance with TQ-AA-223 Temp Date of Purpose of Change ILT/LORT Action Revision Change# Change Approval Tracking Date Ill. REVISION HISTORY:

A. If a Revision affects a Task Performance from VISION Terminal Performance Objectives then the revision must also be made in the VISION database.

B. The description of the Revision should adequately indicate how the training content of the Revision has changed.

C. The description of the Revision should also include previous format reference and number and previous template used (i.e. for conversion to LLOJPM format).

D. For Revision 000, put reason for writing this JPM and for all subsequent revisions, annotate the changes that were made or incorporated.

Revision # Date of Description of Revision and Affect on Training Content Number Revision 000 This JPM replaces LLOJPM0210 Rev. 13. Revised to new template 10/11/14 and to align with latest procedure revision.

001 Revision 001 has no description 10/01/16 002 Revised to fix minor typos and to align with latest procedure revision. 10/03/16 003 Revised to align with latest procedure revision 10/3/16

Date of Revision - refers to date revision was released for approval LOJPM2210 Rev003.doc SRRS: 30.105 Page 3 of 9 (When used for operator initial or continuing training)

J .FExelon Generation IV. TASK STANDARD:

Scram air header is depressurized.

V. INITIAL CONDITIONS:

1. Unit is in an ATWS.

VI. INITIATING CUE:

Shift Supervision directs you to perform T-216 on Unit_.

Information for Evaluator's Use:

Any UNSAT requires written comments on respective step.

Denotes critical steps Number any comments in the "Comment Number" column on the following pages. Then annotate that comment in the "Comments" section. The comment section should be used to document: the reason that a step is marked as unsatisfactory, marginal performance relating to management expectations, or problems the examinee had while performing the JPM. Comments relating to procedural or equipment issues should be entered and tracked using the site's appropriate tracking system.

Some operations that are performed from outside the control room may require multiple steps.

These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed.

The JPM Start Time clock starts when the candidate acknowledges the initiating cue.

LOJPM2210 Rev003.doc SRRS: 3D.105 Page 4 of 9 (When used for operator initial or continuing training)

1-= Exelon Generation VII. PERFORMANCE CHECKLIST:

JPM Start Time-----

ELEMENT STANDARD I-

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NOTE:

IF this JPM is the first of multiple T-200 series JPMs being performed by a single candidate THEN steps #1 applies.

OTHERWISE mark step #1 as N/A AND provide the following to the candidate :

a. INITIATING CUE(S)

b. CUE: "You are now in possession of the T-216 equipment container. It contains all tools and equipment required by the procedure. You are to simulate their use during performance of the procedure."

c. PROCEDURE COPY

1. Obtain current revision of Obtain current revision of T-216, as well as necessary T-216 and tools from tools/equipment from Unit

T-200 equipment locker cabinet in OSC:

2 8" adjustable wrenches

1 flashlight CUE: you have obtained the equipment

2. CLOSE 47-*F095, "Air Supply to Air supply valve to the scram Scram Viv Pilot Air Hdr" (402-R15- air header 47-*F095 253/475-R17-253) handwheel rotated clockwise (ATIACHMENT 1) until the valve is closed CUE: The handwheel rotates and then comes to a stop LOJPM2210 Rev003.doc SRRS: 30.105 Page 5 of 9 (When used for operator initial or continuing training)

1

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3. CLOSE RV-047-*01, "Pl-*R-013, Root valve for PT-47-*N052 PT-47-*N052 CRD SCRAM VALVE and Pl-47-*R013 (handwheel PILOT AIR" on East side of rotated clockwise until the instrument rack *OC213 (402-R15- valve is closed) 253/4 75-R 17-253)

(ATTACHMENT 1 & 2)

CUE: The handwheel rotates and then comes to a stop)

EVALUATORS NOTE:

Steps 4 - 5 are to be completed when performing this JPM on Unit 1.

Steps 6 - 7 are to be completed when performing this JPM on Unit 2.

Steps for the Unit NOT selected for this JPM may be marked N/A even though they are marked as critical steps.

4. UNIT 1 ONLY Using the adjustable wrench, REMOVE test connection cap from rotate the cap in the IIV-047-101.1, "PT-1 N052 CRD counter-clockwise (CCW)

SCRAM VALVE PILOT AIR" on direction and remove the test North side of instrument rack connection cap downstream 10C213 (402-R15-253) of the root valve for PT-(ATTACHMENT 1 & 2) 1N052 CUE: "The cap rotates until it comes free from the end of the pipe."

5. UNIT 1 ONLY Using the adjustable wrench, REMOVE test connection cap from rotate the cap in the IIV-047-101.2, "Pl-1 R013 CRD counter-clockwise (CCW)

SCRAM VALVE PILOT AIR" on direction and remove the test South side of instrument rack connection cap downstream 10C213 (402-R15-253) of the root valve for (ATTACHMENT 1 & 2) Pl-47-1R013 CUE: "The cap rotates until it comes free from the end of the pipe."

LOJPM2210 Rev003.doc SRRS: 3D.105 Page 6 of 9 (When used for operator initial or continuing training)

-" Exelon

~

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6. UNIT 2 ONLY Using the adjustable wrench, REMOVE test connection cap from rotate the cap in the IIV-047-201.1, "PT-2N052 CRD counter-clockwise (CCW)

SCRAM VALVE PILOT AIR" on direction and remove the test North side of instrument rack connection cap downstream 20C213 (475-R17-253) of the root valve for (ATTACHMENT 1 & 2) PT-2N052 CUE: "The cap rotates until it comes free from the end of the pipe."

7. UNIT 2 ONLY Using the adjustable wrench, REMOVE test connection cap from rotate the cap in the IIV-047-201.2, "Pl-2R013 CRD counter-clockwise (CCW)

SCRAM VALVE PILOT AIR" on direction and remove the test South side of instrument rack connection cap downstream 20C213 (475-R17-253) of the root valve for (ATTACHMENT 1 & 2) Pl-2R013 CUE: "The cap rotates until it comes free from the end of the pipe."

8. WHEN RV-047-*01, Main Control Room notified "Pl-*R013, PT-*N052 CRD SCRAM VALVE PILOT AIR" will be opened, THEN NOTIFY MCR that control rod movement should occur

9. OPEN RV-047-*01, "Pl-*R013, Root valve for PT- N052 PT-*N052 CRD SCRAM VALVE and Pl-- R013 handwheel PILOT AIR" on East side of rotated counter-clockwise instrument rack *OC213 (CCW) until the valve is open CUE: "The handwheel rotates and then comes to a stop. You can hear air escaping from the test connections."

CUE: You have met the termination criteria for this JPM JPM Completion Time _ _ _ __

LOJPM2210 Rev003.doc SRRS: 3D.105 Page 7 of 9 (When used for operator initial or continuing training)

I= Exelon Generation JPM

SUMMARY

Operator's Name: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _____;,

Job

Title:

D SEO D SM D SRO D RO D STA/IA D EO D OTHER JPM

Title:

Manual Isolation and Vent of the Scram Air Header JPM Number: LOJPM2210 Revision Number: 003 Task Number and

Title:

2000550501, (T-216) Manually Isolate and Vent Scram Air Header (RO) 2000310504, Perform Manual Isolation and Vent of Scram Air Header (EO)

KIA Number and Importance: 212000 A4.17 4.1/4.1 295037 EA1.05 3.9/4.0 Level of Difficulty (1-5) ...1...

Suggested Testing Environment: In-Plant Alternate Path:0 Yes [8J No SRO Only: D Yes [8J No Time Critical: D Yes [8J No Reference(s): T-216 Manual Isolation and Vent of Scram Air Header U/1 Rev. 18 T-216 Manual Isolation and Vent of Scram Air Header U/2 Rev. 16 Actual Testing Environment: D Simulator D Control Room [8J In-Plant D Other Testing Method: [8J Simulate D Perform Estimated Time to Complete: 20 minutes Actual Time Used: minutes EVALUATION

SUMMARY

Were all the Critical Elements performed satisfactorily? D Yes D No The operator's performance was evaluated against standards contained within this JPM and has been determined to be: D Satisfactory D Unsatisfactory Comments:

Evaluator's Name: - - - - - - - - - - - - - - - - - (Print)

Evaluator's Signature: _ _ _ _ _ _ _ _ _ _ _ _ _ __ Date:

LOJPM2210 Rev003.doc SRRS: 3D.105 Page 8 of 9 (When used for operator initial or continuing training)

Exelon Generation LIMERICK GENERATING STATION JOB PERFORMANCE MEASURE INDIVIDUAL BRIEFING SHEET INITIAL CONDITIONS

1. Unit is in an ATWS.

INITIATING CUE STATEMENT:

Shift Supervision directs you to perform T-216 on Unit_.

Page 9 of 9

Ir Exelon Generation.

LIMERICK GENERATING STATION JOB PERFORMANCE MEASURE ALTERNATE INJECTION FROM THE FIRE SYSTEM JPM Number: LOJPM2260 REVISION NUMBER: 001 DATE: ----

Developed By:

Instructor Date Validated By:

SME or Instructor Date Reviewed By:

Operations Representative Date Reviewed By:

EP Representative Date Approved By:

Training Department Date LOJPM2260 Rev001 SRRS: 30.105 Page 1 of 10 (When used for operator initial or continuing training)

1.= Exelon Generation Note: This LGS format satisfies the TQ-JA-150 Format I. JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation.

Prior to JPM usage, revalidate JPM using steps 9 through 13 below.

1. Task description and number, JPM description and number are identified.

2. Knowledge and Abilities (KIA) references are included.

3. Performance location specified. (in-plant, control room, simulator, or other)

4. Initial setup conditions are identified.

5. Initiating cues (and terminating cues if required) are properly identified.

6. Task standards identified and verified by SME review.

7. Critical steps meet the criteria for critical steps and are identified with an asterisk

(*).

8. If an alternate path is used, the task standard contains criteria for successful completion.

9. Verify the procedure(s) referenced by this JPM reflects the current revision:

Procedure T-244 U/2 Rev: ---'-'18:;.....__

Procedure_ _ _ _ _ _ _ _ __ Rev: _ __

Procedure Rev: - - -

Rev: _ __

Procedure----------

Procedure - - - - - - - - - - Rev: ---

10. Verify cues both verbal and visual are free of conflict.

11. Verify performance time is accurate

12. If the JPM cannot be performed as written with proper responses, then revise the JPM.

13. When JPM is initially validated, sign and date JPM cover page.

Subsequent validations, sign and date below:

SME / Instructor Date SME / Instructor Date SME / Instructor Date LOJPM2260 Rev001 SRRS: 3D.105 Page 2 of 10 (When used for operator initial or continuing training)

I~ Exelon Generation II. RECORD OF TEMPORARY CHANGES:

A. Approval of Pen & Ink Changes will be by the ILTor LORT Lead Instructor with OTM concurrence B. All Pen & Ink Changes are to be tracked in ILTor LOR Program Action Tracking for Next Revision C. All Pen & Ink Changes shall be in accordance with TQ-AA-223 Temp Date of Purpose of Change ILT/LORT Action Revision Change# Change Approval Tracking Date Ill. REVISION HISTORY:

A. If a Revision affects a Task Performance from VISION Terminal Performance Objectives then the revision must also be made in the VISION database.

B. The description of the Revision should adequately indicate how the training content of the Revision has changed.

C. The description of the Revision should also include previous format reference and number and previous template used (i.e. for conversion to LLOJPM format).

D. For Revision 000, put reason for writing this JPM and for all subsequent revisions, annotate the changes that were made or incorporated.

Revision # Date of Description of Revision and Affect on Training Content Number Revision 000 This JPM supersedes LLOJPM0260 Rev. 7. Revised to new template and to 10/12/16 align with latest procedure revision.

001 Revised with latest procedure revision. 10/02/17

Date of Revision - refers to date revision was released for approval LOJPM2260 Rev001 SRRS: 3D.105 Page 3 of 10 (When used for operator initial or continuing training)

I~ Exelon Generation IV. TASK STANDARD:

Hoses connected and valves aligned per T-244 U/2, Alternate Injection From The Fire System V. SIMULATOR SETUP N/A VI. INITIAL CONDITIONS:

1. Unit 2 reactor level is low and injection is being established.

2. Reactor pressure is 50 psig.

VII. INITIATING CUE:

Shift Supervision directs you to perform T-244 for Unit 2 to supply Fire Water to raise reactor water level.

LOJPM2260 Rev001 SRRS: 3D.105 Page 4 of 10 (When used for operator initial or continuing training)

I£' Exelon Generation Information for Evaluator's Use:

Any UNSAT requires written comments on respective step.

Denotes critical steps Number any comments in the "Comment Number" column on the following pages. Then annotate that comment in the "Comments" section. The comment section should be used to document: the reason that a step is marked as unsatisfactory, marginal performance relating to management expectations, or problems the examinee had while performing the JPM.

Comments relating to procedural or equipment issues should be entered and tracked using the site's appropriate tracking system.

Some operations that are performed from outside the control room may require multiple steps.

These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed.

The JPM Start Time clock starts when the candidate acknowledges the initiating cue.

LOJPM2260 Rev001 SRRS: 3D.105 Page 5 of 10 (When used for operator initial or continuing training)

[= ExelonGeneration.

VIII. PERFORMANCE CHECKLIST:

JPM Start Time ELEMENT STANDARD I-

<(

u, For In-Plant T-200 JPMs, include the following:

NOTE:

IF this JPM is the first of multiple T-200 series JPMs being performed by a single candidate THEN steps #1 and #2 apply.

OTHERWISE mark steps #1 and #2 as N/A AND provide the following to the candidate:

a. INITIATING CUE(S)

b. CUE: "You are now in possession of the T-244 U/2 equipment container. It contains all tools and equipment required by the procedure. You are to simulate their use during performance of the procedure."

c. PROCEDURE COPY

1. Obtain current revision of T-244 U/2, Candidate demonstrates Alternate Injection From The Fire ability (actual or discuss) to System locate T-244 U/2.

CUE: Candidate is given a copy of T-244 U/2 when knowledge of the correct location of procedure is demonstrated.

2. Obtain necessary Tools/Equipment Tools obtained.

from Unit 2 T-225/T-244 Hose Storage Locker (475-R17-253), BL-840 key required.

CUE: You have the necessary tools/equipment in your possession.

3. [T-244 4.1]

N/A PERFORM the following in 475-R17-253 (Attachment 1):

LOJPM2260 Rev001 SRRS: 3D.105 Page 6 of 10 (When used for operator initial or continuing training)

I:' Exelon Generation I- a:::

I- ZW ELEMENT STANDARD I- <C Wm

> Oz 0

4. [T-244 4. 1. 1] Hose connected between 51-CONNECT hose at 51-2179 "2A 2179 "2A" RHR Fire RHR Fire Protection Crosstie Drain Protection Crosstie Drain Viv Valve" AND ROUTE to drain. AND routed to drain.

CUE: End of hose is connected to 51-2179 4a. [T-244 4.1.2] 51-2179 cycled open and CYCLE 51-2179 open AND closed closed.

to ensure pipe drained.

5. [T-244 4. 1. 3] Hose connected between 22-CONNECT hose at 22-2430 "Fire 2430 "Fire Protection/RHR Protection/RHR Interconnection Orn Interconnection Orn Viv AND Viv" AND ROUTE to drain routed to drain CUE: End of hose is connected to 22-2430.

Sa. [T-244 4.1.4] 22-2430 cycled open and CYCLE 22-2430 open AND closed closed.

to ensure pipe drained.

6. [T-244 4. 1. 5] Fire hose is connected to 22-

CONNECT hose to fitting 2429.

downstream of 22-2429, Fire Protection/RH R Interconnection Isolation Valve."

CUE: End of hose is connected to 22-2429.

LOJPM2260 Rev001 SRRS: 3D.105 Page 7 of 10 (When used for operator initial or continuing training)

I,=" Exelon Generation I- 0::::

I- Zw ELEMENT STANDARD I-

<(

u, Wm

E :E u, z :E :::>

> Oz 0

7. [T-244 4. 1. 6]

CONNECT other end of hose to Hose is connected from 22-fitting downstream of 51-2178, 2429 to 51-2178.

"RHR/Fire Protection Interconnection Isolation Valve."

CUE: End of hose is connected to 51-2178.

8. [T-244 4. 1. 7] 22-2429 turned full counter-

OPEN 22-2429 clockwise CUE: Valve handwheel rotates several turns and then comes to a stop.

9. [T-244 4. 1. BJ 51-2178, using LV-200,

UNLOCK AND OPEN 51-2178 unlocked and open (turned full counterclockwise)

CUE: Valve handwheel rotates several turns and then comes to a stop.

CUE: You have met the termination criteria for this JPM JPM Completion Time _ _ _ __

LOJPM2260 Rev001 SRRS: 3D.105 Page 8 of 10 (When used for operator initial or continuing training)

I,F Exelon Generation JPM

SUMMARY

Operator's Name: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _-----:.

Job

Title:

D SEO D SM D SRO D RO D STA/IA D EO D OTHER JPM

Title:

ALTERNATE INJECTION FROM THE FIRE SYSTEM JPM Number: LOJPM2260 Revision Number: 001 Task Number and

Title:

(T-244) Alternate Injection From The Fire System KIA Number and Importance: 295031 EA1.08 3.8/3.9 Safety Function (1-9) 2 (Reactor Water Inventory Control)

Admin Category (A1-4) NIA Level of Difficulty (1-5) __2_.o__

Suggested Testing Environment: In-Plant Alternate Path:0 Yes~ No SRO Only: D Yes ~ No Time Critical: D Yes ~ No Reference(s): T-244 U/2 Alternate Injection From The Fire System, Rev018 Actual Testing Environment: D Simulator D Control Room ~ In-Plant D Other Testing Method: ~ Simulate D Perform Estimated Time to Complete: 15 minutes Actual Time Used: minutes EVALUATION

SUMMARY

Were all the Critical Elements performed satisfactorily? D Yes D No The operator's performance was evaluated against standards contained within this JPM and has been determined to be: D Satisfactory D Unsatisfactory Comments:

Evaluator's Name: - - - - - - - - - - - - - - - - - (Print)

Evaluator's Signature: _ _ _ _ _ _ _ _ _ _ _ _ _ __ Date: ---

LOJPM2260 Rev001 SRRS: 3D.105 Page 9 of 10 (When used for operator initial or continuing training)

~, Exelon Generation LIMERICK GENERATING STATION JOB PERFORMANCE MEASURE INDIVIDUAL BRIEFING SHEET INITIAL CONDITIONS:

1. Unit 2 reactor level is low and injection is being established.

2. Reactor pressure is 50 psig.

INITIATING CUE:

Shift Supervision directs you to perform T-244 for Unit 2 to supply Fire Water to raise reactor water level.

Page 10 of 10

LIMERICK GENERATING STATION

,.:.** Exelon Generation SIMULATOR EXERCISE GUIDE CODE NO: SEG-2159E REV NO: 000 AUTHOR: T. BYERS APPROXIMATE 60 minutes RUN TIME:

TYPE: SIMULATOR EVALUATION EFFECTIVE DATE: 12/01/17 GUIDE PROGRAM: LICENSED OPERATOR TRAINING COURSE: LICENSED OPERATOR (REQUALIFICATION/INITIAL) TRAINING TITLE: Simulator Evaluation Guide for Individual and Crew Performance Prepared By: T. A. By_ers/S/ Date: 11/20/17 Training Instructor - Signature Reviewed By: N/A for NRC ILT Date: N/A LORT Lead Instructor - Signature Reviewed By: N/A Date: NIA EP (as appropriate) - Signature Reviewed By: N/A Date: N/A RE (as appropriate) - Signature Approval: Bill Martin/SI Date: 11/30/17 OPS Manager - Signature Approved For Use: Dan Semeter/S/ Date: 12/01/17 Training Manager - Signature SEG-2159E Rev 000.doc Page 1 of 45

LIMERICK GENERATING STATION

,:," Exelon Generation SIMULATOR EXERCISE GUIDE Appendix D Scenario Outline Form ES-D-1 Facility: Limerick 1 & 2 Scenario No.: SEG-2159E Rev _o_ Op-Test No.: 1 Examiners: Operators:

Initial Conditions:

Unit 1 Reactor Power is 100%

Unit 2 Reactor Power is 100%

Turnover:

Perform ST-6-077-310-1, Drywell Unit Cooler Hydrogen Mixing System Operability Test Run Critical Tasks:

1. Trip and isolate Recirc Pump

2. Manually Scram the Reactor

3. Spray the Drywell

4. Perform Emergency Slowdown per T-112 Event Malfunction Event Event No. Number Type* Description 1 None N-PRO Perform Drywell Unit Cooler Hydrogen Mixing System Operability Test Run MFW246A C-RO 2 MFW552C C-PRO Trip of '1C' RFP with discharge check valve stuck open 3 MCR547 C-RO Running CRD Pump Trip HCU accumulator Trouble for HCU MRD016C TS-SRO 18-47 C-PRO 4 MRR433B R-RO Sequential failures of '1 B' Recirc Pump Seals MRR434B TS-SRO 5 MMS067 M-AII Steam leak in the Drywell 6 MRP029C C-RO RPS 'A' fails to scram (ARI successful)

Downcomer break results in Suppression Pool pressure 7 MPC476 C-PRO equalizing with Drywell pressure requiring blowdown on Pressure Suppression Curve HS-51-F016A First Drywell spray method selected will be un-successful 8 or C-PRO requiring use of other train HS-51-F016B

(N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor SEG-2159E Rev 000.doc Page 2 of 45

..-- LIMERICK GENERATING STATION

' ' Exelon Generation SIMULATOR EXERCISE GUIDE A. ILT Target Quantitative Attributes ACTUAL (Per Scenario; See ES-301Section D.5.d) NUMBER

1. Malfunctions after EOP entry (1-2) 3

2. Abnormal events (2-4) 3

3. Major transients (1-2) 1

4. EOPs entered/requiring substantive actions (1-2) 2

5. EOP contingencies requiring substantive actions (0-2) 2

6. Critical tasks (2-3) 4 Review TQ-AA-151 attachment 5 and ES-301-5 for individual position requirements for scenario and scenario set SEG-2159E Rev 000.doc Page 3 of 45

--* Exelon Ger1eration LIMERICK GENERATING STATION SIMULATOR EXERCISE GUIDE II. PURPOSE: Systematically evaluate individual and team performance to identify areas for improvement. Critical Tasks and Assessment Items from this evaluation guide are to be used to assess crew and individual performance and as input into a 4.0 Crew Critique Process.

Ill. SIMULATOR EVALUATION GUIDE OBJECTIVES:

A. The following evaluation objectives apply to the Crew (C), Shift Manager (SM), Control Room Supervisor (S), Unit Reactor Operator I Plant Reactor Operator (R), or Incident Assessor/ Shift Technical Advisor (A) as indicated in the following categories.

1. The general condition for each of the evaluation objectives will be "Given the plant conditions and sequence of events in the Simulator Evaluation Guide (SEG)".

2. The general acceptable evaluation objective criteria for each of the evaluation objectives will be "To perform effectively as an individual and contribute to successful crew performance in accordance with appropriate reference plant procedures and Operations Expectations, Fundamentals and Strategies".

3. Specific UNSAT evaluation objective criteria will be consistent with TQ-AA-155, Conduct of Simulator Training and Evaluation with applicable forms and job aids.

4. During performance of this Simulator Evaluation Guide, the individuals and crew should satisfactorily demonstrate the following overall procedure and plant control objectives:

Direct and perform actions per GP-5 Appendix 3, Unintentional Drop In Power.

Direct and perform actions per ON-107, Control Rod Drive System Problems.

Direct and perform actions per OT-100, Reactor Low Level

Direct and perform actions per OT-101, Drywell High Pressure

Direct and perform actions per SE-10, LOCA

Direct and perform actions per T-101, RPV Control

Direct and perform actions per T-102, Primary Containment Control

Direct and perform actions per T-112, Emergency Slowdown SEG-2159E Rev ODO.doc Page 4 of 45

LIMERICK GENERATING STATION

-* Exelon Generation SIMULATOR EXERCISE GUIDE IV. RECORD OF TEMPORARY CHANGES

A. Approval of Pen & Ink Changes will be by the ILT or LORT Lead Instructor with OTM concurrence B. All Pen & Ink Changes are to be tracked in ILTor LOR Program Action Tracking for Next Revision C. All Pen & Ink Changes shall be in accordance with TQ-AA-223 Temp Date of Purpose of Change LORT Action Revision Change# Change Approval Tracking Date V. REVISION HISTORY:

A. If a Revision affects a Task Performance from VISION Terminal Performance Objectives then the revision must also be made in the VISION database.

B. The description of the Revision should adequately indicate how the training content of the Revision has changed.

C. The description of the Revision should also include previous format reference and number and previous template used (e.g for conversion of LSTS to LLORSEG format).

Revision # Date of Description of Revision and Affect on Training Content Number Revision RevOOO NewSEG 8/15/17

Date of Revision - refers to date revision was released for approval SEG-2159E Rev ODO.doc Page 5 of 45

LIMERICK GENERATING STATION

Exelon Generation SIMULATOR EXERCISE GUIDE SCENARIO EVENT AND EVALUATION

SUMMARY

Event One: When the crew assumes responsibility for the shift, the PRO will commence performance of ST-6-077-310-1,"Drywell Unit Cooler Hydrogen Mixing System Operability Test".

Evaluation: Evaluate the PRO's ability to perform the ST and the CRS ability to provide oversite during the evolution.

Event Two: Shortly after the PRO completes the switch lineup for the ST, the '1 C' RFP Turbine will trip and the pump discharge check valve will stick open. This will lead to lowering Rx water level and require the crew to lower power and manually close the feed pump discharge valve.

Evaluation: Evaluate the crew's ability to recognize the RFP Turbine trip and failure of the discharge check valve to close. Evaluate crew's execution of OT-100 for lowering Rx level and reduce Rx power. The crew is expected to lower power such that total FW flow is less than 13 Mlbm/hr. The crew should manually close the '1C' RFP discharge valve.

Event Three: When the plant has been stabilized following the power reduction for the RFP trip, the running CRD Pump trips as a result of a clogged suction filter. Also a CRD accumulator trouble alarm is received.

Evaluation: Evaluate the crew's ability to recognize and respond to the tripped CRD Pump. The crew is expected to execute ON-107, Control Rod Drive System Problems, and take actions required by Tech Spec 3.1.3.5.

Event Four: Following the restart of the CRD Pump, a sequential failure of both the Reactor Recirc Pump Seals will occur for the 1B Reactor Recirc Pump.

Evaluation: To evaluate the crews response to increasing drywell pressure and temperature, including the initial execution of OT-101, Drywell High Pressure, and tripping and isolating the '1 B' Reactor Recirc Pump.

Event Five and Following the isolation of the '1 B' Reactor Recirc Pump, a steam leak into the drywell Six and Seven: will occur requiring a plant shutdown. On the shutdown a failure of the "A" side of RPS to de-energize will occur. Also, following the Reactor Scram, a downcomer break will occur resulting in Suppression Pool pressure rising faster, and exceeding the Pressure Suppression Curve.

Evaluation: To evaluate the crews ability to diagnose and respond to the rising Drywell pressure condition. To evaluate the ability of the RO to use alternate means (ARI) to shut the reactor down. To evaluate the ability of the SRO to direct actions from T-101 and T-102 to mitigate the leak and direct the PRO to spray the Suppression Pool and the Drywell per T-225. To evaluate the PRO and SRO's ability to recognize the rising Suppression Pool pressure and implement T-112 Emergency Slowdown when the safe side of the PC/P curve cannot be maintained. The PRO will open 5 ADS SRVs to blowdown the reactor to the Suppression Pool.

SEG-2159E Rev 000.doc Page 6 of 45

-* Exelon Gener*ation LIMERICK GENERATING STATION SIMULATOR EXERCISE GUIDE SCENARIO EVENT AND EVALUATION

SUMMARY

cont'd:

Event Eight: To control the Drywell pressure and temperature increase, Drywell spray operation will be required. The first Drywell spray method selected by the crew will be un-successful (either HV-051-1F016A or HV-051-1F016B will fail to open) requiring use of other train to spray the drywell.

Evaluation: To evaluate crews ability to re-direct the unaffected RHR train to Drywell Spray.

Termination The scenario may be terminated when an Emergency Depressurization has been Criteria: performed, Drywell Spray is in service, control rods inserted and reactor level is restored.

SEG-2159E Rev 000.doc Page 7 of 45

LIMERICK GENERATING STATION

~** Exelon Generation SIMULATOR EXERCISE GUIDE VI. REFERENCES A Training Procedures

1. TQ-AA-150, Operator Training Programs

2. TQ-AA-151, ILT Certification and NRC Examination Development and Administration

3. TQ-AA-155, Conduct of Simulator Training and Evaluation

4. TQ-LG-150, Limerick Operator Training Program B. Annunciator Response Cards (ARC)

1. 101 F-5, 1A,1B,1C, RFPT BEARING DRAIN OIL HI TEMP

2. 101 G-2, LEFM TROUBLE

3. 101 1-1, 1C RFPT CONTROLLER TROUBLE

4. 101 1-2, RFPT GOVERNOR TROUBLE

5. 102 C-1, 1C RFPT TRIP

6. 107 1-2, VIBRATION ALERT

7. 107 1-3, VIBRATION DANGER

8. 107 F-2, DRYWELL HI/LO PRESS

9. 107 D-5, FWLC TROUBLE

10. 107 H-2, REACTOR HI/LO LEVEL

11. 108 G-1, 1A/1B CRD WATER PUMP TRIP

12. 108 G-3, 1A/1B CRD PUMP SUCTION LO PRESS

13. 108 H-3, CRD PUMP SUCTION FILTER HI DP

14. 108 H-4, CRD CHARGING WATER LO PRESS

15. 108 F-1, CRD ACCUMULATOR TROUBLE

16. 109 F-1/ F-2 1 MAIN STEAM LINE DIVISION 1 RAD MONITOR HI/DOWNSCALE

17. 111/112 B-3, 1A/B RECIRC ASD MINOR FAILURE

18. 112 A-1, 18 RECIRC PUMP SEAL STAGE HI/LO FLOW

19. 112 A-2, 1B RECIRC PUMP SEAL LEAKAGE HI FLOW

20. 112 C-5, DRYWELL EQUIPMENT DRAIN TANK/FLOOR DRAIN SUMP LEAKAGE HI FLOW

21. 115 B-5, DRYWELL COOLER DRAIN FLOW HIGH

22. 127 1-1, 1 UNIT HWC SYSTEM TROUBLE C. System Procedures (S)

1. S06.2.A U/1, Shutdown Reactor Feed Pump from Standby Condition

2. S 12.1.A, RHR Service Water System Startup.

3. S46.1.A, Control Rod Drive Hydraulic System Startup D. General Procedures (GP)

1. GP-4, Rapid Plant Shutdown to Hot Shutdown

2. GP-5, Appendix 2, Rx Maneuvering Without Shutdown

3. GP-5 Appendix 3, Unintentional Drop In Power.

E. Off Normal Procedures (ON)

1. ON-107, Control Rod Drive System Problems.

SEG-2159E Rev 000.doc Page 8 of 45

--*~

Exelon Generation LIMERICK GENERATING STATION SIMULATOR EXERCISE GUIDE F. Operating Transient Procedures (OT) 1 . OT-100, Reactor Low Level

2. OT-104, Unexpected/Unexplained Positive or Negative Reactivity Addition

3. OT-101, High Drywell Pressure

4. OT-112, Unexpected/Unexplained Change in Core Flow G. Event Procedures (E)

H. Special Event Procedures (SE)

1. SE-10, LOCA I. Surveillance Test and Routine Test Procedures (ST and RT)

1. ST-6-077-310-1, Drywell Unit Cooler Hydrogen Mixing System Operability Test Run.

J. Technical Specifications and TRM (TS)

1. TRM 3.3. 7.13 - Feedwater Flow Instrumentation

2. 3.4.5 - Specific Activity

3. 3.1.3.5 - Control Rod Scram Accumulators

4. 3.4.1.1 - Recirculation Loops K. Transient Response Implementation Procedures (T-100 series)/SAMPs

1. T-101, RPV Control

2. T-102, Primary Containment Control

3. T-112, Emergency Slowdown L. TRIP 200 Series Procedures

1. T-225, Startup and Shutdown of Suppression Pool and Drywell Spray Operation M. EP-AA-1008, Limerick, Radiological Emergency Plan Annex for Limerick Generating Station N. Administrative Procedures

1. OP-AA Procedures

a. OP-AA-1, Conduct of Operations

b. OP-AA-20, Conduct of Operations Process Description

c. OP-AA-101-111-1003, Operations Department Standards and Expectations

d. OP-AA-101-113, Operations Fundamentals

e. OP-AA-101-113-1006, 4.0 Crew Critique Guidelines

f. OP-AA-106-101-1006, Operational Decision Making Process

2. OP-LG Procedures

a. OP-LG-101-111-1000, Licensed Operator Duties

b. OP-LG-102-106, Operator Response Time Program at Limerick

c. OP-LG-103-102-1000, Human Performance Continuing Good Practices

d. OP-LG-103-102-1002, Strategies for Successful Transient Mitigation

e. OP-LG-108-101-1001, Simple Quick Acts I Transient Acts

0. Current Shift Night Orders Forced Outage Plan P. INPO Significant Operating Experience Reports (SOER}, Significant Event Reports (SER) and INPO Event Reports (IER)

1. SOER 10-02, Engaged Thinking Organizations

2. INPO 15-004, Operator Fundamentals SEG-2159E Rev 000.doc Page 9 of 45

-,,,,...., Exelon Generation LIMERICK GENERATING STATION SIMULATOR EXERCISE GUIDE VII. PREBRIEF INSTRUCTIONS

Unit 1 is at 100% power

Unit 2 is at 100% power Specific Plant Conditions are as Follows:

None Inoperable/Out of Service Equipment and Estimated Time of Return (ETR):

None Restrictions on Plant Operations:

None Planned Evolutions:

Perform Drywell Unit Cooler Hydrogen Mixing System Operability Test Documents Provided:

ST-6-077-310-1, Drywell Unit Cooler Hydrogen Mixing System Operability Test Run.

SEG-2159E Rev 000.doc Page 10 of 45

LIMERICK GENERATING STATION

,=:w Exelon Generation. SIMULATOR EXERCISE GUIDE VIII. DIRECTIONS FOR EVALUATION PREPARATION A. INITIAL PREPARATION

~ ITEM / MALFUNCTION / REMOTE FUNCTIONS Complete TQ-AA-155, Operator Training Programs Attachment 02, Evaluated Scenario Administration Checklist.

Complete TQ-LG-201-0113, Limerick Training Department Simulator Examination Security Actions Checklist

8. SIMULATOR SETUP

~ ITEM / MALFUNCTION / REMOTE FUNCTIONS Complete Limerick Simulator Pre-Evaluation Checklist Reset Simulator to the Pre-loaded IC developed for the Evaluation OR Reset the simulator to designated base load IC AND Load scenario file SEG2159E RevOOO.scn

Verify that all Malfunctions, Remotes, Overrides, Annunciators and Triggers are properly loaded OR

Manually enter the Malfunctions, Remotes, Overrides, Annunciators and Triggers per the Scenario Generator Screen Shots:

Simulator Operator (Driver) perform the following:

Momentarily place simulator in RUN

Acknowledge and clear all spurious alarms

Place the simulator back into FREEZE

Provide copy of ST-6-077-310-1, Drywell Unit Cooler Hydrogen Mixing System Operability Test.

SEG-2159E Rev 000.doc Page 11 of 45

LIMERICK GENERATING STATION

.=.** Exelon Generation SIMULATOR EXERCISE GUIDE C. MALFUNCTION/REMOTE/OVERRIDE/ANNUNCIATORS FUNCTION TIME TABLE Ma/function Summary Mall ID Mult ID Descr' ion Current Value Tar et Value Rmptine Actime Dacline ~

MM46A ReactorF~CT~ F.ise True 00:10:15 1 VIC104C2 1CRFPT T11biie lrrmlance at Prooe 104C02 2mm 10.cmxi 00:10:00 00:00:15 1 MCR547 RlffllQ CAD PllnP T~ on Cklgged Sucoon Fier F.ise True 00:04:30 2 MRD016C 18-47 Control Rod Faue,Acwiuala Trm F.ise True 00:~:00 2 MRR43ll MRR4348 Recic Pimp 1BSeal No. 1Faue Recic Pimp 18 Seal No. 2Fehe F*

False True True 00:02:00 00:04:00 3

3 MMS~7 Stean Leak ri Drywel (0-5IXX) !Pill noo !DJ.0000 00:09:00 00:02:00 4 MPC476 Drywel Ai;pace Lealc. to S~essoo Clmber Aispace noo 50.00lll 00:03:00 00:lli:OO 4 r Timer Pause -Pending r Timer Pause Delete All -Pending SEG-2159E Rev 000.doc Page 12 of 45

,_. Exelon Generation.

LIMERICK GENERATING STATION SIMULATOR EXERCISE GUIDE D. EVENT TRIGGERS ASSIGNMENT

1. Timers should be used on event triggers where possible for time validation

2. Timing of event triggers may be altered by the Lead Evaluator (or designee)

3. Verify triggers are actuated automatically as designed or manually initiate the trigger when the initiating action has occurred.

4. Inform Lead Evaluator (or designee) of expected plant response prior to actuation of each trigger.

5. Trigger #1 is manually initiated at Lead Evaluator (or designee) direction after the crew assumes responsibility for operation.

TRIGGER/ MALFUNCTION /

@ TIME EVENT DESCRIPTION 1 Manual Initiates '1 C' Reactor Feed Pump Rising vibrations and timed trip.

Auto / FWZR607R Total steam flows 13.1 Mlbm/hr 2 Initiates clogged CRD Suction Filter and HCU

<=26015 accumulator trouble.

Auto / ZLCS07 AR II '1A' or '1 B' CRD Pump Handswitch to start 3 Initiates sequential failures of the '1 B' Reactor ZLCS07BR Recirc Pump seals.

Total steam flows 8.5 Mlbm/hr 4 Auto/ Initiates steam leak into the Drywell and leak FWZR607R<=16890 between the Drywell and the Suppression Pool air spaces .

""------~= -

- -' .;,>,'.l~* ~ - -

f.avorites Iriggers Tri er ti Tri er Text - 0 per at ors:

1 Arithmetic:

2 FWZR607R <*26015

Multiplication 3 ZLCS07AR IIZLCS07BR I Division 4 FWZR607R <*16890 + Addition 5

Subtraction 6

Relational:

7

> Greater than 8

>* Greater than 9 or equal 10 < Less than 11 <* Less than or 12 equal 13 == Equalto 14 !* Not equal to 15 Logical:

16

&& And 17 II Or 18

! Not 19 Other:

Open Paren Close Paren lrigger Now I ,!;;lear C]earAII I e,ccept SEG-2159E Rev 000.doc Page 13 of 45

LIMERICK GENERATING STATION

~" Exelon Generation SIMULATOR EXERCISE GUIDE E. EQUIPMENT REPORTS AND SIMULATOR INSTRUCTOR OPERATIONS

1. This table section is moved and now integrated with Assessment of Crew Performance to facilitate simulator Operator and Instructor observation of crew activities related to simulator operation and instructor intervention.

2. Scripted Activity Reports should be followed with adherence to Operations Communication standards of performance.

3. The T-200 procedure reference book should be used for familiarity of reports to aid in operator prompting and expected communications.

4. The Lead Evaluator (or designee) should be informed if any event is not reported as scripted due to lack of Operator request.

5. The Standard Equipment Operator Response Times are per Attachment 1

6. A record of communications from the MCR and to the MCR will be maintained by the Simulator Operator using Attachment 2.

7. The OCOEE Simulator Operator Station P&1Ds, Floor Plans and Panels must be used by the Simulator Operator as reference information when making reports to the MCR for plant parameters which are not driven by a communications script. Examples include: ARMs, Blowout Panel status, Reactor Building Area Temperatures and Pressures, RMMS, Turbine Enclosure parameters etc.

SEG-2159E Rev 000.doc Page 14 of 45

LIMERICK GENERATING STATION

, ' Exelon Generation SIMULATOR EXERCISE GUIDE IX. CREW CRITICAL TASKS A Critical Tasks are based on the current Crew Critical Task List revision, NU REG 1021, and TQ-AA-150 requirements.

1. OT-101.1 If both shaft seals on a Reactor Recirculation Pump have failed, trip and isolate the pump.

KIA 295010 AK3.04 3.5/3.8 KIA 295010 AA2.02 3.8/3.9 Standard: Trip the applicable Reactor Recirculation Pump, close the pump discharge valve, seal purge valve, and suction valve to isolate the reactor coolant leakage into the Drywell.

SAT/UNSAT

2. T-101.7 Manually Scram the reactor KIA 212000 A4.01 4.6/4.6 KIA 295015 AA1.02 4.0/4.2 Standard: When any Reactor Protection System (RPS) setpoint is exceeded, then manually SCRAM the reactor. If a manual SCRAM is inserted prior to a monitored RPS parameter exceeding its setpoint, then the intent of this standard is met.

SAT/UNSAT

3. T-102.1 Spray the Drywell per T-225.

KIA 295012 AA2.01 3.2/4.2 KIA 295010 AK2.01 3.2/3.3 KIA 295010 AA1.07 3.2/3.4 Standard: Before Drywell temperature reaches 340°F, with Drywell temperature and pressure on the SAFE side of the Drywell Spray Initiation Limit curve and Suppression Pool level below 37.4 feet, then spray the Drywell per T-225 before exceeding 340°F.

SAT/UNSAT SEG-2159E Rev 000.doc Page 15 of 45

LIMERICK GENERATING STATION

: Exelon Generation SIMULATOR EXERCISE GUIDE

4. T-102.2 Perform emergency blowdown per T-112.

KIA 295012 AA2.01 3.8/3.9 KIA 295010 AA1.05 3.1/3.4 Standard: When Drywell temperature cannot be restored and maintained below 340°F or Suppression Pool pressure cannot be maintained below the Pressure Suppression Pressure (PSP) curve, then enter T-112 and perform an emergency blowdown by opening five Safety Relief Valves (SRVs).

SAT/UNSAT SEG-2159E Rev 000.doc Page 16 of 45

~ Exelon Generation LIMERICK GENERATING STATION SIMULATOR EXERCISE GUIDE X. ASSESSMENT OF CREW PERFORMANCE DURING CONDUCT OF THE DYNAMIC SIMULATOR EVALUATIONS:

A. Conduct the Simulator Evaluation Session per TQ-AA-155, Conduct of Simulator Training and Evaluation, Attachment 02, Evaluated Scenario Administration Checklist B. Assessment of Crew and Individual performance shall be consistent with OP-AA-20, Conduct of Operations Process Description C. Where possible record the time and position responsible for performance of each task or assessment item D. Items not performed as expected SHALL be discussed in the post performance crew critique E. During the performance of the evaluation, the Simulator Evaluators shall MAINTAIN notes of observations and information consistent with the timeline F. Assessment items with the Co symbol indicate a time critical standard for performance G. Assessment items with the ~ symbol indicate a Probabilistic Risk Assessment (PRA) association with the task H. The Simulator Operator will respond with scripted or proceduralized responses when requested by the MCR operators with Procedure completion times requested per Attachment 1 I. The Simulator Operator will also maintain a timeline and record of all reports and requests issued by the MCR personnel with response provided by the simulator operator using Attachment 2 J. Shaded items do not require assessment for ILT Evaluations. The CRS may be requested to complete the Shift ED forms and determine the EAL classification at the completion of the scenario.

SEG-2159E Rev 000.doc Page 17 of 45

LIMERICK GENERATING STATION

,=,:, Exelon Generation SIMULATOR EXERCISE GUIDE

1. EVENT-1 DRYWELL UNIT COOLER OPERABILITY TEST Simulator Operator Instructions:

Inform Floor Instructor prior to each event trigger.

Respond to request for assistance as appropriate.

SEG-2159E Rev ODO.doc Page 18 of 45

LIMERICK GENERATING STATION

,=:t' Exelon Generation SIMULATOR EXERCISE GUIDE TIME ASSESSMENT ITEMS AND TASK PERFORMANCE POSITION

1. EVENT-1 DRYWELL UNIT COOLER OPERABILITY TEST Lead Evaluator (or designee) Notes: Crew will perform the ST-6-077-310-1, Drywell Unit Cooler Hydrogen Mixing System Operability Test Run.

Obtain copy of ST-6-077-310-1, Drywell Unit Cooler Hydrogen Mixing System PRO Operability Test Run.

[ST-6-077-310-1 4.3.1] PRO RECORD "AS FOUND" position of all switches/valves listed on Attachment 1.

[ST-6-077-310-1 4.3.3] PRO ALIGN switches for the following at panel 1OC681, to OFF, and ENSURE fans not running.

1A1V212 "A1 Drywell Unit Cooler Fan" (A1)

1A2V212 "A2 Drywell Unit Cooler Fan" (A2)

181V212 "81 Drywell Unit Cooler Fan" (81)

182V212 "82 Drywell Unit Cooler Fan" (82)

1G1V212 "G1 Drywell Unit Cooler Fan" (G1)

1G2V212 "G2 Drywell Unit Cooler Fan" (G2)

1H1V212 "H1 Drywell Unit Cooler Fan" (H1)

1H2V212 "H2 Drywell Unit Cooler Fan" (H2)

[ST-6-077-310-1 4.3.4] PRO START the following fans and RECORD start time:

1A2V212 "A2 Drywell Unit Cooler Fan" (A2)

182V212 "82 Drywell Unit Cooler Fan" (82)

1G2V212 "G2 Drywell Unit Cooler Fan" (G2)

1H2V212 "H2 Drywell Unit Cooler Fan" (H2)

Lead Evaluator (or designee) Notes: The scenario may proceed to the next event ('1 C' RFP trip) when directed by the Lead Evaluator during the Drywell Unit Cooler Hydrogen Mixing System Operability Test Run.

SEG-2159E Rev 000.doc Page 19 of 45

LIMERICK GENERATING STATION

' ' Exelon Generation SIMULATOR EXERCISE GUIDE

2. EVENT-2 '1 C' RFP TRIP Simulator Operator Instructions:

Inform Floor Instructor prior to each event trigger.

Respond to request for assistance as appropriate.

Manually actuate Trigger !.1... when requested by Lead Evaluator, to trip the for the '1C' Rx Feed Water Pump ('1C' RFP).

SEG-2159E Rev 000.doc Page 20 of 45

LIMERICK GENERATING STATION

.. Exelon Generation SIMULATOR EXERCISE GUIDE TIME ASSESSMENT ITEMS AND TASK PERFORMANCE POSITION

2. EVENT-2 '1 C' RFP TRIP Lead Evaluator (or designee) Notes: The crew will recognize vibration on the '1C' RFPT and failure of the discharge check valve to close, when tripped. The crew will execute OT-100 for lowering Rx level and reduce Rx power. The crew is expected to lower power such that total FW flow is less than 13 Mlbm/hr. The crew will manually close the '1 C' RFP discharge valve Reference appropriate ARC: RO/PRO

107 1-2 VIBRATION ALERT Recognize vibration on '1 C' RFP PRO Develop plan to reduce/remove load on '1 C' RFP SRO Reference appropriate ARC: PRO/RO

111/112 B-3, 1A/B RECIRC ASD MINOR FAILURE

101 F-5, 1A, 1B, 1C, RFPT BEARING DRAIN OIL HI TEMP

107 D-5, FWLC TROUBLE

107 H-2, REACTOR HI/LO LEVEL

101 G-2, LEFM TROUBLE

101 1-1, 1C RFPT CONTROLLER TROUBLE

101 1-2, RFPT GOVERNOR TROUBLE

102 C-1, 1C RFPT TRIP

127 1-1, 1 UNIT HWC SYSTEM TROUBLE

109 F-1, F-2 1 MAIN STEAM LINE DIVISION 1 RAD MONITOR HI/DOWNSCALE Recognize and report '1 C' RFP tripped RO

[ARC-MCR-107 H-2] SRO/RO Enter and execute OT-100, Reactor Low Level, IF Reactor water level is low and unexpected or unexplained

[OT-100 (Immediate Operator Action)] RO IF drop in level caused by RFP trip THEN immediately REDUCE Rx power to 85% (use of PB-43-105, Loss of FWP 63%)

[ARC-MCR-102 C-1] RO IF Rx power was reduced as a result of RFPT trip, THEN enter GP-5 Appendix 2, Rx Maneuvering Without Shutdown.

[ARC-MCR-102 C-1, OT-100 Attach #1, OR GP-5 App 2 p.2 Note 6] RO With only two RFPs IN SERVICE Rx power should be limited such that total FW flow does not exceed 13 Mlbm/hr

[ARC-MCR-102 C-1] PRO/RO Dispatch appropriate personnel and/or EO to determine the cause of the RFPT trip.

SEG-2159E Rev 000.doc Page 21 of 45

LIMERICK GENERATING STATION

~***** Exelon Generation SIMULATOR EXERCISE GUIDE

2. EVENT-2 '1C' RFP TRIP Simulator Operator Instructions:

Inform Floor Instructor prior to each event trigger.

Respond to request for assistance as appropriate.

When '1C' RFP trips DELETE VIC104C2, '1C' RFPT vibration.

At time 10 min after FSSV or EO action requested to investigate the '1C' RFP trip:

report: The cause of the '1 C' RFP trip is unknown at this time. Maintenance is on their way to support troubleshooting.

At time 5 min If action requested, from FSSV or EO to check/re-align HWC (HWC currently aligned to the '1A' and '18' RFP),

report: HWC is not aligned to '1C' RFP.

SEG-2159E Rev 000.doc Page 22 of 45

LIMERICK GENERATING STATION

~ Exelon Generation SIMULATOR EXERCISE GUIDE TIME ASSESSMENT ITEMS AND TASK PERFORMANCE POSITION

2. EVENT-2 '1 C' RFP TRIP Identify '1 C' RFP Discharge Check Valve is stuck open (Malfunction) PRO Close the '1 C' RFP Discharge Valve to stop reverse feedwater flow RO/PRO

[GP-5 App #2 Note 11] PRO/RO IF Rx power changes of >15% RTP occur in less than one hour, THEN Chemistry must be informed of Rx power change.

Enter OT-100, Reactor Low Level SRO

[OT-100, 3.1] SRO DIRECT performance of OT-100 Attachment #1 Enter OT-104, Unexpected/Unexplained Positive or Negative Reactivity SRO Addition

[OT-104 3.3] SRO DETERMINE correct Power/Flow Map, determine Core flow and VERIFY plant is operating in authorized region of Power/Flow Map.

[ARC-MCR-107 D-5] RO Respond in accordance with S06.1.H U/1, Responding To Alarms And Selected Events At The Feedwater Level Control System Operator Station.

[ARC-MCR-102 C-1] RO Refer to S06.2.A U/1, Shutdown Reactor Feed Pump from Standby Condition

[ARC-MCR-102 C-1] RO Refer to S06.8.H, Startup, Shutdown and Operation of the Hydrogen Water Chemistry System Dispatch EO to align Hydrogen Water Chemistry to operating RFPs PRO/RO Notify Transmission System Operator (TSO) and Power Team Generation PRO/RO Dispatch of reactor power reduction Lead Evaluator (or designee) Notes: The scenario may proceed to the next event after LEFM has been swapped to Venturi, or as directed by Lead Evaluator.

[ARC-MCR-101- G-2] RO/PRO Perform S06.7.B U/1, Operation of the LEFM System. Swap from LEFM to Venturi Section 4.2 Chemistry notified of power changes TS 3.4.5.c PRO Enter TRM 3.3.7.13, (LEFM) Action a. SRO

a. With the Leading Edge Flow Meter system inoperable, restore the required instrumentation to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . Otherwise, reduce power to < 3458 MWt within the next two hours.

SRO contacts Work Week Manager for support SRO SEG-2159E Rev 000.doc Page 23 of 45

Exelon Gener*ation LIMERICK GENERATING STATION SIMULATOR EXERCISE GUIDE

3. EVENT-3 CRD PUMP TRIP / HCU ACCUMULATOR TROUBLE Simulator Operator Instructions:

Inform Floor Instructor prior to each event trigger.

Respond to request for assistance as appropriate.

Ensure Trigger Jt.1.... automatically actuates when total steam flow is < 13.1 Mlbm/hr to trip the '1A' CRD Pump on clogged suction filter.

At time 6 min after FSSV or EO action requested to bypass CRD suction DELETE malfunction MRC547 and, report: Unit 1 CRD suction filter is bypassed (046-1 F045 is open).

At time 5 min after FSSV or EO action requested to inspect HCU for accumulator trouble report: The accumulator pressure for HCU 18-47 is reading 950 psig.

After '1A' CRD Pump restarted:

DELETE malfunction MRD016C, Accumulator trouble alarm SEG-2159E Rev ODO.doc Page 24 of 45

=* Exelon Generation LIMERICK GENERATING STATION SIMULATOR EXERCISE GUIDE TIME ASSESSMENT ITEMS AND TASK PERFORMANCE POSITION

3. EVENT-3 CRD PUMP TRIP/ HCU ACCUMULATOR TROUBLE Lead Evaluator (or designee) Notes: The running CRD Pump trips as a result of a clogged suction filter, and a CRD accumulator trouble is received. The crew will recognize and respond to the tripped CRD Pump. The crew is expected to execute ON-107, Control Rod Drive System Problems, and take actions required by Tech Spec 3.1.3.5.

Reference appropriate ARC: RO/PRO

108 G-1, 1A/1B CRD WATER PUMP TRIP

108 G-3, 1A/1 B CRD PUMP SUCTION LO PRESS

108 H-3, CRD PUMP SUCTION FILTER HI DP

108 H-4, CRD CHARGING WATER LO PRESS

108 F-1, CRD ACCUMULATOR TROUBLE

107 1-2, VIBRATION ALERT

107 1-3, VIBRATION DANGER Determine '1A' Control Rod Drive Pump tripped on low suction pressure RO

[ARC-MCR-108 G-1] SRO/RO Enter ON-107, Control Rod Drive System Problems.

[ARC-MCR-108 G-3] SRO/RO Refer to ON-107, Control Rod Drive System Problems and verify suction valve line-up per S46.1.A

[ARC-MCR-108 F-1] RO/PRO Dispatch Equipment Operator (EO) to inspect Unit 1 HCU 18-47 for accumulator trouble alarm

[ON-107 Att #2 step 2.a.]

CRS/RO Direct field EO to OPEN 046-1 F045 "Pump Suction Filter Bypass" AND START pump.

[ON-107 Att #2 step 2.b.] RO START 1AP158, "Rod Drive Pump" (PUMP) using HS-046-108A at 10-C603.

Lead Evaluator (or designee) Notes: Procedure S46.1.A, Control Rod Drive Hydraulic System Startup, will be used to verify CRD parameters.

ENSURE Fl-046-1 R605, "Cooling Water Flow" (FL), from 50 to 63 gpm. RO VERIFY PDl-046-1 R603, "Cooling Water Differential Pressure" (Delta PX) RO from 10 to 25 psi.

ENSURE PDl-046-1 R602, "Drive Water Differential Pressure" (Delta PX) from PRO/RO 255 to 265 psi.

SEG-2159E Rev 000.doc Page 25 of 45

LIMERICK GENERATING STATION

,: Exelon Generation SIMULATOR EXERCISE GUIDE

3. EVENT-3 CRD PUMP TRIP/ HCU ACCUMULATOR TROUBLE Simulator Operator Instructions:

Inform Floor Instructor prior to each event trigger.

Respond to request for assistance as appropriate.

At time 8 min after FSSV or EO action requested to bypass CRD suction DELETE malfunction MRC547 and, report: Unit 1 CRD suction filter is bypassed (046-1 F045 is open).

At time 5 min after FSSV or EO action requested to inspect HCU for accumulator trouble report: The accumulator pressure for HCU 18-47 is reading 950 psig.

After '1A' CRD Pump restarted:

DELETE malfunction MRD016C, Accumulator trouble alarm SEG-2159E Rev 000.doc Page 26 of 45

=- Exelon Gener*ation LIMERICK GENERATING STATION SIMULATOR EXERCISE GUIDE TIME ASSESSMENT ITEMS AND TASK PERFORMANCE POSITION

3. EVENT-3 CRD PUMP TRIP/ HCU ACCUMULATOR TROUBLE VERIFY the following parameters of started Rod Drive Pump: RO

108 G-3, 1N1 B CRD PUMP SUCTION LO PRESS, alarm cleared

Normal pump motor running current on N*1803-2 (N*1703-2), "Rod Drive Pump Ammeter," (AM) at *O-C603 VERIFY CRD Accumulator Trouble annunciator clear at 108 F-1, CRD RO Accumulator Trouble Contact Work Week Manager for support SRO Enter Tech Spec 3.1.3.5 SRO IF one CRD scram accumulator is inoperable, THEN PERFORM the following within 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months s:

RESTORE the inoperable accumulator to operable OR DECLARE associated control rod inoperable.

IF restoration is not completed, THEN TAKE action to be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

Lead Evaluator (or designee) Notes: The scenario may proceed to the next event (Recirc Pump Seal failure) after the CRD Pump is re-started and the SRO has determined Tech Spec implications.

SEG-2159E Rev 000.doc Page 27 of 45

LIMERICK GENERATING STATION

.*** Exelon Generation SIMULATOR EXERCISE GUIDE

4. EVENT-4 RECIRC PUMP SEAL FAILURES Simulator Operator Instructions:

Inform Floor Instructor prior to each event trigger.

Respond to request for assistance as appropriate.

Ensure Trigger .!..l._ automatically actuates when CRD Pump restarted to initiate Recirc Pump Seal failures SEG-2159E Rev 000.doc Page 28 of 45

,=!' Exelon Generation LIMERICK GENERATING STATION SIMULATOR EXERCISE GUIDE TIME ASSESSMENT ITEMS AND TASK PERFORMANCE POSITION

4. EVENT-4 RECIRC PUMP SEAL FAILURES Lead Evaluator (or designee) Notes: A sequential failure of both the Reactor Recirc Pump Seals will occur for the '18' Reactor Recirc Pump. The crews will respond to increasing drywell pressure and temperature, including the initial execution of OT-101, Drywell High Pressure, and tripping and isolating the '18' Reactor Recirc Pump.

Reference appropriate ARCs: RO/PRO

112 A-1, 18 RECIRC PUMP SEAL STAGE HI/LO FLOW

112 A-2, 18 RECIRC PUMP SEAL LEAKAGE HI FLOW Recognize failure of '18' Recirc Pump Seal No. 1 RO/PRO Establish monitoring of '18' Recirc Pump Seal No. 2 as Critical Parameter SRO Recognize failure of '18' Recirc Pump Seal No. 2 RO Crew enters OT-101, High Drywell Pressure,on rising Drywell Pressure Crew

[OT-101 3.1] SRO ESTABLISH Drywell pressure as a Critical Parameter with reporting interval Perform OT-101, Att. 1 Recirc Pump Seals (Malfunction) RO/PRO Monitor Drywell Floor Drain Sump 2 min flow average PRO Establish Critical Parameter for Drywell Floor Drain Sump 2 min flow average SRO (10 gpm)

[OT-101 Att#1] PRO Trip '18' Recirc Pump (Critical Task)

[OT-101 Att #1] SRO Enter OT-112, Unexpected/Unexplained Change in Core Flow

[OT-101 Att#1] PRO Close '18' Recirc Pump Discharge Valve (HV-043-1F0318) (Critical Task)

[OT-101 Att #1] PRO Close '18' Recirc Pump Seal Purge Valve (HV-046-1158)

[OT-101 Att #1] PRO Close '18' Recirc Pump Suction Valve (HV-043-1 F0238) (Critical Task)

Enter OT-112, Unexpected/Unexplained Change in Core Flow SRO

[OT-112 3.2] SRO DIRECT RO to monitor for THI indications

[OT-112 3.4] RO If Rx power > 80% then INSERT 8 Control Rods per RMSI

[OT-112 3.5] PRO Perform Attachment #1 Trip of a Recirc Pump SEG-2159E Rev 000.doc Page 29 of 45

LIMERICK GENERATING STATION

,:;* Exelon Generation SIMULATOR EXERCISE GUIDE

4. EVENT-4 RECIRC PUMP SEAL FAILURES Simulator Operator Instructions:

Inform Floor Instructor prior to each event trigger.

Respond to request for assistance as appropriate.

SEG-2159E Rev 000.doc Page 30 of 45

=..-,

Exelon Generation LIMERICK GENERA TING STATION SIMULATOR EXERCISE GUIDE TIME ASSESSMENT ITEMS AND TASK PERFORMANCE POSITION

4. EVENT-4 RECIRC PUMP SEAL FAILURES

[OT-112 3.6] RO Perform OT-112, Attachment #3 to determine position on Power/Flow Map

[OT-112 3.7] RO DEMAND a P-1 edit and determine whether a Thermal Limit violation exists

[OT-112 3.9] SRO ENTER GP-5, Appendix 2, Rx Maneuvering Without Shutdown

[OT-112 3.10] SRO IF trip of a single Recirc Pump has occurred THEN perform requirements for Single Recirc Loop Operation SRO contacts Work Week Manager for support and planned single Recirc SRO loop operation Enter Tech Spec 3.4.1.1 for operable Recirculation Loops SRO Lead Evaluator (or designee) Notes: The scenario may advance to the next event (Steam Leak in Drywell) after the SRO determines actions for loss of a Recirc Pump.

SEG-2159E Rev 000.doc Page 31 of 45

LIMERICK GENERATING STATION

,=:* Exelon Generatior1 SIMULATOR EXERCISE GUIDE

5. EVENT-5 STEAM LEAK IN DRYWELL Simulator Operator Instructions:

Inform Floor Instructor prior to each event trigger.

Respond to request for assistance as appropriate.

Ensure Trigger# _L automatically actuates when total steam flow <8.5 Mlbm/hr to initiate steam leak in the Drywell and Downcomer failure.

SEG-2159E Rev 000.doc Page 32 of 45

,=:* Exelon Generation LIMERICK GENERATING STATION SIMULATOR EXERCISE GUIDE TIME ASSESSMENT ITEMS AND TASK PERFORMANCE POSITION

5. EVENT-5 STEAM LEAK IN DRYWELL Lead Evaluator (or designee) Notes: The following steps, due to the steam leak in the drywell, are directed to shutdown the plant per GP-4, Rapid Plant Shutdown to Hot Shutdown, and stabilize the plant per, T-101, RPV Control, and T-102, Primary Containment Control.

Reference ARCs RO/PRO

107 F-2, DRYWELL HI/LO PRESS

112 C-5, DRYWELL EQUIPMENT DRAIN TANK/FLOOR DRAIN SUMP LEAKAGE HI FLOW

115 B-5, DRYWELL COOLER DRAIN FLOW HIGH Recognize Drywell pressure continues to rise Crew Recognize OT-101 actions are ineffective in reversing rising Drywell pressure SRO trend Enter GP-4, Rapid Plant Shutdown to Hot Shutdown (time permitting) SRO EnterT-101 and T-102 on Hi Drywell Pressure (1.68 psig) SRO

[T-101 RC-4] RO Place Mode Switch in SHUTDOWN SEG-2159E Rev 000.doc Page 33 of 45

=" Exelon Generation LIMERICK GENERATING STATION SIMULATOR EXERCISE GUIDE 6/8. EVENTS 6 -8 RPS FAILS/ DOWNCOMMER BREAK/ DW SPRAY FAILS Simulator Operator Instructions:

Inform Floor Instructor prior to each event trigger.

Respond to request for assistance as appropriate.

SEG-2159E Rev 000.doc Page 34 of 45

~**** Exelon Generation LIMERICK GENERATING STATION SIMULATOR EXERCISE GUIDE TIME ASSESSMENT ITEMS AND TASK PERFORMANCE POSITION 6/8. EVENTS 6-8 RPS FAILS/ DOWNCOMMER BREAK/ DW SPRAY FAILS On the scram, identify that 'A' RPS failed to de-energize and arm and depress all RPS manual pushbuttons RO Enter T-101 with RPV level< +12.5 inches or >4% reactor power with scram condition SRO

[T-101 RC/Q-5]

RO Initiate RRCS (Critical Task)

Recognize ARI inserted Control Rods RO

[T-101 RC-6]

RO Insert SRMs/lRMs

[T-101 RQ-2] PRO Ensure Turbine Tripped and Generator Lockout Direct to depressurize RPV within 100 °F/hour cooldown rate to minimize heat input into Primary Containment PRO

[T-102 PC/P-5]

PRO Before Supp Pool pressure reaches 7.5 psig Spray the Suppression Pool per T-225, Startup and Shutdown of Suppression Pool and Drywell Spray Operation Lead Evaluator (or designee) Notes: The following steps are performed as directed by T-225, Startup and Shutdown of Suppression Pool and Drywell Spray Operation.

[T-225 4.2.3]

PRO IF RHR pump not running THEN start 1A(B)P202 "RHR Pump"

[T-225 4.2.4]

PRO ENSURE the following valves open:

HV-51-1F047A(B), "1A(B) RHR Htx Shell Side Inlet Viv" (INLET)

HV-51-1F003A(B), "1A(B) RHR Htx Shell Side Outlet Viv" (OUTLET)

HV-C-51-1F048A(B), "1A(B) RHR Htx Shell Side Bypass Viv" (HEAT EXCH BYPASS)

[T-225 4.2.5]

PRO OPEN HV-51-1 F024A(B), "1A(B) RHR Pp Full Flow Test Return Viv" (SUPP POOL CLG A(B)) AND OBTAIN flow of 8,000 to 8,500 gpm as indicated on Fl-51-1 R603A(B), FL SEG-2159E Rev 000.doc Page 35 of 45

LIMERICK GENERATING STATION

Exelon Generation SIMULATOR EXERCISE GUIDE 6/8. EVENTS 6-8 RPS FAILS/ DOWNCOMMER BREAK/ DW SPRAY FAILS Simulator Operator Instructions

Inform Floor Instructor prior to each event trigger.

Respond to request for assistance as appropriate.

SEG-2159E Rev 000.doc Page 36 of 45

=*

Exelon Generation LIMERICK GENERATING STATION SIMULATOR EXERCISE GUIDE TIME ASSESSMENT ITEMS AND TASK PERFORMANCE POSITION 6/8. EVENTS 6-8 RPS FAILS/ DOWNCOMMER BREAK/ DW SPRAY FAILS

[T-225 4.2.6] PRO OPEN HV-51-1F027A(B), "1A(B) RHR Supp Pool Spray Line PCIV" (SUPP POOL SPRAY)

[T-225 4.2.8] PRO PLACE RHR Service Water Pump for RHR Heat Exchanger to be used in service per S12.1.A, RHR Service Water System Startup Lead Evaluator (or designee) Notes: The following steps are performed as directed by S 12.1.A, RHR Service Water System Startup.

[S12.1.A 4.1.4 or App1 1.1] PRO OPEN HV-51-*F014A(B), HEAT EXCHANGER INLET

[S12.1.A 4.1.5 or App1 1.2] PRO Throttle OPEN HV-51-*F068A(B) for 18 to 20 seconds

[S12.1.A 4.1.6(7) or App1 1.3] PRO VERIFY Pl-51-*05A-1(B), HX DISCH, indicates system static pressure greater than or equal to 15 psig

[S12.1.A 4.1.8 orApp1 1.4] PRO IF the HI RAD AND/OR HI Pump Discharge pressure trips need to be bypassed AND the required actions of ODCM Part 1 Control 3.1.1 have been met for the INOPERABLE RHRSW Radiation Monitor, THEN PLACE HSS-12-002A(B), PUMP TRIP BYPASS, in "BYPASS"

[S 12.1.A 4.2.1 or App1 1.6] PRO IF 'A'/'B' Loop pump (OA(C)-P506) (OB(D)-P506) is to be placed in service, THEN ENSURE OA(B)-V543 OR OC(D)-V543, Spray Pond Pump Room Fans, in "RUN" at OOC681.

[S12.1.A 4.2.2 orApp1 1.7] PRO START OA(B,C,D)P506, RHRSW PUMP

[S12.1.A 4.2.3 or App1 1.8] PRO THROTTLE HV-51-*F068A(B) to the maximum obtainable position without exceeding 11,000 gpm on Fl-51-*R602A(B) while maintaining pump disch pressure (Pl-12-001 A-1 (B)) between 75 psig to 85 psig

[T-225 4.2.9] PRO CLOSE HV-C-51-1F048A(B), "1A(B) RHR Htx Shell Side Bypass Viv" (HEAT EXCH BYPASS)

SEG-2159E Rev 000.doc Page 37 of 45

LIMERICK GENERATING STATION

~, Exelon Generation SIMULATOR EXERCISE GUIDE 6/8. EVENTS 6-8 RPS FAILS/ DOWNCOMMER BREAK/ DW SPRAY FAILS Simulator Operator Instructions:

Inform Floor Instructor prior to each event trigger.

Respond to request for assistance as appropriate.

DELETE 168 override for '18' Drywell Spray, if crew attempts to use '1A' Drywell Spray.

OR DELETE 16A override for '1A' Drywell Spray, if crew attempts to use '1 B' Drywell Spray.

At time 10 minutes Load all SE-10 Floor Actions with time delays scenario, after Crew requests SE-10 Shunt Trip Resets for DIV 1, 3 and 4 loads and report: The status of individual resets as requested or when all resets are timed out or report: All SE-10 Floor Actions are complete when all SE-10 timers have expired.

SEG-2159E Rev 000.doc Page 38 of 45

..-- LIMERICK GENERATING STATION

' ' Exelon Generation SIMULATOR EXERCISE GUIDE TIME ASSESSMENT ITEMS AND TASK PERFORMANCE POSITION 6/8. EVENTS 6-8 RPS FAILS/ DOWNCOMMER BREAK/ DW SPRAY FAILS

[T-225 4.2.10] PRO IF more spray flow is required, THEN REDUCE flow through Full Flow Test line by throttling closed HV-51-1 F024A(B), "1A(B) RHR Pp Full Flow Test Return Viv" (SUPP POOL CLG A(B))

Establish Suppression Pool pressure as Critical Parameter SRO Recognize Suppression Pool pressure rising at faster rate and determine PRO possible downcommer break Lead Evaluator (or designee) Notes: The following steps, to spray the Drywell, are directed from T-102, and performed from T-225. The crew will re-align RHR from Suppression Pool Spray to Drywell Spray.

WHEN Suppression Pool pressure exceeds 7.5 psig AND on safe side of SRO Drywell Spray Initiation Limit curve PC/P-2 OR Before DW temp reaches 340°F, THEN spray the Drywell per T-225 (Critical Task)

[T-102 PC/P-10] PRO Spray the Drywell per T-225, Startup and Shutdown of Suppression Pool and Drywell Spray Operation (Critical Task)

[T-225 4.6.6] PRO/RO REMOVE Drywell cooling Fans from service

[T-225 4. 6. 7] PRO/RO IF LOCA signal not present- Initiate LOCA signal Recognize failure of either HV-051-1F016A or 1F016B, RHR Loop A or B PRO Drywell Spray Valves to OPEN on demand (Malfunction)

OPEN alternate Drywell Spray Valve HV-051-1 F016A or 1F016B, in PRO designated loop Recognize LOCA permissive when RPV pressure drops below 455 psig PRO Enter SE-10, LOCA SRO Perform SE-10 Immediate Actions PRO

[SE-10 3.1] PRO PLACE the following to "CLOSE"

52-20224/CS, "0*24 Safeguard L.C. 0*24-G-D MCC Bkr" (SAFEGUARDS B), on *BC661.

52-20124/CS, "0*14 Safeguard LC. 0*14-G-D MCC Bkr" (SAFEGUARDS A), on *AC661 PLACE to "RESET": PRO

43-22322/CS, "Div. Ill Non SFGD Instr. Panel" (INST AC 201 CONTROL PNL), on *CC661

43-22422/CS, "Div. IV Non SFGD Instr. Panel" (INST AC 202 CONTROL PNL), on *DC661.

SEG-2159E Rev 000.doc Page 39 of 45

LIMERICK GENERATING STATION

.=:*** Exelon Generation SIMULATOR EXERCISE GUIDE 6/8. EVENTS 6 -8 RPS FAILS/ DOWNCOMMER BREAK/ DW SPRAY FAILS Simulator Operator Instructions:

Inform Floor Instructor prior to each event trigger.

Respond to request for assistance as appropriate.

At time 10 minutes Load all SE-10 Floor Actions with time delays scenario, after Crew requests SE-10 Shunt Trip Resets and report: The status of individual resets as requested or when all resets are timed out or report: All SE-10 Floor Actions are complete when all SE-10 timers have expired.

SEG-2159E Rev 000.doc Page 40 of 45

LIMERICK GENERATING STATION

~** Exelon Generation SIMULATOR EXERCISE GUIDE TIME ASSESSMENT ITEMS AND TASK PERFORMANCE POSITION 6/8. EVENTS 6-8 RPS FAILS/ DOWNCOMMER BREAK/ DW SPRAY FAILS Dispatch Equipment Operator to perform SE-10-1 field actions PRO Recognize SAFE side of the Pressure Suppression Pressure (PSP) curve SRO (Curve PC/P-3) cannot be maintained WHEN (or BEFORE) UNSAFE side of the Pressure Suppression Pressure SRO (PSP) curve (Curve PC/P-3) cannot be maintained, enter T-112 Lead Evaluator (or designee) Notes: The following step is directed from T-112, Emergency Slowdown.

[T-112 EB-11] CRS/PRO DIRECT Open all 5 ADS valves using (Critical Task)

Restore RPV level between +12.5 inches and +54 inches Crew Lead Evaluator (or designee) Notes: The scenario may be terminated when an Emergency Depressurization has been performed, Drywell Spray is in service, control rods inserted and reactor level is restored.

SEG-2159E Rev 000.doc Page 41 of 45

LIMERICK GENERATING STATION

,=**** Exelon Generation SIMULATOR EXERCISE GUIDE Attachment 1 Simulator Operator Response Times

Response

Procedure Performance Time (Minutes)

T-209 Injection from the Standby Liquid Control Storage Tank with the RCIC 45 System T-212 Bypassing SQUIB Valves for SLC Injection 19 T-215 De-energization of Scram Solenoids 7 T-216 Manual Isolation and Vent of Scram Air Header 7 T-217 RPS/ARI Reset and Backup Method of Draining Scram Discharge 17 Volume T-219 Maximizing CRD Cooling Water Header Flow during ATWS Conditions 23 T-221 MSIV Isolation Bypass Procedure 11 T-225 Startup and Shutdown of Suppression Pool and Drywell Spray 8

Operations T-240 Maximizing CRD flow after Shutdown During Emergency Conditions 8 T-245 RPV Injection from RHR SID Cooling 12 T-248 Injection from SLC Test Tank to RPV 15 T-251 Establish a HPCI Injection flow Path VIA Feedwater Only 6 T-270 Terminate and Prevent Injection into the RPV 7 T-290 Instrumentation Available for T-103 SAMP-2 5 S46.7.A Control Rod Drive Hydraulic System Operation Following Reactor (4.2.1) Scram (Securing CRD flow to the Reactor - Close 46-1 F060, CRD 7 Water Pressure Control Station Inlet Valve)

SE-10-1 Breaker Reset Following LOCA (Also reset ARMs, RHRSW Rad Resets and Monitor and RDCS) 10 Floor action SEG-2159E Rev 000.doc Page 42 of 45

LIMERICK GENERATING STATION

: Exelon Generation SIMULATOR EXERCISE GUIDE Attachment 2 Communications Log CREW: _ __

DATE: _ _ __ LSEG:

START TIME: - - - - - STOP T I M E : - - - -

SM: RO: WCS: - - - - - -

CRS: - - - - - PRO: - - - - - FSSV:

PERSON CALL PERSON TIME BEING COMMUNICATION / REQUEST BACK CALLING CALLED TIME SEG-2159E Rev 000.doc Page 43 of 45

=

Exelon Generation LIMERICK GENERATING STATION SIMULATOR EXERCISE GUIDE THIS PAGE INTENTIONALLY LEFT BLANK SEG-2159E Rev 000.doc Page 44 of45

LIMERICK GENERATING STATION

,::, Exelon Generation SIMULATOR EXERCISE GUIDE XI. CREW PREBRIEF INSTRUCTIONS

Unit 1 is at 100% power

Unit 2 is at 100% power Specific Plant Conditions are as Follows:

None Inoperable/Out of Service Equipment and Estimated Time of Return (ETR):

None Restrictions on Plant Operations:

None Planned Evolutions:

Perform Drywell Unit Cooler Hydrogen Mixing System Operability Test Documents Provided:

ST-6-077-310-1, Drywell Unit Cooler Hydrogen Mixing System Operability Test Run.

SEG-2159E Rev ODO.doc Page 45 of 45

-,cc Exelon Generation LIMERICK GENERATING STATION SIMULATOR EVALUATION GUIDE CODE NO: SEG-3005E REV NO: 001 AUTHOR: T. BYERS APPROXIMATE 60 minutes RUN TIME:

TYPE: SIMULATOR EVALUATION EFFECTIVE DATE: 12/01/17 GUIDE PROGRAM: LICENSED OPERATOR TRAINING COURSE: LICENSED OPERATOR (REQUALIFICATION/INITIAL) TRAINING TITLE: Simulator Evaluation Guide for Individual and Crew Performance Prepared By: T. A. By_ers/S/ Date: 11/20/17 Training Instructor - Signature Reviewed By: N/A for NRC ILT Date: N/A LORT Lead Instructor - Signature Reviewed By: N/A Date: N/A EP (as appropriate) - Signature Reviewed By: N/A Date: N/A RE (as appropriate) - Signature Approval: Bill Martin/SI Date: 11/30/17 OPS Manager - Signature Approved For Use: Dan Semeter/S/ Date: 12/01/17 Training Manager - Signature SEG-3005E Rev001.docx SRRS: 3D.126 Page 1 of 39

~ LIMERICK GENERATING STATION

,=,*. Exelon Generation SIMULATOR EVALUATION GUIDE Appendix D Scenario Outline Form ES-D-1 Facility: Limerick 1 & 2 Scenario No.: SEG-3005E Rev _1_ Op-Test No.:_1_.

Examiners: Operators:

Initial Conditions:

Unit 1 is at 5.0 % power. Unit 2 is at 100% power.

Turnover:

D12 D/G is running 12arallel to 201 Safeguard Bus following maintenance. D12 D/G has been running loaded for 11/2 hours of the reguired 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 12er S92.2.N ste12 4.6.4.

Planned Evolutions :

When the 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months loaded run is com12lete, secure D12 D/G 12er S92.2.N beginning with ste12 4.6.4.

Critical Tasks:

1. Manually Insert Control Rods

2. Direct performance of T-290 to personnel outside the control room

3. Perform Emergency Slowdown per T-112 Event Malfunction Event Event No. Number Type* Description C-PRO 1 MESW600B 'OB' ESW Pump trip TS-SRO MCU002A MCU002B C-PRO 2 RWCU Isolation failure on differential flow MCU193 TS-SRO HS44-1F004 C-RO 3 MED280A Trip of 1AY160, RPS/UPS Distribution Panel C-PRO 4 MRD016G C-RO Failure of 3 (three) Control Rods to scram.

MFW251B 5 C-RO SIU Level Control Valve and HV-06-108A fail closed HS06-108A 6 MHP445 M-ALL T-103 Steam Leak in HPCI MHP446A 7 C-PRO HPCI Steam Isolation Valves fail to close MHP446B MFW245B '1 B' Reactor Feedpump Loss of HP steam supply 8 C-PRO MRC460 RCIC injection valve fails to open Automatically (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor SEG-3005E Rev001.docx SRRS: 3D.126 Page 2 of 39

- -- Exelon Generation LIMERICK GENERATING STATION SIMULATOR EVALUATION GUIDE QUANTITATIVE ATTRIBUTES A. ILT Target Quantitative Attributes ACTUAL (Per Scenario; See ES-301 Section D.5.d) NUMBER

1. Malfunctions after EOP entry (1-2) 2

2. Abnormal events (2-4) 4

3. Major transients (1-2) 1

4. EOPs entered/requiring substantive actions (1-2) 2

5. EOP contingencies requiring substantive actions (0-2) 1

6. Critical tasks (2-3) 3 Review TQ-AA-151 attachment 5 and ES-301-5 for individual position requirements for scenario and scenario set SEG-3005E Rev001.docx SRRS: 3D.126 Page 3 of 39

~ Exelon Generation LIMERICK GENERATING STATION SIMULATOR EVALUATION GUIDE II. PURPOSE: Systematically evaluate individual and team performance to identify areas for improvement. Critical Tasks and Assessment Items from this evaluation guide are to be used to assess crew and individual performance and as input into a 4.0 Crew Critique Process.

Ill. SIMULATOR EVALUATION GUIDE OBJECTIVES:

A. The following evaluation objectives apply to the Crew (C), Shift Manager (SM), Control Room Supervisor (S), Unit Reactor Operator/ Plant Reactor Operator (R), or Incident Assessor/ Shift Technical Advisor (A) as indicated in the following categories.

1. The general condition for each of the evaluation objectives will be "Given the plant conditions and sequence of events in the Simulator Evaluation Guide (SEG)".

2. The general acceptable evaluation objective criteria for each of the evaluation objectives will be "To perform effectively as an individual and contribute to successful crew performance in accordance with appropriate reference plant procedures and Operations Expectations, Fundamentals and Strategies".

3. Specific UNSAT evaluation objective criteria will be consistent with TQ-AA-155, Conduct of Simulator Training and Evaluation with applicable forms and job aids.

4. During performance of this Simulator Evaluation Guide, the individuals and crew should satisfactorily demonstrate the following overall procedure and plant control objectives:

Direct and perform actions per OT-112, Unexpected/Unexplained Change in Core Flow

Direct and perform actions per OT-200, Operations Transient Hard Cards

Direct and perform actions per GP-8.5, Isolation Bypass of Crucial Systems

Direct and perform actions per E-1AY160, Loss of 1A RPS UPS Power

Direct and perform actions per T-250, Remote Manual Primary Containment Isolations

Direct and perform actions per T-290, Instrumentation Available for T-103/SAMPS-2

Direct and perform actions per T-101, RPV Control

Direct and perform actions per T-103, Secondary Containment Control

Direct and perform actions per T-112, Emergency Slowdown SEG-3005E Rev001.docx SRRS: 3D.126 Page 4 of 39

~

.-- LIMERICK GENERATING STATION Exelon Generation SIMULATOR EVALUATION GUIDE IV. RECORD OF TEMPORARY CHANGES:

A. Approval of Pen & Ink Changes will be by the ILT or LORT Lead Instructor with OTM concurrence B. All Pen & Ink Changes are to be tracked in ILT or LOR Program Action Tracking for Next Revision C. All Pen & Ink Changes shall be in accordance with TQ-M-223 Temp Date of Purpose of Change LORT Action Revision Change# Change Approval Tracking Date V. REVISION HISTORY:

A. If a Revision affects a Task Performance from VISION Terminal Performance Objectives then the revision must also be made in the VISION database.

B. The description of the Revision should adequately indicate how the training content of the Revision has changed.

C. The description of the Revision should also include previous format reference and number and previous template used (e.g for conversion of LSES to SEG format).

Revision # Date of Description of Revision and Affect on Training Content Number Revision RevOOO This is a new SEG 10/08/16 Rev001 This SEG was reformatted to incorporate revisions to Critical Tasks, and 8/20/17 format changes in SEG development.

Date of Revision - refers to date revision was released for approval SEG-3005E Rev001.docx SRRS: 3D.126 Page 5 of 39

LIMERICK GENERATING STATION Exelon Generation SIMULATOR EVALUATION GUIDE VI. SCENARIO EVENT AND EVALUATION

SUMMARY

Events One: At shift turnover, the crew will be directed to Shutdown D12 EOG following an additional 30 minutes run time. However, before the crew can secure the diesel, the 'OB' ESW Pump trips removing cooling water from the running D12 EOG.

Evaluation: The crew is expected to identify the loss of cooling water to the operating DIG and start the alternate 'OD' ESW Pump, or perform an emergency shutdown of the EOG. The SRO will identify the Tech Spec requirements 3.7.1.2 / 3.8.1 for the loss of the 'OB' ESW Pump.

Event Two: After the 'OB' ESW Pump trips, and 'OD' ESW Pump is started or D12 DIG secured, and Tech Spec referenced, a RWCU heat exchanger tube leak into RECW will cause a differential (delta) flow annunciator alarm. The RWCU delta flow is designed to isolate the RWCU system after a time delay.

Complicating the event will be the failure of HV-44-1 F004 (RWCU Outboard Isolation PCIV) to close from the handswitch.

Evaluation: Evaluate the crew's ability to diagnose that RWCU failed to isolate on delta flow and RWCU water is flowing into the RECW system. The crew will identify the Hi delta flow and take action to manually isolate the RWCU system including closing HV-44-1 F001 (RWCU Inboard Isolation PCIV) and reference Tech Specs 3.6.3 for INOP PCIV and TRM 4.4.4.c for loss of conductivity monitoring.

Event Three After the RWCU system is isolated and Tech Specs referenced, a loss of the Four & Five: '1A' RPS UPS power supply, panel 1A-Y160 will occur. The power supply loss will result in a loss of RECW, DWCW, and PCIG, along with a Reactor HVAC isolation. A loss of 1A-Y160 at a power level when the Main Turbine is tripped will result in both Recirculation Pumps tripping. With no Recirc Pumps in operation the operators will scram the plant as directed by OT-112, Unexpected/ Unexplained Change in Core Flow and enter T-100, Scram / Scram Recovery. Complicating the scram, three rods will fail to insert. Complicating RPV Level Control, during the scram, a failure of the Reactor S/U Level Controller will occur and the '1A' RFP discharge valve will fail to open.

Evaluation: Evaluate the crew's ability to diagnose the power loss and execute E-1AY160, identify both Recirc Pumps have tripped, and scram the reactor, enter T-100, and bypass and restore the RECW, DWCW and PCIG systems. The RO will identify the 3 rod ATWS and insert the rods manually and identify the failed SIU level controller while controlling reactor level, and maintain RPV level using the '1 B' RFP.

SEG-3005E Rev001.docx SRRS: 3D.126 Page 6 of 39

.-- LIMERICK GENERATING STATION

=:( Exelon Generation SIMULATOR EVALUATION GUIDE SCENARIO EVENT AND EVALUATION

SUMMARY

cont'd Event Six Once the reactor is shutdown and T-100 steps are being executed, a steam And Seven: leak will occur in the HPCI Room. Both the Inboard and Outboard HPCI steam isolation valves will fail to isolate, and the steam leak will propagate into a second area.

Evaluation: Evaluate the crew's response during execution of T-103, Secondary Containment Control, due to the elevated HPCI room temperatures. Due to the unisolable HPCI steam leak, and once a second area reaches MSO temperatures, a T-112, Emergency Slowdown, will be performed.

Event Eight: While operating the '1 B' RFP for injection, the Hi Pressure Steam supply to the RFPT will fail and the '1 B' RFP will stop injecting. When the crew transitions to RCIC, the RCIC injection valve will fail to open automatically.

The Operator will be able to manually open the injection valve from the MCR.

Evaluation: To evaluate the Operator's ability to recognize the failure and control RPV level with the RCIC system following manually opening the RCIC Injection Valve.

Termination This scenario may be terminated after two rooms have temperatures above Criteria: MSO and when 5 SRVs opened to depressurize the reactor and reactor level is restored between +12.5" to +54".

SEG-3005E Rev001.docx SRRS: 3D.126 Page 7 of 39

,,,,.._ LIMERICK GENERATING STATION

~"' Exelon Generation SIMULATOR EVALUATION GUIDE VII. REFERENCES A. Training Procedures

1. TQ-LG-150, Limerick Operator Training Program

2. TQ-AA-151, ILT Certification and NRC Examination Development and Administration

3. TQ-AA-155, Conduct of Simulator Training and Evaluation B. Annunciator Response Cards (ARC)

1. 002 F-5, REAC ENCL STM FLOODING DAMPER PNL 10C234 TRBL

2. 004 B-1, B DRYWELL CHILLER TRIP/ FAILED TO START

3. 004 B-3, REACTOR ENCLOSURE LOW dP/LOSS OF POWER/INOP

4. 004 E-1, A REACTOR ENCL. ISOLATION SIGNAL INITIATED

5. 004 E-3, A REFUELING FLOOR ISOLATION SIGNAL INITIATED

6. 004 A-3, B REAC ENCL HVAC PNL 1BC208 TROUBLE

7. 005 B-3, DIESEL FIRE PUMP RUNNING

8. 005 A-2, MOTOR DRIVEN FIRE PUMP RUNNING

9. 006 F-2U, REAC I EL 177 HPCI PUMP

10. 011 D-1, DIV 2 ESW SYSTEM OUT OF SERVICE

11. 011 D-3, B ESW PUMP MOTOR OVERCURRENT

12. 107 H-1, REACTOR WATER BELOW LEVEL 3 TRIP

13. 107 G-5, DIV 2 STEAM LEAK DET SYS HI TEMP/ TROUBLE

14. 107 1-5, DIV 4 STEAM LEAK DET SYS HI TEMP/ TROUBLE

15. 108 A-1, NEUTRON MONITORING SYSTEM TRIP

16. 108 B-1/B-2, AUTO SCRAM CHANNEL 'A1'/'A2'

17. 109 B-1, 1 REAC ENCL COOLING WATER HI RADIATION

18. 110 E-3, RPS SYSTEM A OUT OF SERVICE

19. 110 E-3, RPS SYSTEM A OUT OF SERVICE

20. 111 D-5, NSSSS ISOL SYS OUT OF SERVICE (INBOARD)

21. 111/112 A-5, 1A/B RECIRC PUMP MOTOR WINDING COOLING WATER LO FLOW

22. 111/112 B-1, 1A/B RECIRC ASD TRIPPED

23. 111/112 E-2, 1A/B RECIRC ASD 13KV BKR TRIP

24. 112 1-3, RWCU HI DIFF FLOW ISLN TIMER INITIATED

25. 117 A-1, HPCI OUT OF SERVICE

26. 118 H-5, REAC ENCLCOOLING WATER HEAD TANK HI/LO LEVEL

27. 120 F-5, 1A RPS & UPS DIST PNL TROUBLE

28. 127 H-4, REAC ENCL FLR DRAIN SUMP PUMPHI-HI WATER LEVEL C. System Procedures (S)

1. S92.2.N, Shutdown Of The Diesel Generators

2. S87.1.A App. 1, Start Up of Standby/Tripped Drywell Chiller HARD CARD

3. S76.8.B App. 1, Initiation of U1 RE Secondary Containment 'B' solation Signal and Restoration of PCIG HARD CARD SEG-3005E Rev001.docx SRRS: 3D.126 Page 8 of 39

~

Exelon Generation LIMERICK GENERATING STATION SIMULATOR EVALUATION GUIDE REFERENCES cont'd

4. S46.7.A, Control Rod Drive Hydraulic System Operation Following Reactor Scram

5. S06.2.C APP. 1, Manually Placing A RFP to Standby During a Plant Event

6. S11.1.A, ESW System Startup D. General Procedures (GP)

1. GP-2, Normal Plant Startup E. Off Normal Procedures (ON)

F. Operating Transient Procedures (OT)

1. OT-101, High Drywell Pressure

2. OT-112, Unexpected/Unexplained Change in Core Flow

3. OT-200, Operations Transient Hardcards G. Event Procedures (E)

1. E-1AY160, Loss Of 1A RPS UPS Power H. Special Event Procedures (SE)

1. SE-8 App. 1, Fire Hard Card I. Surveillance Test and Routine Test Procedures (ST and RT)

J. Technical Specifications and TRM (TS)

1. 3.7.1.2

2. 3.3.1

3. 3.6.3

4. 3.8.1.1

5. 3.3.2

6. 3.4.3.1 K. Transient Response Implementation Procedures (T-100 series)/SAMPs

1. T-100, Scram I Scram Recovery

2. T-101, RPV Control

3. T-103, Secondary Containment Control

4. T-112, Emergency Slowdown L. TRIP 200 Series Procedures

1. T-250, Remote Manual Primary Containment Isolations

2. T-290, Instrumentation Available for T-103/SAMPS-2 M. EP-AA-1008, Limerick, Radiological Emergency Plan Annex for Limerick Generating Station N. Administrative Procedures

1. OP-AA Procedures

a. OP-AA-1, Conduct of Operations

b. OP-AA-20, Conduct of Operations Process Description

c. OP-AA-101-111-1003, Operations Department Standards and Expectations

d. OP-AA-101-113, Operations Fundamentals

e. OP-AA-101-113-1006, 4.0 Crew Critique Guidelines

f. OP-AA-106-101-1006, Operational Decision Making Process SEG-3005E Rev001.docx SRRS: 30.126 Page 9 of 39

-- LIMERICK GENERATING STATION

--- Exelon Generation SIMULATOR EVALUATION GUIDE REFERENCES cont'd

2. OP-LG Procedures

a. OP-LG-101-111-1000, Licensed Operator Duties

b. OP-LG-102-106, Operator Response Time Program at Limerick

c. OP-LG-103-102-1000, Human Performance Continuing Good Practices

d. OP-LG-103-102-1002, Strategies for Successful Transient Mitigation

e. OP-LG-108-101-1001, Simple Quick Acts/ Transient Acts

0. Current Shift Night Orders Forced Outage Plan P. INPO Significant Operating Experience Reports (SOER), Significant Event Reports (SER) and INPO Event Reports (IER)

1. SOER 10-02, Engaged Thinking Organizations

2. INPO 15-004, Operator Fundamentals SEG-3005E Rev001. docx SRRS: 3D.126 Page 10 of 39

__. Exelon Generation LIMERICK GENERATING STATION SIMULATOR EVALUATION GUIDE VIII. PREBRIEF INSTRUCTIONS Unit 2 is in OPCON 1 at 100% power Unit 1 is in OPCON 1 at 5.0% power Specific Plant Conditions are as Follows:

Reactor Startup in progress per GP-2 complete to step 3.5.1.3

Two Condensate Pumps in service

RFPs maintaining RPV level

Main Turbine BPVs controlling Rx pressure

HPCI and RCIC are operable

Offgas Recombiner is in service

Main Turbine Chest warmed

The QOM has been contacted and Start-Up Review is in progress in preparation for going to RUN Inoperable/Out of Service Equipment and Estimated Time of Return (ETR):

None Restrictions on Plant Operations:

None Planned Evolutions:

Make preparations to enter OPCON 1 (Planned OPCON change is 4 hrs. from now)

D12 DIG is running parallel to 201 Safeguard Bus following 201-D12 Breaker compartment maintenance to repair a damaged cell switch linkage arm.

D12 DIG has been running loaded for 1 hr 30 mins and is ready, in 30 minutes, to be secured per S92.2.N step 4.6.4. An EO is standing by in the D12 DIG Bay.

Documents Provided:

S92.2.N, Shutdown of the Diesel Generators

GP-2 complete to step 3.5.1.3

Control Rod Move Sheet

S73.1.A, Normal Operation Of The Reactor Manual Control System SEG-3005E Rev001.docx SRRS: 3D.126 Page 11 of 39

,--, LIMERICK GENERATING STATION

~* Exelon Generation SIMULATOR EVALUATION GUIDE IX. DIRECTIONS FOR EVALUATION PREPARATION A. INITIAL PREPARATION

., ITEM / MALFUNCTION / REMOTE FUNCTIONS Complete TQ-AA-155, Operator Training Programs Attachment 02, Evaluated Scenario Administration Checklist.

Complete TQ-LG-201-0113, Limerick Training Department Simulator Examination Security Actions Checklist B. SIMULATOR SETUP ITEM / MALFUNCTION / REMOTE FUNCTIONS Complete Limerick Simulator Pre-Evaluation Checklist Reset Simulator to the Pre-loaded Cycle IC developed for this SEG OR Reset the simulator to IC-21 AND Load scenario file SEG3005E Rev001.scn

Verify that all Malfunctions, Remotes, Overrides, Annunciators and Triggers are properly loaded OR

Manually enter the Malfunctions, Remotes, Overrides, Annunciators and Triggers per the Scenario Generator Screen Shots:

Simulator Operator (Driver) perform the following:

Momentarily place simulator in RUN

Acknowledge and clear all spurious alarms

Place the simulator back into FREEZE

Perform the following:

1. Provide a marked-up copy of S92.2.N, Shutdown of the Diesel Generators

2. Provide a marked-up copy of GP-2, to step 3.5.1.3

3. Provide a marked-up copy of the control rod pull sheet

4. Provide S73.1.A, Normal Operation Of The Reactor Manual Control System

5. Change the following Service Water return valves to green

11-1013 and 11-2013 SEG-3005E Rev001.docx SRRS: 3D.126 Page 12 of 39

~

--, LIMERICK GENERATING STATION

~ Exelon Generation. SIMULATOR EVALUATION GUIDE C. MALFUNCTION/REMOTE/OVERRIDE/ANNUNCIATORS FUNCTION TIME TABLE r Timer,,.._ Pending NOTE: For the MRC460 to work correctly it requires the malfunction to be active in the IC with the Simulator in run. Once active, then assign trigger 6 with the 1 second deactivation time. Once snapped in the IC using the above method, the simulator resets work normally and the above steps are no longer needed.

r Timer Pause Clear List I Pending SEG-3005E Rev001.docx SRRS: 3D.126 Page 13 of 39

..-,, LIMERICK GENERATING STATION

~ Exelon Generation. SIMULATOR EVALUATION GUIDE r Timer Pause DeleteA/1 I Pending D. EVENT TRIGGERS ASSIGNMENT

1. Timers should be used on event triggers where possible for time validation

2. Timing of event triggers may be altered by the Lead Evaluator (or designee)

3. Verify triggers are actuated automatically as designed or manually initiate the trigger when the initiating action has occurred.

4. Inform Lead Evaluator (or designee) of expected plant response prior to actuation of each trigger.

5. Trigger #1 is manually initiated at Lead Evaluator (or designee) direction after the crew assumes responsibility for operation.

TRIGGER/ MALFUNCTION /

@ TIME EVENT DESCRIPTION 1 Manual Initiates 'OB' ESW Pump Trip 2 Manual Initiates RWCU differential flow 3 Manual Initiates loss of 1A-Y160 RMS to SHUTDOWN 4 Auto / ZRPS 1SON Initiates SIU Level Control Valve fails closed Auto / FWZM604B 1B FW Flow>= 0.3 Mlbm/hr 5

>= 1404 Initiates 1B RFPT Vibrations and Trip HV-049-1 F013 Handswitch to Open removes 6 Auto I ZRCS 113C malfunction allowing HV-049-1 F013 to be manually opened 7 Manual Initiates HPCI Stm Line Break Inside Pump Rm SEG-3005E Rev001.docx SRRS: 3D.126 Page 14 of 39

~ Exelon Generation LIMERICK GENERATING STATION SIMULATOR EVALUATION GUIDE

,~-------------i~n

~ --~'~"~:'..t' ~:':

favorites Iriggers Trigger tt Trigger Text Operators:

1 Arithmetic:

2

Multiplication J

/ Division 4 ZRPS15DN + Addition 5 F'w'ZM6048 >= 1404 Subtraction 6 ZRCS113C Relational:

7

> Greater than 8

>= Greater than 9 or equal 10 < Less than 11 <= Less than or 12 equal 13 == Equal to 14 != Not equal to 15 Logical:

16

&& And 17 II Or 18

! Not 19 Other:

Open Paren I Close Paren 3

I_Irigger_Now.J ,!;;lear CJearAII accept SEG-3005E Rev001. docx SRRS: 3D.126 Page 15 of 39

,--, LIMERICK GENERATING STATION

~' Exelon Generation SIMULATOR EVALUATION GUIDE E. EQUIPMENT REPORTS AND LEAD EVALUATOR (OR DESIGNEE) OPERATIONS

1. Scripted Activity Reports should be followed with adherence to Operations Communication standards of performance.

2. The T-200 procedure reference book should be used for familiarity of reports to aid in operator prompting and expected communications.

3. The Lead Evaluator (or designee) should be informed if any event is not reported as scripted due to lack of Operator request.

4. The Standard Equipment Operator Response Times are per Attachment 1

5. A record of communications from the MCR and to the MCR will be maintained by the Simulator Operator using Attachment 2.

6. The OCOEE Simulator Operator Station P&IDs, Floor Plans and Panels should be used by the Simulator Operator as reference information when making reports to the MCR for plant parameters which are not driven by a communications script. Examples include: ARMs, Blowout Panel status, Reactor Building Area Temperatures and Pressures, RMMS, Turbine Enclosure parameters etc.

SEG-3005E Rev001. docx SRRS: 3D.126 Page 16 of 39

.....- LIMERICK GENERATING STATION

..* Exelon Generation SIMULATOR EVALUATION GUIDE X. CREW CRITICAL TASKS A. Critical Tasks are based on the current Crew Critical Task List revision, NU REG 1021 Rev. 11 and TQ-AA-150 requirements.

1. T-103.1 Direct the performance of T-290.

KIA 295032 EA2.01 3.8/3.8 Standard: Direct the performance of T-290 to operations personnel located outside the control room.

SAT/UNSAT

2. T-103.3 Perform emergency blowdown per T-112.

KIA 295032 EK3.01 3.5/3.8 KIA 295033 EK3.01 3.3/3.5 KIA 295036 EK3.01 2.6/2.8 Standard: After it is determined that two areas listed on the T-103 Maximum Safe Operating (MSO) Values table have exceeded MSO values and a primary system is still discharging into Secondary Containment, then enter T-112 and perform an emergency blowdown by opening five Safety Relief Valves (SRVs).

SAT/UNSAT

3. T-101.6 Insert control rods manually.

KIA 295037 EA1.07 3.9/4.0 KIA 295037 EA1.08 3.6/3.6 KIA 295015 AA2.02 4.1/4.2 KIA 295015 AA1.05 2.5/2.8*

Standard: If the reactor has not been determined to be shut down under all conditions without boron, then insert all control rods to or beyond 02 with the Reactor Manual Control System (RMCS}, bypassing the Rod Worth Minimizer (RWM) when it prevents rod movement.

SAT/UNSAT SEG-3005E Rev001.docx SRRS: 3D.126 Page 17 of 39

-*~fJr-:

LIMERICK GENERATING STATION

~ Exelon Generation SIMULATOR EVALUATION GUIDE XI. ASSESSMENT OF CREW PERFORMANCE DURING CONDUCT OF THE DYNAMIC SIMULATOR EVALUATIONS:

A. Conduct the Simulator Evaluation Session per TQ-AA-155, Conduct of Simulator Training and Evaluation, Attachment 02, Evaluated Scenario Administration Checklist B. Assessment of Crew and Individual performance shall be consistent with OP-AA-20, Conduct of Operations Process Description C. Where possible record the time and position responsible for performance of each task or assessment item D. Items not performed as expected SHALL be discussed in the post performance crew critique E. During the performance of the evaluation, the Simulator Evaluators shall MAINTAIN notes of observations and information consistent with the timeline F. Assessment items with the Cv symbol indicate a time critical standard for performance G. Assessment items with the \t::,,- symbol indicate a Probabilistic Risk Assessment (PRA) association with the task H. The Simulator Operator will respond with scripted or proceduralized responses when requested by the MCR operators with Procedure completion times requested per Attachment 1 I. The Simulator Operator will also maintain a timeline and record of all reports and requests issued by the MCR personnel with response provided by the simulator operator using Attachment 2 J. Shaded items do not require assessment for ILT Evaluations. The CRS may be requested to complete the Shift ED forms and determine the EAL classification at the completion of the scenario.

SEG-3005E Rev001.docx SRRS: 3D.126 Page 18 of 39

__. LIMERICK GENERATING STATION

~ ~. Exelon Generation SIMULATOR EVALUATION GUIDE This Page Intentionally Blank SEG-3005E Rev001.docx SRRS: 3D.126 Page 19 of 39

...-, LIMERICK GENERATING STATION

~,c Exelon Generation SIMULATOR EVALUATION GUIDE

1. EVENT-1 'OB' ESW PUMP TRIP (Malfunction)

Simulator Operator Instructions:

Inform Floor Instructor prior to each event trigger Manually actuate Trigger #_1_ when requested by Lead Evaluator, to initiate 'B' ESW Pump trip.

SEG-3005E Rev001. docx SRRS: 3D.126 Page 20 of 39

Exelon Generation LIMERICK GENERATING STATION SIMULATOR EVALUATION GUIDE TIME ASSESSMENT ITEMS AND TASK PERFORMANCE POSITION

1. EVENT-1 'OB' ESW PUMP TRIP (Malfunction)

EVALUATORS NOTE: As operator is evaluating reducing load on D12 EOG Trigger #_1_ will be activated to trip the 'OB' ESW Pump. The operator is expected to identify the tripped ESW Pump and start the standby 'OD' ESW Pump, or secure the EOG.

Reference ARC: PRO

011 D-1, DIV 2 ESW SYSTEM OUT OF SERVICE

011 D-3, B ESW PUMP MOTOR OVERCURRENT

[ARC MCR 011 D-3] PRO/RO Recognize 'OB' ESW Pump tripped DIRECT start of 'OD' ESW Pump or perform an emergency shutdown of D12 SRO D/G (Malfunction)

Reference S 11.1.A, ESW System Startup PRO

'OD' ESW Pump, if started, verify running (N/A if ESW Pump not started, and PRO D12 D/G shutdown option chosen)

Dispatch the FSSV or an EO to investigate tripped 'OB' ESW Pump PRO Enter Tech Spec 3.7.1.2 action a.1 for the trip of 'OB' ESW SRO SEG-3005E Rev001.docx SRRS: 3D.126 Page 21 of 39

..._.. LIMERICK GENERATING STATION

.' Exelon Generation SIMULATOR EVALUATION GUIDE

2. EVENT-2 RWCU FLOW DIFFERENTIAL ISOLATION FAILURE (Abnormal)

Simulator Operator Instructions:

Inform Floor Instructor prior to each event trigger.

Manually activate Trigger !...!... when directed by Lead Evaluator, to initiate RWCU High Differential Flow At time 6 min after FSSV or EO action requested to investigate RWCU system flow to RECW report: RECW tank level indicates high. If asked, Level is 80" and steady.

SEG-3005E Rev001.docx SRRS: 3D.126 Page 22 of 39

~ LIMERICK GENERATING STATION

~/ Exelon Generation SIMULATOR EVALUATION GUIDE TIME ASSESSMENT ITEMS AND TASK PERFORMANCE POSITION

2. EVENT-2 RWCU FLOW DIFFERENTIAL ISOLATION FAILURE (Abnormal)

Lead Evaluator (or designee) Notes: The Reactor Enclosure Cooling Water alarms follow the RWCU Delta flow alarm, and shortly thereafter the RECW Hi radiation alarm annunciates. If the operator immediately secures the RWCU system the Hi Rad and Head Tank level will not alarm, and the operators will not be able to immediately identify the cause of the delta flow. In either case RWCU should be isolated by manual isolation.

Reference appropriate ARCs:

109 B-1, 1 REAC ENCL COOLING WATER HI RADIATION PRO/RO

112 1-3, RWCU HI DIFF FLOW ISLN TIMER INITIATED

118 H-5, REAC ENCL COOLING WATER HEAD TANK HI/LO LEVEL

[ARC MCR 112 1-3) PRO IF timer does not clear after 30 seconds, THEN manually close the HV 1F004 Identify that HV-44-1 F004 failed to respond to the Handswitch operation PRO

[OT-200 Appendix 7) SRO Direct isolation of the RWCU system by closing the Inboard Isolation PCIV (HV-44-1 F001)

Isolate RWCU system by closing the Inboard Isolation PCIV (HV-44-1 F001) PRO Lead Evaluator (or designee) Notes: If the operator does not immediately secure the RWCU system, and the Hi Rad and Head Tank level alarm, the operators will not be able to identify the cause of the delta flow.

[ARC MCR 109 B-1) RO Verify HI radiation on RISH-13-1K606, and on recorder RR-13-1R604

[ARC MCR 109 B-1) RO Notify chemistry to obtain grab sample

[ARC MCR 112 1-3) PRO IF leaking into RECW, THEN transfer into other set of Non-Regen HTXCH

[ARC MCR 118 H-5) PRO Direct EO to verify RECW Head Tank level locally

[ARC MCR 118 H-5] PRO IF in conjunction with RECW High Radiation alarm, THEN refer to S13.0.B, RECW High Radiation If isolation initiated, verify isolation Group Ill using PMS PRO Enter Tech Specs 3.6.3 action a for HV-44-1 F004 INOP SRO SEG-3005E Rev001.docx SRRS: 30.126 Page 23 of 39

.-.- Exelon Generation LIMERICK GENERATING STATION SIMULATOR EVALUATION GUIDE 3/4/5. EVENTS 3 - 5 LOSS OF 1AY160 / 3 Rod ATWS / S/U LEVEL CONTROLLER FAILS (Abnormal)

Simulator Operator Instructions:

Inform Floor Instructor prior to each event trigger.

Manually actuate TriggerJLL when requested by Lead Evaluator, to trip of 1A-Y160 panel.

At time 4 min after FSSV or EO action requested to investigate trip of 1A-Y160, report: There is an acrid smell in the Inverter Room, but there is no fire.

At time 3 min after FSSV or EO action requested to investigate 1AY160 feed breaker:

report: The normal DC INPUT (from 250 VDC MCC "1 DA") inverter supply breaker is tripped At time 4 min after FSSV or EO action requested to investigate 1AY160 alternate feed breaker report: The primary alternate AC INPUT (from 480 VAC MCC "144D-C-F") is tripped open.

SEG-3005E Rev001.docx SRRS: 3D.126 Page 24 of 39

.-- LIMERICK GENERATING STATION

=:'* Exelon Generation SIMULATOR EVALUATION GUIDE TIME ASSESSMENT ITEMS AND TASK PERFORMANCE POSITION 3/4/5. EVENTS 3-5 LOSS OF 1AY160 / 3 ROD ATWS / S/U LEVEL CONTROLLER FAILS (Abnormal)

EVALUATORS NOTE: '1A' RPS/UPS electrical panel trips with the following indications to the crew. Reactor half scram, DWCW trip, RECW Isolation, RWCU Isolation, PCIG Isolation and RX HVAC trip with SBGT Fan start, and with the Main Turbine not reset both Recirc Pumps trip. The crew must restore these systems and take actions for both Recirc Pumps tripped.

Reference appropriate ARCs: PRO/RO

108 A-1, NEUTRON MONITORING SYSTEM TRIP

108 B-1/8-2, AUTO SCRAM CHANNEL 'A1'/'A2'

110 E-3, RPS SYSTEM A OUT OF SERVICE

111/112 A-5, 1A/B RECIRC PUMP MOTOR WINDING COOLING WATER LO FLOW

111/112 B-1, 1A/B RECIRC ASD TRIPPED

111 /112 E-2, 1A/8 RECIRC ASD 13KV BKR TRIP

120 F-5, 1A RPS & UPS DIST PNL TROUBLE

004 B-1, B DRYWELL CHILLER TRIP/ FAILED TO START

004 B-3, REACTOR ENCLOSURE LOW dP/LOSS OF POWER/INOP

004 E-3, A REFUELING FLOOR ISOLATION SIGNAL INITIATED

004 E-1, A REACTOR ENCL. ISOLATION SIGNAL INITIATED

[ARC MCR 108 B-1 /B-2] PRO/RO Recognize loss of 1AY160 and reactor 'A' half scram

[ARC MCR 120 F-5] SRO Enter E-1AY160, Loss of '1A' RPS UPS Power.

[ARC MCR 111/112 B-1] RO Recognize '1A' and '1 B' Recirc Pumps tripped Enter, OT-104, Unexpected/Unexplained Positive or Negative Reactivity SRO Addition

[ARC MCR 111/112 B-1] SRO Enter OT-112, Unexpected/Unexplained Change in Core Flow

[OT-1123.1] RO Manually Scram and enter T-100, Scram/Scram Recovery

[T-100 S-5] RO Ensure SRMs and IRMs inserted Recognize 3 control rods failed to insert on the scram RO EVALUATORS NOTE: On the scram 3 control rods will fail to insert. The RO will recognize the A TWS (3 control rods not inserted) and manually drive-in the rods. The control rods will be inserted as directed by T-100, Scram/Scram Recovery. If an entry condition for T-101, RPV Control, is required, T-100 will be exited.

SEG-3005E Rev001.docx SRRS: 3D.126 Page 25 of 39

--- Exelon Generation LIMERICK GENERATING STATION SIMULATOR EVALUATION GUIDE 3/4/5. EVENTS 3 - 5 LOSS OF 1AY160 / 3 ROD ATWS / S/U LEVEL CONTROLLER FAILS (Abnormal)

Simulator Operator Instructions:

Inform Floor Instructor prior to each event trigger.

At time 7 min when S46. 7 .A , step 4.2.1, requested for Control Rod Drive Hydraulic System Operation Following Reactor Scram (Securing CRD flow to the Reactor INSERT RCR009 to close 46-1 F034, CRD Water Pressure Control Station Inlet Valve.

SEG-3005E Rev001.docx SRRS: 3D.126 Page 26 of 39

LIMERICK GENERATING STATION

~ Exelon Generation. SIMULATOR EVALUATION GUIDE TIME ASSESSMENT ITEMS AND TASK PERFORMANCE POSITION 3/4/5. EVENTS 3-5 LOSS OF 1AY160 / 3 ROD ATWS / S/U LEVEL CONTROLLER FAILS (Abnormal)

[T-100 RC/Q-3] RO Insert rods manually with the RWM Bypassed (Critical Task)

[T-100 RC/L-2] RO Maintain RPV level between +12.5" and +54" using Cond/FW Recognize failure of LV-C-06-138A to align for post-scram level control RO Take manual control of RFP '1A' attempt to open HV-06-108A discharge RO valve Recognize HV-06-108A discharge valve fails to open RO Manually open HV-06-108B and maintain RPV level between +12.5" and +54" RO using '1 B' RFP

[T-100 RC/P-2] RO Stabilize RPV press below 1096 psig using Turb BPVs Enter ON-113, Loss Of RECW SRO EVALUATORS NOTE: E-1AY160 directs the operator to enter ON-113, Loss of RECW, and restore RECW to the Recirc Pump seal and motor oil coolers. This step is performed assuming the Recirc Pumps are in operation. With the Recirc Pumps tripped the operator may place a lower priority in restoration of RECW to the Recirc Pumps

[E-1AY160 2.2] (Malfunction) PRO Bypass and restore RECW flow

PLACE HS-13-112 to "BYPASS"

PLACE HS-13-106 to "OPEN"

PLACE HS-13-107 to "OPEN" Enter OT-101, Drywell High Pressure due to loss of DW Cooling SRO

[E-1AY160 2.3] (Malfunction) PRO Bypass and restore DWCW flow

PLACE HS-87-116 to "BYPASS"

PLACE HSS-87-121A to OPEN

PLACE HSS-87-121A to OPEN

[E-1AY160 2.3.3] PRO IF Drywell Chiller trips, REFER to S87.1.A Appendix 1 Hard Card and start Drywell Chilled Water System.

[S87.1.A Appendix 1] PRO PERFORM the following:

PLACE 1A/BK111 Drywell Chiller to STOP PLACE 1A/B161 Drywell Chiller Water Pump to OFF SEG-3005E Rev001.docx SRRS: 30.126 Page 27 of 39

~

.._,. LIMERICK GENERATING STATION Exelon Generation SIMULATOR EVALUATION GUIDE 3/4/5. EVENTS 3 - 5 LOSS OF 1AY160 / 3 ROD ATWS / S/U LEVEL CONTROLLER FAILS (Abnormal)

Simulator Operator Instructions:

Inform Floor Instructor prior to each event trigger.

SEG-3005E Rev001.docx SRRS: 3D.126 Page 28 of 39

.A. .11111\j.f LIMERICK GENERATING STATION

__.. Exelon Generation SIMULATOR EVALUATION GUIDE TIME ASSESSMENT ITEMS AND TASK PERFORMANCE POSITION 3/4/5. EVENTS 3-5 LOSS OF 1AY160 / 3 ROD ATWS / S/U LEVEL CONTROLLER FAILS (Abnormal)

[S87.1.A Appendix 1] PRO PLACE 1A/BK111 Drywell Chiller to START ENSURE 1A/B161 Drywell Chiller Water Pump to RUN

[E-1AY160 2.4] (Malfunction) PRO Bypass and restore PCIG

PLACE HS-59-129A to "CLOSE"

PLACE HS-59-191A to "BYPASS"

PLACE HS-59-129A to "AUTO"

PLACE HS-59-101 to "OPEN" Note Tech Spec entry times for PCIV's at time isolation is bypassed SRO/PRO Reference Technical Specification LCOs: SRO

3.6.3 action a

[ARC-MCR-004 E-3] PRO Verify Refueling Floor Secondary Containment isolates, and Primary Containment groups VIA AND VIB isolate.

Verify, by checking DP, Secondary Containment integrity with 'A' Standby PRO Gas Fan running SEG-3005E Rev001.docx SRRS: 3D.126 Page 29 of 39

LIMERICK GENERATING STATION Exelon Generation SIMULATOR EVALUATION GUIDE 6-7. EVENTS 6-7 HPCI ROOM STEAM LEAK/ HPCI FAILS TO ISOLATE Simulator Operator Instructions:

Inform Floor Instructor prior to each event trigger.

Ensure Trigger#~ automatically actuates when RMS taken to SHUTDOWN to initiate steam leak in HPCI room.

When Fire Brigade Leader is dispatched, report: This is Fire Brigade Leader ( ) responding to the fire alarm code 1-1-3.

At time 6 min after FSSV or EO action requested to investigate panel 1BC208 trouble, report: HPCI Pump Room temperature is ( ) and both unit coolers are running.

(NOTE: 150 °F is top of scale)

At time 5 min after FSSV or EO action requested T-290 numbers, provide initial readings report {via phone): HPCI Pump Room (Room 109) temperature is ( ) and the trend is

( ). All other temperatures and radiation levels are below MNO.

Fire Brigade Leader at time 6 min report: The Unit 1 HPCI Pump Room door is hot to the touch and the sound of steam can be heard in the HPCI Pump Room. I am unable to enter the HPCI Room at this time to investigate for indications of a fire. I am exiting the Reactor Enclosure.

At time 5 min When requested to close HPCI Isolation valves from MCC, report: RP is restricting entry into the Unit 1 Reactor Enclosure until they can fully assess the conditions.

DRIVER NOTE:

HPCI Pump Room Maximum Normal Operating (MNO) temperature value is 120 °F.

HPCI Pump Room (Room 109) temperature at Maximum Safe Operating (MSO) value (176 °F) must be reported per T-290. In addition, Room 309 temperature at MNO (120 °F) and MSO (145 °F) must be reported per T-290.

IF the crew decides to rapidly depressurize the RPV to the Main Condenser, THEN when RPV pressure reaches 400 psig, report Room 309 temperature is "145 °F UP SLOW" if a value above this temperature has not yet been reported.

SEG-3005E Rev001.docx SRRS: 3D.126 Page 30 of 39

-cc

.-., Exelon Generation LIMERICK GENERATING STATION SIMULATOR EVALUATION GUIDE TIME ASSESSMENT ITEMS AND TASK PERFORMANCE POSITION 6-7. EVENTS 6-7 HPCI ROOM STEAM LEAK/ HPCI FAILS TO ISOLATE Reference ARC PRO/RO

006 F-2U, "REAC I EL 177 HPCI PUMP"

107 G-5, DIV 2 STEAM LEAK DET SYS HI TEMP / TROUBLE

107 1-5, DIV 4 STEAM LEAK DET SYS HI TEMP / TROUBLE

004 A-3, B REAC ENCL HVAC PNL 1BC208 TROUBLE

117 A-1, HPCI OUT OF SERVICE

[ARC-MCR-006 F-2U] SRO Enter SE-8, and Dispatch Fire Brigade Leader (FBL)

[SE-8 App. 1 2.0] PRO Record time of fire/alarm code

[SE-8 App. 1 3.0] PRO Activate Fire Brigade Leader

[SE-8 App. 1 4.0] PRO PERFORM evacuation announcement

[ARC-MCR-004 A-3] PRO/RO Dispatch Operator to investigate Panel 1BC208 Trouble alarm to determine room cooler trouble

[ARC-MCR-117 A-1] PRO/RO Notify Fire Brigade Leader (FBL) of potential for steam leak in HPCI room

[ARC MCR 006 F-2U] PRO/RO Notify FBL of Fire Procedure F-R-109

[ARC MCR 107 G-5/1-5] SRO Enter T-103 (Division 2 and 4 Steam Leak Detection alarms)

[T-103 SCC-3] SRO Direct use of PAMS, Fuel Zone, and EQ PMS only

[T-1 03 SCC-6] SRO Direct performance of T-290, Instrumentation Available for T-103/SAMP-2, to operations personnel located outside the control room. (Critical Task)

[ARC-MCR-117 A-1] PRO Recognize indications of a HPCI steam leak Dispatch Floor Personnel to close HPCI Steam Supply Valves from the MCC PRO per OT-200 Attachment 9

[T-1 03 SCC/T-5] SRO Direct isolation of HPCI System per T-250 after report of exceeding MNO SEG-3005E Rev001.docx SRRS: 3D.126 Page 31 of 39

--- Exelon Generation LIMERICK GENERATING STATION SIMULATOR EVALUATION GUIDE 6-7. EVENTS 6-7 HPCI ROOM STEAM LEAK/ HPCI FAILS TO ISOLATE Simulator Operator Instructions:

Inform Floor Instructor prior to each event trigger.

When T-290 Update(s) requested, report (using phone): temperatures with trends as indicated on OCOEE T-103 display.

If Radwaste Operator is requested for status of Reactor Enclosure Floor Drain Sump Pumps report: Both Unit 1 Reactor Enclosure Floor Drain Sump Pumps are running.

At time when T-290 monitored parameter reaches the Maximum Normal Operating (MNO) or Maximum Safe Operating (MSO) value report via phone: Appropriate temperature/radiation level with trend (UP FAST or UP SLOW} to MCR CRS SEG-3005E Rev001.docx SRRS: 30.126 Page 32 of 39

--- Exelon Generation LIMERICK GENERATING STATION SIMULATOR EVALUATION GUIDE TIME ASSESSMENT ITEMS AND TASK PERFORMANCE POSITION 6-7. EVENTS 6-7 HPCI ROOM STEAM LEAK/ HPCI FAILS TO ISOLATE Direct manual isolation of HPCI Outboard Isolation Valve (HV-55-1 F003) SRO Place HV-55-1 F003 key switch in CLOSE PRO Recognize/report failure of HV-55-1 F003 to close PRO Direct manual isolation of HPCI Inboard Isolation Valve (HV-55-1 F002) SRO Place HV-55-1 F002 key switch in CLOSE PRO Recognize/report failure of HV-55-1 F002 to close PRO Recognize failure of HPCI to isolate with active steam leak in progress Crew Establish T-290 Temperatures as Critical Parameters SRO Re-enter T-103 (1 BC208 Trouble Alarm and Report) SRO

[T-103 SCC/T-8] SRO WHEN determined a pri system is discharging into RE (Recognize HPCI temperature cannot be maintained below MSO)

[T-1 03 SCC/T-9] SRO Enter T-101 and execute concurrently

[T101 RC/P-19] SRO/RO Reduce Rx pressure to 600 psi to reduce the driving force - the HPCI leak Reference ARCs PRO

005 A-2, MOTOR DRIVEN FIRE PUMP RUNNING

005 8-3, DIESEL FIRE PUMP RUNNING

127 H-4, REAC ENCL FLR DRAIN SUMP PUMPHI-HI WATER LEVEL

002 F-5, REAC ENCL STM FLOODING DAMPER PNL 10C234 TRBL Re-enter T-103 (Reactor Enclosure Floor Drain Sump Alarm and Report) SRO Recognize second area, Room 309, reported above MNO temperature value SRO Track Room 309 temperature toward MSO temperature value SRO

[T-101 RC/P-6] SRO Consider rapidly depressurizing the RPV using Main Turbine Bypass Valves prior to exceeding MSO value in two Reactor Enclosure areas

[T-103 SCC/T-10 and SCC/T-11] SRO When MSO temp is still exceeded in 2 OR more area and pri system still discharging - Enter T-112, Emergency Slowdown

\t>, [T-112 EB-12] PRO Open 5 ADS SRVs (Critical Task)

SEG-3005E Rev001.docx SRRS: 30.126 Page 33 of 39

-- LIMERICK GENERATING STATION

--- Exelon Generation SIMULATOR EVALUATION GUIDE 8-9. EVENTS 8 - 9 '1 B' RFP HP STEAM FAILS/ RCIC FLOW CONTROLLER FAILS Simulator Operator Instructions:

Inform Floor Instructor prior to each event trigger.

Ensure Trigger ..,!Lautomatically actuated when '1 B' RFP FW flow> 0.3 Mlbm/hr At time 7 min when S46. 7 .A , step 4.2.1, requested for Control Rod Drive Hydraulic System Operation Following Reactor Scram (Securing CRD flow to the Reactor - Insert RCR009 to close 46-1 F034, CRD Water Pressure Control Station Inlet Valve)

If crew chooses to reduce RPV Pressure prior to attempting to inject with RCIC, With lead evaluator permission at RPV Pressure of 700 psig, Trip all Condensate Pumps.

SEG-3005E Rev001.docx SRRS: 3D.126 Page 34 of 39

~

Exelon Generation LIMERICK GENERATING STATION SIMULATOR EVALUATION GUIDE TIME ASSESSMENT ITEMS AND TASK PERFORMANCE POSITION 8-9. EVENTS 8-9 '18' RFP HP STEAM FAILS/ RCIC FLOW CONTROLLER FAILS Lead Evaluator (or designee) Notes: In STARTUP reactor level is maintained by the SIU level controller through the '1A' RFP, however the S/U level controller has failed to open and the '1A' RFP discharge valve will not open. The RO will attempt to use the '1 B' RFP to maintain reactor level. The operator will find the HP steam to the B RFP is unavailable, and the '1 B' RFP is unable to maintain RPV level. The RO will attempt to maintain reactor level using the RCIC system.

RO identifies the '1 B' RFPT is not maintaining RPV level, indicating no flow or PRO pump speed.

RO identifies loss of HP steam supply to the '1 B' RFP (Malfunction) RO Transfer RPV level control to RCIC SRO/PRO Recognize RCIC Discharge Valve (HV-049-1F013) fails to open automatically PRO Manually open RCIC Discharge Valve PRO

[T-100 RC/L-3] RO Restore RPV water level between +12.5" and +54" using available systems, including low pressure ECCS systems If RPV level drops below +12.5" enter T-101 RC/L SRO Lead Evaluator (or designee) Notes: The scenario may be terminated when an Emergency Slowdown has been completed and RPV level has been stabilized in band.

SEG-3005E Rev001.docx SRRS: 3D.126 Page 35 of 39

~ Exelon Generation LIMERICK GENERATING STATION SIMULATOR EVALUATION GUIDE TIME ASSESSMENT ITEMS AND TASK PERFORMANCE POSITION Rough log maintained by the crew with the following items noted: Crew

'OB' ESW Pump trip

RWCU Delta Flow isolation

E-1AY160 entry

Reactor Scram (OT-112)

HPCI fire alarm

HPCI Pump Room Steam Supply Line Break

Startup Level Controller (LCV-06-138) Failure To Open

Room 309 Temperature Rise

'B' RFP trip

RCIC Discharge Valve Malfunction

T-112 Entry SEG-3005E Rev001. docx SRRS: 3D.126 Page 36 of 39

Attachment 1 Simulator Operator Response Times

Response

Procedure Performance Time (Minutes)

T-209 Injection from the Standby Liquid Control Storage Tank with the RCIC 45 System T-212 Bypassing SQUIB Valves for SLC Injection 19 T-215 De-energization of Scram Solenoids 7 T-216 Manual Isolation and Vent of Scram Air Header 7 T-217 RPS/ARI Reset and Backup Method of Draining Scram Discharge 17 Volume T-219 Maximizing CRD Cooling Water Header Flow during A TWS Conditions 23 T-221 MSIV Isolation Bypass Procedure 11 T-225 Startup and Shutdown of Suppression Pool and Drywell Spray 8

Operations T-240 Maximizing CRD flow after Shutdown During Emergency Conditions 8 T-245 RPV Injection from RHR SID Cooling 12 T-248 Injection from SLC Test Tank to RPV 15 T-251 Establish a HPCI Injection flow Path VIA Feedwater Only 6 T-270 Terminate and Prevent Injection into the RPV 7 T-290 Instrumentation Available for T-103 SAMP-2 5 S46.7.A Control Rod Drive Hydraulic System Operation Following Reactor (4.2.1) Scram (Securing CRD flow to the Reactor - Close 46-1 F060, CRD 7 Water Pressure Control Station Inlet Valve)

Page 37 of 39

Attachment 2 Communications Log CREW:

DATE: _ _ __ SEG:

START TIME: STOPTIME:

SM: RO: WCS:

CRS: PRO: FSSV: _ _ _ __

PERSON CALL PERSON TIME BEING COMMUNICATION / REQUEST BACK CALLING CALLED TIME Page 38 of 39

XII. CREW PREBRIEF INSTRUCTIONS Unit 2 is in OPCON 1 at 100% power Unit 1 is in OPCON 1 at 5.0% power Specific Plant Conditions are as Follows:

Reactor Startup in progress per GP-2 complete to step 3.5.1.3

Two Condensate Pumps in service

RFPs maintaining RPV level

Main Turbine BPVs controlling Rx pressure

HPCI and RCIC are operable

Offgas Recombiner is in service

Main Turbine Chest warmed

The QOM has been contacted and Start-Up Review is in progress in preparation for going to RUN Inoperable/Out of Service Equipment and Estimated Time of Return (ETR):

None Restrictions on Plant Operations:

None Planned Evolutions:

Make preparations to enter OPCON 1 (Planned OPCON change is 4 hrs. from now)

D12 DIG is running parallel to 201 Safeguard Bus following 201-D12 Breaker compartment maintenance to repair a damaged cell switch linkage arm.

D12 DIG has been running loaded for 1 hr 30 mins and is ready, in 30 minutes, to be secured per S92.2.N step 4.6.4. An EO is standing by in the D12 DIG Bay.

Documents Provided:

S92.2.N, Shutdown of the Diesel Generators

GP-2 complete to step 3.5.1.3

Control Rod Move Sheet

S73.1.A, Normal Operation Of The Reactor Manual Control System Page 39 of 39

LIMERICK GENERATING STATION

". Exelon Generation SIMULATOR EXERCISE GUIDE CODE NO: SEG-4158E REV NO: 000 AUTHOR: T.BYERS APPROXIMATE 60 minutes RUN TIME:

TYPE: SIMULATOR EVALUATION EFFECTIVE DATE: 12/01/17 GUIDE PROGRAM: LICENSED OPERATOR TRAINING COURSE: LICENSED OPERATOR (REQUALIFICATION/INITIAL) TRAINING TITLE: Simulator Evaluation Guide for Individual and Crew Performance Prepared By: T. A. Byers/SI Date: 11/20/17 Training Instructor - Signature Reviewed By: N/A for NRC ILT Date: N/A LORT Lead Instructor - Signature Reviewed By: N/A Date: N/A EP (as appropriate) - Signature Reviewed By: N/A Date: N/A RE (as appropriate) - Signature Approval: Bill Martin/SI Date: 11/30/17 OPS Manager - Signature Approved For Use: Dan Semeter/S/ Date: 12/01/17 Training Manager - Signature SEG-41 SBE RevOOO. doc Page 1 of 49

,,: Exelon Generation LIMERICK GENERATING STATION SIMULATOR EXERCISE GUIDE Appendix D Scenario Outline Form ES-D-1 Facility: Limerick 1 & 2 Scenario No.: SEG- 4158E Rev _o_ Op-Test No.: __.

Examiners: Operators:

Initial Conditions:

Unit 1 Reactor Power is 100%

Unit 2 Reactor Power is 100%

Turnover:

Maintain 100% power Critical Tasks:

1. Inhibit Automatic ADS

2. Perform actions to maintain/restore RPV water level above Top of Active Fuel (TAF)

3. Spray the Drywell Event Malfunction Event Event No. Number Type* Description Ann. 118-15 C-PRO 1 Loss of Isa-Phase Bus Cooling C-RO R-RO 2

MHP450 C-PRO Inadvertent HPCI Start Up TS-SRO MNS161B I-PRO Inadvertent NSSSS ISOLATION 3

MNS001 TS-SRO Failure of PCIG to Isolate MCN604B 4 Trip of '1 B' Condensate Pump with Failure of the '1A' MRR507A C-RO Reactor Recirc Pump to automatically run back.

5 MED262A M-ALL Loss of the 11 BUS / Loss of All Condensate & Feed MRR440A MHP447B LOCA, HPCI Aux Oil Pump Failure, RCIC Overspeed 6 C-PRO MRC457B trip.

MRC466 MDG420D D14 Bus fails to auto swap on Dead Bus Transfer, and 7 MED014 C-PRO failure of D14 EOG to auto start.

MED015H

(N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor SEG-4158E RevOOO.doc Page 2 of 49

LIMERICK GENERATING STATION

"' Exelon Generation SIMULATOR EXERCISE GUIDE A. ILT Target Quantitative Attributes ACTUAL (Per Scenario; See ES-301Section D.5.d) NUMBER

1. Malfunctions after EOP entry (1-2) 2

2. Abnormal events (2-4) 4

3. Major transients (1-2) 1

4. EOPs entered/requiring substantive actions (1-2) 1

5. EOP contingencies requiring substantive actions (0-2) 1

6. Critical tasks (2-3) 3 Review TQ-AA-151 attachment 5 and ES-301-5 for individual position requirements for scenario and scenario set SEG-4158E RevOOO.doc Page 3 of 49

--- Exelon Ger1eratior1 LIMERICK GENERATING STATION SIMULATOR EXERCISE GUIDE II. PURPOSE: Systematically evaluate individual and team performance to identify areas for improvement. Critical Tasks and Assessment Items from this evaluation guide are to be used to assess crew and individual performance and as input into a 4.0 Crew Critique Process.

Ill. SIMULATOR EVALUATION GUIDE OBJECTIVES:

A. The following evaluation objectives apply to the Crew (C), Shift Manager (SM), Control Room Supervisor (S), Unit Reactor Operator/ Plant Reactor Operator (R), or Incident Assessor I Shift Technical Advisor (A) as indicated in the following categories.

1. The general condition for each of the evaluation objectives will be "Given the plant conditions and sequence of events in the Simulator Evaluation Guide (SEG)".

2. The general acceptable evaluation objective criteria for each of the evaluation objectives will be "To perform effectively as an individual and contribute to successful crew performance in accordance with appropriate reference plant procedures and Operations Expectations, Fundamentals and Strategies".

3. Specific UNSAT evaluation objective criteria will be consistent with TQ-AA-155, Conduct of Simulator Training and Evaluation with applicable forms and job aids.

4. During performance of this Simulator Evaluation Guide, the individuals and crew should satisfactorily demonstrate the following overall procedure and plant control objectives:

Direct and perform actions per ON-101, Loss of Isa-phase Bus Cooling

Direct and perform actions per GP-5, App. 2, Planned Rx Maneuvering Without Shutdown

Direct and perform actions per GP-8.5, Isolation Bypass of Crucial Systems

Direct and perform actions per OT-110, Reactor High Level

Direct and perform actions per OT-101, High Drywell Pressure

Direct and perform actions per OT-104, Unexpected/Unexplained Positive or Negative Reactivity Addition

Direct and perform actions per T-101, RPV Control

Direct and perform actions per T-111, RPV Level Control

Direct and perform actions per T-102, Primary Containment Control

Direct and perform actions per T-112, Emergency Slowdown SEG-4158E RevOOO. doc Page 4 of 49

--***---- Exelon Generation LIMERICK GENERATING STATION SIMULATOR EXERCISE GUIDE IV. RECORD OF TEMPORARY CHANGES:

A. Approval of Pen & Ink Changes will be by the ILTor LORT Lead Instructor with OTM concurrence B. All Pen & Ink Changes are to be tracked in ILTor LOR Program Action Tracking for Next Revision C. All Pen & Ink Changes shall be in accordance with TQ-M-223 Temp Date of Purpose of Change LORT Action Revision Change# Change Approval Tracking Date V. REVISION HISTORY:

A. If a Revision affects a Task Performance from VISION Terminal Performance Objectives then the revision must also be made in the VISION database.

B. The description of the Revision should adequately indicate how the training content of the Revision has changed.

C. The description of the Revision should also include previous format reference and number and previous template used (e.g for conversion of LSTS to LLORSEG format).

Revision # Date of Description of Revision and Affect on Training Content Number Revision RevOOO NewSEG 8/15/17

Date of Revision - refers to date revision was released for approval SEG-4158E RevOOO. doc Page 5 of 49

---,* Exelon Generation LIMERICK GENERATING STATION SIMULATOR EXERCISE GUIDE SCENARIO EVENT AND EVALUATION

SUMMARY

Events One: After the crew assumes responsibility, the operating lso-phase Bus Cooling Fan will trip with a failure of the standby fan to auto start. This will require the crew to enter and execute ON-101 for Loss of lso-phase Bus Cooling.

Evaluation: Evaluate the crew's response to the loss of lso-phase Bus Cooling and their execution of the ON procedure. The crew should minimize VARS on the main generator and lower power as necessary to control lso-phase bus temperature.

When power is lowered below 90%, lso-phase bus cooling will be restored.

Event Two: After the lso-phase Bus cooling is restored, the HPCI system will experience an inadvertent startup. The HPCI injection will result in an initial rise in RPV water level and a rise in Reactor Power.

Evaluation: Evaluate the crew's response to the HPCI malfunction including actions taken per OT-104, and OT-110. The crew should reduce power and secure the injection from HPCI as well as reference Tech Specs due HPCI lnoperability.

Event Three: When the plant has been stabilized and HPCI isolated per OT-104, an inadvertent NSSSS Group VIIA and VIIIA isolation will occur. This will cause a loss of RECW cooling to the Recirc Pump Seals, a Loss of Drywell Cooling and a loss of Instrument Gas (PCIG). Complicating this event, the PCIG outboard suction valve will fail to isolate Evaluation: Evaluate the crew's ability to recognize equipment affected, enter OT-101 for loss of DWCW and ON-113 for Loss of RECW. The crew should bypass and restore DWCW, RECW, and PCIG. The CRS should evaluate Tech Specs' implications for bypassed isolation signals, per T.S. 3.6.3 Event Four: Once actions are taken for the Group VIIA and VIIIA NSSSS isolation, a trip of the '1 B' Condensate Pump will occur from an electrical fault. Complicating the trip, the '1A' Reactor Recirc Pump (RRP) will fail to automatically runback to 42% speed.

Evaluation: Evaluate the crew's ability to recognize the loss of the '1 B' Condensate Pump and failure of the RRP to runback. The crew should take action per OT-100 to manually runback the Recirc pump and ensure Feedwater Flow is maintained below 11.3 Mlbm/hr.

Event Five: Once actions are taken for the loss of the '1 B' Condensate Pump, the 11 Aux Bus will trip from an electrical fault causing a loss of all Condensate and Feedwater.

Evaluation: Evaluate the crew's ability to recognize the loss of the 11 Aux Bus and scram the reactor on lowering water level. The crew should enter T-101, RPV Control. The crew should initiate RCIC to control Rx water level.

SEG-4158E RevOOO.doc Page 6 of 49

LIMERICK GENERATING STATION

Exelon Generation SIMULATOR EXERCISE GUIDE SCENARIO EVENT AND EVALUATION

SUMMARY

cont'd:

Event Six: Once actions are taken for the Scram, a coolant leak will develop in the Drywell that eventually develops into a Recirc Loop rupture with increased severity. Complicating the event will be a failure of the HPCI Aux Oil Pump and a RCIC over-speed trip.

Evaluation:

Determine the crews ability to take appropriate actions and use procedures to mitigate the effects of the leak in the DW. The crew is expected to execute OT-101, Drywell High Pressure, T-101, RPV Control, T-102, Primary Containment Control, and T-111, Level Restoration/Steam Cooling.

Event Seven: When the plant receives a LOCA signal on -129" Rx Level, the 201-D14 breaker will trip de-energizing the D-14 Bus with the 101-D14 breaker failing to auto close, also the D14 EDG fails to auto start.

Evaluation: The crew is expected to manually start D14 EOG and manually close the output breaker or manually close the 101-D 14 Breaker.

Termination The scenario may be terminated when the crew has performed an Emergency Criteria: Depressurization per T-112 with 5 ADS/SRVs open, restored Rx level to the normal band, and place Drywell Spray is in service.

SEG-4158E RevOOO.doc Page 7 of 49

LIMERICK GENERATING STATION

~* Exelon Generation SIMULATOR EXERCISE GUIDE VI. REFERENCES A. Training Procedures

1. TQ-AA-150, Operator Training Programs

2. TQ-AA-151, ILT Certification and NRC Examination Development and Administration

3. TQ-AA-155, Conduct of Simulator Training and Evaluation

4. TQ-AA-150, Limerick Operator Training Programs B. Annunciator Response Cards (ARC)

1. 104 F-2, 1B CONDENSATE PUMP TRIP

2. 107 H-2, REACTOR HI/LO LEVEL

3. 107 F-2, DRYWELL HI/LO PRESSURE

4. 110 B-4, DIV 1 REACTOR LEVEL 3 ADS PERMISSIVE

5. 110 D-4, DIV 3 REACTOR LEVEL 3 ADS PERMISSIVE

6. 111 E-2, 1A RECIRC ASD 13KV BRK TRIP

7. 111 A-3, 1A RECIRC PUMP SEAL COOLING WATER LO FLOW

8. 111 A-5, 1A RECIRC PUMP MOTOR WINDING COOLING WATER LO FLOW

9. 112 A-3, 1B RECI RC PUMP SEAL COOLING WATER LO FLOW

10. 112 A-5, 18 RECIRC PUMP MOTOR WINDING COOLING WATER LO FLOW

11. 112 B-3, 18 RECIRC ASD MINOR FAILURE

12. 112 C-4, 18 RECIRC FLOW LIMIT

13. 112 K-2, DRYWELL FLOOR DRAIN TANK HI/LO LEVEL

14. 112 C-5, DRYWELL EQUIPMENT DRAIN TANK/FLOOR DRAIN SUMP LEAKAGE HI FLOW

15. 113 B-5, CORE SPRAY LINE INTERNAL BREAK

16. 115 B-5, DRYWELL COOLER DRAIN FLOW HIGH

17. 115 E-4, DIV 2 DRYWELL HI PRESS

18. 117 B-5, HPCI VACUUM TANK HI/LO LEVEL

19. 117 B-3, HPCI PUMP LOW FLOW

20. 118 1-5, UNIT 1 ISOPHASE BUS COOLER TROUBLE

21. 120 F-2, 101 SAFEGUARD XFMR TROUBLE

22. 125 E-2, 1 MAIN XFMR TROUBLE

23. 125 F-1, 11 BUS BKR TRIP

24. 126 A-1, 11 UNIT AUX BUS NEG O SEQUENCE

25. 126 B-1, 11 UNIT AUX BUS UNDERVOLTAGE C. System Procedures (S)

1. S12.1.A, RHR Service Water System Startup.

2. S34.2.B, Placing Alternate lso-Phase Bus Cooling Unit in Service

3. S43.0.D, Response to Recirc Pump Motor High Temperature Condition

4. S87.1.A, Startup of Drywell Chilled Water System.

General Procedures (GP)

1. GP-5, App. 2, Planned Rx Maneuvering Without Shutdown

2. GP-8.5, Isolation Bypass of Crucial Systems D. Off Normal Procedures (ON)

1. ON-101 , Loss of lsophase Bus Cooling SEG-41 SBE RevOOO. doc Page 8 of 49

LIMERICK GENERATING STATION

,::,, Exelon Gene rat ion SIMULATOR EXERCISE GUIDE

2. ON-113, Loss of RECW E. Operating Transient Procedures (OT)

1. OT-101, High Drywell Pressure

2. OT-100, Reactor Low Level

3. OT-110, Reactor High Level

4. OT-112, Unexpected/Unexplained Change in Core Flow F. Event Procedures (E)

G. Special Event Procedures (SE)

1. SE-10, LOCA H. Surveillance Test and Routine Test Procedures (ST and RT)

I. Technical Specifications and TRM (TS)

1. 3.3.2.1, Isolation Actuation Instrumentation

2. 3.3.3.1, ECCS Instrumentation

3. 3.6.3, Primary Containment Isolation Valves

4. 3.5.1, Core Spray/ RHR J. Transient Response Implementation Procedures (T-100 series)/SAMPs

1. T-101, RPV Control

2. T-102, Primary Containment Control

3. T-111, Level Restoration/Steam Cooling

4. T-112, Emergency Slowdown K. TRIP 200 Series Procedures

1. T-225, Startup and Shutdown of Suppression Pool and Drywell Spray Operation

2. T-240, Maximize CRD Flow After Shutdown During Emergency Conditions L. EP-AA-1008, Limerick, Radiological Emergency Plan Annex for Limerick Generating Station M. Administrative Procedures

1. OP-AA Procedures

a. OP-AA-1, Conduct of Operations

b. OP-AA-20, Conduct of Operations Process Description

c. OP-AA-101-111-1003, Operations Department Standards and Expectations

d. OP-AA-101-113, Operations Fundamentals

e. OP-AA-101-113-1006, 4.0 Crew Critique Guidelines

f. OP-AA-106-101-1006, Operational Decision Making Process

2. OP-LG Procedures

a. OP-LG-101-111-1000, Licensed Operator Duties

b. OP-LG-102-106, Operator Response Time Program at Limerick

c. OP-LG-103-102-1000, Human Performance Continuing Good Practices

d. OP-LG-103-102-1002, Strategies for Successful Transient Mitigation

e. OP-LG-108-101-1001, Simple Quick Acts/ Transient Acts N. Current Shift Night Orders Forced Outage Plan

0. INPO Significant Operating Experience Reports (SOER), Significant Event Reports (SER) and INPO Event Reports (IER)

1. SOER 10-02, Engaged Thinking Organizations

2. INPO 15-004, Operator Fundamentals SEG-4158E RevOOO.doc Page 9 of 49

....... LIMERICK GENERATING STATION

"'

' Exelon Generation SIMULATOR EXERCISE GUIDE VII. PREBRIEF INSTRUCTIONS Unit 1 is in OPCON 1 at 100 % power Unit 2 is in OPCON 1 at 100 % power Specific Plant Conditions are as Follows:

Operation per GP-5, Steady State Operations Inoperable/Out of Service Equipment and Estimated Time of Return (ETR):

None Restrictions on Plant Operations:

None Planned Evolutions:

Maintain 100%.

Documents Provided:

None SEG-4158E RevOOO.doc Page 10 of 49

LIMERICK GENERATING STATION

~ Exelon Generation . SIMULATOR EXERCISE GUIDE VIII. DIRECTIONS FOR EVALUATION PREPARATION A INITIAL PREPARATION

., ITEM / MALFUNCTION / REMOTE FUNCTIONS Complete TQ-AA-155, Operator Training Programs Attachment 02, Evaluated Scenario Administration Checklist.

Complete TQ-LG-201-0113, Limerick Training Department Simulator Examination Security Actions Checklist B. SIMULATOR SETUP

., ITEM / MALFUNCTION / REMOTE FUNCTIONS Complete Limerick Simulator Pre-Evaluation Checklist Reset Simulator to the Pre-loaded IC developed for the Evaluation OR Reset the simulator to designated base load IC AND Load scenario file SEG4158E RevOOO.scn

Verify that all Malfunctions, Remotes, Overrides, Annunciators and Triggers are properly loaded OR

Manually enter the Malfunctions, Remotes, Overrides, Annunciators and Triggers per the Scenario Generator Screen Shots:

Simulator Operator (Driver) perform the following:

Momentarily place simulator in RUN

Acknowledge and clear all spurious alarms

Place the simulator back into FREEZE C. MALFUNCTION/REMOTE/OVERRIDE/ANNUNCIATORS FUNCTION TIME TABLE r nmerPause Pending SEG-4158E RevOOO. doc Page 11 of 49

~ ExelonGeneration.

LIMERICK GENERATING STATION SIMULATOR EXERCISE GUIDE MALFUNCTION/REMOTE/OVERRIDE/ANNUNCIATORS FUNCTION TIME TABLE cont'd MalfundionSummary*~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~*1 Ma11D M~ ID D~ w1ent Value T Value Dactine Ti" MHP4&1 lnad¥erteri HPO Stat Up False 00:00:15 2 MNS1618 NSSSS 61041 BlnedYwrt laolmi False 00:00:15 3

- - - * - - - - - - _...._ - - -- ~ - ..... -- _ _ _ __..... --- +- - - - -- ---

MCN6048 Cmlenr.u PIii., 1BP102 Bkr Ti.,a FALSE TRUE 00:00:15 MAR~ Recicum, LoapA A'4U noo 1.0DDI 00:10:00 00:04:15 MED262A ButFd on 13.2KVUriAuim)I But 11 False True 00:00:15 MHP4'?8 HPO Alie 01PIii., Ti.,a False True 00:00:25 MRC41i6 lnad¥erteri Tr., d RCC O'tlffllN!lld Mechnm False True 00:0030 r TimerPause DeleteA/1 I Pending SEG-4158E RevOOO.doc Page 12 of 49

-* Exelon Generation LIMERICK GENERATING STATION SIMULATOR EXERCISE GUIDE D. EVENT TRIGGERS ASSIGNMENT

1. Timers should be used on event triggers where possible for time validation

2. Timing of event triggers may be altered by the Lead Evaluator (or designee)

3. Verify triggers are actuated automatically as designed or manually initiate the trigger when the initiating action has occurred.

4. Inform Lead Evaluator (or designee) of expected plant response prior to actuation of each trigger.

5. Trigger #1 is manually initiated at Lead Evaluator (or designee) direction after the crew assumes responsibility for operation.

TRIGGER/ MALFUNCTION /

(r) TIME EVENT DESCRIPTION 1 Manual Initiates lso-phase Bus cooler trouble alarm 2 Manual Initiates HPCI system start 3 Manual Initiates NSSSS isolation 4 Manual Initiates '1 B' Condensate Pump trip 5 Manual Initiates 11 Bus trip 6 Auto/ ZRPS1SDN RMS to SHUTDOWN Initiates LOCA 7 Auto / RCZM600 > RCIC system RPM / flow > 200 gpm

= 9362 Initiates RCIC overspeed trip 8 Auto / MSZR23AR RPV level< -129"

<=4621 Initiates D14 Bus transfer failure and D14 EDG fails to auto start favorites Iriggers Triaaer # I Trigger T e>et

'j I Operators:

Arithmetic:

Multiplication I Division 4 + Addition 5 Subtraction t, ZRPS15DN Relational:

7 RCZMR600 >= 9362

> Greater than 8 MSZR23AR <= 4621

>= Greater than 9 or equal 1, 10 < Less than 11 <- Less than or 12 equal 13 == Equal to 14 !- Not equal to 15 Logical:

16 g.g. And 17

18 19 II Or Not

~

Other:

Open Paren Close Paren I

I' .Irigger Now I J;;;lear C]earAU l e,ccept

--E~

"'"" ~ CV>

SEG-4158E RevOOO.doc Page 13 of 49

~

LIMERICK GENERATING STATION

.::'"' Exelon Generation SIMULATOR EXERCISE GUIDE E. EQUIPMENT REPORTS AND SIMULATOR INSTRUCTOR OPERATIONS

1. This table section is moved and now integrated with Assessment of Crew Performance to facilitate simulator Operator and Instructor observation of crew activities related to simulator operation and instructor intervention.

2. Scripted Activity Reports should be followed with adherence to Operations Communication standards of performance.

3. The T-200 procedure reference book should be used for familiarity of reports to aid in operator prompting and expected communications.

4. The Lead Evaluator (or designee) should be informed if any event is not reported as scripted due to lack of Operator request.

5. The Standard Equipment Operator Response Times are per Attachment 1

6. A record of communications from the MCR and to the MCR will be maintained by the Simulator Operator using Attachment 2.

7. The OCOEE Simulator Operator Station P&I Os, Floor Plans and Panels must be used by the Simulator Operator as reference information when making reports to the MCR for plant parameters which are not driven by a communications script. Examples include: ARMs, Blowout Panel status, Reactor Building Area Temperatures and Pressures, RMMS, Turbine Enclosure parameters etc.

SEG-4158E RevOOO.doc Page 14 of 49

LIMERICK GENERATING STATION

,=.* Exelon Ger1eration SIMULATOR EXERCISE GUIDE IX. CREW CRITICAL TASKS A. Critical Tasks are based on the current Crew Critical Task List revision, NUREG 1021, and TQ-AA-150 requirements.

1. T-111.3 Inhibit Automatic ADS KIA 218000 A2.06 4.2/4.3 Standard: Prevent automatic initiation of the Automatic Depressurization System (ADS) prior to exceeding -129" reactor level and completion of ADS logic.

SAT/UNSAT

2. T-111.2 Maintain RPV water level greater than the Top of Active Fuel (TAF).

KIA 295031 EA1 .01 4.4/4.5 KIA 295031 EA1.02 4.5/4.5 KIA 295031 EA1 .05 4.3/4.3 KIA 295031 EA1.11 4.1/4.1 KIA 295031 EA1.12 3.9/4.1 Standard: Operate injection systems to maintain reactor water level greater than the top of active fuel (TAF) or enter T-112 and perform an emergency blowdown by opening five Safety Relief Valves (SRVs). When pressure permits, inject with low pressure injection sources to restore RPV level above TAF.

SAT/UNSAT SEG-41 SBE RevOOO. doc Page 15 of 49

'"" Exelon Generatior1 LIMERICK GENERATING STATION SIMULATOR EXERCISE GUIDE CREW CRITICAL TASKS cont'd

3. T-102.1 Spray the Drywell per T-225.

KIA 295012 AA2.01 3.2/4.2 KIA 295010 AK2.01 3.2/3.3 KIA 295010 AA1.07 3.2/3.4 Standard: Before Drywell temperature reaches 340°F, with Drywell temperature and pressure on the SAFE side of the Drywell Spray Initiation Limit curve and Suppression Pool level below 37.4 feet, then spray the Drywell per T-225 before exceeding 340°F.

SAT/UNSAT SEG-4158E RevOOO. doc Page 16 of 49

~I""

LIMERICK GENERATING STATION

- Exelon Generation SIMULATOR EXERCISE GUIDE X. ASSESSMENT OF CREW PERFORMANCE DURING CONDUCT OF THE DYNAMIC SIMULATOR EVALUATIONS:

A. Conduct the Simulator Evaluation Session per TQ-AA-155, Conduct of Simulator Training and Evaluation, Attachment 02, Evaluated Scenario Administration Checklist B. Assessment of Crew and Individual performance shall be consistent with OP-AA-20, Conduct of Operations Process Description C. Where possible record the time and position responsible for performance of each task or assessment item D. Items not performed as expected SHALL be discussed in the post performance crew critique E. During the performance of the evaluation, the Simulator Evaluators shall MAINTAIN notes of observations and information consistent with the timeline F. Assessment items with the Cu symbol indicate a time critical standard for performance G. Assessment items with the rb-' symbol indicate a Probabilistic Risk Assessment (PRA) association with the task H. The Simulator Operator will respond with scripted or proceduralized responses when requested by the MCR operators with Procedure completion times requested per Attachment 1 I. The Simulator Operator will also maintain a timeline and record of all reports and requests issued by the MCR personnel with response provided by the simulator operator using Attachment 2 J. Shaded items do not require assessment for ILT Evaluations. The CRS may be requested to complete the Shift ED forms and determine the EAL classification at the completion of the scenario.

SEG-4158E RevOOO.doc Page 17 of 49

--* Exelon Generation LIMERICK GENERATING STATION SIMULATOR EXERCISE GUIDE

1. EVENT-1 LOSS OF ISO-PHASE BUS COOLING Simulator Operator Instructions:

Respond to request for assistance as appropriate.

Inform Floor Instructor prior to each event trigger.

Manually actuate Trigger #_1_ to initiate alarm indicating Iso-phase Bus trouble.

At time 5 min when requested to investigate Unit 1 !so-phase Bus Cooling, report: The '1A' lso-phase Bus Cooling Fan is tripped and the '1 B' Fan has failed to auto start. I am attempting to start the '1 B' lso-phase Bus Cooling Fan.

As soon as power is lowered less than 90%,

DELETE override for annunciator 118 1-5, contact MCR and report: '1 B' Iso-phase Bus Cooling Fan is running and lso-phase Bus temperatures are lowering.

If requested, at time 5 min from initial request to report lso-phase Bus Temperatures, report: 'A' phase temperature is 75°C and rising slow. 'C' phase temperature is 80°C and rising slowly. If crew asks for a trend. report: Both temperatures are rising approximately 1 degree/minute.

Alarm setpoints T1SH-10-123A, 176 deg F T1SH-10-123C, 80 deg C SEG-4158E RevOOO.doc Page 18 of 49

--' Exelon Gener-at ion LIMERICK GENERATING STATION SIMULATOR EXERCISE GUIDE TIME ASSESSMENT ITEMS AND TASK PERFORMANCE POSITION

1. EVENT-1 LOSS OF ISO-PHASE BUS COOLING Lead Evaluator (or designee) Notes: The crew will enter ON-101, when loss of lso-phase Bus Cooling is verified. ON-101 directs the crew to minimize main generator VARS on the main generator and lower power as necessary to control the lso-phase Bus temperatures. When power is lowered to 90%, lso-phase Bus Cooling will be restored.

Reference ARC: PRO

118 1-5, UNIT 1 ISOPHASE BUS COOLER TROUBLE

[ARC-MCR-118-1-5] PRO Dispatch EO to 1OC930 panel to investigate cause of alarm

[ARC-MCR-118-1-5] SRO If a total loss of Isolated Phase Bus Cooling ENTER ON-101, Loss of lso-phase Bus Cooling Enter ON-101 after receiving report of no cooling fans running SRO

[ON-101 2.2] PRO Direct EO to restore cooling using S34.2.B, Placing Alternate lso-Phase Bus Cooling Unit in Service

[ON-101 2.3] PRO Lower Main Generator reactive load to O MVARs (Malfunction)

Lead Evaluator (or designee) Notes: OP-LG 103-102-1002, Strategies for Successful Transient Mitigation, allows use of the "63% LOSS OF FWP" pushbutton in the case of Loss of Iso-phase Bus Cooling.

[ON-101 2.4] SRO/RO Recognize cooling will not be restored within 10 minutes and reduce power IAW GP5 Appendix 2 and RMSI until Generator Amps <20,000 amps

[ON-101 2.5] PRO Direct EO to monitor lso-phase Bus temperatures

[GP-5 App#2 3.1] SRO DETERMINE target power level for intended drop in Rx power

[GP-5 App#2 3.1] PRO Notify PECO TSO and generation Dispatch of Rx power reduction Respond to report of lsophase Bus Cooling restored and stop lowering power RO The SRO calls out to Work Week Manager for support SRO Contact Reactor Engineering for support SRO SEG-4158E RevOOO.doc Page 19 of 49

LIMERICK GENERATING STATION

,=,

Exelon Gener-at ion SIMULATOR EXERCISE GUIDE

2. EVENT- 2 INADVERTENT HPCI START Simulator Operator Instructions:

Inform Floor Instructor prior to each event trigger.

Respond to request for assistance as appropriate.

Manually actuate Trigger #...1.... when directed by Lead Evaluator, to initiate HPCI System start.

If requested, at time 5 min EO notifies the MCR on HPCI start:

reports: No obvious cause of HPCI start.

When WWM contacted to investigate HPCI system start:

report: l&C will be notified to investigate HPCI start.

SEG-4158E RevOOO.doc Page 20 of 49

LIMERICK GENERATING STATION

,::*

Exelon Generation SIMULATOR EXERCISE GUIDE TIME ASSESSMENT ITEMS AND TASK PERFORMANCE POSITION

2. EVENT- 2 INADVERTENT HPCI START Lead Evaluator (or designee) Notes: HPCI system inadvertently starts and injects into the RPV.

The crew will identify the power excursion and enter OT-104, Unexpected/Unexplained Positive or Negative Reactivity Addition, for the power rise, and when verified the start was inadvertent, isolate the HPCI system. Once HPCI is isolated and Tech Specs referenced at Lead Evaluators direction move to Event 3.

Reference appropriate ARCs: PRO

117 B-5, HPCI VACUUM TANK HI/LO LEVEL

117 B-3, HPCI PUMP LOW FLOW

107 H-2, REACTOR HI/LO LEVEL

113 B-5, CORE SPRAY LINE INTERNAL BREAK Recognize and report HPCI start PRO Determine HPCI start signal is not valid and minimize HPCI injection PRO Enter OT-104, Unexpected/Unexplained Positive or Negative Reactivity SRO Addition

[OT-104 IOA] RO Reduce Recirc Flow, per GP-5 Appendix 2, and RMSI, to reduce power below pre-transient level

[OT-104 3.1] SRO/PRO Enter and execute OT-104, Attachment 2, HPCI/RCIC Inadvertent Injection

[OT-104 Att#2] PRO Secure HPCI in accordance with S55.2.A, HPCI Shutdown From Automatic Or Manual Initiation.

Manually isolate HPCI Steam Supply, closing HV-55-1 F003, HPCI Steam PRO Line Outboard Isolation Valve.

[OT-104 3.5] RO Request P-1 and determine whether a Thermal Limit violation exists Enter 3.5.1.c.1 and 3.3.3.1, (if investigation is conducted), for HPCI INOP and SRO determine action.

The SRO calls out to Work Week Manager for support SRO SEG-41 SBE RevOOO. doc Page 21 of 49

LIMERICK GENERATING STATION

,*** Exelon Generation SIMULATOR EXERCISE GUIDE

3. EVENT-3 INADVERTENT NSSSS ISOLATION Simulator Operator Instructions:

Respond to request for assistance as appropriate.

Inform Floor Instructor prior to each event trigger.

Manually actuate Trigger# ..l_ when directed by Lead Evaluator to initiate NSSSS isolation.

At time 10 min after FSSV or EO action requested for Group 8 NSSSS isolation:

report: l&C is investigating, no cause has been identified to MCR SEG-4158E RevOOO.doc Page 22 of 49

LIMERICK GENERATING STATION

.="~

Exelon Generation SIMULATOR EXERCISE GUIDE TIME ASSESSMENT ITEMS AND TASK PERFORMANCE POSITION

3. EVENT-3 INADVERTENT NSSSS ISOLATION Lead Evaluator (or designee) Notes: An inadvertent Group VIIA and VIIIA NSSSS isolation occurs causing a loss of RECW cooling to the Recirc Pump seals, a loss of drywell cooling, and a loss of Instrument Gas (PCIG). The crew is expected to identify the PCIG outboard suction valve failed to isolate on the NSSSS signal.

Reference appropriate ARCs: PRO/RO

111 A-3, 1A RECIRC PUMP SEAL COOLING WATER LO FLOW

111 A-5, 1A RECIRC PUMP MOTOR WINDING COOLING WATER LO FLOW

112 A-3, 1B RECIRC PUMP SEAL COOLING WATER LO FLOW

112 A-5, 1B RECIRC PUMP MOTOR WINDING COOLING WATER LO FLOW Recognize increase in Drywell pressure Crew Enter OT-101, High Drywell Pressure SRO Crew verifies parameters and determines isolation signal inadvertent Crew Establish Drywell pressure as Critical Parameter SRO Direct PRO to bypass and restore DWCW, RECW, and PCIG SRO/PRO

[ARC-MCR-111 A-3] RO/PRO Monitor Recirc Pump seal cavity temperatures and refer to S43.0.D (Section 4.5)

Enter ON-113, Loss of RECW SRO

[ON-113 2.1] PRO IF RECW flow is not expected to be restored to Recirc Pump seals within 10 minutes, THEN INFORM CRS to consider a rapid plant shutdown per GP-4, Rapid Plant Shutdown To Hot Shutdown.

[ON-113 2.2] SRO/PRO

!f.RECW flow is not restored to Recirc Pump seals within 10 minutes, THEN immediately TRIP Recirc Pumps 10 seconds apart per S43.2.A, Shutdown Of A Recirculation Pump.

Lead Evaluator (or designee) Notes: The crew will bypass and restore RECW per GP-8.5, Isolation Bypass of Crucial Systems AND/OR as directed using ON-113, Loss of RECW

[GP-8.5 3.3.1] PRO/RO IF RECW Head Tank HI/LO Alarm (118 services H-5) is not in alarm OR RECW Pump suction pressure is greater than 80 psig as read on Pl-013-105A(B) (local Pl at pumps) THEN perform the following: Otherwise do not bypass the isolation.

SEG-4158E RevOOO.doc Page 23 of 49

Exelon Generation LIMERICK GENERATING STATION SIMULATOR EXERCISE GUIDE

3. EVENT-3 INADVERTENT NSSSS ISOLATION Simulator Operator Instructions:

Respond to request for assistance as appropriate.

Inform Floor Instructor prior to each event trigger.

At time 10 min after FSSV or EO action requested for Group 8 NSSSS isolation:

report: l&C is investigating, no cause has been identified to MCR SEG-4158E RevOOO. doc Page 24 of49

=,

Exelon Generation LIMERICK GENERATING STATION SIMULATOR EXERCISE GUIDE TIME ASSESSMENT ITEMS AND TASK PERFORMANCE POSITION

3. EVENT-3 INADVERTENT NSSSS ISOLATION

[GP-8.5 3.3.3] SRO/PRO IF an Outboard Isolation has occurred THEN perform the next step to bypass the isolation signals for:

HV-13-108 Recirc Pp Clg Wtr In (SUPPLY/RETURN TO SEALS/OIL CLRS)

HV-13-111 Recirc Pp Clg Wtr Out (SUPPLY/RETURN TO SEALS/OIL CLRS)

[GP-8.5 3.3.3.1] [ON-113 2.5.1] PRO Position HS-13-113 in BYPASS.

PLACE HS-013-*13, "Reac Recirc Pmp Clg Wtr MOV lsln Bypass Switch" (SEALS/OIL CLRS OUTBD ISOL BYPASS), in "BYPASS."

[ON-113 2.5.1] PRO OPEN HV-013-*08, "Rx Recirc Pump RECW Inlet PCIV" AND HV-013-*11, "Rx Recirc Pmp RECW Outlet PCIV," by placing HS-013-*08, "RECW To Recirc Pp" (SUP/RET SEAL/OIL CLRS) (HV-013-*08/*11), in "OPEN."

[OT-101 3.15.3 or GP-8.5] SRO/PRO IF the Drywell Chilled Water System has undergone an inadvertent isolation THEN RESET per GP-8.3 OR BYPASS per GP-8.5.

[GP-8.5 3.2.1] RO/PRO IF DWCW Head Tank HI/LO Alarm (PMS Point G532) is "NORMAL" OR DWCW Pump suction pressure is greater than 35 psig as read on Pl-087-109A(B) (local Pl at pumps) THEN perform the following: Otherwise do not bypass the isolation.

[GP-8.5 3.2.2] PRO IF an Inboard Isolation has occurred THEN perform the next step to bypass the isolation signals for:

HV-87-128 A D/W Chilled Water Supply (LOOP A)

HV-87-129 A D/W Chilled Water Return (LOOP A)

HV-87-122 B D/W Chilled Water Supply (LOOP B)

HV-87-123 B D/W Chilled Water Return (LOOP B)

[GP-8.5 3.2.2.1] PRO Position HS-87-115 in BYPASS.

SEG-41 SBE RevOOO. doc Page 25 of 49

LIMERICK GENERATING STATION

~.., Exelon Generation SIMULATOR EXERCISE GUIDE

3. EVENT-3 INADVERTENT NSSSS ISOLATION Simulator Operator Instructions:

Respond to request for assistance as appropriate.

Inform Floor Instructor prior to each event trigger.

SEG-4158E RevOOO.doc Page 26 of 49

...,. LIMERICK GENERATING STATION

~* Exelon Generation SIMULATOR EXERCISE GUIDE TIME ASSESSMENT ITEMS AND TASK PERFORMANCE POSITION

3. EVENT-3 INADVERTENT NSSSS ISOLATION Lead Evaluator (or designee) Notes: When possible only bypass the effected valve(s) so that the isolation capability of the entire penetration in not bypassed.

Per [GP-8.4 3.1] WHEN bypass logic is completed, THEN POSITION valve handswitches used to make up logic as necessary.

Open the following valves repositioned for bypassing logic: PRO

HV-87-128 A D/W Chilled Water Supply (LOOP A)

HV-87-129 A D/W Chilled Water Return (LOOP A)

HV-87-122 B D/W Chilled Water Supply (LOOP B)

HV-87-123 B D/W Chilled Water Return (LOOP B)

Lead Evaluator (or designee) Notes: If required, Drywell Cooling is restored using S87.1.A Appendix 1, Startup of Standby/Tripped Drywell Chiller Hard Card or S87 .1.A, Startup of Drywell Chilled Water System.

Restore Drywell Cooling per S87 .1.A Appendix 1, Startup of Standby/Tripped PRO Drywell Chiller Hard Card or S87 .1.A, Startup of Drywell Chilled Water System.

[S87.1.A App1 2.1] PRO PLACE *A(B)K111 Drywell Chiller (CHILLER) to STOP (Green Flagged).

[S87.1.A App1 2.2] PRO PLACE DW Chilled water pump *A-P161 to OFF.

[S87.1.A App1 2.3] PRO PLACE DW Chilled water pump *B-P161 to OFF.

[$87.1.A App1 4.0] PRO PLACE *B(A)K111, "D/W Chiller (CHILLER) for oncoming Drywell Chiller in "START."

[S87.1.A App1 4.0] PRO VERIFY HV-087-*02B(A), "CHILLER Discharge," opens

[S87.1.A App1 4.0] PRO ENSURE *A-P161 in RUN.

[S87.1.A App1 4.0] PRO ENSURE *B-P161 in RUN.

SEG-4158E RevOOO.doc Page 27 of 49

_,, LIMERICK GENERATING STATION

- Exelon Generation SIMULATOR EXERCISE GUIDE

3. EVENT-3 INADVERTENT NSSSS ISOLATION Simulator Operator Instructions:

Respond to request for assistance as appropriate.

Inform Floor Instructor prior to each event trigger.

SEG-4158E RevOOO.doc Page 28 of 49

LIMERICK GENERATING STATION

=:* Exelon Generation SIMULATOR EXERCISE GUIDE TIME ASSESSMENT ITEMS AND TASK PERFORMANCE POSITION

3. EVENT-3 INADVERTENT NSSSS ISOLATION Lead Evaluator (or designee) Notes: The crew will identify the PCIG outboard suction valve HV-59-102, Instrument Gas PCIV (OUTBD) failed-to-close on the NSSSS isolation signal. When identified, the operator is expected to close the PCIG isolation valve. PCIG is then restored as directed using GP-8.5 section 3.1 Identify HV-59-102, Instrument Gas PCIV (OUTBD) failed-to-close on PRO isolation signal (Malfunction)

Bypass and restore PCIG per GP-8.5 PRO

[GP-8.5 3.1.3] PRO IF an Outboard Isolation has occurred THEN perform the next step to bypass the isolation signals for:

HV-59-102 PCIG Compressor Suction (OUTBOARD)

HV-59-129B PCIG B Header Supply (DRYWELL B)

[GP-8.5 3.1.3.1] PRO Position switches as listed:

HSS-57-191B BYPASS

HV-59-102 CLOSE

HV-59-129B CLOSE NOTE: [GP-8.4 3.1] [GP-8.5 3.1.1]

WHEN bypass logic is completed, THEN POSITION valve handswitches used to make up logic as necessary.

Open the following valves repositioned for bypassing logic: PRO

HV-59-102

HV-59-129B Lead Evaluator (or designee) Notes: PCIG header may be restored to service using Instrument Air OR after PCIG is restored per GP-8.5, it is acceptable to either wait for PCIG pressure to build up OR open air to gas valves. (difference is < 1 min and NOT consequential)

[ON-113 2.15] PRO IE.Primary Containment Instrument Gas (PCIG) Compressors trip due to loss of RECW flow, THEN OPEN HV-059-*28A(B}, "Inst Air Supply Viv To 'A'('B')

Inst Gas Hdr" (INST GAS A(B, on Panel *OC655 to pressurize PCIG System with Instrument Air. Enter Tech Spec 3.6.3, PCIVs and TS 3.3.2, Isolation Actuation SRO Instrumentation (with investigation) Contact l&C/ Floor Supervisor/ WWM to investigate inadvertent isolation CRS/PRO The SRO calls out to Work Week Manager for support SRO SEG-4158E RevOOO.doc Page 29 of 49

_,....... Exelon Gener*ation LIMERICK GENERATING STATION SIMULATOR EXERCISE GUIDE

4. EVENT - 4 CONDENSATE PUMP TRIP Simulator Operator Instructions:

Respond to request for assistance as appropriate. Inform Floor Instructor prior to each event trigger. Manually actuate Trigger#.....!_ to Initiate Condensate Pump trip at Lead Evaluator's discretion. At time 5 Min after FSSV or EO action requested for '1 B' Condensate Pump report: The '1 B' Condensate pump breaker has tripped on overcurrent. SEG-4158E RevOOO.doc Page 30 of 49

=- Exelon Generation LIMERICK GENERATING STATION SIMULATOR EXERCISE GUIDE TIME ASSESSMENT ITEMS AND TASK PERFORMANCE POSITION

4. EVENT-4 CONDENSATE PUMP TRIP Lead Evaluator (or designee) Notes: '1 B' Condensate Pump will trip. The '1 B' Condensate Pump trip will limit RFP speed to 78%, and result in an expected 42% Recirc system runback for both Recirc Pumps, however the '1A' Recirc Pump will fail to runback. The Operator will identify the failure and manually insert a 42% Recirc runback on the '1A' Recirc Pump.

Reference appropriate ARCs: RO/PRO

112 8-3, 1B RECIRC ASD MINOR FAILURE
104 F-2, 18 CONDENSATE PUMP TRIP
112 C-4, 18 RECIRC FLOW LIMIT Recognize '1 B' Condensate Pump Trip RO/PRO

[ARC MCR 112 8-3] PRO Reference HMI Faults & Alarms screen at panel 1OC626 [ARC MCR 112 C-4] RO/PRO Verify '1 B' Recirc Pump runback and identify '1A' Recirc Pump failed to runback. (Malfunction) [ARC MCR 112 C-4] RO Reduce speed manually on '1A' Recirc Pump to 42%, using 42% PB on 1OC603 panel. Enter OT-112, Unexpected/Unexplained Change In Core Flow, Attachment 2, SRO and Attachment 3. [OT-112 3.2] SRO DIRECT RO to monitor for THI indications [OT-112 3.3] SRO DIRECT RO, IF indications of THI exist, to manually SCRAM the reactor. [OT-112 Att #2] RO/PRO NOTIFY CRS to enter GP-5, Appendix 2 and Tech Spec 3.4.1.3 [OT-112 Att #3] SRO CHECK plant operating in authorized region of Power/Flow Map. Enter OT-100, Reactor Low Level, on '1 B' Condensate Pump trip. SRO [OT-100 3.1] SRO Direct performance of OT-100 Attachment #1 [OT-100 Att #1] PRO Dispatch EO to determine if Condensate/Feedpump vibration levels are elevated SEG-41 SBE RevOOO. doc Page 31 of 49

LIMERICK GENERATING STATION ~* Exelon Generatior1 SIMULATOR EXERCISE GUIDE

4. EVENT-4 CONDENSATE PUMP TRIP Simulator Operator Instructions:

Respond to request for assistance as appropriate. Inform Floor Instructor prior to each event trigger. At time 5 Min after FSSV or EO action requested for '1 B' Condensate Pump report: The '1 B' Condensate pump breaker has tripped on overcurrent. SEG-4158E RevOOO.doc Page 32 of 49

LIMERICK GENERATING STATION

Exelon Generation SIMULATOR EXERCISE GUIDE TIME ASSESSMENT ITEMS AND TASK PERFORMANCE POSITION

4. EVENT-4 CONDENSATE PUMP TRIP

[OT-100 Att #1, GP-5, Appendix 2,] RO REDUCE reactor power, per GP-5, Appendix 2, by control rod insertion (2-3 control rods) to maintain RFP suction pressure above 300 psig AND Total FW flow~ 11.3 Mlbs/hr. Enter OT-104, Unexpected, Unexplained Positive or Negative Reactivity SRO Insertion. [OT-104 3.5] RO Demand P-1 edit and determine possibility of a Thermal Limit violation [GP-5 App #2] PRO Chemistry notified >15% Rx power change Enter Tech Spec 3.4.1.3, Recirc loop flow mismatch SRO The SRO calls out to SOS and SOM for prompt and OCC support SRO SEG-4158E RevOOO. doc Page 33 of 49

LIMERICK GENERATING STATION

,, Exelon Generation SIMULATOR EXERCISE GUIDE 5-7. EVENTS 5 -7 LOSS OF 11 BUS / LOCA / RCIC TRIP/ D14 EDG FAILURE Simulator Operator Instructions

Respond to request for assistance as appropriate. Inform Floor Instructor prior to each event trigger. Manually actuate Trigger#_§__ at Lead Evaluator's discretion, to initiate Loss of 11 BUS At time 5 Min If requested to investigate trip of 11 Unit Aux Bus report: There are overcurrent flags up on the 'A' and 'B' phases of the 11 Bus Breaker. It smells like burnt insulation in the room." If requested, there is no evidence of a fire. If requested to perform steps of S44.2.A, Reactor Water Cleanup Shutdown, perform sections of procedure as requested. SEG-4158E RevOOO.doc Page 34 of 49

=,,,,,_,, Exelon Generation LIMERICK GENERATING STATION SIMULATOR EXERCISE GUIDE TIME ASSESSMENT ITEMS AND TASK PERFORMANCE POSITION 5-7. EVENTS 5 -7 LOSS OF 11 BUS / LOCA / RCIC TRIP/ D14 EOG FAILURE Lead Evaluator (or designee) Notes: The 11 Aux Bus trips from an electrical fault initiating a loss of high pressure feed, and a reactor low level scram. The crew will identify the loss of all high pressure feed to the vessel and take action to restore reactor level. Also, as actions are being taken for the scram, a coolant leak develops in the drywell that eventually develops into a Recirc Loop rupture with increased severity. Reference appropriate ARCs: RO/PRO

125 E-2, 1 MAIN XFMR TROUBLE
125 F-1, 11 BUS BKR TRIP
126 A-1, 11 UNIT AUX BUS NEG O SEQUENCE
126 8-1, 11 UNIT AUX BUS UNDERVOLTAGE
111 E-2, 1A RECIRC ASD 13KV BRK TRIP
120 F-2, 101 SAFEGUARD XFMR TROUBLE
107 H-2, REACTOR HI/LO LEVEL
110 8-4, DIV 1 REACTOR LEVEL 3 ADS PERMISSIVE
110 D-4, DIV 3 REACTOR LEVEL 3 ADS PERMISSIVE Recognize/report loss of 11 Unit Auxiliary Bus RO/PRO Dispatch personnel to investigate loss of 11 Unit Aux Bus PRO Recognize/report reactor scram and low RPV level RO Enter T-101 (RPV level < +12.5 inches) SRO

[T-101 RC-4] RO Place Mode Switch in SHUTDOWN [T-101 RC-6] RO Insert SRM's and IRM's [T-101 RQ-2] PRO Ensure Turbine trip and Generator Lockout [T-101 RC/P-4] RO/PRO Stabilize RPV pressure below 1096 psig Verify RCIC running and injecting into RPV PRO Establish RPV Level as Critical Parameter SRO Lead Evaluator (or designee) Notes: T-111, Level Restoration/Steam Cooling is entered from T-101 when it is determined RPV level cannot be maintained above TAF (-161"). This conclusion may be reached prior to RPV level reaching -161". Enter T-111, Level Restoration/Steam Cooling SRO [T-111 LR/5] SRO/PRO Inhibit automatic ADS (Critical Task) SEG-4158E RevOOO.doc Page 35 of 49

Exelon Generation LIMERICK GENERATING STATION SIMULATOR EXERCISE GUIDE 5-7. EVENTS 5 - 7 LOSS OF 11 BUS / LOCA / RCIC TRIP/ D14 EDG FAILURE Simulator Operator Instructions: Respond to request for assistance as appropriate. Inform Floor Instructor prior to each event trigger. At time 5 Min If requested to investigate trip of 11 Unit Aux Bus report: There are overcurrent flags up on the 'A' and 'B' phases of the 11 Bus Breaker. It smells like burnt insulation in the room." If requested, there is no evidence of a fire. SEG-4158E RevOOO. doc Page 36 of 49

=* Exelon Generation LIMERICK GENERATING STATION SIMULATOR EXERCISE GUIDE TIME ASSESSMENT ITEMS AND TASK PERFORMANCE POSITION 5-7. EVENTS 5 -7 LOSS OF 11 BUS / LOCA / RCIC TRIP/ D14 EDG FAILURE [T-111 LR/6] RO Perform T-240, Maximize CRD Flow After Shutdown During Emergency Conditions [T-111 LR/7] RO Start two SLC Pumps [T-111 LR/8] PRO Start two Subsystems (a subsystem is defined as any motor-driven system loop that is independently capable of injecting into the RPV) Verify isolations (+12.5 inches, -38 inches) PRO Recognize RCIC Overspeed trip (trips 6.5 minutes after injection starts) PRO Dispatch Operator to reset RCIC Turbine Overspeed trip locally PRO Lead Evaluator (or designee) Notes: As the crew is taking actions to restore reactor level, a coolant leak develops in the Drywell that eventually develops into a Recirc Loop Rupture. OT-101, Attachment #4 isolates non-essential sections of piping within the Drywell which could cause a Drywell pressure rise if a hole or crack in the piping exists. Respond to annunciators: RO/PRO

107 F-2, DRYWELL HI/LO PRESSURE
112 K-2, DRYWELL FLOOR DRAIN TANK HI/LO LEVEL
115 B-5, DRYWELL COOLER DRAIN FLOW HIGH
112 C-5, DRYWELL EQUIPMENT DRAIN TANK/FLOOR DRAIN SUMP LEAKAGE HI FLOW
115 E-4, DIV 2 DRYWELL HI PRESS Recognize rising Drywell pressure RO/PRO Enter OT-101, High Drywell Pressure SRO Establish Drywell and Suppression Pool pressure as Critical Parameters SRO CRS directs OT-101, High Drywell Pressure Attachment #4, Unidentified or SRO RWCU system cause of rising drywell pressure

[OT-101, Att. 4] PRO ENSURE Main Steam Line and Recirc sample valves closed [OT-101, Att. 4] PRO ENSURE RWCU System secured [OT-101, Att. 4] PRO ENSURE Main Steam Line drains closed SEG-4158E RevOOO.doc Page 37 of 49

~r--

Exelon Generation LIMERICK GENERATING STATION SIMULATOR EXERCISE GUIDE 5-7. EVENTS 5 - 7 LOSS OF 11 BUS / LOCA / RCIC TRIP/ D14 EDG FAILURE Simulator Operator Instructions: Respond to request for assistance as appropriate. Inform Floor Instructor prior to each event trigger. At time 5 Min If requested to investigate trip of 11 Unit Aux Bus report There are overcurrent flags up on the 'A' and 'B' phases of the 11 Bus Breaker. It smells like burnt insulation in the room." If requested, there is no evidence of a fire. If requested to perform steps of S44.2.A, Reactor Water Cleanup Shutdown, perform sections of procedure as requested. SEG-4158E RevOOO.doc Page 38 of 49

Exelon Generation LIMERICK GENERATING STATION SIMULATOR EXERCISE GUIDE TIME ASSESSMENT ITEMS AND TASK PERFORMANCE POSITION 5-7. EVENTS 5 -7 LOSS OF 11 BUS / LOCA / RCIC TRIP/ D14 EDG FAILURE When Drywell pressure exceeds 1.68 psig, re-enter T-101 SRO When Drywell pressure exceeds 1.68 psig, enter T-102 SRO Un-Bypass all NSSSS systems bypassed during inadvertent NSSSS signal PRO when Drywell pressure exceeds 1.68 When Drywell temperature exceeds 145 °F, re-enter T-102 SRO

[T-102 DW/T-5] PRO Maximize Drywell Cooling bypassing isolations per GP-8 as necessary Verify DWCW Head Tank level PRO Verify isolations on RPV level <+12.5" PRO Verify isolations on 1.68 psig Drywell pressure PRO Secure Recirculation Pumps running without cooling RO/PRO Observe HPCI system (isolated), Aux Oil pump will fail to start if unisolated for PRO RPV injection. [T-1 02 PC/P-5] SRO/PRO Before Supp Pool pressure reaches 7.5 psig Spray the Suppression Pool per T-225, Startup and Shutdown of Suppression Pool and Drywell Spray Operation Lead Evaluator (or designee) Notes: The following steps are performed as directed by T-225, Startup and Shutdown of Suppression Pool and Drywell Spray Operation. [T-225 4.2.3] PRO IF RHR pump not running THEN start 1A(B)P202 "RHR Pump" [T-225 4.2.4] PRO ENSURE the following valves open:

HV-51-1 F047 A(B), "1A(B) RHR Htx Shell Side Inlet Viv" (INLET)
HV-51-1F003A(B), "1A(B) RHR Htx Shell Side Outlet Viv" (OUTLET)
HV-C-51-1F048A(B), "1A(B) RHR Htx Shell Side Bypass Viv" (HEAT EXCH BYPASS)

[T-225 4.2.5] PRO OPEN HV-51-1 F024A(B), "1A(B) RHR Pp Full Flow Test Return Viv" (SUPP POOL CLG A(B)) AND OBTAIN flow of 8,000 to 8,500 gpm as indicated on Fl-51-1 R603A(B), FL SEG-4158E RevOOO.doc Page 39 of 49

Exelon Ger1eration LIMERICK GENERATING STATION SIMULATOR EXERCISE GUIDE 5-7. EVENTS 5 - 7 LOSS OF 11 BUS / LOCA / RCIC TRIP/ D14 EDG FAILURE Simulator Operator Instructions: Respond to request for assistance as appropriate. Inform Floor Instructor prior to each event trigger. At time 5 Min If requested to investigate trip of 11 Unit Aux Bus report: There are overcurrent flags up on the 'A' and 'B' phases of the 11 Bus Breaker. It smells like burnt insulation in the room." If requested, there is no evidence of a fire. If requested to perform steps of S44.2.A, Reactor Water Cleanup Shutdown, perform sections of procedure as requested. SEG-4158E RevOOO.doc Page 40 of 49

LIMERICK GENERATING STATION ~** Exelon Generatior1 SIMULATOR EXERCISE GUIDE TIME ASSESSMENT ITEMS AND TASK PERFORMANCE POSITION 5-7. EVENTS 5 -7 LOSS OF 11 BUS / LOCA / RCIC TRIP/ D14 EDG FAILURE [T-225 4.2.6] PRO OPEN HV-51-1F027A(B), "1A(B) RHR Supp Pool Spray Line PCIV" (SUPP POOL SPRAY) [T-225 4.2.8] PRO PLACE RHR Service Water Pump for RHR Heat Exchanger to be used in service per S 12.1.A, RHR Service Water System Startup Lead Evaluator (or designee) Notes: The following steps are performed as directed by S 12.1.A, RHR Service Water System Startup. [S12.1.A 4.1.4 or App1 1.1] PRO OPEN HV-51-*F014A(B), HEAT EXCHANGER INLET [S12.1.A 4.1.5 orApp1 1.2] PRO Throttle OPEN HV-51-*F068A(B) for 18 to 20 seconds [S12.1.A 4.1.6(7) or App1 1.3] PRO VERIFY Pl-51-*05A-1 (B), HX DISCH, indicates system static pressure greater than or equal to 15 psig [S12.1.A 4.1.8 orApp1 1.4] PRO IF the HI RAD AND/OR HI Pump Discharge pressure trips need to be bypassed AND the required actions of ODCM Part 1 Control 3.1.1 have been met for the INOPERABLE RHRSW Radiation Monitor, THEN PLACE HSS-12-002A(B), PUMP TRIP BYPASS, in "BYPASS" [S12.1.A 4.2.1 orApp1 1.6] PRO IF 'A'/'B' Loop pump (OA(C)-P506) (OB(D)-P506) is to be placed in service, THEN ENSURE OA(B)-V543 OR OC(D)-V543, Spray Pond Pump Room Fans, in "RUN" at OOC681. [S12.1.A 4.2.2 orApp1 1.7] PRO START OA(B,C,D)P506, RHRSW PUMP [S12.1.A 4.2.3 orApp1 1.8] PRO THROTTLE HV-51-*F068A(B) to the maximum obtainable position without exceeding 11,000 gpm on Fl-51-*R602A(B) while maintaining pump disch pressure (Pl-12-001A-1 (B)) between 75 psig to 85 psig [T-225 4.2.9] PRO CLOSE HV-C-51-1F048A(B), "1A(B) RHR Htx Shell Side Bypass Viv" (HEAT EXCH BYPASS) SEG-4158E RevOOO.doc Page 41 of 49

LIMERICK GENERATING STATION ~ Exelon Generation SIMULATOR EXERCISE GUIDE 5-7. EVENTS 5 - 7 LOSS OF 11 BUS / LOCA / RCIC TRIP/ 014 EOG FAILURE Simulator Operator Instructions: Respond to request for assistance as appropriate. Inform Floor Instructor prior to each event trigger. At time 5 Min If requested to investigate trip of 11 Unit Aux Bus report: There are overcurrent flags up on the 'A' and 'B' phases of the 11 Bus Breaker. It smells like burnt insulation in the room." If requested, there is no evidence of a fire. At time 10 minutes Load all SE-10 Floor Actions with time delays scenario, after Crew requests SE-10 Shunt Trip Resets and report: The status of individual resets as requested or when all resets are timed out or report: "All SE-10 Floor Actions are complete" when all SE-10 timers have expired. SEG-4158E RevOOO. doc Page 42 of 49

Exelon Ger1eration LIMERICK GENERATING STATION SIMULATOR EXERCISE GUIDE TIME ASSESSMENT ITEMS AND TASK PERFORMANCE POSITION 5-7. EVENTS 5-7 LOSS OF 11 BUS / LOCA / RCIC TRIP/ D14 EDG FAILURE [T-225 4.2.1 O] PRO IF more spray flow is required, THEN REDUCE flow through Full Flow Test line by throttling closed HV-51-1F024A(B), "1A(B) RHR Pp Full Flow Test Return Viv" (SUPP POOL CLG A(B)) Lead Evaluator (or designee) Notes: The following steps, to spray the Drywell, are directed from T-102, and performed from T-225. The crew will re-align '1 B' RHR from Suppression Pool Spray to Drywell Spray. [T-102 PC/P-9] CRS DIRECT to Spray the Drywell per T-225, Startup and Shutdown of Suppression Pool and Drywell Spray Operation [T-102 PC/P-9] PRO PERFORMS Spray the Drywell per T-225, Startup and Shutdown of Suppression Pool and Drywell Spray Operation (Critical Task) Lead Evaluator (or designee) Notes: When the plant receives the LOCA signal at -129" RPV level, the 101-D14 breaker will trip with the 201-D14 breaker failing to auto close rendering the D14 Bus de-energized until manual actions are taken. Crew monitors RPV level decrease and re-aligns ECCS systems to RPV Crew Enter SE-10, LOCA Crew Perform SE-10, LOCA, actions in MCR RO/PRO Direct performance of SE-10 Floor Actions RO/PRO [SE-10 3.1] RO PLACE the following to "CLOSE"

52-20224/CS, "0*24 Safeguard L.C. 0*24-G-D MCC Bkr" (SAFEGUARDS 8), on *BC661.
52-20124/CS, "0*14 Safeguard L.C. 0*14-G-D MCC Bkr" (SAFEGUARDS A), on *AC661 Recognize failure of D-14 Bus to fast transfer from the 201 SFGD Bus to 101 PRO SFGD Bus Recognize failure of D-14 EOG to auto start on LOCA signal and Manually PRO start D-14 EOG

[SE-10 3.2] RO PLACE to "RESET":

43-22322/CS, "Div. Ill Non SFGD Instr. Panel" (INST AC 201 CONTROL PNL), on *CC661
43-22422/CS, "Div. IV Non SFGD Instr. Panel" (INST AC 202 CONTROL PNL), on *DC661 (following D-14 EOG start)

SEG-4158E RevOOO. doc Page 43 of 49

LIMERICK GENERATING STATION ~" Exelon Generation SIMULATOR EXERCISE GUIDE 5-7. EVENTS 5-7 LOSS OF 11 BUS / LOCA / RCIC TRIP/ D14 EDG FAILURE Simulator Operator Instructions: Respond to request for assistance as appropriate. Inform Floor Instructor prior to each event trigger. At time 5 Min If requested to investigate trip of 11 Unit Aux Bus report: There are overcurrent flags up on the 'A' and 'B' phases of the 11 Bus Breaker. It smells like burnt insulation in the room." If requested. there is no evidence of a fire. At time 10 minutes Load all SE-10 Floor Actions with time delays scenario, after Crew requests SE-10 Shunt Trip Resets and report: The status of individual resets as requested or when all resets are timed out or report: "All SE-10 Floor Actions are complete" when all SE-10 timers have expired. SEG-4158E RevOOO.doc Page 44 of 49

LIMERICK GENERATING STATION

'.. Exelon Generation SIMULATOR EXERCISE GUIDE TIME ASSESSMENT ITEMS AND TASK PERFORMANCE POSITION 5-7. EVENTS 5 -7 LOSS OF 11 BUS / LOCA / RCIC TRIP/ D14 EDG FAILURE Restart '1A' CRD Pump following LOCA RO Restart SLC Pumps following LOCA RO Lead Evaluator (or designee) Notes: The following steps are directed from T-112, Emergency Slowdown.

[T-112 EB-11] SRO/PRO DIRECT Open all 5 ADS valves using (Critical Task) Maximize injection with all available RPV injection sources (Critical Task) RO/PRO When RPV level is restored above -161 inches, exit T-111 and re-enter RC/L SRO leg of T-101 Align/ Realign RHR to Spray the Drywell per T-225, Startup and Shutdown PRO of Suppression Pool and Drywell Spray Operation (Critical Task) Restore RPV level between +12.5 inches and +54 inches Crew Lead Evaluator (or designee) Notes: The scenario may be terminated when an Emergency Depressurization has been performed, Drywell Spray is in service, control rods inserted and reactor level is restored. SEG-4158E RevOOO.doc Page 45 of 49

~** Exelon Generation LIMERICK GENERATING STATION SIMULATOR EXERCISE GUIDE Attachment 1 Simulator Operator Response Times

Response

Procedure Performance Time (Minutes) T-209 Injection from the Standby Liquid Control Storage Tank with the RCIC 45 System T-212 Bypassing SQUIB Valves for SLC Injection 19 T-215 De-energization of Scram Solenoids 7 T-216 Manual Isolation and Vent of Scram Air Header 7 T-217 RPS/ARI Reset and Backup Method of Draining Scram Discharge 17 Volume T-219 Maximizing CRD Cooling Water Header Flow during ATWS Conditions 23 T-221 MSIV Isolation Bypass Procedure 11 T-225 Startup and Shutdown of Suppression Pool and Drywell Spray 8 Operations T-240 Maximizing CRD flow after Shutdown During Emergency Conditions 8 T-245 RPV Injection from RHR S/D Cooling 12 T-248 Injection from SLC Test Tank to RPV 15 T-251 Establish a HPCI Injection flow Path VIA Feedwater Only 6 T-270 Terminate and Prevent Injection into the RPV 7 T-290 Instrumentation Available for T-103 SAMP-2 5 S46.7.A Control Rod Drive Hydraulic System Operation Following Reactor (4.2.1) Scram (Securing CRD flow to the Reactor - Close 46-1 F060, CRD 7 Water Pressure Control Station Inlet Valve) SE-10-1 Breaker Reset Following LOCA (Also reset ARMs, RHRSW Rad Resets and Monitor and RDCS) 10 Floor action SEG-4158E RevOOO.doc Page 46 of 49

LIMERICK GENERATING STATION .:-* Exelon Generation SIMULATOR EXERCISE GUIDE Attachment 2 Communications Log CREW: _ _ __ DATE: LSEG: _ _ __ START T I M E : - - - - - STOP T I M E : - - - - RO: WCS: SM: CRS: - - - - - PRO: - - - - - FSSV: - - - - - - PERSON CALL PERSON TIME BEING COMMUNICATION / REQUEST BACK CALLING CALLED TIME SEG-4158E RevOOO. doc Page 47 of 49

=,,- Exelon Generation LIMERICK GENERATING STATION SIMULATOR EXERCISE GUIDE THIS PAGE INTENTIONALLY LEFT BLANK SEG-4158E RevOOO.doc Page 48 of 49

LIMERICK GENERATING STATION ~ Exelon Generation SIMULATOR EXERCISE GUIDE XI. CREW PREBRIEF INSTRUCTIONS Unit 1 is in OPCON 1 at 100 % power Unit 2 is in OPCON 1 at 100 % power Specific Plant Conditions are as Follows:

Operation per GP-5, Steady State Operations Inoperable/Out of Service Equipment and Estimated Time of Return (ETR):
None Restrictions on Plant Operations:
None Planned Evolutions:
Maintain 100%.

Documents Provided:

None SEG-4158E RevOOO.doc Page 49 of 49

=* Exelon Generation LIMERICK GENERATING STATION SIMULATOR EXERCISE GUIDE CODE NO: SEG-6217E REV NO: 000 AUTHOR: T.BYERS APPROXIMATE 60 minutes RUN TIME: TYPE: SIMULATOR EVALUATION EFFECTIVE DATE: 12/01/17 GUIDE PROGRAM: LICENSED OPERATOR TRAINING COURSE: LICENSED OPERATOR (REQUALIFICATION/INITIAL) TRAINING TITLE: Simulator Evaluation Guide for Individual and Crew Performance Prepared By: T. A. BY,.ers/S/ Date: 11/20/17 Training Instructor - Signature Reviewed By: NIA for NRC ILT Date: N/A LORT Lead Instructor - Signature Reviewed By: N/A Date: N/A EP (as appropriate) - Signature Reviewed By: N/A Date: N/A RE (as appropriate) - Signature Approval: Bill Martin/SI Date: 11/30/17 OPS Manager - Signature Approved For Use: Dan Semeter/S/ Date: 12/01/17 Training Manager - Signature SEG-6217E RevOOO Page 1 of 55

: Exelon Gener-at ion LIMERICK GENERATING STATION SIMULATOR EXERCISE GUIDE Appendix D Scenario Outline Form ES-D-1 Facility: Limerick 1 & 2 Scenario No.: SEG-6217E Rev _o_ Op-Test No.:_1_.

Examiners: Operators: Initial Conditions: Unit 1 Reactor Power is 75% Unit 2 Reactor Power is 100% Turnover: Restore Unit 1 power to 100% using by withdrawing Control Rods and raising Core Flow Critical Tasks:

1. Inhibit Auto ADS

2. Terminate and prevent injection into the RPV (second lowering)

3. Direct performance of control rod insertion via T-217 to personnel located outside the MCR Event Malfunction Event Event No. Number Type* Description 1 None R-RO Continue raising reactor power 2 MRD016D C-RO Control Rod (38-39) fails stuck C-PRO 3 MPC257 '1 D' RHR Pump suction leak TS-SRO C-PRO 4 MED2828 Loss of Div 2 DC TS-SRO MVl2328 C-RO 5 Reactor Level Transmitter Failure/ Failure to Half Scram.

MRP029A TS-SRO 6 MRR441 C-PRO Small coolant leak into Drywell MSL559 7 M-ALL Hydraulic A lWS with failure of Standby Liquid Control MRD556 8 MRD024 C-RO RDCS Inoperative 9 MAD145E C-PRO '1J' SRV Fails Open Mechanically

*           (N)ormal,        (R)eactivity,      (l)nstrument,       (C)omponent,          (M)ajor SEG-6217E RevOOO                                                                           Page 2 of 55

--* Exelon Generation LIMERICK GENERATING STATION SIMULATOR EXERCISE GUIDE A. ILT Target Quantitative Attributes ACTUAL (Per Scenario; See ES-301Section D.5.d) NUMBER

1. Malfunctions after EOP entry (1-2) 2

2. Abnormal events (2-4) 4

3. Major transients (1-2) 1

4. EOPs entered/requiring substantive actions (1-2) 1

5. EOP contingencies requiring substantive actions (0-2) 1

6. Critical tasks (2-3) 3 Review TQ-AA-151 attachment 5 and ES-301-5 for individual position requirements for scenario and scenario set SEG-6217E RevOOO Page 3 of 55

~ Exelon Generation LIMERICK GENERATING STATION SIMULATOR EXERCISE GUIDE II. PURPOSE: Systematically evaluate individual and team performance to identify areas for improvement. Critical Tasks and Assessment Items from this evaluation guide are to be used to assess crew and individual performance and as input into a 4.0 Crew Critique Process. Ill. SIMULATOR EVALUATION GUIDE OBJECTIVES: A. The following evaluation objectives apply to the Crew (C), Shift Manager (SM), Control Room Supervisor (S), Unit Reactor Operator I Plant Reactor Operator (R), or Incident Assessor I Shift Technical Advisor (A) as indicated in the following categories.

1. The general condition for each of the evaluation objectives will be "Given the plant conditions and sequence of events in the Simulator Evaluation Guide (SEG)".

2. The general acceptable evaluation objective criteria for each of the evaluation objectives will be "To perform effectively as an individual and contribute to successful crew performance in accordance with appropriate reference plant procedures and Operations Expectations, Fundamentals and Strategies".

3. Specific UNSAT evaluation objective criteria will be consistent with TQ-AA-155, Conduct of Simulator Training and Evaluation with applicable forms and job aids.

4. During performance of this Simulator Evaluation Guide, the individuals and crew should satisfactorily demonstrate the following overall procedure and plant control objectives:

Direct and perform actions per S73.1.A, Normal Operation Of The Reactor Manual Control System
Direct and perform actions per OT-101, High Drywell Pressure
Direct and perform actions per OT-114, Inadvertent Opening Of A Relief Valve
Direct and perform actions per OT-117, RPS Failures
Direct and perform actions perT-217, RPS/ARI Reset and Backup Method Of Draining Scram Discharge Volume
Direct and perform actions per T-270, Terminate And Prevent Injection Into the RPV
Direct and perform actions per T-101 , RPV Control
Direct and perform actions per T-102, Primary Containment Control
Direct and perform actions per T-117, Level/Power Control SEG-621 lE RevOOO Page 4 of 55

~***** Exelon Generation LIMERICK GENERATING STATION SIMULATOR EXERCISE GUIDE IV. RECORD OF TEMPORARY CHANGES: A. Approval of Pen & Ink Changes will be by the ILT or LORT Lead Instructor with OTM concurrence B. All Pen & Ink Changes are to be tracked in ILTor LOR Program Action Tracking for Next Revision C. All Pen & Ink Changes shall be in accordance with TQ-AA-223 Temp Date of Purpose of Change LORT Action Revision Change# Change Approval Tracking Date V. REVISION HISTORY: A. If a Revision affects a Task Performance from VISION Terminal Performance Objectives then the revision must also be made in the VISION database. B. The description of the Revision should adequately indicate how the training content of the Revision has changed. C. The description of the Revision should also include previous format reference and number and previous template used (e.g for conversion of LSTS to LLORSEG format). Revision # Date of Description of Revision and Affect on Training Content Number Revision RevOOO NewSEG 8/18/17

# Date of Revision - refers to date revision was released for approval SEG-6217E RevOOO                                                                          Page 5 of 55

Exelon Generation LIMERICK GENERATING STATION SIMULATOR EXERCISE GUIDE SCENARIO EVENT AND EVALUATION

SUMMARY

Events One: When the crew takes the shift, the RO will raise power by withdrawing control rods. Evaluation: To evaluate the RO's ability to properly operate RMCS to raise Reactor Power with control rods. Event Two: As the RO withdraws control rods, one of the control rods will fail stuck. Evaluation: To evaluate the RO's ability to recognize the stuck rod and take actions as directed by S73.1.A, Normal Operation Of The Reactor Manual Control, for the stuck control rod. Event Three: Following the stuck control rod event, a leak will develop in the suction line for the '1 D' RHR Pump. Evaluation: To evaluate the crew's ability to enter and execute SE-4, Flood and T-103, and taking action to close the '1 D' RHR Pump suction valve to stop the leak. The SRO will evaluate Tech Spec 3.5.1 for the out of service RHR Pump. Event Four: After the RHR leak has been isolated and Tech Specs referenced, a loss of Division 2 DC will occur. Evaluation: To evaluate the crew's ability to recognize the loss of DIV 2 DC and enter and execute E-1 FB, placing the MCR HVAC in a Chlorine isolation (PRO) and to call plant personnel for support. The SRO is expected to reference Tech Spec 3.0.3 and 3.8.2.1 for loss of DC. Event Five: After the crew responds to the loss of DC, a downscale failure of a RPS Reactor Water Level instrument will occur with a failure to cause a half scram. Evaluation: Evaluate the crews' ability to implement OT-117, RPS Failures and respond to a failure to half scram. The crew will be evaluated on their ability to implement OT-117 to determine the instrument failure and insert a manual half scram. The CRS is expected to reference Tech Specs for the failure of the RPS system. Event Six: After the crew responds to the instrument failure, a small coolant leak will occur in the drywell causing Drywell pressure to rise. Eventually, pressure will rise to the point requiring the crew to perform a GP-4, Rapid Plant Shutdown to Hot Shutdown. Evaluation: Evaluate the crews' ability to recognize rising drywell pressure and execute OT-101 for rising drywell pressure including isolating RWCU. When Drywell pressure approaches the scram setpoint, the crew should perform a GP-4 Rapid Plant Shutdown to Hot Shutdown, or manually scram the reactor. SEG-6217E RevOOO Page 6 of 55

Exelon Generation LIMERICK GENERATING STATION SIMULATOR EXERCISE GUIDE SCENARIO EVENT AND EVALUATION

SUMMARY

cont'd: Event Seven: When the Mode Switch is taken to shutdown, a Hydraulic A TWS will prevent the scramming of control rods. Complicating the event, Standby Liquid Control will fail to inject into the reactor. Evaluation: Evaluate the crews' ability to enter and execute T-101, RPV Control, and T-117, Level/Power Control. The crew should recognize the Hydraulic A TWS and make the proper callouts for Trip procedures to assist in the Reactor shutdown. Event Eight: After the Mode Switch is taken to shutdown, RDCS will become inoperative and prevent manual insertion of control rods. Evaluation: Evaluate the crews' ability to recognize the failure of RDCS and call out for floor assistance in resetting RDCS in the AER. Once RDCS is reset, the crew is expected to manually insert control rods to help mitigate the ATWS condition. Event Nine: After Rx level is lowered below -50", the '1J' SRV will fail open mechanically adding heat to the Suppression Pool. The crew should enter OT-114 and attempt SRV closure by removing fuses to the SRV. Evaluation: Evaluate the crews' ability to respond to the inadvertent SRV opening per OT-114 and their ability to track the rising Suppression Pool temperatures. When Suppression Pool temperature exceeds 110°F, the crew should perform a second lowering of reactor water level as directed by T-117, Level/Power Control. Termination The scenario is terminated following performance of T-217, RPS/ARI Reset and Backup Criteria: Method of Draining Scram Discharge Volume, to insert all Control Rods, and RPV level is established above -161 inches (TAF), and stabilized for Cooldown Rate Control. SEG-6217E RevOOO Page 7 of 55

LIMERICK GENERATING STATION .=:* Exelon Generation SIMULATOR EXERCISE GUIDE VI. REFERENCES A. Training Procedures

1. TQ-AA-150, Operator Training Programs

2. TQ-AA-151, ILT Certification and NRC Examination Development and Administration

3. TQ-AA-155, Conduct of Simulator Training and Evaluation

4. TQ-LG-150, Limerick Operator Training Programs B. Annunciator Response Cards (ARC)

1. 002 F-4 & F-5, RE SFD PNLs 1OC245, 1OC243 TROUBLE

2. 002 A-1, CONTROL ROOM RADIATION ISOLATION INITIATED

3. 002 A-2, CONTROL ROOM CHLORINE ISOLATION INITIATED

4. 003 B-2, Unit 1&2 CONTAINMENT LEAK DETECTOR HI RADIATION

5. 107 H-1, REACTOR WATER BELOW LEVEL 3 TRIP

6. 107 F-2, DRYWELL HI / LO PRESS

7. 108 E-4, RDCS INOPERATIVE

8. 110 B-1, SRV/HEADVENTVALVE LEAKING

9. 110 B-2, SAFETY RELIEF VALVE OPEN

10. 112 C-5, DRYWELL EQUIPMENT DRAIN TANK/FLOOR DRAIN SUMP LEAKAGE HI FLOW

11. 115 G-5, 1B-1 D RHR PUMP ROOM FLOOD

12. 115 B-5, DRYWELL COOLER DRAIN FLOW HIGH

13. 115 E-5, FLOOR DRAIN LEAKAGE HI FLOW

14. 122 G-1, 1 UNIT DIV 2 SFGD BATTERY CHARGERS TROUBLE

15. 122 G-2, 1DB-1 250V DC MCC UNDERVOLTAGE

16. 122 G-3, 1DB-2 250V DC MCC UNDERVOLTAGE

17. 122 G-4, 1PPB1/1PPB3125VDC DIST PANELS UNDERVOLTAGE

18. 122 G-5, 1PPB2125VDC DC DIST PANEL UNDERVOLTAGE

19. 122 D-1, D12 D-G TROUBLE

20. 122 D-2, D12 STANDBY AC POWER SYS OUT OF SERVICE

21. 122 E-3, DIV 2 MCC SHUNT TRIP COIL AUX CIRCUIT UNDERVOLTAGE

22. 122 E-4, DIV 2 MCC SHUNT TRIP COIL UNDERVOLTAGE

23. 122 F-4, 1B RPS & UPS DIST PNL. TROUBLE

24. 122 A-5, 18 RPS & UPS STATIC INVERTER TROUBLE

25. 127 H-4, REACTOR ENCLOSURE FLOOR DRAIN SUMP HI-HI WATER LEVEL C. System Procedures (S)

1. S12.1.A, RHR Service Water System Startup

2. S51.8.A, Suppression Pool Cooling Operation (Startup And Shutdown And Level Control)

3. S73.1.A, Normal Operation Of The Reactor Manual Control System General Procedures (GP)

1. GP-4, Rapid Plant Shutdown To Hot Shutdown D. Off Normal Procedures (ON)

E. Operating Transient Procedures (OT)

1. OT-101, High Drywell Pressure

2. OT-114, Inadvertent Opening Of A Relief Valve

3. OT-117, RPS Failures SEG-6217E RevOOO Page 8 of 55

Exelon Generation LIMERICK GENERATING STATION SIMULATOR EXERCISE GUIDE REFERENCES cont'd F. Event Procedures (E) 1 . E-1 FB, Loss of Division 1 Safeguard 125/250 VDC Bus 1FB G. Special Event Procedures (SE)

1. SE-4, Plant Flood

2. SE-10, LOCA H. Surveillance Test and Routine Test Procedures (ST and RT)

I. Technical Specifications and TRM (TS)

1. 3.0.3 both offsite sources and one EOG

2. 3.0.6 provided safety function determined to be functional

3. 3.1.3.1 Control Rods

4. 3.3.1 RPS Instrumentation

5. 3.8.2.1.c DC Sources (2 hr. LCO)

6. 3.8.3.1.b Onsite Power Distribution (8 hr. LCO)

7. 3.5.1 HPCI

8. 3.1.5 SLC

9. 3.3.4.1 RRCS/ATWS RPT Breakers

10. 3.5.1 Core Spray / RHR

11. 3.7.1.2 ESW

12. 3.7.1.1 RHRSW J. Transient Response Implementation Procedures (T-100 series)/SAMPs

1. T-101, RPV Control

2. T-102, Primary Containment Control

3. T-117, Level/Power Control K. TRIP 200 Series Procedures

1. T-209, Injection From SLCS (SLC) Storage Tank With The RCIC System

2. T-217, RPS/ARI Reset and Backup Method Of Draining Scram Discharge Volume

3. T-218, Control Rod Insertion By Withdraw Line Venting

4. T-221, MSIV Isolation Bypass Procedure

5. T-270, Terminate And Prevent Injection Into the RPV

6. T-290, Instrumentation Available for T-103/SAMP-2 L. EP-AA-1008, Limerick, Radiological Emergency Plan Annex for Limerick Generating Station M. Administrative Procedures

1. OP-AA Procedures

a. OP-AA-1, Conduct of Operations

b. OP-AA-20, Conduct of Operations Process Description

c. OP-AA-101-111-1003, Operations Department Standards and Expectations

d. OP-AA-101-113, Operations Fundamentals

e. OP-AA-101-113-1006, 4.0 Crew Critique Guidelines

f. OP-AA-106-101-1006, Operational Decision Making Process SEG-621 lE RevOOO Page 9 of 55

---* Exelon Generation LIMERICK GENERATING STATION SIMULATOR EXERCISE GUIDE REFERENCES cont'd

2. OP-LG Procedures

a. OP-LG-101-111-1000, Licensed Operator Duties

b. OP-LG-102-106, Operator Response Time Program at Limerick

c. OP-LG-103-102-1000, Human Performance Continuing Good Practices

d. OP-LG-103-102-1002, Strategies for Successful Transient Mitigation

e. OP-LG-108-101-1001, Simple Quick Acts/ Transient Acts N. Current Shift Night Orders Forced Outage Plan

0. INPO Significant Operating Experience Reports (SOER), Significant Event Reports (SER) and INPO Event Reports (IER)

1. SOER 10-02, Engaged Thinking Organizations

2. INPO 15-004, Operator Fundamentals SEG-6217E RevOOO Page 10 of 55

LIMERICK GENERATING STATION ~*

Exelon Generation SIMULATOR EXERCISE GUIDE VII. PREBRIEF INSTRUCTIONS Unit 1 Reactor Power is 75%

Unit 2 Reactor Power is 100% Specific Plant Conditions are as Follows:

None Inoperable/Out of Service Equipment and Estimated Time of Return (ETR):
None Restrictions on Plant Operations:
None Planned Evolutions:
Restore Unit 1 power to 100% by withdrawing Control Rods and raising Core flow
Reactor Engineering has determined there are no known Channel Distorted Control Rods.

Documents Provided:

ReMA
GP-5, Appendix #2 completed to step 3.2.22
S73.1.A, Normal Operation Of The Reactor Manual Control System SEG-6217E RevOOO Page 11 of 55

--' Exelon Ger1eration LIMERICK GENERATING STATION SIMULATOR EXERCISE GUIDE VIII. DIRECTIONS FOR EVALUATION PREPARATION A. INITIAL PREPARATION

       .,                          ITEM / MALFUNCTION / REMOTE FUNCTIONS Complete TQ-AA-155, Operator Training Programs Attachment 02, Evaluated Scenario Administration Checklist.

Complete TQ-LG-201-0113, Limerick Training Department Simulator Examination Security Actions Checklist

8. SIMULATOR SETUP ITEM/ MALFUNCTION/ REMOTE FUNCTIONS Complete Limerick Simulator Pre-Evaluation Checklist Reset Simulator to the Pre-loaded IC developed for the Evaluation OR Reset the simulator to designated base load IC AND Load scenario file SEG6217E RevOOO.scn

Verify that all Malfunctions, Remotes, Overrides, Annunciators and Triggers are properly loaded OR
Manually enter the Malfunctions, Remotes, Overrides, Annunciators and Triggers per the Scenario Generator Screen Shots:

Simulator Operator (Driver) perform the following:

Reduce Reactor power to 75% using ReMA for scenario (if not using pre-loaded IC)
Provide the following:
GP-5, Appendix #2 M/U to step 3.2.22, Return to Power
ReMA
S73. 1.A, Normal Operation Of The Reactor Manual Control System
Momentarily place simulator in RUN
Acknowledge and clear all spurious alarms
Place the simulator back into FREEZE SEG-6217E RevOOO Page 12 of 55

LIMERICK GENERATING STATION ~ Exelon Generation SIMULATOR EXERCISE GUIDE C. MALFUNCTION/REMOTE/OVERRIDE/ANNUNCIATORS FUNCTION TIME TABLE CtJrentVu Dactine T. MPC257 LNkF11111S~Pod0*100.IDlp) 0.00 000015 1 MED282B Fu Ill DC Saie,.d Bus 1BD1(! False 000015 2 MVl232II ReadorVeaelLMI Trnrilllr(RPSJ N1811\Faislow False 000015 3 r Timer Pause C/earList I r Timer Pause De/ete A/1 I Penclng SEG-6217E RevOOO Page 13 of 55

LIMERICK GENERATING STATION

"' Exelon Generatior1 SIMULATOR EXERCISE GUIDE D. EVENT TRIGGERS ASSIGNMENT

1. Timers should be used on event triggers where possible for time validation

2. Timing of event triggers may be altered by the Lead Evaluator (or designee)

3. Verify triggers are actuated automatically as designed or manually initiate the trigger when the initiating action has occurred.

4. Inform Lead Evaluator (or designee) of expected plant response prior to actuation of each trigger.

5. Trigger #1 is manually initiated at Lead Evaluator (or designee) direction after the crew assumes responsibility for operation.

TRIGGER/ MALFUNCTION / (o TIME EVENT DESCRIPTION 1 Manual Initiates '1 D' RHR Pump Room flooding 2 Manual Initiates loss of Div 2 DC 3 Manual Initiates RPS Level transmitter fails 4 Manual Initiates Small Coolant Leak in Drywell 5 Auto I ZRPS 1SON RMS to Shutdown Initiates RDCS INOP and SRV fails open 6 Manual Racks out '1 D' RHR Pump breaker 7 Manual Racks out '1 B' RHR Pump breaker favorites Iriggers Trigger It Trigger Text Operators: 1 Arithmetic: 2 K Multiplication

I Division 4 + Addition 5 ZRPS1SDN Subtraction 6 Relational: 7 I > Grealer than I 8 9

                                                                                                 >= Greater than or equal I         10 11 12
                                                                                                    < Less than
                                                                                                  <* Less than or equal 13                                                                                     *= Equal to I                                                                                                 != Not equal to 14 15                                                                                   Logical:

16 t,t, And 17 18 II Or I Not 19

Other: OpenParen l CloseParen Irigger Now I Clear C]earAII Accept E!!it SEG-621 lE RevOOO Page 14 of 55

Exelon Generation LIMERICK GENERATING STATION SIMULATOR EXERCISE GUIDE E. EQUIPMENT REPORTS AND SIMULATOR INSTRUCTOR OPERATIONS

1. This table section is moved and now integrated with Assessment of Crew Performance to facilitate simulator Operator and Instructor observation of crew activities related to simulator operation and instructor intervention.

2. Scripted Activity Reports should be followed with adherence to Operations Communication standards of performance.

3. The T-200 procedure reference book should be used for familiarity of reports to aid in operator prompting and expected communications.

4. The Lead Evaluator (or designee) should be informed if any event is not reported as scripted due to lack of Operator request.

5. The Standard Equipment Operator Response Times are per Attachment 1

6. A record of communications from the MCR and to the MCR will be maintained by the Simulator Operator using Attachment 2.

7. The OCOEE Simulator Operator Station P&IDs, Floor Plans and Panels must be used by the Simulator Operator as reference information when making reports to the MCR for plant parameters which are not driven by a communications script. Examples include: ARMs, Blowout Panel status, Reactor Building Area Temperatures and Pressures, RMMS, Turbine Enclosure parameters etc.

SEG-6217E RevOOO Page 15 of 55

LIMERICK GENERATING STATION ~ Exelon Generation SIMULATOR EXERCISE GUIDE IX. CREW CRITICAL TASKS A. Critical Tasks are based on the current Crew Critical Task List revision, NUREG 1021, and TQ-AA-150 requirements.

1. T-117.1 Inhibit automatic ADS.

KIA 295037 EA2.06 4.0/4.1 KIA 218000 AA4.04 4.1/4.1 Standard: Prevent automatic initiation of the Automatic Depressurization System (ADS) prior to exceeding -129" reactor level and completion of ADS logic. SAT/UNSAT

2. T-117.10 Terminate and prevent injection into the RPV.

KIA 295037 EK1 .02 4.1/4.3 KIA 295037 EK3.03 4.1/4.5 KIA 295037 EA2.02 4.1/4.2 Standard: Reactor water level deliberately lowered by performing T-270. When reactor power is below 4% or reactor water level reaches -161 inches or all Safety Relief Valves (SRVs) closed and Drywell pressure is below 1.68 psig, then stop lowering reactor water level AND continue. SAT/UNSAT

3. T-101.4 Implement T-217 to insert control rods.

KIA 295037 EA1.05 3.9/4.0 KIA 295037 EA2.05 4.2/4.3 KIA 295037 EA1.02 3.8/4.0 KIA 295037 EA1.03 4.1/4.1 KIA 212000 A4.04 3.9/3.9 Standard: Direct the performance of T-217 to Operations personnel located outside the Main Control Room (MCR). SAT/UNSAT SEG-6217E RevOOO Page 16 of 55

Exelon Generation LIMERICK GENERATING STATION SIMULATOR EXERCISE GUIDE X. ASSESSMENT OF CREW PERFORMANCE DURING CONDUCT OF THE DYNAMIC SIMULATOR EVALUATIONS: A. Conduct the Simulator Evaluation Session per TQ-AA-155, Conduct of Simulator Training and Evaluation, Attachment 02, Evaluated Scenario Administration Checklist B. Assessment of Crew and Individual performance shall be consistent with OP-AA-20, Conduct of Operations Process Description C. Where possible record the time and position responsible for performance of each task or assessment item D. Items not performed as expected SHALL be discussed in the post performance crew critique E. During the performance of the evaluation, the Simulator Evaluators shall MAINTAIN notes of observations and information consistent with the timeline F. Assessment items with the Co symbol indicate a time critical standard for performance G. Assessment items with the \t::,,- symbol indicate a Probabilistic Risk Assessment (PRA) association with the task H. The Simulator Operator will respond with scripted or proceduralized responses when requested by the MCR operators with Procedure completion times requested per Attachment 1 I. The Simulator Operator will also maintain a timeline and record of all reports and requests issued by the MCR personnel with response provided by the simulator operator using Attachment 2 J. Shaded items do not require assessment for ILT Evaluations. The CRS may be requested to complete the Shift ED forms and determine the EAL classification at the completion of the scenario. SEG-6217E RevOOO Page 17 of 55

,=:, Exelon Generation LIMERICK GENERATING STATION SIMULATOR EXERCISE GUIDE

1. EVENT-1 RAISE REACTOR POWER WITH CONTROL RODS I FLOW Simulator Operator Instructions:

Inform Floor Instructor prior to each event trigger. Respond as requested for floor support. The crew will raise reactor power by withdrawing control rods. As control rod (38-39) is selected and withdrawal attempt made, the RO will determine the control rod is stuck. SEG-6217E RevOOO Page 18 of 55

-, Exelon Generation LIMERICK GENERATING STATION SIMULATOR EXERCISE GUIDE TIME ASSESSMENT ITEMS AND TASK PERFORMANCE POSITION

1. EVENT-1 RAISE REACTOR POWER WITH CONTROL RODS / FLOW Lead Evaluator (or designee) Notes: The crew will raise reactor power by withdrawing control rods. As control rod (38-39) is selected and withdrawal attempt made, the RO will determine the control rod is stuck.

The following steps are directed in S73.1.A, Normal Operation Of The Reactor Manual Control System, for each Control Rod withdrawn. This SEG uses section 4.3 for Continuous Withdraw, however the crew may choose to use section 4.2 for Single Notch Withdraw. NOTE: Control Rod movement requires a PEER CHECK prior to Control Rod movement. Withdraw control rods IAW Control Rod move sheet and S73.1.A, Normal RO Operation Of The Reactor Manual Control System [S73.1.A 4.3.1] RO REVIEW Attachment 1 AND VERIFY the control rod to be withdrawn is not channel distortion susceptible [S73.1.A 4.3.2) RO ENSURE drive water pressure is 255 to 265 psid, as indicated on PDl-046-1R602 [S73.1.A 4.3.3) RO SELECT next in-sequence Control Rods per rod withdraw sheet [S73.1.A 4.3.4) RO VERIFY correct rod position on Four-Rod-Display [S73.1.A 4.3.7) RO Simultaneously DEPRESS WITHDRAWAL AND CONTINUOUS WITHDRAWAL pushbuttons. [S73.1.A 4.3.8) RO VERIFY proper RDCS light sequence.

INSERT light lit and then extinguishes 0.6 sec .
WITHDRAWAL and CONTINUOUS WITHDRAWAL lights lit

[S73.1.A 4.3.11] RO VERIFY SETTLE light lit and extinguishes 6.1 sec [S73.1.A 4.3.13) RO VERIFY control rod withdrawn to target position at Four Rod Display Select next control rod in sequence RO SEG-6217E RevOOO Page 19 of 55

LIMERICK GENERATING STATION

Exelon Generation SIMULATOR EXERCISE GUIDE

2. EVENT-2 CONTROL ROD (38-39) FAILS STUCK Simulator Operator Instructions:

Inform Floor Instructor prior to each event trigger. Respond to request for assistance as appropriate. When requested for Reactor Engineering support: Provide assistance as necessary. If asked, control rod (38-39) triple notch withdrawal is acceptable. When requested for l&C support provide assistance as necessary. When reactor operator makes several attempts to withdraw control rod (38-39) and has raised CRD Drive Water pressure, as directed by S73.1.A, step 4.4.4: AND at evaluators request: DELETE MRD016D Control Rod (38-39) fails stuck allowing control rod movement. SEG-6217E RevOOO Page 20 of 55

Exelon Generation LIMERICK GENERATING STATION SIMULATOR EXERCISE GUIDE TIME ASSESSMENT ITEMS AND TASK PERFORMANCE POSITION

2. EVENT-2 CONTROL ROD (38-39) FAILS STUCK Lead Evaluator (or designee) Notes: The following steps are directed per S73.1.A, Normal Operation Of The Reactor Manual Control System, for each Control Rod withdrawn, and if required, ON-104, Control Rod Problems.

Lead Evaluator (or designee) Notes: After reactor operator has raised CRD Drive Water Pressure per S73.1.A Attachment 5 THEN NOTIFY simulator driver to: DELETE Control Rod (38-39) stuck malfunction allowing control rod movement. NOTE: Control Rod movement requires a PEER CHECK prior to Control Rod movement. Recognize/report inability to withdraw control rod (38-39) RO NOTIFY CRS that a control rod (38-39) failed to move on a withdraw RO command CRS references Tech Spec 3.1.3.1 for Inoperable Control Rod. SRO CRS directs PRO to attempt rod withdraw IAW S73.1.A, Normal Operation Of SRO The Reactor Manual Control System section 4.4 [S73.1.A 4.4.1] RO VERIFY no rod block exists [S73.1.A 4.4.4] RO ATTEMPT several single notch withdrawals using WITHDRAW pushbutton Lead Evaluator (or designee) Notes: If control rod remains stuck and cannot be withdrawn per S73.1.A, Reactor Engineering will be contacted to determine if triple notching the control rod will violate thermal power or any thermal Limit. [S73.1.A 4.4.5] SRO IF control rod fails to reposition in step 4.4.4. THEN PERFORM the following:

1. IF the control rod is capable of performing a triple notch THEN DIRECT Reactor Engineering to perform an evaluation of consequences of an inadvertent triple notch control rod withdrawal.

2. IF an inadvertent triple notch control rod withdrawal is permissible AND IF control rod is at position 00, THEN PERFORM Attachment 5

[S73.1.A Step 4.4.5.3] RO IF an inadvertent triple notch control rod withdrawal is permissible OR IF control rod is at notch position 46, THEN PERFORM the following:

a. RAISE drive water pressure to 300 to 350 psid, as indicated on PDl-046-*R602, "Drive Water Differential Pressure Indicator."

b. ATTEMPT several single notch withdrawals using WITHDRAW pushbutton.

SEG-6217E RevOOO Page 21 of 55

LIMERICK GENERATING STATION

' Exelon Generation SIMULATOR EXERCISE GUIDE

2. EVENT-2 CONTROL ROD (38-39) FAILS STUCK Simulator Operator Instructions:

Inform Floor Instructor prior to each event trigger. Respond to request for assistance as appropriate. When requested for Reactor Engineering support: Provide assistance as necessary. If asked control rod (38-39) triple notch withdrawal is acceptable. When requested for l&C support provide assistance as necessary. When reactor operator makes several attempts to withdraw control rod (38-39) and has raised CRD Drive Water pressure, as directed by S73.1.A, step 4.4.4: AND at evaluators request: DELETE MRD016D Control Rod (38-39) fails stuck allowing control rod movement. SEG-6217E RevOOO Page 22 of 55

LIMERICK GENERATING STATION ,,::, Exelon Generation SIMULATOR EXERCISE GUIDE TIME ASSESSMENT ITEMS AND TASK PERFORMANCE POSITION

2. EVENT-2 CONTROL ROD (38-39) FAILS STUCK NOTIFY CRS that a control rod (38-39) has withdrawn on command RO

[S73.1.A 4.4.5.d] RO ENSURE drive water pressure restored to 255 to 265 psid The SRO calls out to WWM for support SRO Lead Evaluator (or designee) Notes: The control rod will successfully withdraw after drive water pressure is raised and the scenario may proceed to the next event (RHR Pump Suction leak). SEG-6217E RevOOO Page 23 of 55

LIMERICK GENERATING STATION ,,:!' Exelon Generation SIMULATOR EXERCISE GUIDE

3. EVENT-3 '1 D' RHR PUMP SUCTION LEAK Simulator Operator Instructions:

Inform Floor Instructor prior to each event trigger. Manually actuate Trigger # _1_ when directed by Lead Evaluator to activate Suppression Pool Leak into RHR Pump Room. At time 4 min When directed to investigate '1 B/1 D' RHR Pump room flooding alarm, report: There is approximately 4" of water on the floor. There is water spraying on the '1 D' RHR Pump motor it is coming from between the '1 D' RHR Pump suction valve and the pump." When the crew contacts the Radwaste Control Room, for RE Sump status: report: Both Unit 1 Reactor Enclosure Sump Pumps are running. At time 5 min activate Trigger#_§_ If crew requests breaker for '1 D' RHR Pump feeder breaker to be racked out, and report: '1 D' RHR Pump breaker has been racked out. At time 5 min activate Trigger #_7_ If crew requests breaker for '1 B' RHR Pump feeder breaker to be racked out, and report: '1 B' RHR Pump breaker has been racked out. After the crew has closed '1 D' RHR Pump suction valve to isolate the leak, DELETE MPC257, '1 D' RHR Pump suction leak. After the crew has taken action to close the '1 D' RHR Pump Suction Valve, report: The leak appears to have stopped and level in the room is lowering. SEG-621 lE RevOOO Page 24 of 55

=.....,,, Exelon Generation LIMERICK GENERATING STATION SIMULATOR EXERCISE GUIDE TIME ASSESSMENT ITEMS AND TASK PERFORMANCE POSITION

3. EVENT-3 '1 D' RHR PUMP SUCTION LEAK Lead Evaluator (or designee) Notes: The '1 D' RHR Pump Suction Valve from the Suppression Pool will develop a leak. The crew will enter and execute SE-4, Flood and T-103, and take action to close the '1 D' RHR Pump Suction Valve to stop the leak. The SRO will evaluate Tech Spec 3.5.1 for the out of service RHR Pump.

Respond to alarm: RO/PRO

127 H-4, REACTOR ENCLOSURE FLOOR DRAIN SUMP HI-HI WATER LEVEL
115 G-5, 1B-1 D RHR PUMP ROOM FLOOD

[ARC-MCR-115 G-5] PRO Dispatch EO/FSSV to '1 B/D' RHR Pump room to check for indications of leakage. [ARC-MCR-115 G-5] SRO Enter SE-4 following report of active leak in the RHR room [ARC-MCR-115 G-5] SRO Enter T-103 following report of active leak in the BID RHR Pump Room Establish Suppression Pool level as critical parameter SRO Enter T-102, Primary Containment Control when Suppression Pool level SRO outside of 22' to 24'3" Establish RHR Room flooding level as critical parameter SRO Monitor Suppression Pool level PRO Determine Suppression Pool level is lowering slowly PRO [T-103, SCC-4] SRO Direct performance of T-290, Instrumentation Available for T-103/SAMP-2 [ARC-MCR-127 H-4] PRO Contact Radwaste Control Room to verify operation of U 1 Reactor Enclosure Sump Pumps Re-enter T-103, Secondary Containment Control for Reactor Enclosure Floor SRO Drain alarm [SE-4-1 Att 1, T-103, SCC/L-4] SRO Direct performance of T-250 to isolate systems discharging into the '1 D' RHR Pump Room Place HV-51-1 F004D keyswitch to CLOSE as directed by T-250, section 4.6 PRO Direct floor personnel to rack out '1 D' RHR Pump feeder breaker Crew Enter Tech Spec 3.5.1.b.1 for INOP RHR subsystem (30 day LCO) SRO Enter Tech Spec 3.6.2.1.a for Suppression Pool level outside of 22' to 24'3" SRO Lead Evaluator (or designee) Notes: The scenario may advance to the next event (Loss of Div 2 DC) after the SRO determines actions for RHR '1 D' subsystem inoperability. SEG-621 lE RevOOO Page 25 of 55

--*,c' Exelon Generatior1 LIMERICK GENERATING STATION SIMULATOR EXERCISE GUIDE

4. EVENT - 4 LOSS OF DIV 2 DC (Abnormal)

Simulator Operator Instructions: Inform Floor Instructor prior to each event trigger. Manually actuate Trigger# .l_ when directed by Lead Evaluator to insert loss of DIV 2 DC. Respond to request for assistance as appropriate. At time 5 min after FSSV or EO action requested to investigate loss of DIV 2 DC report: A fault has occurred in the main fuse panel on Division 2 DC. I will contact Electrical Maintenance for support. At time 5 min after FSSV or EO action requested to investigate Steam Flooding Damper Panels 1OC234 and 1OC245 on loss of DIV 2 DC: report: On the 1OC234 and 1OC245 panels, all of the 'B' Steam Flooding Damper lights are off. All of the 'A' Steam Flooding Dampers on both panels indicate open." SEG-6217E RevOOO Page 26 of 55

--" Exelon Generation LIMERICK GENERATING STATION SIMULATOR EXERCISE GUIDE TIME ASSESSMENT ITEMS AND TASK PERFORMANCE POSITION

4. EVENT-4 LOSS OF DIV 2 DC (Abnormal)

Reference appropriate ARCs: RO/PRO

122 G-1, 1 UNIT DIV 2 SFGD BATTERY CHARGERS TROUBLE
122 G-2, 108-1 250V DC MCC UNDERVOLTAGE
122 G-3, 108-2 250V DC MCC UNDERVOLTAGE
122 G-4, 1PPB1/1PPB3125VDC DIST PANELS UNDERVOLTAGE
122 G-5, 1PPB2125VDC DC DIST PANEL UNDERVOLTAGE
122 D-1, 012 D-G TROUBLE
122 D-2, 012 STANDBY AC POWER SYS OUT OF SERVICE
122 E-3, DIV 2 MCC SHUNT TRIP COIL AUX CIRCUIT UNDERVOLTAGE
122 E-4, DIV 2 MCC SHUNT TRIP COIL UNDERVOLTAGE
122 F-4, 18 RPS & UPS DIST PNL. TROUBLE
122 A-5, 18 RPS & UPS STATIC INVERTER TROUBLE
002 F-4 & F-5, RE SFD PNLs 1OC245, 1OC243 TROUBLE
002 A-1, CONTROL ROOM RADIATION ISOLATION INITIATED
002 A-2, CONTROL ROOM CHLORINE ISOLATION INITIATED Recognize/report loss of Div 2 DC RO/PRO Enter and execute E-1 FB, Loss of Division 2 Safeguard 125/250 VDC Bus SRO 1FB Lead Evaluator (or designee) Notes: The following steps are directed in E-1FB, Loss of Division 2 Safeguard 125/250 voe Bus 1FB.

[E-1FB 1.1.3] SRO/PRO Loss of DC AND HPCI Aux Oil Pump indications on 1O-C647 HPCI [E-1 FB 1.2] SRO/PRO Refer to E-1 FB Attachment 1 for Confirming Indication Annunciators for loss of DIV2 DC [E-1 FB 2.2] PRO REFER to Attachment #3 and VERIFY RE/RF isolations per S76.9.A, Verification of Reactor Enclosure or Refueling Floor Secondary Containment Isolation Verify SBGT and RERS fan start and maintain Secondary Containment due PRO to Reactor Enclosure and Refueling Floor Secondary Containment Isolation [E-1 FB 2.3] PRO REFER to S94.2.B, By-passing and Removing the *B RPS and UPS Static Inverter from Service, and remove '1 B' RPS/UPS Inverter from service [E-1 FB 3.2] PRO Dispatch appropriate personnel to investigate loss of Div 2 DC SEG-6217E RevOOO Page 27 of 55

  ..-i, LIMERICK GENERATING STATION

Exelon Generation SIMULATOR EXERCISE GUIDE: 4. EVENT - 4 LOSS OF DIV 2 DC (Abnormal)

Simulator Operator Instructions: Respond to request for assistance as appropriate. Inform Floor Instructor prior to each event trigger. At time 5 min after FSSV or EO action requested to investigate loss of DIV 2 DC report: A fault has occurred in the main fuse panel on Division 2 DC. I will contact Electrical Maintenance for support. At time 5 min after FSSV or EO action requested to investigate Steam Flooding Damper Panels 1OC234 and 1OC245 on loss of DIV 2 DC: report: On the 1OC234 and 1OC245 panels, all of the 'B' Steam Flooding Damper lights are off. All of the 'A' Steam Flooding Dampers on both panels indicate open." SEG-6217E RevOOO Page 28 of 55

LIMERICK GENERATING STATION ~* Exelon Generation SIMULATOR EXERCISE GUIDE TIME ASSESSMENT ITEMS AND TASK PERFORMANCE POSITION

4. EVENT-4 LOSS OF DIV 2 DC (Abnormal)

[E-1 FB 3.5] PRO Dispatch floor personnel to Steam Flooding Damper panels 1OC234 and 10C245 [E-1FB 2.1] CRS Direct to Manually INITIATE MCR Chlorine Isolation per Attachment #2 Lead Evaluator (or designee) Notes: The following steps are directed in E-1 FB, Loss of Division 2 Safeguard 125/250V DC Bus 1FB (Attachment #2) for 'A' Subsystem [E-1 FB Att #2 1.1] PRO ENSURE the following; HS-078-010A, OA-V127 in AUTO HS-078-010B, OB-V127 in STANDBY [E-1 FB Att #2 1.2] PRO Place HS-78-017C in RESET C to RESET Place HS-78-017A in RESET A to RESET [E-1 FB Att #2 1.3] PRO Place HSS-78-017C, TRIP C to Cl2 Place HSS-78-017A, TRIP A to Cl2 [E-1 FB Att #2 1.4] PRO Place HS-78-017C in RESET C to AUTO Place HS-78-017A in RESET A to AUTO [E-1 FB Att #2 1.4] PRO Depress and Release HSS-78-017C, TRIP C Depress and Release HSS-78-017A, TRIP A [E-1 FB Att #2 1.7] PRO ENSURE CHLOR ISLN Channel A, C amber lights are Lit [E-1 FB Att #2 1.8] PRO VERIFY annunciator 002 A-3, CONTROL ROOM ISOLATION NOT COMPLETE not alarmed after 25 second T/D. ENSURE the following are running: PRO

OA-V127, Emergency Air Fan A
OA(B)-V116, Control Room Air Supply Fan A(B)
OA(B)-V121, Control Room Air Return Fan A(B)

[E-1 FB Att #2 1.12] PRO VERIFY PDl-078-054, Control Room Air Inside/Outside at O" water after T/D SEG-6217E RevOOO Page 29 of 55

Exelon Generation LIMERICK GENERATING STATION SIMULATOR EXERCISE GUIDE

4. EVENT - 4 LOSS OF DIV 2 DC (Abnormal)

Simulator Operator Instructions: Respond to request for assistance as appropriate. Inform Floor Instructor prior to each event trigger. SEG-6217E RevOOO Page 30 of 55

LIMERICK GENERATING STATION

' . Exelon Generation SIMULATOR EXERCISE GUIDE TIME ASSESSMENT ITEMS AND TASK PERFORMANCE POSITION: 4. EVENT-4 LOSS OF DIV 2 DC (Abnormal)

Lead Evaluator (or designee) Notes: The following steps are directed in E-1 FB, Loss of Division 2 Safeguard 125/250V DC Bus 1FB (Attachment #2) for 'B' Subsystem [E-1 FB Att #2 2.1] PRO Place HS-78-017D in RESET D [E-1 FB Att #2 2.2] PRO Place HSS-78-017D, TRIP D to CL2 [E-1 FB Att #2 2.3] PRO Place HS-78-017D in AUTO [E-1 FB Att #2 2.4] PRO Depress and Release HSS-78-017D, TRIP D [E-1 FB Att #2 2.5] PRO ENSURE CHLOR ISLN Channel D amber lights are Lit Lead Evaluator (or designee) Notes: The following steps are directed in E-1 FB, Loss of Division 2 Safeguard 125/250V DC Bus 1FB (Attachment #3) for RE/RF isolations [E-1 FB Att #3 1.1] PRO VERIFY Channel B Rx Enclosure isolation signal initiated by:

004 F-1, B REAC ENCL ISOLATION SIGNAL INITIATED

[E-1 FB Att #3 1.2] PRO VERIFY Channel A and B Rx Enclosure HVAC isolation valves have repositioned by alarms NOT alarmed:

004 E/F-2, NB REAC ENCL !SOLATION NOT COMPLETE

[E-1 FB Att #3 1.4] PRO ENSURE "B" SGTS FAN is running at OO-C681 [E-1 FB Att #3 1.6] PRO VERIFY RERS flow by checking PDl-076-1898 at ~3 inches W.G [E-1 FB Att #3 2.2] PRO VERIFY Channel A and B Rx Enclosure HVAC isolation valves have repositioned by alarms NOT alarmed:

004 E/F-4, NB REFUELING FLOOR ISOLATION NOT COMPLETE CRS briefs crew on impact of loss of DIV 2 DC including inability to remotely SRO or automatically start:

             * '18' RHR                            * 'OB' RHRSW
             * '1 B' Core Spray                    * '18' SBLC

HPCI
D12 Diesel Generator

             * '18' ESW SEG-6217E RevOOO                                                                      Page 31 of 55

LIMERICK GENERATING STATION ,=.** Exelon Generation SIMULATOR EXERCISE GUIDE

4. EVENT - 4 LOSS OF DIV 2 DC (Abnormal)

Simulator Operator Instructions: Respond to request for assistance as appropriate. Inform Floor Instructor prior to each event trigger. SEG-6217E RevOOO Page 32 of 55

=, Exelon Ger1eration LIMERICK GENERATING STATION SIMULATOR EXERCISE GUIDE TIME ASSESSMENT ITEMS AND TASK PERFORMANCE POSITION

4. EVENT-4 LOSS OF DIV 2 DC (Abnormal)

Lead Evaluator {or designee) Notes: The following Tech Specs will be entered as directed by E-1FB, due to loss of DIV 2 DC depending on time allotted: Initiate temporary LCO Log to include the following: SRO

3.8.2.1.c DC Sources (2 hr. LCO)
3.8.3.1.b Onsite Power Distribution (8 hr. LCO)
3.5.1, HPCI
3.1.5 SLC
3.3.4.1 RRCS/AlWS RPT Breakers
3.3.3/3.5.1 ADS
3.5.1 Core Spray / RHR
3.7.1.2 ESW
3.8.1.1 One Offsite Source and D12 Diesel Generator Evaluate the following TS: SRO
3.8.2.1.c DC Sources (2 hr. LCO)
3.0.3 both offsite sources and one EOG
3.0.6 provided safety function determined to be functional Lead Evaluator {or designee) Notes: After the SRO has determined the Div 2 DC Tech Spec implications, the scenario may advance to the next event (RPS level transmitter failure).

SEG-6217E RevOOO Page 33 of 55

_,- Exelon Generation LIMERICK GENERATING STATION SIMULATOR EXERCISE GUIDE

4. EVENT-5 RPS LEVEL TRANSMITTER FAILURE Simulator Operator Instructions:

Inform Floor Instructor prior to each event trigger. Respond to request for assistance as appropriate. Manually actuate Trigger# .1... when directed by Lead Evaluator to initiate RPV level transmitter failure. At time 5 min after FSSV or EO action requested to investigate RPS Level Trip units in AER, report: LIS-042-1 N680A is indicating downscale. When the crew has inserted the manual scram; DELETE MRP029A, "RPS Fails to Scram, Auto Only". SEG-6217E RevOOO Page 34 of 55

--*---- Exelon Generation LIMERICK GENERATING STATION SIMULATOR EXERCISE GUIDE TIME ASSESSMENT ITEMS AND TASK PERFORMANCE POSITION

5. EVENT-5 RPS LEVEL TRANSMITTER FAILURE Lead Evaluator (or designee) Notes: RPS reactor level transmitter (LIS-042-1 N680A) fails downscale. The failed RPS instrument will result in a failed RPS channel (Will fail to de-energize).

Reference appropriate ARC: RO

107 H-1, REACTOR WATER BELOW LEVEL 3 TRIP Verify Rx level normal with RPS low level transmitter alarm RO Recognize failure to Yi scram on 'A' RPS and inform CRS RO Dispatch an EO to investigate the Rx level transmitter PRO/RO Enter OT-117, RPS Failures, for failure to Yi scram on 'A' RPS SRO

[OT-117 3.2.1] SRO DIRECT Insert manual Yi scram on 'A 1' Side PERFORM Arm and depress 'A 1' RPS RO [OT-117 3.2.1.2] RO Recognize SCRAM lights off on 'A 1' RPS [OT-117 3.2.1.2] SRO LEAVE half SCRAM in [OT-117 3.2.1.2] SRO NOTIFY Senior Plant Staff Member [OT-117 3.2.1.2] SRO INITIATE investigation Enter TS 3.3.1 action a. to identify the minimum number of Rx level channels SRO is 2 per trip system. The SRO calls out to WWM for support SRO SEG-6217E RevOOO Page 35 of 55

...... Exelon Gener*ation LIMERICK GENERATING STATION SIMULATOR EXERCISE GUIDE

6. EVENT- 6 COOLANT LEAK IN DRYWELL Simulator Operator Instructions:

Respond to request for assistance as appropriate. Inform Floor Instructor prior to each event trigger Manually actuate Trigger# ~ when directed by Lead Evaluator to initiate small coolant leak in the Drywell. At time 11 min after FSSV or EO action requested for T-221, perform the following: Toggle Remote Function RTR051 to "BYPASS" and report (via phone): T-221 is complete on Unit 1. At time 7 min OR immediately if pre-staged for at least 7 minutes after FSSV or EO action requested for T-270, manually perform T-270 as follows: Toggle Remote Functions RTR220 through RTR227 to "TEST" OR load the ?-minute T-270 file from the Ops Training Scenarios\Remotes folder and report (via phone): Section 4.6 of T-270 is complete At time 6 min after FSSV or EO action requested for implementation of T-251; contact MCR: and have Operators verify that HV-055-1 F006 indicates closed in the MCR AND perform the following: Toggle Remote Function RTR309 to "OPEN" and report: T-251 is complete in the field SEG-6217E RevOOO Page 36 of 55

~ Exelon Generation LIMERICK GENERATING STATION SIMULATOR EXERCISE GUIDE TIME ASSESSMENT ITEMS AND TASK PERFORMANCE POSITION

6. EVENT- 6 COOLANT LEAK IN DRYWELL Lead Evaluator (or designee) Notes: A coolant leak in the drywell causes the crew to recognize rising drywell pressure and execute OT-101 for rising drywell pressure including isolating RWCU.

When Drywell pressure approaches the scram setpoint, the crew should perform a GP-4, Rapid Plant Shutdown to Hot Shutdown, or manually scram the reactor. Reference appropriate ARCs: RO/PRO

115 B-5, DRYWELL COOLER DRAIN FLOW HIGH
115 E-5, FLOOR DRAIN LEAKAGE HI FLOW
003 B-2, Unit 1&2 CONTAINMENT LEAK DETECTOR HI RADIATION
112 C-5, DRYWELL EQUIPMENT DRAIN TANK/FLOOR DRAIN SUMP LEAKAGE HI FLOW
107 F-2, DRYWELL HI / LO PRESS Check D/W Cooler Drain flow Fl-87-120 at 10C624 panel for high flow. PRO Proceed as directed by ARC using S61.0.A to panel OOC424 to identify PRO leakage (time permitting)

Crew recognizes/reports rising Drywell pressure Crew CRS enters OT-101, High Drywell Pressure SRO Lead Evaluator (or designee) Notes: The following steps are directed by OT-101, High Drywell Pressure. [OT-101, 3.1] SRO Establish Drywell pressure as Critical Parameter Notifies RO of Drywell pressure and when to perform manual scram SRO [OT-101, 3.3] SRO Direct OT-101, High Drywell Pressure Attachment. 4 [OT-101, Att. 4] PRO ENSURE the Main Steam and Recirc sample/drains valves closed: [OT-101, Att. 4] PRO PRO secures and isolates RWCU (time permitting) SECURE operating RWCU pump(s) ENSURE the following valves closed:

HV-C-044-1 F033
HV-44-1 F001, INBD
HV-44-1 F004, OUTBD
HV-44-1F100, BOTTOM HEAD DRAIN
HV-44-1F105, INLET FLOW SEG-6217E RevOOO Page 37 of 55

Exelon Generatior1 LIMERICK GENERATING STATION SIMULATOR EXERCISE GUIDE

6. EVENT- 6 COOLANT LEAK IN DRYWELL Simulator Operator Instructions:

Respond to request for assistance as appropriate. Inform Floor Instructor prior to each event trigger At time 11 min after FSSV or EO action requested for T-221, perform the following: Toggle Remote Function RTR051 to "BYPASS" and report (via phone): T-221 is complete on Unit 1. At time 7 min OR immediately if pre-staged for at least 7 minutes after FSSV or EO action requested for T-270, manually perform T-270 as follows: Toggle Remote Functions RTR220 through RTR227 to "TEST" OR load the 7-minute T-270 file from the Ops Training Scenarios\Remotes folder and report (via phone): Section 4.6 of T-270 is complete At time 6 min after FSSV or EO action requested for implementation of T-251; contact MCR: and have Operators verify that HV-055-1 F006 indicates closed in the MCR AND perform the following: Toggle Remote Function RTR309 to "OPEN" and report: T-251 is complete in the field SEG-6217E RevOOO Page 38 of 55

~-                                LIMERICK GENERATING STATION

- Exelon Generation SIMULATOR EXERCISE GUIDE TIME ASSESSMENT ITEMS AND TASK PERFORMANCE POSITION

6. EVENT- 6 COOLANT LEAK IN DRYWELL Lead Evaluator (or designee) Notes The following steps are directed by GP-4, Rapid Plant Shutdown to Hot Shutdown, T-101, RPV Control, and T-102, Primary Containment Control.

[OT-101, Att. 4] SRO/RO Crew recognizes that Drywell pressure continues to rise following RWCU isolation Direct GP-4 Rapid Plant Shutdown SRO [GP-4 3.1] TRANSFER house loads to startup buses per S91.6.B, Transferring house Loads To S/U Buses [GP-4 3.2] RO REDUCE Rx Recirculation system pump speed to minimum [GP-4 3.3] RO WHEN core flow reduces to nominal 60% THEN immediately SCRAM Rx AND ENTER T-100, Scram Recovery OR T-101, RPV Control (core flow is

          <60%)

Enter T-101 and T-102 on Hi Drywell Pressure SRO [T-101 RC-4] RO Place Mode Switch in SHUTDOWN Recognize Control Rods failed to insert on scram RO SEG-6217E RevOOO Page 39 of 55

Exelon Generation LIMERICK GENERATING STATION SIMULATOR EXERCISE GUIDE 7-9. EVENTS 7 - 9 ATWS / RDCS INOP / SRV FAILS OPEN Simulator Operator Instructions: Respond to request for assistance as appropriate. Inform Floor Instructor prior to each event trigger Ensure Trigger#_§__ automatically actuates when RMS taken to SD to initiate RDCS INOP and SRV failure. SEG-6217E RevOOO Page 40 of 55

LIMERICK GENERATING STATION ,:: Exelon Generation SIMULATOR EXERCISE GUIDE TIME ASSESSMENT ITEMS AND TASK PERFORMANCE POSITION 7-9. EVENTS 7 -9 ATWS / RDCS INOP / SRV FAILS OPEN Lead Evaluator (or designee) Notes: As a result of the coolant leak in the drywell, a reactor shutdown is required. On the scram the Control Rods will fail to insert, resulting in an ATWS. The CRS will take actions to mitigate the ATWS while addressing the increasing drywell pressure. The RO will to recognize the failure of RDCS and call out for floor assistance in resetting RDCS in the AER. Once RDCS is reset, the crew is expected to manually insert control rods to help mitigate the ATWS condition. Enter T-101, RPV Control on Scram Condition with power> 4% RO [T-101 RC-6) RO Insert SRMs/lRMs [T-101 RC/Q-5) RO Initiate RRCS (Malfunction) Verify after 118 seconds after RRCS initiation SLC pumps start and inject RO Recognize failure of SLC Pumps RO Manually attempt SLC injection including '1C' SLC Pump RO Recognize/report SLC low discharge pressure RO Direct securing SLC SRO Secure SLC pumps RO [T-101 RC/Q-8) (May have been completed previously by GP-4) RO Runback Recirc pumps to minimum with 28% runback pushbutton [T-101 RC/Q-10) RO Trip both Recirc pumps at least 10 seconds apart Verify position of scram valves are open RO [T-101 RC/Q-13) SRO Direct performance of T-217,RPS/ARI Reset and Backup Method Of Draining Scram Discharge Volume (Critical Task) [T-101 RC/Q-13) SRO Direct performance of T-218, Control Rod Insertion By Withdraw Line Venting Reference appropriate ARC: PRO

108 E-4, RDCS INOPERATIVE Recognize and report RDCS INOP alarm RO Direct RDCS Reset in AER (Malfunction) RO When RDCS Reset in the MCR manually insert control rods RO SEG-6217E RevOOO Page 41 of 55

LIMERICK GENERATING STATION SIMULATOR EXERCISE GUIDE 7-9. EVENTS 7 - 9 ATWS / RDCS INOP / SRV FAILS OPEN Simulator Operator Instructions: Respond to request for assistance as appropriate. Inform Floor Instructor prior to each event trigger At time 11 min after FSSV or EO action requested for T-221, perform the following: Toggle Remote Function RTR051 to "BYPASS" and report (via phone): T-221 is complete on Unit 1. At time 7 min OR immediately if pre-staged for at least 7 minutes after FSSV or EO action requested for T-270, manually perform T-270 as follows: Toggle Remote Functions RTR220 through RTR227 to "TEST" OR load the 7-minute T-270 file from the Ops Training Scenarios\Remotes folder and report (via phone): Section 4.6 of T-270 is complete SEG-6217E RevOOO Page 42 of 55

LIMERICK GENERATING STATION ~* Exelon Generation SIMULATOR EXERCISE GUIDE TIME ASSESSMENT ITEMS AND TASK PERFORMANCE POSITION 7-9. EVENTS 7 -9 ATWS / RDCS INOP / SRV FAILS OPEN

 ~     [T-101 RC/Q-19-0R- T-117 LQ/5]                                               PRO Inhibit Auto ADS (Critical Task)

[T-101 RC/Q-20] SRO Direct performance of T-209, Injection From SLCS (SLC) Storage Tank With The RCIC System Stabilize RPV pressure PRO Enter and execute T-117, Level/Power Control SRO [T-101 RC/P-11] SRO Direct performance of T-221, MSIV Isolation Bypass Procedure, to personnel outside Main Control Room (MCR) [T-117 LQ/7] SRO Direct to establish RPV level< -50 inches performing T-270, Terminate And Prevent Injection Into the RPV. Direct performance of Section 4.6 of T-270 to personnel outside Main Control PRO Room (MCR). [T-270 4.2.1] PRO IF HPCI initiation signal is present - (HPCI INOP due to loss of DIV 2 DC). [T-270 4.4.1] RO ENSURE HV-06-138A, (BYPASS) is closed. [T-270 4.4.2] RO ENSURE LIC-06-138, (STARTUP BYPASS) in Manual and set to 0% [T-270 4.4.3] RO ENSURE LIC-06-120, (PUMP BYPASS) in Manual and set to 0% at [T-270 4.4.4] RO ENSURE FIC-M1-1 R601A, B, C "A,B,C RFPT Speed Controller in Manual for all three RFPTs [T-270 4.4.5] RO DEPRESS EMERGENCY STOP pushbutton for ALL AVAILABLE RFPTs at panel 1OC603 [T-270 4.4.6] RO WHEN the emergency stop light goes out, THEN DEPRESS AUTO START pushbutton for ALL AVAILABLE RFPTs SEG-621 lE RevOOO Page 43 of 55

LIMERICK GENERATING STATION ,=;' Exelon Generation SIMULATOR EXERCISE GUIDE 7-9. EVENTS 7-9 ATWS / RDCS INOP / SRV FAILS OPEN Simulator Operator Instructions: Respond to request for assistance as appropriate. Inform Floor Instructor prior to each event trigger SEG-6217E RevOOO Page 44 of 55

LIMERICK GENERATING STATION

Exelon Generation SIMULATOR EXERCISE GUIDE TIME ASSESSMENT ITEMS AND TASK PERFORMANCE POSITION 7-9. EVENTS 7-9 ATWS / RDCS INOP / SRV FAILS OPEN

[T-270 4.4.7] RO CLOSE HV-06-108A, "1A RFP Discharge" [T-270 4.4.8] (following closure of HV-06-108A) RO CLOSE HV-06-1088, "18 RFP Discharge" [T-270 4.4.9] (following closure of HV-06-1088) RO CLOSE HV-06-108C, "1C RFP Discharge" Stabilize RPV level between -60" and -100" RO [T-101 RC-5] PRO Isolations verified for +12.5" and -38" and 1.68 psig drywell pressure [T-117 LQ/18] SRO Recognize T-251, Establish A HPCI Injection Flow Path via Feedwater Only is unavailable due to loss of DIV 2 DC SEG-6217E RevOOO Page 45 of 55

=* Exelon Generation LIMERICK GENERATING STATION SIMULATOR EXERCISE GUIDE 7-9. EVENTS 7 -9 ATWS / RDCS INOP / SRV FAILS OPEN Simulator Operator Instructions: Respond to request for assistance as appropriate. Inform Floor Instructor prior to each event trigger At time 5 min after FSSV or EO action requested to reset RDCS DELETE MRD024 and toggle RRD001 to RESET and report: "RDCS has been reset in the AER" At time 6 min after FSSV or EO action requested to pull fuses for '1J' SRV per OT-114 Attachment #1 Toggle Remote Function RADS212 to OUT and; report (via phone): "The fuses for the '1 J' SRV have been removed per OT-114." SEG-6217E RevOOO Page 46 of 55

LIMERICK GENERATING STATION

."'. Exelon Generation SIMULATOR EXERCISE GUIDE TIME ASSESSMENT ITEMS AND TASK PERFORMANCE POSITION 7-9. EVENTS 7 -9 ATWS / RDCS INOP / SRV FAILS OPEN Lead Evaluator (or designee) Notes: After Rx level is lowered below -50", the '1J' SRV will fail open mechanically adding heat to the Suppression Pool. The crew should enter OT-114 and attempt SRV closure by removing fuses to the SRV.

The crew, with drywell pressure increasing and during a high power ATWS, is expected to place RHRSW in service. The following steps are directed by S 12.1.A, RHR Service Water System Startup followed by, S51.8.A, Suppression Pool Cooling Operation (Startup and Shutdown) and Level Control. [B RHRSW and B RHR are unavailable due to loss of DIV2] Reference appropriate ARC: PRO

110 B-1, SRV/HEADVENTVALVE LEAKING
110 B-2, SAFETY RELIEF VALVE OPEN Enter OT-114, Inadvertent Opening Of A Relief Valve SRO

[OT-114 IOA] RO/PRO CONFIRM SRV is open ('1J' SRV confirmed open) [OT-114 IOA] PRO PLACE both loops of Suppression Pool Cooling in service [B RHR unavailable due to loss of DIV2] [OT-114 3.1] PRO DISPATCH EO to attempt SRV closure by pulling fuses for 1J SRV per Att #1 Re-enter T-102, Primary Containment Control on Supp Pool Temp> 95°F SRO Establish Suppression Pool Temperature as a Critical Parameter SRO

  ~      [T-102 SP/T-2]                                                                PRO Place Two Loops of Suppression Pool Cooling in service per S51.8.A, Suppression Pool Cooling Operation (Startup And Shutdown And Level Control) [B RHR unavailable due to loss of DIV 2 DC]

START selected RHR Service Water Pump loop per S12.1.A, RHR Service PRO Water System Startup [B RHRSW unavailable due to loss of DIV2] [S12.1.A 4.1.4 or App #2 1.3/1.4] PRO OPEN HV-51-1F014A(B), HEAT EXCHANGER INLET [S12.1.A 4.1.5 orApp#2 1.3/1.4] PRO Throttle OPEN HV-51-1F068A(B) for 18 to 20 seconds [S 12.1.A 4.1.6(7) or App #2 1.5/1.6] PRO VERIFY Pl-51-105A-1(B), HX DISCH, indicates system static pressure greater than or equal to 15 psig [S12.1.A 4.1.8 or App #2 1.7] PRO IF the HI RAD AND/OR HI Pump Discharge pressure trips need to be bypassed AND the required actions of ODCM Part 1 Control 3.1.1 have been met for the INOPERABLE RHRSW Radiation Monitor, THEN PLACE HSS-12-002A(B), PUMP TRIP BYPASS, in "BYPASS" SEG-6217E RevOOO Page 47 of 55

---* Exelon Generation LIMERICK GENERATING STATION SIMULATOR EXERCISE GUIDE 7-9. EVENTS 7 - 9 ATWS / RDCS INOP / SRV FAILS OPEN Simulator Operator Instructions: Respond to request for assistance as appropriate. Inform Floor Instructor prior to each event trigger At time 10 min after FSSV or EO action requested to perform SE-10 Floor Actions Load All SE-10 Floor Actions with Time Delays Scenario and, report: status of individual resets as requested or when all resets are timed out OR report: "All SE-10 Floor Actions are complete." When FSSV or EO action requested for T-217, and when RPV level is below -50 inches, toggle Remotes RTR181 and RTR303 to BYPASS and report (via phone): Steps 4.1.1 thru 4.1.6 of T-217 have been completed in the Auxiliary Equipment Room. We are ready for the MCR to perform Steps 4.1. 7 through 4.1.10. When RPV level is being maintained between -161 inches and -186 inches and Lead Evaluator directs, perform the following: Verify MCR performs Steps 4.1. 7 through 4.1.10 of T-217 AND SDV Level is less than 25 gallons indicated level in the simulator, and report (via phone): Step 4.1.12 of T-217, all SDV level indications are less than 62% and Step 4.2.1 is complete. We are continuing with Step 4.2.2 of T-217. Expect control rod motion. DRIVER NOTES: DELETE MAD145E, '1J' SRV Fails open, after RPV level drops to <-161" DELETE MRP029A, "RPS Fails to Scram, Auto Only" prior to attempting control rod insertion. (These malfunctions do not work together). Insert Control Rods per T-217 as Follows: DELETE MRD556, Hydraulic ATWS; AND Toggle Remote Function RTR181 to "Normal" (control rods will insert) SEG-6217E RevOOO Page 48 of 55

Exelon Gener,ation LIMERICK GENERATING STATION SIMULATOR EXERCISE GUIDE TIME ASSESSMENT ITEMS AND TASK PERFORMANCE POSITION 7-9. EVENTS 7 -9 ATWS / RDCS INOP / SRV FAILS OPEN

[S12.1.A 4.2.1 or App #2 1.8 / 1.9] PRO START OA(B,C,D)V543 Spray Pond Room Fan [S12.1.A 4.2.2 orApp#1 1.10/1.12] PRO START OA(B,C,D)P506, RHRSW PUMP [B RHRSW loop unavailable due to loss of DIV2 DC] [S12.1.A 4.2.3 orApp#1 1.11/1.13] PRO THROTTLE HV-51-1F068A(B) to the maximum obtainable position without exceeding 11,000 gpm on Fl-51-1 R602A(B) while maintaining pump disch pressure (Pl-12-001A-1(B)) between 75 psig to 85 psig [S51.8.A App #1 step 1.4) PRO START 1A(B)P202, RHR Pump (PUMP) [B RHR unavailable due to loss of DIV2 DC] [S51.8.A App #1 step 1.5) PRO OPEN HV-51-1 F024A(B) "RHR Pump Full Flow Test Return" (SUPP POOL CLG), AND MAINTAIN flow indicated on Fl-51-1R603A(B), "RHR Loop Flow" between 8000 to 8500 gpm [S51.8.A App #1 step 1.6) PRO CLOSE HV-C-51-1F048A(B), HEAT EXCH BYPASS When SP temperature reaches 110 °F DIRECT perform T-270 to lower level SRO until -161, SRV closed or <4% power Perform T-270 to lower level until -161, SRV closed or <4% power PRO/RO (Critical Task) Re-perform T-270 steps to Emergency Stop Reactor Feed Pumps RO Lead Evaluator (or designee) Notes: The following steps are from SE-10, LOCA and are performed at the SAFEGUARDS PANEL (Diesel Panel). NOTE: Failure of DIV 2 DC will eliminate the need for closing the 52-20124/CS, "0*24 Safeguard LC. 0*24-G-D MCC Breaker" (SAFEGUARDS A), on *BC661 Enter SE-10, LOCA during performance of T-270 for -129" LOCA signal Crew [SE-10 3.1) RO PLACE the following to "CLOSE"

52-20124/CS, "0*14 Safeguard L.C. 0*14-G-D MCC Bkr" (SAFEGUARDS A), on *AC661.

[SE-10 3.2) RO PLACE to "RESET":

43-22322/CS, "Div. 111 Non SFGD Instr. Panel" (INST AC 201 CONTROL PNL), on *CC661
43-22422/CS, "Div. IV Non SFGD Instr. Panel" (INST AC 202 CONTROL PNL), on *DC661.

SEG-6217E RevOOO Page 49 of 55

- ~

, ._ Exelon Generation LIMERICK GENERATING STATION SIMULATOR EXERCISE GUIDE 7-9. EVENTS 7 - 9 ATWS / RDCS INOP / SRV FAILS OPEN Simulator Operator Instructions: Respond to request for assistance as appropriate. Inform Floor Instructor prior to each event trigger At time 10 min after FSSV or EO action requested to perform SE-10 Floor Actions Load All SE-10 Floor Actions with Time Delays Scenario and, report: status of individual resets as requested or when all resets are timed out OR report: "All SE-10 Floor Actions are complete." When FSSV or EO action requested for T-217, and when RPV level is below -50 inches, toggle Remotes RTR181 and RTR303 to BYPASS and report (via phone): Steps 4.1.1 thru 4.1.6 of T-217 have been completed in the Auxiliary Equipment Room. We are ready for the MCR to perform Steps 4.1. 7 through 4.1.10. When RPV level is being maintained between -161 inches and -186 inches and Lead Evaluator directs, perform the following: Verify MCR performs Steps 4.1.7 through 4.1.10 of T-217 AND SDV Level is less than 25 gallons indicated level in the simulator, and report (via phone): Step 4.1.12 of T-217, all SDV level indications are less than 62% and Step 4.2.1 is complete. We are continuing with Step 4.2.2 of T-217. Expect control rod motion. DRIVER NOTES: DELETE MAD145E, '1J' SRV Fails open, after RPV level drops to <-161" DELETE MRP029A, "RPS Fails to Scram, Auto Only" prior to attempting control rod insertion. (This malfunction with T-217 do not work together). Insert Control Rods per T-217 as Follows: DELETE MRD556, Hydraulic A TWS; AND Toggle Remote Function RTR181 to "Normal" (control rods will insert) Re-INSERT MRD024, RDCS INOP, when Rx power reaches 20% power. SEG-6217E RevOOO Page 50 of 55

LIMERICK GENERATING STATION ~* Exelon Gener-at ion SIMULATOR EXERCISE GUIDE TIME ASSESSMENT ITEMS AND TASK PERFORMANCE POSITION 7-9. EVENTS 7-9 ATWS / RDCS INOP / SRV FAILS OPEN Lead Evaluator (or designee) Notes: The scenario is terminated when RPV level has been maintained -186" to -161", followed by Control Rods inserted per T-217, RPS/ARI Reset and Backup Method Of Draining Scram Discharge Volume. After the scenario is terminated, direct the SRO to make the highest EAL classification for the scenario. Dispatch Equipment Operator to perform SE-10-1 field actions PRO Re-inject with Feedwater when RPV level is< -161" (TAF) and stabilize level RO between -186" and -161" RPV level restored and stabilized between -186 and -161 inches RO (Critical Task) MCR notified of expected control rod movement and recognize all rods in due RO to T-217, RPS/ARI Reset and Backup Method Of Draining Scram Discharge Volume (Critical Task) Secure SLC Pumps that restart on LOCA Signal RO Exit T-117 when all Control Rod inserted SRO Isolations verified for -129" RPV level PRO Stabilize level with the core covered after rod insertion to maintain the RO cooldown rate Slowly raise Reactor Level Band 12.5" to 54" RO SEG-6217E RevOOO Page 51 of 55

_,......, Exelon Generation LIMERICK GENERATING STATION SIMULATOR EXERCISE GUIDE Attachment 1 Simulator Operator Response Times

Response

Procedure Performance Time (Minutes) T-209 Injection from the Standby Liquid Control Storage Tank with the RCIC 45 System T-212 Bypassing SQUIB Valves for SLC Injection 19 T-215 De-energization of Scram Solenoids 7 T-216 Manual Isolation and Vent of Scram Air Header 7 T-217 RPS/ARI Reset and Backup Method of Draining Scram Discharge 17 Volume T-219 Maximizing CRD Cooling Water Header Flow during ATWS Conditions 23 T-221 MSIV Isolation Bypass Procedure 11 T-225 Startup and Shutdown of Suppression Pool and Drywell Spray 8 Operations T-240 Maximizing CRD flow after Shutdown During Emergency Conditions 8 T-245 RPV Injection from RHR S/D Cooling 12 T-248 Injection from SLC Test Tank to RPV 15 T-251 Establish a HPCI Injection flow Path VIA Feedwater Only 6 T-270 Terminate and Prevent Injection into the RPV 7 T-290 Instrumentation Available for T-103 SAMP-2 5 S46.7.A Control Rod Drive Hydraulic System Operation Following Reactor (4.2.1) Scram (Securing CRD flow to the Reactor - Close 46-1 F060, CRD 7 Water Pressure Control Station Inlet Valve) SE-10-1 Breaker Reset Following LOCA (Also reset ARMs, RHRSW Rad Resets and Monitor and RDCS) 10 Floor action SEG-6217E RevOOO Page 52 of 55

Exelon Generation LIMERICK GENERATING STATION SIMULATOR EXERCISE GUIDE Attachment 2 Communications Log CREW: ----

DATE: _ _ __ LSEG: _ _ __ START T I M E : - - - - - STOP T I M E : - - - - SM: RO: WCS: CRS: - - - - - PRO: - - - - - FSSV: - - - - - - PERSON CALL PERSON TIME BEING COMMUNICATION / REQUEST BACK CALLING CALLED TIME SEG-6217E RevOOO Page 53 of 55

=* Exelon Gener-ation LIMERICK GENERATING STATION SIMULATOR EXERCISE GUIDE THIS PAGE INTENTIONALLY LEFT BLANK SEG-6217E RevOOO Page 54 of 55

LIMERICK GENERATING STATION

Exelon Gener*ation SIMULATOR EXERCISE GUIDE XI. CREW PREBRIEF INSTRUCTIONS Unit 1 Reactor Power is 75%

Unit 2 Reactor Power is 100% Specific Plant Conditions are as Follows:

None Inoperable/Out of Service Equipment and Estimated Time of Return (ETR):
None Restrictions on Plant Operations:
None Planned Evolutions:
Restore Unit 1 power to 100% by withdrawing Control Rods and raising Core flow
Reactor Engineering has determined there are no known Channel Distorted Control Rods.

Documents Provided:

ReMA
GP-5, Appendix #2 completed to step 3.2.22
S73.1.A, Normal Operation Of The Reactor Manual Control System SEG-6217E RevOOO Page 55 of 55}}

ML18088A662

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