Text

And Peach Bottom Lsro - Draft Operating Exam (SRO - Sections a & B Only)
	ML102150190
Person / Time
Site:	Peach Bottom, Limerick
Issue date:	06/06/2010
From:	Dickenson R, Wasong A; Exelon Generation Co, Exelon Nuclear
To:	D'Antonio J; Operations Branch I
	HANSELL S
Shared Package
ML092470056	List: IR 05000277/2010301; ML102150100; ML102150104; ML102150190; ML102420204; ML102420248; ML102420261; ML102520084;
References
	TAC U01795, TAC U01796, NLSR02084
	Download: ML102150190 (184)
	v • d • e

{{#Wiki_filter:( Exelon Nuclear Job Performance Measu re LSRO Only - FUEL HANDLING DIRECTOR TURNOVER CONDITIONS NOT MEETING TECHNICAL SPECIFICATION REQUIREMENTS \\-'PM Number: NLSR02084 Revision Number: 000 Date: ____ Developed By: D. M Monahan Instructor Date Validated By: SME or Instructor Date Reviewed By: Operations Representative Date Approved By: Training Department Date SRRS: 3D.105 (when utilized for operator initial or continuing training)

NLSR02084 RevOOO JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate..IPM using steps 9 and 12 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.

Verify the procedure(s) referenced by this JPM reflects the current revision: Procedure OP-AA-112-101 Rev: - Procedure OP-LG-112-101-F-11 Rev: __ Procedure ________ Rev: -

9.

Verify cues both verbal and visual are free of conflict.

10. Verify performance time is accurate

11. If the JPM cannot be performed as written with proper responses, then revise the..I PM.

12. When..IPM is initially validated, sign and date JPM cover page. Subsequent validations, sign and date below:

SME I Instructor Date SME I Instructor Date SME I Instructor Date SRRS: 3D.105 (when utilized for operator initial or continuing training) Page 2 of 6

NLSR02084 RevOOO REVISION RECORD (Summary)

1. Revision 00 Nt A SIMULATOR SETUP INSTRUCTIONS

1. NtA TASK CONDITIONS:

Unit 1 is in OPCON 5 Unit 2 is in OPCON 1 The Electronic OP's log is unavailable due to a software error INITIATING CUES: Review completed Fuel Handling Director Shift Turnover Checklist prior to taking shift.

Identify any potential conflicts with Evolutions in Progress I Planned for next shift, including determination of Tech Spec compliance.

TASK STANDARD(S): Determine the following Evolutions in Progress I Planned for next shift must be stopped, or cannot occur: Spent fuel pool transfers: Tech Spec. 3.9.8 is not met as water level is not 22 feet above the irradiated fuel assemblies in the Fuel pool. Movement of fuel assemblies in the spent fuel pool must be suspended, after placing fuel assemblies and crane in a safe condition Core Transfers: Tech Spec. 3.9.8 is not met as water level is not 22 feet above the reactor pressure vessel flange, Core Alterations cannot occur. Additionally, Tech Spec. 3.9.5 is not met as Control Room communications is intermittent, Core Alterations cannot occur. The following can occur: Control Rod withdrawal to support uncoupling: As this is occurring in defueled cells, and therefore is not a Core Alteration and not impacted the low water level, or intermittent communication. Information for Evaluator's Use: Any UNSA T 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...'PM. 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 SRRS: 30.105 (when utilized for operator initial or continuing training) Page 3 of 6

NLSR02084 RevOOO JPM

SUMMARY

Operator's Name: Job

Title:

O SED 0 SM OSRO o STAIIA IZl OTHER JPM

Title:

FUEL HANDLING DIRECTOR TURNOVEH CONDITIONS NOT MEETING TECHNICAL SPECIFICATION REQUIREMENTS JPM Number: NLSR00284 Revision Number: 000 Task Number and

Title:

82-1 FHD Turnover KIA Number and Importance: G 2.1.3, RO: 3.7 SRO: 3.9 Suggested Testing Environment: quiet area with appropriate documents Alternate Path: OYes IZlNo SRO Only: IZlYes ONo Time Critical: OYes IZlNo Reference(s): Procedure OP-AA-112-101 Rev: 6 Procedure OP-LG-112-101-F-11 Rev: -..!..- Procedure Actual Testing Environment: 0 Simulator 0 Control Room 0 In-Plant IZl Other Testing Method: 0 Simulate IZl Perform Estimated Time to Complete: 20 minutes Actual Time Used: minutes EVALUATION

SUMMARY

Were all the Critical Elements performed satisfactorily? OYes ONo The operator's performance was evaluated against standards contained within this JPM and has been determined to be: o Satisfactory 0 Unsatisfactory Comments:_______________________________ Evaluator's Name: ________________ (Print) Evaluator'S Signature: _______________ Date: _____ SRRS: 3D.105 (when utilized for operator initial or continuing training) Page 4 of 6

NLSR02084 RevOOO JPM Start Time: ____ Critical Element( s) indicated by "*" in Performance Checklist. STEP

1.
2 ELEMENT CUE: Provide candidate with the Fuel Handling Director Turnover Checklist AND Copy of Technical Specifications Evolutions in Progress I Planned for next shift:
Current CCTAS is for Spent fuel pool transfers only Evolutions in Progress I Planned for next shift:
Core Transfers I

STANDARD N/A Determine Movement of spent fuel in the Spent Fuel Pool cannot occur: Tech Spec. 3.9.8 is not met as water level is not 22 feet above the irradiated fuel assemblies in the Fuel pool. Movement of fuel assemblies in the pent fuel pool must be suspended, after placing fuel assemblies and crane in a safe condition Determine Core Transfers cannot occur: Tech Spec. 3.9.8 is not met as water level is not 22 feet above the reactor pressure vessel flange, Core Alterations cannot occur. Tech Spec. 3.9.5 is not met as Control Room communications is intermittent, Core Alterations cannot occur. c.... I- ~ Q),8 <C tJ) E E tJ) z E ::::t

J 8 z SRRS: 3D.105 (when utilized for operator initial or continuing training)

Page 5 of 6

NLSR02084 RevOOO

3.

Control Rod withdrawal to Determine Control Rod support uncoupling: withdrawal to support uncoupling can occur: As this is occurring in defueled cells, and therefore is not a Core Alteration and not impacted the low water level, or intermittent communication. I You have met the termination criteria for this "IPM JPM Stop Time: SRRS: 30.105 (when utilized for operator initial or continuing training) Page 6 of 6

TASK CONDITIONS: Unit 1 is in OPCON 5 Unit 2 is in OPCON 1 The Electronic OP's log is unavailable due to a software error INITIATING CUES: Review completed Fuel Handling Director Shift Turnover Checklist prior to taking shift.

Identify any potential conflicts with Evolutions in Progress I Planned for next shift, including determination of Tech Spec compliance.

SRRS: 3D.105 (when utilized for operator initial or continuing training)

OP~LG~112-1 01-F-11 Revision # Page 1 of 4 Nuclear FUEL HANDLING DIRECTOR SHIFT TURNOVER CHECKLIST NOTE: Complete this form at turnover Date:__..!.!.M.!!.!MI=D.!::::D.!.-'IY~Y~_________ Oncoming Shif(9 Y,Z (circle one) Part A - Offgoing Fuel Handling Director (FHD) Evolutions in Progress I Planned for next shift: -Current CCTAS is for Spent fuel pool transfers only -When Current CCTAS is complete, Next CCTAS will include Core Transfers -Control Rod withdrawal to support uncoupling is ongoing in defueled cells Comments and Problem Areas:

1. No Fuel moves into Core at this time

2. Spent Fuel Pool Water Level 1 inch below fuel pool weir plate bolts

3. Bridge experiencing Mild Crabbing

4. Control Room RO Console Communication Device intermittent, box to be replaced

5. IRM C and D Bypassed

'Jffgoing FHD Signature: _--,T:...:::o~m~S~m.:.:.:it::..:h___________ SRRS: 3D.1 05 (when utilized for operator initial or continuing tmining)

OP-LG-112-101-F-11 Revision ## Page 2 of 4

1.

FHD Log and information on page 1 reviewed.

2.

Fuel Floor local panel annunciators (both units) and Refuel Platform I nterlocklControls reviewed.

3.

Status of work reviewed with Maint. Supervisor and RP Technician.

4.

RP Drywell Control Point contacted and has verified access control to upper elevations is in place as required. RP Contacted: _~A..:.:I....::S::.::e:..:.n:.::;te:::.!r~______,

5.

IF irradiated component transfers through cask pit will occur, RP has posted RB 313' areas as required.

6.

Refueling Platform checkout per S97.1.A is complete as required.

7.

FHDs, Refuel Platform Operators (RPOs), and Spotters are quali'fied and completed all required reading.

8.

Continuous communications established between Control Room and Refueling Platform during CORE ALTERATIONS.

9.

FHD conducted a pre-evolution brief with refuel platform personnel.

10.

Work environment assessed for error-free challenges; actions taken as necessary. (water clarity; water surface; ambient noise; ambient lighting; distractions on platform/floor; refuel platform operation - workarounds; time pressure)

11.

An RP qualified person is present on the Refuel Floor for any work in fuel pool, Reactor cavity, or equipment pit.

12.

CCTAS reviewed, and verified same title/rev. as Reactor Operator and Spotter copies.

13.

IF not in use, THEN GE RCWP Jib Hoist Booms rotated away from RPV center.

14.

Dedicated Spotter present when: Fuel handling concurrent with Areva RCWP hoist installed OR Fuel handling concurrent with GE RCWP jib hoist load handling.

15.

Auxiliary hoist jam blocks set properly during in-vessel maintenance.

16.

Refuel Floor inflatable seal backup bottle cart staged (not blocked by other equipment) and diamond plate unobstructed at seal station for Seals No.3 &4.

17.

Fuel Floor permanent ARMs, temporary ARM(s) if required, and Refuel Platform ARM(s) indicate on scale. Refuel Platform rad monitor audible alarm check performed.

1.

RAC

2.

RAC

3.

RAC

4.

RAC

5.

RAC

6.

RAC

7.

RAC

8.

RAC

9.

RAC

10. RAC

11. RAC

12.

RAC

13.

RAC

14.

RAC

15.

RAC

16.

RAC

17.

RAC NOTE: following step assures compliance with requirement for 22 ft of water over fuel seated in racks and RPV flange, and for 8 ft water over active fuel being handled.

18. *Spent Fuel Pool water level at least touching bolts which secure spent fuel pool weir plates.

SRRS: 3D.1 05 (when utilized for operator initial or continuing training)

OP-LG-112-101-F-11 Revision ## Page 3 of4

18.

RAC

19. Refueling Interlocks and Refuel Platform equipment operable as required by Tech Specs. ST-6-097-630-1 (2) OR ST-6-1 07-633-1 (2).

19.

RAC

20.

Reactor Mode switch locked in REFUEL position.

20.

RAC

21.

All control rods are fully inserted and indicate full in as required by Tech Specs.

21.

RAC

22.

For irradiated Fuel Handling, RPV Water Level verified as required by Tech Specs as follows: Level as stated on OP Aid next to Shutdown and Upset Range instruments LI-42-*R605, LR-42-*R608 AND is not to be less than 487.5" per Tech Specs.

22.

RAC

23. Moderator temperature!:: 68° F OR a lower cycle-speci'fic temperature specified by Reactor Engineering.

23. NOTE #1

24. Both Recirc pumps secured OR allin-core Instruments supported.

24.

RAC

25.

RHR SOC flow ~ 6000 gpm OR allin-core instruments supported.

25. NOTE #2

26.

LCO, PLCO, prior shift ops narrative log entries reviewed.

26.

RAC

27.

Outage supervisor white board reviewed.

27.

RAC NOTE Tech Spec 3.9.2 requires at least two SRM channels to be OPERABLE and inserted to the normal operating level with: Continuous visual indication in the control room At least one with audible alarm in the control room One of the required SRM detectors located in the quadrant where CORE ALTERATIONS are being performed and the other required SRM detector located in an adjacent quadrant, and Unless adequate SHUTDOWN MARGIN has been demonstrated, the "shorting links" shall be removed 'from the RPS Circuitry prior to and during the time any control rod is withdrawn.

28. SRMs are operable as required by Tech Spec 3.9.2.

(Circle operable SRMs ABC D).

28.

RAC

29. Verify IRMs operable as required by Tech Specs.

29.

RAC SRRS: 3D.1 05 (when utilized for operator initial or continuing training)

OP-LG-112-101-F-11 Revision ## Page 4 of 4

30.

Main Control Room Emergency Fresh Air Supply System AND instrumentation operable.

30.

RAC

31.

SBGTS operable as required by Tech Specs.

31.

RAC

32.

Secondary Containment, SCIVs AND instrumentation operable OR Refuel Area HVAC is in service with operable ventilation exhaust radiation monitors OR Standby Gas Treatment is in service to the Refuel Area.

32.

RAC

33. ECCS operable as required by Tech Specs.

33.

RAC

34.

Electrical systems AND instrumentation operable as required by Tech Specs.

34.

RAC

35.

RHR method(s) set per Tech Spec requirements.

35.

RAC

36. Current plant status reviewed with Unit Reactor Operator.

36.

RAC Comments _____________________________________________________________ NOTE # 1 RPV temp at TE-051-1 N004A is 98° F 'OTE # 2 "A" RHR in ADHR flow 5700 gpm Oncoming FHD Signature: _____..:....R:.:.......:.N..:.:a::::.:t.:..:.he:::.:r~-----------------Time: SRRS: 30.105 (when utilized for operator initial or continuing training)

NF-LG-31 0-2000 Revision ## Page 1 Of 2 ATTACHMENT 8 "Sample" CCTAS Instruction/Approval Page Page 1 of 1 CCT AS Instructionl Approval Page Core Component Transfer Authorization Sheet Page _!..--_ of --.::::..--_ Unit LIMERICK GENERATING STATION Date MM/DDNY Title Fuel bundle moves in U1 Spent Fuel pool (Rev.#) ~#~#:..:.:#__

1. This CCTAS provides the moves necessary to Fuel bundles within the U1 Spent Fuel Pool

2. This CCTAS assumes that SRM A, B, C, 0 are in service.

3. Emergency Setdown Location

4. This CCTAS must be used in conjunction with appropriate maintenance procedures.

5. This CCTAS must be used in conjunction with appropriate fuel handling procedures.

6. All changes to this CCTAS must be made in accordance with procedure NF-AA-309.

7. This CCTAS involves the transfer of Special Nuclear Material (SNM). S[\\IM transfers shall be controlled in accordance with procedure NF-AA-300.

8. Reactor Engineer contact: H Potter X####

9. List pen and ink revisions and affected pages here:

____~R~Fo=u=s=t_____________________ I __~M~M~/~D~D~N~Y~_____ Preparer DATE ____~G~S=n=id=e~rt~_________________ I ___=M=M~/=D=DN~Y______ Independent Reviewer DATE ____....::.H...:...::...P-=-ot=te=r_________________ I __-=M=M~/=D=DN~Y_____Distribution Legible YES Reactor Engineer DATE Return completed CCTAS (or a copy if original is contaminated) to Reactor Engineering.

eview of Completed Move Sheets: ____________________ 1__________

SNM Custodian DATE SRRS: 30.105 (when utilized for operator initial or continuing training)

NF-I,.. ~31 0-2000 ...;vision ## Page 2 of 2 ATTACHMENT 6 CCTAS For Non Core Transfer Page 1 of 1 Written By: R Foust ___ Unit Reviewed By: G Snidert ____ Title CCTAS FOR NON CORE TRANSFERS Authorized By: H Potter STEP COMPONENT MOVE FROM ORIENT MOVE TO ORIENT FHD RPO DATE TIME NO. SERIAL NO. 1 LY8487 12SPENT KK-158 SW l1SPENTH8 SW 2 LY8488 12SPENT KK156 SW LlSPENT U-57 SW 3 LY8811 12SPENT KK-l54 SW L 1 SPENT U-56 SW 4 lYN091 12SPENT KK-152 SW l1SPENTV*58 SW 5 LY8812 12SPENT KK-150 SW LlSPENT V-56 SW 6 LY8813 12SPENT KKl48 SW L 1 SPENT W-58 SW 7 LYN104 12SPENT KKl46 SW L 1 SPENT W-S7 SW SRRS: 3D.1 05 (when utilized for operator or continuing training)

Exelon Nuclear Job Performance Measure LSRO Only - GP-13, CON"rROL ROD DRIVE AND MAINTENANCE COORDINATION I ALTERNATE PATH - TWO CELL SEPARATION NOT ENSURED JPM Number: NLSR02083 Revision Number: 000 Date: --- Developed By: D. M. Monahan Instructor Date Validated By: SME or Instructor Date Reviewed By: Operations Representative Date Approved By: Training Department Date SRRS: 3D.1 05 (when utilized for operator initial or continuing training)

NLSR02083 RevOOO 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 and 12 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.

Verify the procedure(s) referenced by this JPM reflects the current revision: Procedure ________ Rev: - Procedure Rev: Procedure ________ Rev: - Procedure Rev:

9.

Verify cues both verbal and visual are free of conflict.

10. Verify performance time is accurate

11. If the JPM cannot be performed as written with proper responses, then revise the J PM.

12. When..IPM is initially validated, sign and date JPM cover page. Subsequent validations, sign and date below:

SME / Instructor Date SM E / Instructor Date SME / Instructor Date SRRS: 3D.1 05 (when utilized for operator initial or continuing training) Page 2 of 5

NLSR02083 RevOOO REVISION RECORD (Summary) 1. Revision 00 1\\11A SIMULATOR SETUP INSTRUCTIONS

1. N/A TASK CONDITIONS:

Unit 1 is in OPCON 5 GP-13, Control Rod Drive/ Control Rod Blade Outage Maintenance Coordination is in progress: o Control Rod Drive Exchange is in progress per Section 3.3 "CRD EXCHANGE ONLY", and Attachment 2 (page 2 of 6)

OUTAGE SERVICES has removed Control Rod Drive 26-35 o Control Rod Blade Shuffle/Replacement is in progress per Section 3.2 "CRB SHUFFLE/ REPLACEMENT ONLY", and Attachment 2 (page 1 of 6) o Maintenance Locations are noted on Core Map Attachment 3 INI1"IATING CUES:

OUTAGE SERVICES Requests permission to remove Control Rod Blade 22-27 per in progress CCT AS. The GP-13 Coordinator has requested you review the above request, and determine permissible actions. TASK STANDARD(S): Identify that Control Rod Blade 22-27 cannot be removed. Identify that Control Rod Blades 38 43 and 54-31 can be removed. 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 SRRS: 3D.105 (when utilized for operator initial or continuing training) Page 3 of 5

NLSR02083 RevOOO JPM

SUMMARY

Operator's Name: ___________Job

Title:

O SED 0 SM DSRO o ST AliA I2SI OTHER JPM

Title:

GP-13, CONTROL ROD DRIVE AND MAINTENANCE COORDINATION I ALTERNATE PATH - TWO CELL SEPARATION NOT ENSURED JPM Number: NLSR00283 Revision Number: 000 Task Number and

Title:

234000-19, Direct actions for installation and removal of fuel support piece and control rod blades KIA Number and Importance: 295003, AA2.01 RO: 3.6 SRO: 4.0 Suggested Testing Environment: quiet area with appropriate documents Alternate Path: DYes I2SI No SRO Only: I2SIYes DNo Time Critical: DYes I2SINo Reference(s): Procedure GP-13 -=~=-------- Rev: -=-- Procedure _________ Rev: Actual Testing Environment: 0 Simulator 0 Control Room 0 In-Plant I2SI Other Testing Method: 0 Simulate I2SI Perform Estimated Time to Complete: 20 minutes Actual Time Used: minutes EVALUATION

SUMMARY

Were all the Critical Elements performed satisfactorily? DYes ONo The operator's performance was evaluated against standards contained within this "IPM and has been determined to be: o Satisfactory 0 Unsatisfactory Comments:_______________________________ Evaluator's Name: __________________ (Print) Evaluator's Signature: _______________ Date: _____ SRRS: 3D.1 05 (when utilized for operator initial or continuing training) Page 4 of 5

I\\ILSR02083 RevOOO JPM Start Time: ____ Critical Element(s) indicated by "*,, in Performance Checklist. STEP ELEMENT

1.

CUE: OUTAGE SERVICES Requests permission to remove Control Rod Blade 22-27

2.

3.2.3 VERIFY that no CRD work is performed on the selected location AND that two cell separation exits between the CRD work location AND surrounding work locations prior to CRB removal.

3.

CUE: This is OUTAGE SERVICES I Understand we do not have permission to remove Control Rod Blade 22-27

4.

CUE: OUTAGE SERVICES Requests identification of all Control Rod Blades that can be scheduled for replacement while Control Rod Drive 26-35 is removed

5.

3.2.3 VERIFY that no CRD work is performed on the selected location AND that two cell separation exits between the CRD work location AND surrounding work locations prior to C RB removal. t::.. CD CD I-c( ~ e..Q STANDARD en ee en z o :::s

)

(.)z N/A N/A i N/A Review Attachment 3 to identify CRB and CRD location Determine Control Rod Blade 22-27 cannot be removed and inform Outages Services N/A i N/A N/A - N/A N/A N/A Determine Control Rod Blade 38-43 and 54-31 can be removed and inform Outages Services i You have met the termination criteria for this JPM JPM Stop Time: _____ SRRS: 3D.105 (when utilized for operator initial or continuing training) Page 5 of 5

TASK CONOrnONS: Unit 1 is in OPCON 5 GP-13, Control Rod Drive/ Control Rod Blade Outage Maintenance Coordination is in progress: o Control Rod Drive Exchange is in progress per Section 3.3 "CRD EXCHANGE ONLY", and Attachment 2 (page 2 of 6)

OUTAGE SERVICES has removed Control Rod Drive 26-35 o Control Rod Blade Shuffle/Replacement is in progress per Section 3.2 "CRB SHUFFLE/ REPLACEMENT ONLY", and Attachment 2 (page 1 of 6) o Maintenance Locations are noted on Core Map Attachment 3 INITIATING CUES:

OUTAGE SERVICES Requests permission to remove Control Rod Blade 22-27 per in progress CCTAS. The GP-13 Coordinator has requested you review the above request, and determine permissible actions. SRRS: 30.105 (when utilized for operator initial or continuing training)

Exelon Nuclear Job Performance Measure Calculate Stay Time JPM Number: NLSR02701 Revision Number: 001 Date: ____ Developed By: D. M Monahan Instructor Date Validated By: SME or Instructor Date Reviewed By: Operations Representative Date Approved By: Training Department Date SRRS: 3D.1 05 (when utilized for operator initial or continuing training)

NLSR02701 Rev001 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation. Prior to..IPM usage, revalidate JPM using steps 9 and 12 below.

1.

Task description and number,..IPM 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.

Verify the procedure(s) referenced by this..IPM reflects the current revision: Procedure Rev: Procedure ________ Rev: Procedure Rev: Procedure _______, Rev: -

9.

Verify cues both verbal and visual are free of conflict

10. Verify performance time is accurate

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

12. When..IPM is initially validated, sign and date JPM cover page. Subsequent validations, sign and date below:

SME / Instructor Date SME / Instructor Date SME / Instructor Date SRRS: 30.105 (when utilized for operator initial or continuing training) Page 2 of 7

NLSR02701 Rev001 REVISION RECORD (Summary)

1. Revision 01, updated procedure reference, calculation numbers, Location, Equipment and format, no rev markers used SIMULATOR SETUP INSTRUCTIONS N/A TASK CONDITIONS:

Unit 2 is in OPCON 5 Monorail Auxiliary Hoist is in use for Control Rod Blade replacement The NES combined Grapple has broken and requires repair High radiation exposure controls are required for this repair During the initial entry the workers Maximum Stay Time was reached and the electronic dosimeter accumulated dose set point was not reached Additional high radiation exposure controls are required Workers have been removed from the Radiation Area until new stay times have been calculated Dose Rates in the Vicinity of the Grapple are 400 mrem/hr The Effective Dose Rate for the entry was determined to be 400 mrem/hr per RP-AA 460-002 step 4.4.4.2.B Job conditions and information are as follows: Dose Rate Alarms Setpoints on their Electronic Dosimeter for both workers: 600 mrern/hr Accumulated Dose Alarm Setpoints on their Electronic Dosimeter for both workers: 1200 mrem RW P Approved Dose for both workers: 1200 mrem Stop Work Dose Rate for both workers: 600 mrern/hr Worker 1 has 900 mrem accumulated dose on his Electronic Dosimeter from his first entry Worker 2 has 600 mrem accumulated dose on his Electronic Dosimeter from his first entry 1.5 man-hrs are required to finish the work Work is to be performed on the Refuel Floor inside a quarantined area. INITIATING CUES: Use RP-AA-460-002, "Additional High Radiation Exposure Controls and Survey Map to determine:

1.

Maximum Stay Times (Worst Case) to reach the Electronic Dosimeter accumulated dose alarms for worker 1 and worker 2.

2.

If the workers can finish the work within 1.5 man-hrs TASK STANDARD: Calculate stay time for workers 1 and 2 until electronic dosimeter accumulated dose alarms set point is reached, and that work can be finished in the allotted time. Information for Evaluator's Use: SRRS: 30.105 (when utilized for operator initial or continuing training) Page 3 of 7

NLSR02701 Rev001 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 SRRS: 30.105 (when utilized for operator initial or continuing training) Page 4 of 7

NLSR02701 Rev001 JPM

SUMMARY

Operator's Name: ___________,.Job

Title:

O SED 0 SM OSRO o STAIIA ~ OTHER JPM

Title:

Calculate Stay Time JPM Number: NLSR02701 Revision Number: 001 Task Number and

Title:

LP NLSRO-1760, Health Physics Procedures KIA Number and Importance: 2.3.7 RO: 3.5 SRO: 3.6 Suggested Testing Environment: quiet area with appropriate documents Alternate Path: OYes ~No SRO Only: ~Y.;,s ONo Time Critical: OYes ~No Reference(s): Procedure RP-AA-460-002 Rev: 0 ~-- Procedure _________ Rev: --- Actual Testing Environment: 0 Simulator 0 Control Room 0 In-Plant ~ Other Testing Method: 0 Simulate [gl Perform Estimated Time to Complete: 20 minutes Actual Time Used: minutes EVALUATION

SUMMARY

Were all the Critical Elements performed satisfactorily? OYes ONo The operator's performance was evaluated against standards contained within this JPM and has been determined to be: o Satisfactory 0 Unsatisfactory Comments:_______________________________ Evaluator's Name: ________________ (Print) Evaluator's Signature: __________._____ Date: _____ SRRS: 30.105 (when utilized for operator initial or continuing training) Page 5 of 7

NLSR02701 Rev001 JPM Start Time: ____ Critical Element(s) indicated by"*" in Performance Checklist. ELEMENT (Cue: Provide copy of RP-AA 460-002 and survey map)

1. Determine new Maximum Stay Time for the required entry

2. For worker 1 :

2.a Determine remaining margin to the electronic dosimeter accumulated does alarm setpoint by subtracting accumulated dose of 900 mr from accumulated dose alarm of 1200 mr to get remaining dose until alarm
2.b Divide remaining margin to alarm by the effective Dose Rate in work area to get Maximum Stay Time (Worst Case)

3. For worker 2:

3.a Determine remaining margin to the electronic dosimeter accumulated does alarm setpoint Subtract accumulated dose of 600 mr from accumulated dose alarm of 1200 mr to get remaining dose until alarm STANDARD N/A N/A Accum - Accum = Remain Dose Dose Dose Alarm Alarm 1200 mr - 900 mr =300 mr Remain I Effective = Max Margin Dose Stay Alarm Rate Time 300mr I 400 mr/hr =.75 hrs Accum - Accum = Remain Dose Dose Dose Alarm Alarm 1200 mr - 600 mr =600 mr I -

e l 01( G>! 01( (f) I-EE (f) z E ::J

)

8 z I SRRS: 3D.1 05 (when utilized for operator initial or continuing training) Page 6 of 7

NLSR02701 Rev001 t::... CI) CI) ~ e Jl (f) ELEMENT STANDARD ~ (f) Z E e o :::J

l OZ

3.b Divide remaining margin Remain I Effective = Max to alarm by the effective Margin Dose Stay Dose Rate in work area Alarm Rate Time to get Maximum Stay 600mr I 400 mr/hr =1.5 hrs Time (Worst Case)

4. Calculate if man-hrs are exceeded:

4.a Add worker 1 Maximum Worker + Worker =Total Stay Time of 45 minutes 1 Stay 2 Stay Stay to worker 2 Maximum Time Time Time Stay Time of 90 minutes 45 min + 90 min =135 min

4.b Determine work can be Determine work can be competed due to completed combined stay time greater than the required 1.5 man-hrs You have met the termination criteria for this JPM JPM Stop Time:

SRRS: 3D.105 (when utilized for operator initial or continuing training) Page 7 of 7

TASK CONDITIONS: Unit 2 is in OPCON 5 Monorail Auxiliary Hoist is in use for Control Rod Blade replacement The NES combined Grapple has broken and requires repair High radiation exposure controls are required for this repair During the initial entry the workers Maximum Stay Time was reached and the electronic dosimeter accumulated dose set pOint was not reached Additional high radiation exposure controls are required Workers have been removed from the Radiation Area until new stay times have been calculated Dose Rates in the Vicinity of the Grapple are 400 mrem/hr The Effective Dose Rate for the entry was determined to be 400 mrern/hr per RP-AA 460-002 step 4.4.4.2.B Job conditions and information are as follows: Dose Rate Alarms Setpoints on their Electronic Dosimeter for both workers: 600 mrem/hr Accumulated Dose Alarm Setpoints on their Electronic Dosimeter for both workers: 1200 mrem RWP Approved Dose for both workers: 1200 mrem Stop Work Dose Rate for both workers: 600 mrern/hr Worker 1 has 900 mrem accumulated dose on his Electronic Dosimeter from his first entry Worker 2 has 600 mrem accumulated dose on his Electronic Dosimeter from his first entry 1.5 man-hrs are required to finish the work Work is to be performed on the Refuel Floor inside a quarantined area. INITIATING CUES: Use RP-AA-460-002, "Additional High Radiation Exposure Controls and Survey Map to determine:

1.

Maximum Stay Times (Worst Case) to reach the Electronic Dosimeter accumulated dose alarms for worker 1 and worker 2.

2.

If the workers can finish the work within 1.5 man-hrs SRRS: 3D.105 (when utilized for operator initial or continuing training)

Attachmen t 1 -ARW S urvey Form Page 1 of 1 RWP No. 10-55 Date: MMlDDIYY Time: #### Survey No.: 10-33 LOCATION: UNIT # 1 BLDG.: RX ELEV.: 352 AREA / LOCATION: RX 1 FUEL FLOOR (Le. room name/number) WORK DESCRIPTION: Monorail Auxilia!)l Hoist ReQair (Task being performed, work order #, etc.) SURVEYED BY: R Smith / RS ARW SUPERVISOR: J Jones NOTIFIED: K. Anderson (Print name) / (Inits) (Supv of ARW performing survey) (RP Tech) SERIAL CAL. DUE VALID SERIAL CAL. DUE VALID INSTRUMENT NO. YES NO INSTRUMENT NO. YES I NO R02A X RM-14 X BETA GAMMA DISTANCE CONTAMINATION R ITEM I LOCATION ITEM I LOCATION mrad/hr mRlhl' (Circle one) SMEAR. dPl'fl/l0~ A Work Area N/A 400 <1K 1 Laydown Area 0 i(15Orii':'y 30 em / G A Low Dose Area N/A 50

I 2 Grapple <10K Cant. I 30 em / GA A T NES Grapple Laydown Area 3 Laydown Area <2K I 0 4 N C) 5 6 Y/ct400 Grapple 7 ~I ~I YI 30 em 400 8 9 10 ~ 11 12 Step-Off Pad 13 14 15 1, X*X*X =Radiological Boundary 20 SMEAR 3, *#1 # =Illy CONTACT

4. *#1 # =f3Iy CONTACT All dose rates in mRlhr unless otherwise noled.

1#

1l1y@30cm REMARKS: Surve~ to sueeort Auxlliar~ Hoist Reeair REVIEWED BY: SWard DATE: MM/DDIYY y SRRS: 3D.105 (when utilized for operator initial or continuing training)

EXELON RADIATION CONTAMINATION DIAGRAM SHEET PAGE __ OF __ LOCATION: RX 1 FUEL FLOOR BRIDGE DATE: TIME: INSIRUMENT SURVEY No.: TYPE SERIAL II CAL. DUE AX POWER: IAN' I / ROOM I RWP No.: lR352BR Si. J BY: INITW.S: RFASON FOR SURVEY: REVIEWED BY: DATE: WORK ORDER I GA Range B8DlacIQ~ to __ mrem/hr All dose rut_ In mrem/hr unless otherwl.. noted N AIRBORNE I lIH.~1 Unidentified OAC Froctlon r-Conto rn ination Smear LOCATION DPM!100CM' 1 2 3 4 =tl 8 9 10 11 12 13 14 15 D Ed 16 17 18 19 20 21 22 23 24 25 26 27 28 ~ [J 32 33 34 35 36 I I I I "IIIII Legend 1-1GA ~ x-x-x - RAD BOUNDARY Ie/I - fl/1 RliIrVlARKS: sOP - STEP OFT PAD I N - NEUTRON l - lARGE AREA WIPE CI) - SMEAR

b. -

A!S LOCATION NOB - No Detectablo Beta K - , Tim...... 100<1 OF - Direct Frisk 1/' -1 Contact /10 30 em Hd-Heod Ch-Cheat W-Walat Kn-Knee R~~ON DATE: 03/13/98 CCPM - CORRECTED COUNTS PER MINUTE

r-----; ~:.:

~

IJ r_

- ARW S urvey Form PaQe 1 of 1 RWP No.

10-55 Date: MM/DDIYY Time: llit## Survey No.: 10-33 LOCATION: UNIT # 1 BLDG.: RX ELEV.: 352 AREA I LOCATIO!\\!: RX 1 FUEL FLOOR BRIDGE (i.e. room name/number) WORK DESCRIPTION: Monorail Auxiliary Hoist Rel2air (Task being performed, work order #, etc.) SURVEYED BY: R Smith / RS ARW SUPERVISOR: J Jones NOTIFIED: K. Anderson (Print name) / (Inits) (Supv of ARW performing survey) (RP Tech) SERIAL CAL. DUE VALID SERIAL CAL. DUE VALID INSTRUMENT NO. YES NO INSTRUMENT NO. YES NO R02A X RM-14 X BETA GAMMA DISTANCE CONTAMINATION R ITEM / LOCATION mrad/hr mRlhr (Circle one) SMEAR# ITEM I LOCATION dpmll00cm! A Work Area N/A 400 1 FLOOR <1K Cont. / 30 em / GA D Low Dose Area N/A 50 2 Platform <1K I Cont. / 30 em / GA A 3 Platform <2K Cont. / 30 em / GA T 4 Platform <4K t;;j I ~CD i 5 0 ~~TIllI : N CD 6 7 8 9 10

-~---.

CD 11 ~ ,~ r r 12 13 CD 14 15 rl I l f--- g q , mmm n ~ ; CD

1. X-X-X = Radiological Boundary 20 =SMEAR

3. *#/ # = fl/y CONTACT

4. *#/ # = fl/y CONTACT All dose rates in mRlhr unless otherwise noted.

/ #

fl/y @ 30 em REMARKS: Surve)l to SU!;!!;!ort Auxiliar)l Hoist Re!;!air REVIEWED BY: SWard DATE: MM/DDIYY

Limerick Generating Station Job Performance Measure Fuel Movement in the Spent Fuel Pool, Hoist Jam Light Illuminates (Alternate Path) JPM Number: 2035 Revision Number: 002 Date:_l_'_ Developed By: Instructor Date Validated By: SME or Instructor Date Review By: Operations Representative Date Approved By: Training Department Date SRRS: 3D.105 (when utilized for operator initial or continuing training)

NLSROJPM2035 REV002 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 and 12 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, or simulator)

4. Initial setup conditions are identified.

5. Initiating and terminating cues 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. Verify the procedure referenced by this JPM matches the most current revision of that procedure:

Procedure Rev. __ Procedure Rev. __ Procedure Rev. __

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

10. Verify performance time is accurate

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

12. 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 SRRS: 3D.105 (when utilized for operator initial or continuing training) Page 2 of 14

NLSROJPM2035 REV002 REVISION RECORD (

SUMMARY

) Rev 002, updated based on procedure rev. Format updated no rev markers used TRAINEE BRIEFING

1. Perform PJB lAW HU-AA-1211.

a. Ensure Roles and Responsibilities are covered

i. Ensure trainee understands that in order to examine requirements of the LSRO program, they may be asked to switch roles during the JPM.

b. Ensure Safety is covered

c. Ensure Human Performance Fundamentals are covered.

BRIDGE SETUP INSTRUCTIONS

1. ENSURE there is NO conflict with scheduled Refuel Floor and/or Fuel Pool work.

2. ENSURE personnel required for performance of S97.0.M are in attendance.

3. PERFORM PREREQUISITES of S97.0.M.

a. Bridge operation will be in Manual.

b. ENSURE there is NO potential for contact with the Auxiliary Platform during performance of any section of this procedure.

c. PERFORM the applicable sections of S97.1.A.

d. PERFORM FH-106.

4. PERFORM PRECAUTIONS of S97.0.M.

5. PERFORM S97.0.M, steps 4.2 through 4.5 as required to set-up Bridge for Candidate to perform S97.0.M step 4.8.

TASK CONDITIONS: SRRS: 30.105 (when utilized for operator initial or continuing training) Page 3 of 14

NLSROJPM2035 REV002

1. All of the Prerequisites and Precautions of procedure S97.0.M have been completed.

2. A CCTAS has been developed to move the dummy fuel bundle to another location in the SFP, OR if a CCTAS is not available, the evaluator will provide instructions on the move.

3. This JPM is written from the standpoint that the LSRO is operating the refuel platform as RPO and the evaluator is providing the Fuel Handling Director verification function.

4. Refuel Floor Secondary Containment is not required.

5. The fuel prep machine is operable and visually verified full down.

INITIAL CONDITIONS:

1. A CCTAS has been developed to move the dummy fuel bundle to another location in the SFP, OR if a CCTAS is not available, the evaluator will provide instructions on the move.

2. Prerequisites of S97.0.M have been met.

3. All encoders are enabled for the bridge, trolley and hoist.

4. This JPM is written from the standpoint that the LSRO is operating the refuel platform as RPO.

5. Refuel Floor Secondary Containment is not required.

6. There are NO irradiated components grappled to any refueling platform hoist.

7. The Aux Hoists are full up with no tools attached.

8. The Unit __ Refueling Platform has been aligned and checked out per S97.1.A, Electrical, Mechanical, and Pneumatic Alignment/Checkout of Refueling Platform Bridge, Trolley, and Main Hoist for Operation.

9. All Prerequisites of FH-106, Core Component and Irradiated Item Movement - No Core Transfer, are complete as applicable.

INITIATING CUES:

1. You have been directed to move the dummy bundle from one SFP location to another in accordance with (lAW) a CCTAS OR at the direction of the evaluator.

2. You are to PERFORM (Simulate if Refuel Platform is not operable) this activity as the Refuel Platform Operator.

3. You are to perform Bridge Moves in Manual.

TASK STANDARD: Appropriate actions are taken upon obtaining an unexpected hoist overload condition while moving the dummy fuel bundle. Information for Evaluator's Use: SRRS: 3D.105 (when utilized for operator initial or continuing training) Page 4 of 14

NLSROJPM2035 REV002 Any UI\\ISAT 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 procE~dure steps instead of calling for each individual item to be performed. The JPM Start Time clock starts when the candidate acknowledges the initiating cue SRRS: 3D.1 05 (when utilized for operator initial or continuing training) Page 5 of 14

NLSROJPM2035 REV002 Operator's Name: = __________Job

Title:

0 SED OSM OSRO ORO o STAIIA o OTHER JPM

Title:

Fuel Movement in the Spent Fuel Pool, Hoist Jam Light Illuminates (Alternate Path) JPM Number: NLSROJPM2035 Revision Number: 002 Task Number and

Title:

234000-46 Direct fuel moves to/from a fuel prep machine KIA Number and Importance: 234000 G2.2.28 IR: 3.5 Suggested Testing Environment: In-Plant Alternate Path: [g] Ves o No SRO Only: [g] Ves o No Time Critical: OVes [g] No

References:

1. S97.1.A, Electrical, Mechanical, and Pneumatic Alignment/Checkout of Refueling Platform Bridge, Trolley, and Main Hoist for Operation

2. FH-106, Core Component and Irradiated Item Movement - No Core Transfer

3. S97.0.M, Refueling Platform Operation Actual Testing Environment: 0 Simulator 0 Control Room 0 In-Plant 0 Other Testing Method: 0 Simulate 0 Perform Estimated Time to Complete: 20 minutes Actual Time Used: _minutes EVALUATION

SUMMARY

Were all the Critical Elements performed satisfactorily? o Ves 0 No The operator's performance was evaluated against the standards contained in this JPM, and has been determined to be: 0 Satisfactory 0 Unsatisfactory Comments:________________________ Evaluator's Name: ______________(Print) Evaluator's Signature: Date ___ SRRS: 30.105 (when utilized for operator initial or continuing training) Page 6 of 14

NLSROJPM2035 REV002 .JPM Start Time: ___ C l-Q) Q) I- ~ U) e,C STEP ELEMENT STANDARD U) z E e o :::I

l

()z I Provide candidate with a copy of S97.0.M Obtain current revision of Current revision of S97.0.M

1.

S97.0.M obtained.

Instructor Note: Once the trainee demonstrates the ability to locate the current revision of the procedure, provide him/her a copy. Instructor Note: If trainee asks about bridge movement in Semi-Auto vs. Manual, the initiating cue requires manual bridge operation. Pickup Location - Fuel Pool N/A

2.

Storage Rack or Cask Pit N/A N/A -

3.

Spotter to RPO: "next location is _- RPO to Spotter: "understand, _-_ Spotter to RPO: "correct"

4.

POSITION Refuel Platform Mast over desired core Refuel Platform positioned over component in accordance with dummy fuel bundle at location Core Component Move Sheet. designated on the Core Component Move Sheet OR as (CUE IF simulated: Refuel directed by the evaluator. Platform is positioned over the dummy fuel bundle) I N/A

5.

NOTE: The following step may ! be performed anytime prior to . setting grapple on component I bail in step 4.8.6. N/A N/A SRRS: 30.105 (when utilized for operator initial or continuing training) Page 7 of 14

NLSROJPM2035 REV002 STEP

6.

7.

8.

ELEMENT IF HMI screen is functional, THEN RPO, VERIFY the "Current Location" displayed on HMI screen matches intended rack location. (CUE IF simulated: "Current Location" displayed matches intended rack location.) LOWER grapple until grapple is near bail. (CUE IF simulated: Grapple has been lowered and is near the bail (180">> ENSURE grapple is open. (CUE IF simulated: Grapple is open) STANDARD RPO, VERIFY the "Current Location" displayed on HMI screen matches intended rack location. Grapple lowered near bail. Grapple open. Verify indicating light is NOT lit Camera indicates grapple is open. I- ~ CP! c " <C U) EE E :::I U) z

)

Oz (.) SRRS: 30.105 (when utilized for operator initial or continuing training) Page 8 of 14

NLSROJPM2035 REV002 C I.. Q) Q) I- ~ S.Q STEP ELEMENT STANDARD <C en S S en Z o ::::J

J OZ CAUTION

9.

Grapple switch guard located on LH Controller side of grapple head interferes with adjacent DBG bail handle when pickup component's bail handle is between the DBG legs and pickup component's bail handle is perpendicular to DBG handle. Grapple guard can also interfere with Spent Fuel Pool rack label pipe couplings. Contact of grapple guard can cause permanent damage to proximity switch electric cable causing refuel platform to be N/A inoperable. Maintain switch guard away from adjacent seated DBG bail handle OR rack label pipe couplings. SBG bail handle will always be perpendicular to DBG bail handle in core. Therefore, for pickup of SBG's in pool, mast must be oriented with switch guard opposite corner of SSG with spacer buttons. I CUE IF asked: There is no interference for thiS bundle. I N/A N/A

SRRS: 30.105 (when utilized for operator initial or continuing training) Page 9 of 14

NLSROJPM2035 REV002 c... CI) CI) ~ E JJ STEP ELEMENT STANDARD ~ tn E E tn Z o ::l

l OZ

10.

ROTATE grapple as necessary to achieve grapple to bail alignment. Grapple rotated and aligned with bail. (CUE IF simulated: Grapple is rotated and aligned with bail)

11.

Slowly LOWER grapple until SLACK CABLE Light is lit. Grapple is lowered, SLACK CABLE Light is lit. (CUE IF simulated: SLACK CABLE Light is lit)

12.

FHD & Spotter, PERFORM Concurrent Verification of proper core component location AND orientation. N/A (CUE IF simulated: Dummy bundle location and orientation concurrently verified by FHD & Spotter) N/A N/A

13.

Spotter to FHD: "Location is _-___" FHD to Spotter: "agree, _-___" Spotter to FHD: "correct" N/A N/A

14.

NOTE: The verifications in the following two steps may be N/A performed in parallel. N/A N/A - Note to the examiner: Steps 4.8.8 (for the FHD and Spotter) and 4.8.9 (for the RPO) of the procedure have the same actions and they may be performed in parallel. This JPM is evaluating the RPO. After the verifications are performed, a cue needs to be given to direct the RPO to engage the grapple. SRRS: 3D.1 05 (when utilized for operator initial or continuing training) Page 10 of 14

NLSROJPM2035 REV002 STEP

15.

16.

17.

18.

19.

ELEMENT FHD, VERIFY the following, SLACK CABLE Light is lit Grapple is centered over bail handle Hoist Position indication agrees with Attachment 2 for item seated in Fuel Pool Storage Rack Grapple appears seated on bail handle using underwater camera for component seated in cask THEN DIRECT RPO to engage grapple. RPO, VERIFY the following SLACK CABLE Light is lit. (CUE IF simulated: Slack Cable Light is lit.) Grapple is centered over bail handle. (CUE IF simulated: Grapple is centered over bail handle.) Hoist Position indication agrees with Attachment 2 for item seated in Fuel Pool Storage Rack. (CUE IF simulated: Hoist Position indicates 197") .... c... I- ~ G>! U) STANDARD ~ E E U) z E :::I

) 8 z N/A N/A N/A N/A N/A N/A Verifies SLACK CABLE light is lit.

Verifies SLACK CABLE light is lit. Verifies hoist position is between 198" and 196". (Depending on calibration, Unit 1 is about 196"-197" and Unit 2 is about 198") SRRS: 3D.105 (when utilized for operator initial or continuing training) Page 11 of 14

NLSROJPM2035 REV002 STEP

20.

21.

22.

23.

24.

25.

ELEMENT STANDARD Grapple appears seated on bail N/A handle using underwater camera for component seated in cask. THEN WHEN directed by FHD, Grapple is engaged. ENGAGE grapple. (CUE IF simulated: The grapple is engaged). FHD to RPO: "engage grapple" RPO to FHD: "understand, engage grapple" FHD to RPO: "correcf' FHD & RPO, PERFORM Peer Verify GRAPPLE ENGAGED Check that GRAPPLE Light is lit. ENGAGED Light is lit. (CUE IF simulated: The GRAPPLE ENGAGED Light is lit). RPO to FHD: "engaged light lit" FHD to RPO: "agree, engaged light lit" RPO to FHD: "correcf' Slowly RAISE load while ensuring FUEL LOADED Light is lit (fuel/dummy bundle only). (CUE IF simulated: If asked; Fuel Loaded light is lit.) ALTERNATE PATH STARTS HERE s::... eD eD I- ~ e Jl <r: en e e en Z o ::s ~ OZ N/A N/A - SRRS: 3D.1 05 (when utilized for operator initial or continuing training) Page 12 of 14

NLSROJPM2035 REV002 STEP ELEMENT

26.

After the candidate starts raising the bundle, provide the following Cue: 1. STOP raising the hoist

2. We are simulating that the hoist has automatically stopped moving.

3. The HOIST LOADED and HOIST JAM lights are lit.

Cue If asked: Hoist load cell indicates 1190 Ibs.

27.

IF during hoist operation

a HOIST JAM light comes on, THEN movement shall be stopped immediately AND lowered until HOIST JAM Light goes out, THEI\\I the Fuel Handling Director shall be stopped immediately AND lowered until HOIST JAM Light goes out, THEN the Fuel Handling Director shall be contacted for instruction.

Cue: After the candidate lowers the hoist, provide the following cue: "The hoist Jam light is out." c... CI) CI) <C e Jl tJ) STANDARD <C tJ) Z E E o ::::J

l OZ RPO immediately stops attempting to raise the bundle AND RPO immediately stops attempting to raise the bundle AND RPO lowers the hoist until Hoist Jam light goes out, AND The FH D is notified (Cue: You can stop here. You have met the termination criteria for this..IPM.)

JPM Stop Time __ SRRS: 3D.105 (when utilized for operator initial or continuing training) Page 13 of 14

INITIAL CONDITIONS:

1. A CCTAS has been developed to move the dummy fuel bundle to another location in the SFP, OR if a CCTAS is not available, the evaluator will provide instructions on the move.

2. Prerequisites of S97.0.M have been met.

3. All encoders are enabled for the bridge, trolley and hoist.

4. This JPM is written from the standpoint that the LSRO is operating the refuel platform as RPO.

5. Refuel Floor Secondary Containment is not required.

6. There are NO irradiated components grappled to any refueling platform hoist.

7. The Aux Hoists are full up with no tools attached.

8. The Unit __ Refueling Platform has been aligned and checked out per S97.1.A, Electrical, Mechanical, and Pneumatic Alignment/Checkout of Refueling Platform Bridge, Trolley, and Main Hoist for Operation.

9. All Prerequisites of FH-106, Core Component and Irradiated Item Movement-No Core Transfer, are complete as applicable.

INITIATING CUES:

1. You have been directed to move the dummy bundle from one SFP location to another in accordance with (lAW) a CCTAS OR at the direction of the evaluator.

2. You are to PERFORM (simulate if Refuel Platform is not operable) this activity as the Refuel Platform Operator.

3. You are to perform Bridge Moves in Manual.

SRRS: 3D.105 (when utilized for operator initial or continuing training)

Exelon Nuclear Job Performance Measure Dummy Bundle Movement within the Spent Fuel Pool (LSRO performs as RPO) (Alternate Path) JPM Number: NLSR02083 Revision Number: 000 Date: Developed By: J. A. Mihm Instructor Date Validated By: SME or Instructor Date Reviewed By: Operations RI3presentative Date Approved By: Training Department Date SRRS: 3D.105 (when utilized for operator initial or continuing training)

NLSR02083Revision 000 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate..!PM using steps 9 and 12 below.

1.

Task description and number,..'PM description and number are identified.

2.

Knowledge and Abilities (1</A) 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.

Verify the procedure(s) referenced by this JPM reflects the current revision: Procedure S97.0.K Rev: __ Procedure S97.0.M Rev: -

9.

Verify cues both verbal and visual are free of conflict.

10. Verify performance time is accurate

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

12. When JPM is initially validated, sign and date JPM cover page. Subsequent validations, sign and date below:

SME I Instructor Date SME I Instructor Date SME I Instructor Date SRRS: 30.105 (when utilized for operator initial or continuing training) Page 2 of 24

NLSR02083Revision 000 REVISION RECORD (Summary)

1. Revision 00 N/ A TRAINEE BRIEFING

1. Perform P..IB lAW HU-AA-1211.

a. Ensure Roles and Responsibilities are covered

i. Ensure trainee understands that in order to examine requirements of the LSRO program, they may be asked to switch roles during the JPM.

b. Ensure Safety is covered

c. Ensure Human Performance Fundamentals are covered.

BRIDGE SETUP INSTRUC"rlONS

1. ENSURE there is NO conflict with scheduled Refuel Floor and/or Fuel Pool work.

2. ENSURE personnel required for performance of S97.0.M are in attendance.

3. PERFORM PREREQUISITES of S97.0.M.

a. Bridge operation will be in Manual.

b. ENSURE there is NO potential for contact with the Auxiliary Platform during performance of any section of this procedure.

c. PERFORM the applicable sections of 897.1.A.

d. PERFORM FH-106.

4. PERFORM PRECAUTIONS of S97.0.M.

5. PERFORM S97.0.M, steps 4.2 through 4.5 as required to set-up Bridge for Candidate to perform 897.0.M step 4.8.

SRRS: 3D.105 (when utilized for operator initial or continuing training) Page 3 of 24

NLSR02083Revision 000 TASK CONDITIONS:

1. A CCTAS has been developed to move the dummy fuel bundle to another location in the SFP, OR if a CCTAS is not available, the evaluator will provide instructions on the move.

2. Prerequisites of S97.0.M have been met.

3. All encoders are enabled for the bridge, trolley and hoist.

4. This JPM is written 'from the standpoint that the LSRO is operating the refuel platform as RPO.

5. Refuel Floor Secondary Containment is not required.

6. There are NO irradiated components grappled to any refueling platform hoist.

7. The Aux Hoists are full up with no tools attached.

8. The Unit __ Refueling Platform has been aligned and checked out per S97.1.A, Electrical, Mechanical, and Pneumatic Alignment/Checkout of Refueling Platform Bridge, Trolley, and Main Hoist for Operation.

9. All Prerequisites of FH-106, Core Component and Irradiated Item Movement - No Core Transfer, are complete as applicable.

INITIATING CUES:

1. You have been directed to move the dummy bundle from one SFP location to another in accordance with (lAW) a CCTAS OR at the direction of the evaluator.

2. You are to PERFORM (simulate if Refuel Platform is not operable) this activity as the Refuel Platform Operator.

3. You are to perform Bridge Moves in Manual.

TASK STANDARD(S):

1. Dummy Bundle is moved from one SFP location to another through an alternate path due to a fault.

SRRS: 3D.105 (when utilized for operator initial or continuing training) Page 4 of 24

NLSR02083Revision 000 Information for Evaluator's Use: Any UNSAT requires written comments on respective step. Denotes critical steps Number any comments in the "Comment Numbeir" 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 outsidl~ 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 SRRS: 3D.1 05 (when utilized for operator initial or continuing training) Page 5 of 24

NLSR02083Revision 000 JPM

SUMMARY

Operator's Name:__________. Job

Title:

D SED DSM DSRO D STAIIA [gI OTHER JPM

Title:

Dummy Bundle Movement within Spent Fuel Pool (LGS) JPM Number: NLSR00283 Revision Number: 000 Task Number and

Title:

KIA Number and Importance: RO: SRO: Suggested Testing Environment: Refuel Platform Alternate Path: [gI Yes D No SROOnly: ~ Yes D No Time Critical: DYes [gI No Reference(s): Procedure _S=:..97'-'.=0.:.:..K.::..-_____ Rev: 14 Procedure _S::::;.9:..7:...!..:::..0.:.:.:M~_____ Rev: 28 Actual Testing Environment: D Simulator [] Control Room [gIln-Plant D Other Testing Method: D Simulate ~ Perform Estimated Time to Complete: 40 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: ______ SRRS: 3D.1 05 (when utilized for operator initial or continuing training) Page 6 of 24

NLSR02083Revision 000 JPM Start Time: ____ Critical Element(s) indicated by "*" in Performance Checklist. c r... -.8 I! ~ CD STEP ELEMENT STANDARD ~ en E E en z E :::J

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Oz o Provide candidate with a copy of S97.0.M Obtain current revision of Current revision of S97.0.M

1.

S97.0.M obtained.

Instructor Note: Once the trainee demonstrates the ability to locate the current revision of the procedure, provide him/her a copy. Instructor Note: If trainee asks about bridge movement in Semi-Auto vs. Manual, the initiating cue requires manual bridge operation. Pickup Location - Fuel Pool N/A

2.

Storage Rack or Cask Pit N/A N/A

3.

Spotter to RPO: "next location is RPO to Spotter: "understand, Spotter to RPO: "correct"

4.

POSITION Refuel Platform Mast over desired core Refuel Platform positioned over component in accordance with dummy fuel bundle at location Core Component Move Sheet. designated on the Core Component Move Sheet OR as (CUE IF simulated: Refuel directe,d by the evaluator. Platform is positioned over the dummy fuel bundle)

5.

NOTE: The following step may N/A be performed anytime prior to setting grapple on component bail in step 4.8.6. N/A N/A - SRRS: 3D.105 (when utilized for operator initial or continuing training) Page 7 of 24

STEP ELEMENT

6.

IF HMI screen is functional, THEN RPO, VERIFY the "Current Location" displayed on HMI screen matches intended rack location. (CUE IF simulated: "Current Location" displayed matches intended rack location.)

7.

LOWER grapple until grapple is near bail. (CUE IF simulated: Grapple has been lowered and is near the bail (180">>

8.

ENSURE grapple is open. (CUE IF simulated: Grapple is open) NLSR02083Revision 000 ...c... G) G) !;i I-eJ:l STANDARD <a: en ee en z o ::I

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()z RPO, VERIFY the "Current Location" displayed on HMI screen matches intended rack location. Grapple lowered near bail. Grapple open. Verify indicating light is NOT lit Camera indicates grapple is open. SRRS: 3D.105 (when utilized for operator initial or continuing training) PageS of 24

NLSR02083Revision 000 STEP ELEMENT CAUTION

9.

Grapple switch guard located on LH Controller side of grapple head interferes with adjacent DBG bail handle when pickup component's bail handle is between the DBG legs and pickup component's bail handle is perpendicular to DBG handle. Grapple guard can also interfere with Spent Fuel Pool rack label pipe couplings. Contact of grapple guard can cause permanent damage to proximity switch electric cable causing refuel platform to be inoperable. Maintain switch guard away from adjacent seated DBG bail handle OR rack label pipe couplings. SBG bail handle will always be perpendicular to DBG bail handle in core. Therefore, for pickup of SBG's in pool, mast must be oriented with switch guard opposite corner of SBG with spacer buttons. CUE IF asked: There is no interference for this bundle.

10.

ROT ATE grapple as necessary to achieve grapple to bail alignment. (CUE IF simulated: Grapple is rotated and aligned with bail) clio.. ~ CD! STANDARD ~ rn EE rn z E :::s ~ 8 z N/A N/A N/A Grapple rotated and aligned with bail. SRRS: 3D.1 05 (when utilized for operator initial or continuing training) Page 9 of 24

NLSR02083Revision 000 c... CI) CI) t- ~ e.o STEP ELEMENT STANDARD <C 0 e e 0 Z o ::s OZ

11.

Slowly LOWER grapple until SLACK CABLE Light is lit. Grapple is lowered, SLACK (CUE IF simulated: SLACK CABLE Light is lit. CABLE Light is lit)

12.

FHD & Spotter, PERFORM Concurrent Verification of proper core component location AND orientation. (CUE IF simulated: Dummy N/A bundle location and orientation concurrently verified by FHD & Spotter) N/A N/A

13.

Spotter to FHD: "Location is _-___" FHD to Spotter: "agree, _-___" Spotter to FHD: "correct" N/A N/A

14.

NOTE: The verifications in the following two steps may be performed in parallel. N/A N/A N/A Note to the examiner: Steps 4.8.8 (for the FHD and Spotter) and 4.8.9 ('for the RPO) of the procedure have the same actions and they may be performed in parallel. This JPM is evaluating the RPO. After the verifications are performed, a cue needs to be given to direct the RPO to engage the grapple. SRRS: 3D.105 (when utilized for operator initial or continuing training) Page 10 of 24

NLSR02083Revision 000 STEP

15.

16.

17.

18.

19.

20.

ELEMENT FHD, VERIFY the following, SLACK CABLE Light is lit Grapple is centered over bail handle Hoist Position indication agrees with Attachment 2 for item seated in Fuel Pool Storage Rack Grapple appears seated on bail handle using underwater camera for component seated in cask THEN DIRECT RPO to engage grapple. RPO, VERIFY the following SLACK CABLE Light is lit. (CUE IF simulated: Slack Cable Light is lit.) Grapple is centered over bail handle. (CUE IF simulated: Grapple is centered over bail handle.) Hoist Position indication agrees with Attachment 2 for item seated in Fuel Pool Storage Rack. (CUE IF simulated: Hoist Position indicates 197") Grapple appears seated on bail handle using underwater camera for component seated in cask. STANDARD N/A N/A Verifies SLACK CABLE light is lit. Verifies SLACK CABLE light is lit. Verifies hoist position is between 198" and 196". (Depending on calibration, Unit 1 is about 196"-197" and Unit 2 is about 198") N/A ~ U) N/A N/A l <C U) z

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N/A N/A e... IU.! E E E ::::s Oz 0 N/A N/A SRRS: 30.105 (when utilized for operator initial or continuing training) Page 11 of 24

NLSR02083Revision 000 c... CD CD ~ e Jl ~ (f) §!5e ELEMENT STANDARD (f) e E z o :::J

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21.

THEN WHEN directed by FHD, Grapple is engaged. ENGAGE grapple. (CUE IF simulated: The grapple is engaged).

22.

FHD to RPO: "engage grapple" RPO to FHD: "understand, engage grapple" FHD to RPO: "correct"

23.

FHD & RPO, PERFORM Peer Verify GRAPPLE ENGAGED Check that GRAPPLE Light is lit. ENGAGED Light is lit. (CUE IF simulated: The GRAPPLE ENGAGED Light is lit). I

24.

RPO to FHD: "engaged light lit" FHD to RPO: "agree, engaged light lit" RPO to FHD: "correct"

25.

Slowly RAISE load while Slowly raise load ensuring FUEL LOADED Light is lit (fuel/dummy bundle only). (CUE IF simulated: If asked; Fuel Loaded light is lit.) ALTERNATE PATH STARTS HERE SRRS: 3D.105 (when utilized for operator initial or continuing training) Page 12 of 24

STEP

26.

ELEMENT WHEN HOIST POSITION indicates between 100" and 50", THEN, CUE: 1. STOP raising the hoist

2. We are simulating that the hoist has automatically stopped moving.

3. For the purpose of this JPM, you are now performing the role of the FHD.

3. PAR representative reports that a hoist tube hang-up is the likely cause of the hoist motion stop.

4.IF requested, screen on RIGHT (interlock status) is displaying a FAUL T LOCKOUT.

5. IF requested, screen on left (HMI) indicates a red system fault detected button is lit.

Note: The following steps are per S97.0.K

27.

Obtain current revision of S97.0.K Cue: Once the trainee demonstrates the ability to locate the current revision of the procedure, provide him/her a copy.

28.

Correct revision of procedure being used.

29.

Procedure printed on white paper. SRRS: 30.105 (when utilized for operator initial or continuing training) NLSR02083Revision 000 STANDARD Per S~~7.0.M step 3.12.6, Student will reference S97.0.K Current revision of S97.0.K obtained. N/A N/A ....c" !;( (1).,8 !;( U) EE U) z E :::J

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Oz 0 N/A N/A N/A N/A Page 13 of 24 I

NLSR02083Revision 000 e... l-Q) Q) <C ELl STEP ELEMENT STANDARD ~ en E E en Z o ::::J

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30.

Briefing performed as required. N/A Cue: If asked; brief was performed during the job PJB.

31.

To avoid extensive physical damage, slow OR Jog speed only shall be used in N/A approaching any wall OR N/A N/A obstruction.

32.

NOTE: ConditionaIIF..*THEN steps that are not applicable AND steps to be skipped per N/A direction of the IF.. THEN step shall be marked N/A AND N/A N/A initialed.

33.

VERIFY all prerequisites N/A N/A N/A satisfied.

34.

VERIFY procedure being N/A N/A N/A performed on correct Unit.

35.

NOTE: The performance steps section of this procedure are separated into the following subsections that may be performed independently: 4.2 RESPONSE TO SYSTEM FAULTS AND ALARMS. N/A 4.3 PLC OVERRIDE 4.5 BYPASSING A FAULTED ENCODER 4.6 RESETTING A DISABLED ENCODER 4.7 CALIBRATING N/A N/A ENCODER(S)

SRRS: 3D.105 (when utilized for operator initial or continuing training) Page 14 of 24

NLSR02083Revision 000 STEP ELEMENT

36.

NOTE: 1. The PLC monitors individual faults AND alarms. The "System Fault Screen" grey button indicates normal operation {no faults/alarms on the system}. When a fault OR alarm condition occurs, the "System Fault Detected" red button will appear. Touching the "System Fault Detected" button displays the "SYSTEM FAULTS" screen.

37.

NOTE:

2. Touching the "FAULT" OR "ALARM" button activated on "SYSTEM FAULTS" screen displays popup screen explaining the condition.

38.

Caution: Troubleshooting system faults should not preclude taking action to place the machine ANDIOR associated load in a safe condition.

39.

To respond to a system fault/alarm condition, PERFORM the following:

40.

VERIFY "System Fault Detected" button is illuminated on Operator Touch Screen. (Cue: System Fault detected button is illuminated) <C eG>!' l-STANDARD ~ en E E en z E::J Oz 0 N/A N/A N/A - N/A N/A N/A N/A N/A N/A N/A Verifies "System Fault Detected" button is illuminated on Operator Touch Screen. SRRS: 3D.105 (when utilized for operator initial or continuing training) Page 15 of 24

NLSR02083Revision 000 STEP ELEMENT

41.

NOTE: Buttons on the SYSTEM FAULTS screen are designated as follows: Normal condition: Green backlight. Fault condition: Red backlight Alarm condition: Yellow backlight

42.

TOUCH "System Fault Detected" AND VERIFY "SYSTEM FAULT" screen appears with individual System fault/alarm condition(s). (Cue:"System Faulf' screen appears. (ATTACHMENT A>>

43.

TOUCH the activated "FAULT/ALARM" button(s) AND VERIFY pop-up screen is displayed explaining the condition. (Cue: "System Fault indicates HOIST TUBE HANGUP(ATTACHMENT B>>

44.

REFER to Appendices for possible causes AND effects on equipment AND potential follow up actions for responding to the fault/alarm condition. e 1 l-G) G) U) E.Q STANDARD !;c <[ U) z E E o :::s

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(,)z N/A N/A N/A - Touches "System Fault Detected" and Verifies the fault is displayed. Touches button for activated fault and Verifies the explanation of the fault condition. REFER to APPENDIX 1 LlMEF~ICK REFUEL PLATFORM FAULT RESPONSE TABLE SRRS: 30.105 (when utilized for operator initial or continuing training) Page 16 of 24

NLSR02083Revision 000 STEP ELEMENT

45.

Review initiating conditions: 1. Hoist hang up detected 2.Hoist was not moving through transition zone AND did not maintain a stable load reading (Cue if simulated: Hoist Position indication reads approximately 75")

46.

Review effect on equipment

47.

Review POTENTIAL FOLLOW UP ACTIONS

48.

1. IF picking up test weight "rHEN RESET Fault per section 4.2 of this procedure.

49.

2. CHECK cables and hose for proper config. and tension.

(Cue: The PAR representative has verified the cables and hoses have the proper configuration and tension.)

50.

3. CONFIRM that load indication is normal.

(Cue if simulated: Load gauge reads normal)

51.

4. IF no problem is detected, CLEAR fault by moving hoist using Travel Override.

Cue: The hoist raises and the hoist tube hangup fault has cleared c... (1),8 ~ U) STANDARD ~ E E U) z E ::s

) 8 z Reviews Screen Hoist motion inhibited N/A N/A N/A N/A N/A N/A VerifiE~s cables and hoses for proper configuration and tension.

Reads Load Gauge and identities it is reading normal Attempt to clear fault by moving hoist IJsing Travel Override. NOTE: The following steps are from S97.0.M SRRS: 3D.105 (when utilized for operator initial or continuing training) Page 17 of 24

NLSR02083Revision 000 ...C

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52.

Slowly RAISE load while ensuring FUEL LOADED Light is lit (fuel/dummy bundle only). Raises load slowly to normal-up (CUE IF simulated: Raised to Normal-Up)

53.

NOTE:

1. IF operating in Automatic AND Quick Auto is enabled, THEI\\!:

- The Refueling Platform will begin automatically moving toward the setdown location as soon as Hoist Clear is reached. - Once the auto move begins, the operator will be required to release the hoist joystick within 5 seconds or the auto move will N/A be terminated.

2.

IF Quick Auto is enabled AND manual hoist motion stops for more than 5 seconds before the auto move begins, the Quick Auto function will time out. Quick Auto can be enabled again when hoist raise command is provided, HOWEVER step will INCREMENT AND require N/A N/A resetting.

54.

I F operating in Full Auto AND use of QUICK AUTO is desired, N/A THEN PERFORM the following: N/A N/A

55.

TOUCH "QUICK AUTO" N/A N/A N/A -

56.

TOUCH "AUTO RUN" N/A N/A N/A SRRS: 30.105 (when utilized for operator initial or continuing training) Page 18 of 24

NLSR02083Revision 000 STEP

57.

58.

59.

60.

61.

62.

~ (/) ELEMENT STANDARD ~ (/) z

)

WHEN prompted, THEN N/A RELEASE joystick N/A N/A CONTINUE raising until grapple is fully raised, THEN VERIFY NORMAL UP Light is lit. Slowly raise to normal-up (CUE IF simulated: Raised to Normal-Up) GO TO appropriate "Release Location" section of this Trainee goes to Section 4.12 procedure as directed by FHD. 4.12 RELEASE LOCATION FUEL POOL STORAGE RACK N/A OR CASK PIT N/A N/A NOTE: I F a fuel assembly is being transferred to the Cask Pit for loading into a Dry Shielded Canister, AND refueling platform is operating in Semi Automatic mode, THEN the N/A platform will automatically stop with the bundle centered over the Cask. At that point, manual positioning of the fuel bundle is necessary to properly locate the bundle in the desired Dry Shielded Canister (DSC) N/A N/A location. Spotter to FHD: "location is _- FHD to Spotter: "agree, Spotter to FHD: "correct" r:: to.. G) G) e Jl e e o ::J (.)z SRRS: 30.105 (when utilized for operator initial or continuing training) Page 19 of 24

NLSR02083Revision 000 STEP ELEMENT

63.

POSITION core component over desired location in accordance with Core Component Move Sheet. (Cue IF simulated: Refuel Platform is positioned over the release location)

64.

NOTE: The following step may be performed anytime prior to component insertion in step 4.12.5.

65.

IF HMI screen is functional, THEN RPO, VERIFY the "Current Location" displayed on HMI screen matches intended rack location. (ref. 5.32). (Cue IF simulated: Current location displayed matches the intended rack location)

66.

Caution: Grapple switch guard located on LH Controller side of grapple head interferes with adjacent seated DBG bail handle when handled component's bail handle is perpendicular to DBG handle. (Cue IF simulated: There is no interference. )

67.

Caution: Grapple guard can also interfere with Spent Fuel Pool rack label pipe couplings. (Cue IF simulated: There is no interference. ) t-c... ~ CD! STANDARD ~ en E E en z E :::J

) 8 z Refuel Platform positioned over location designated on the Core Component Move Sheet or as directE~d by the evaluator.

N/A N/A N/A Verifies the current location matches the move sheet or instructions from evaluator. N/A N/A N/A N/A N/A N/A SRRS: 3D.105 (when utilized for operator initial or continuing training) Page 20 of 24

NLSR02083Revision 000 e: I l-CI) CI) I-EJl STEP ELEMENT STANDARD en E E en Z o ::l OZ

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68.

Caution: Contact of grapple guard can cause permanent damage to proximity switch electric cable N/A causing refuel platform to be inoperable. (Cue IF simulated: There is no N/A N/A interference.)

69.

Caution: Maintain switch guard away from adjacent seated DBG bail handle OR rack label pipe N/A couplings. (Cue IF simulated: There is no N/A N/A interference.)

70.

ROT ATE core component as necessary to achieve proper orientation. (Cue IF simulated: Component rotated.)

71.

NOTE: Component may be inserted into the fuel rack, up to hoist N/A position "30", in parallel with verification of core component N/A N/A location and orientation.

72.

FHD & Spotter, PERFORM Concurrent Verification of proper core component location AND orientation. N/A (Cue IF simulated: 4.12.4 is N/A N/A complete, lower the hoist)

SRRS: 3D.1 05 (when utilized for operator initial or continuiing training) Page 21 of 24

NLSR02083Revision 000 e: ~ - l-Q)Q) ~ STEP ELEMENT STANDARD !c en EJl EE en Z o ::::J

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73.

FHD to RPO: "lower hoist" RPO to FHD: "understand, lower hoist" FHD to RPO: "correct"

74.

LOWER hoist until core component is seated Lowers hoist until component is AND SLACK CABLE Light is lit. seated and slack cable light is lit. (Cue IF simulated: Slack Cable light is lit.)

75.

NOTE: The verifications in the following N/A two steps may be performed in N/A N/A parallel.

76.

FHD, VERIFY the following: SLACK CABLE Light is lit Component elevation appears equivalent to other stored components in the rack. Hoist Position indication agrees N/A with Attachment 2 for item seated in Fuel Storage Rack, OR ISFSI cask. THEN DIRECT RPO to release and raise grapple. (Cue IF simulated: FHD directs N/A N/A you to raise grapple.)

77.

RPO, VERIFY the following, N/A N/A N/A

78.

SLACK CABLE Light is lit (Cue IF simulated: Slack cable Verifies slack cable light lit. light is lit.) SRRS: 3D.105 (when utilized for operator initial or continuing training) Page 22 of 24

NLSR02083Revision 000 STEP ELEMENT STANDARD

79.

Component elevation appears equivalent to other stored components in the rack. VerifiE!S elevation is equivalent (Cue IF simulated: Component to oth43r components in rack. appears at the same elevation as other components in the rack.)

80.

Hoist Position indication agrees with Attachment 2 for item seated in Fuel Storage Rack, Hoist Position indicates about OR ISFSI cask. 198" (Cue IF simulated: Hoist position indicates 198".)

81.

FHD to RPO: "release grapple" RPO to FHD: "understand, release grapple" FHD to RPO: "correct"

82.

THEN WHEN directed by FHD, RELEASE grapple. Receives communication from FHD to release grapple. (Cue IF simulated: FHD directs you to release grapple.)

83.

VERIFY grapple is "OPEN". VerifiE~s grapple open. (Cue IF simulated: Grapple is open.)

84.

Slowly RAISE grapple while verifying FUEL LOADED Slowly raises grapple and remains out. verifies fuel loaded light remains NOT lit. (Cue IF simulated: Grapple is raising.)

85.

RPO to FHD: "clear" FHD to RPO: "agree clear" RPO to FHD: "correct" SRRS: 3D.1 05 (when utilized for operator initial or continuing training) c... t-G) G) <C E'o ~ en E E en Z o ::s

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NLSR02083Revision 000 ....c... G>! STEP ELEMENT STANDARD ~ U) EE U) z E :::J

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86.

FHD & RPO, PERFORM Peer Check that grapple is clear of Performs peer check with FHD component. that grapple is clear. (Cue IF simulated: I agree, grapple is clear.) -i You have met the termination criteria for this JPM CUE: I'd like you to raise the grapple to Normal-up ..IPM Stop Time: _____ SRRS: 30.105 (when utilized for operator initial or continuing training) Page 24 of 24

NLSR02083Revision 000 INITIAL CONDITIONS:

1. A CCT AS has been developed to move the dummy fuel bundle to another location in the SFP, OR if a CCTAS is not available, the evaluator will provide instructions on the move.

2. Prerequisites of S97.0.M have been met.

3. All encoders are enabled for the bridge, trolley and hoist.

4. This JPM is written from the standpoint that the LSRO is operating the refuel platform as RPO.

5. Refuel Floor Secondary Containment is not required.

6. There are NO irradiated components grappled to any refueling platform hoist.

7. The Aux Hoists are full up with no tools attached.

8. The Unit Refueling Platform has been aligned and checked out per S97.1.A, Electrical, Mechanical, and Pneumatic Alignment/Checkout of Refueling Platform Bridge, Trolley, and Main Hoist for Operation.

9. All Prerequisites of FH-106, Core Component and Irradiated Item Movement - No Core Transfer, are complete as applicable.

INl"rlATING CUES:

1. You have been directed to move the dummy bundle from one SFP location to another in accordance with (lAW) a CCTAS OR at the direction of the evaluator.

2. You are to PERFORM (simulate if Refuel Platform is not operable) this activity as the Refuel Platform Operator.

3. You are to perform Bridge Moves in Manual.

SRRS: 3D.1 05 (when utilized for operator initial or continuing training)

NLSR02083Revision 000 Attachment A SRRS: 30.105 (when utilized for operator initial or continuing training)

NLSR02083Revision 000 Attachnlent B SRRS: 3D.105 (when utilized for operator initial or continuing training)

Limerick Generating Station Job Performance Measure Refuel Floor ARM Return to Service JPM Number: 2086 Revision Number: 000 Date: Developed By: Instructor Date Validated By: SME or Instructor Date Review By: Operations Representative Date Approved By: Training Department Date SRRS: 30.105 (when utilized for operator initial or continuing training)

NLSROJPM2086 REVOOO 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 and 12 below.

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

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

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

4. Initial setup conditions are identifi,ed.

5. Initiating and terminating cues 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. Verify the procedure referenced by this JPM matches the most current revision of that procedure:

Procedure Rev. __ Procedure __________ Rev. __ Procedure Rev. __

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

10. Verify performance time is accurate

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

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

Subsequent validations, sign and date below: SME I Instructor Date SME I Instructor Date SME I Instructor Date SRRS: 3D.1 05 (when utilized for operator initial or continuing training) Page 2 of 10

NLSROJPM2086 REVOOO REVISION RECORD (

SUMMARY

) Rev 000, N/A INITIAL CONDl"rlONS:

1.

Unit Reactor pressure vessel disassembly is in progress per M-041-200

2.

The Steam Separator has been placed in the equipment pool, Shift Management permission to return Refuel Floor ARMs to service per M-041-200 Attachment 5 has been obtained.

3.

Unit RO communication is established INITIATING CUES: You have been directed to perform M-041-200 Attachment 5, " REFUEL FLOOR ARM RETURN TO SERVICE" to return Unit _Refuel Floor ARM to service. TASK STANDARD:

1.

ARMs are returned to service and all communications are complete

2.

Tech Spec limitations identified for failed ARM 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 sE~ction 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 SRRS: 3D.105 (when utilized for operator initial or continuing training) Page 3 of 10

NLSROJPM2086 REVOOO Operator's Name: __________Job

Title:

0 SED 0 SM OSRO 0 RO o STAIIA 0 OTHER JPM

Title:

Removing Refuel ARM from Service to support Transport of Steam Dryer JPM Number: NLSROJPM2086 Revision Number: 000 Task Number and

Title:

272000-1 Perform actions to remove are radiation monitors from service I return area radiation monitors to service KIA Number and Importance: 272000 G2.1.30 IB: 4.4/4.0 Suggested Testing Environment: In-Plant Alternate Path: OVes [8jNo SRO Only: [8jVes ONo Time Critical: OVes [8jNo

References:

1. M-041-200, Rev 026 REACTOR PRESSURE VESSEL DISASSEMBLV

2. Technical Specifications Actual Testing Environment: 0 Simulator 0 Control Room 0 In-Plant 0 Other Testing Method:

[8j Simulate 0 Perform Estimated Time to Complete: 20 minutes Actual Time Used: _minutes EVALUATION

SUMMARY

Were all the Critical Elements performed satisfactorily? o Yes 0 No The operator's performance was evaluated against the standards contained in this JPM, and has been determined to be: 0 Satisfactory 0 Unsatisfactory Comments: Evaluator's Name: ________________(Print) Evaluator's Signature: Date ___ SRRS: 3D.1 05 (when utilized for operator initial or continuing training) Page 4 of 10

NLSROJPM2086 REVOOO JPM Start Time: ___ ELEMENT STANDARD SAT UNSAT Comment Number Evaluator Note:

1. Blue Equipment Status tags would be on the mode switches for the following ARM:

RIS30-M1-*K600 RIS33-M1-*K600 RIS29-M1-*K600

2. For the purpose of this JPM the evaluator will provide a cue that a Blue Equipment Status Tag is on the equipment when the candidate identifies a ARM to be operated.

If the candidate asks for a Peer Check, inform them: "For the purposes of this JPM no Peer check will be provided"

3. If step 4C of this JPM is to be performed in the AER, a Copy of Unit Technical Specification must be supplied.

1.

Obtain current revision of M-Current revision of M-041-200 041-200 "REFUEL FLOOR ARM RETURN TO SERVICE" Cue: Once the trainee obtained demonstrates the ability to locate the current revision of the procedure, provide him/her a copy of "REFUEL FLOOR ARM RETURN TO SERVICE"

2.

NOTE: This activity returns N/A N/A N/A three (3) fuel floor ARMs to service (2 of which are Criticality Monitors). SRRS: 30.105 (when utilized for operator initial or continuing training) Page 5 of 10

NLSROJPM2086 REVOOO ELEMENT STANDARD SAT UNSAT Comment Number

3.

NOTE: The following steps place Refuel Outage Unit N/A N/A N/A ARM RIS 30-M1- *K600, Steam Separator Area EI 352, ARM RIS 33-M1

K600,. Pool Plug Laydown Area EI 352 AND ARM RIS 29-M1-*K600, DIW Head Laydown Area EI 352 into service. Once the mode switch is back in operate the Reset Button may be pressed on the ARM Trip unit to clear the low or high lights.

4.

CAUTION: Placement of the ARM's back to operate may N/A N/A N/A cause a spike and a high set point alarm. For this reason the operator shall be in constant communication with the outage unit Reactor Operator while placing the switches to the operate position. IF this occurs THEN the reset shall be pressed immediately. SRRS: 3D.105 (when utilized for operator initial or continuing training) Page 6 of 10

NLSROJPM208B REVOOO ELEMENT STANDARD SAT UNSAT Comment Number

5.

At Auxiliary Equipment Room Panel *OCB05 PLACE: Mode Switch for ARM RIS30-M1-*KBOO, Steam Separator Area EI 352, to the "OPERATE" position AND REMOVE Blue Equipment Status Tag. Mode Switch for ARM RIS30-M1

KBOO, Stearn Separator Area EI 352, to the "OPERATE" position AND REMOVE Blue Equipment Cue: IF Candidate is at correct Status Tag.

ARM: -ARM mode switch is in "ZERO" position -White LOW light is lit. -There is a Blue Equipment status tag on that ARM

5.a Mode Switch for ARM RIS30-M1-*KBOO, Steam Separator Area EI 352, placed "OPERATE" Mode Switch for ARM RIS30-M 1
KBOO, Steam Separator Area EI 352, rotated to "OPERATE CUE: Mode Switch is in "OPERATE" The White LOW light is NOT lit.

5.b AND REMOVE Blue CUE: Equipment Status Tag. Equipment Status Tag is Equipment Status Tag is removed removed SRRS: 3D.105 (when utilized for operator initial or continuing training) Page 7 of 10

NLSROJPM2086 REvOOO ELEMENT STANDARD SAT UNSAT Comment Number

6.

At Auxiliary Equipment Room Panel *OC605 PLACE: Mode Switch for ARM RIS 33-M1-*K600, Pool Plug Laydown Area EI 352, to the IIOPERATE" position AND REMOVE Blue Equipment Status Tag. CUE: I F Candidate is at correct ARM: -ARM mode switch is in "ZERO" position -White LOW light is lit. -There is a Blue Equipment status tag on that ARM

6.a Mode Switch for ARM ARM RIS 33-M1-*K600, Pool Plug Laydown Area EI 352, placed "OPERATE" Mode Switch for ARM RIS33-M1
K600, Steam Separator Area EI 352, rotated to "OPERATE CUE: -Mode Switch will NOT rotate to "OPERATE"

-White LOW light is lit.

6.b Take action to identify broken component.

Take action to generate an IR, or contact Personnel contacted CUE: Actions have been taken to regarding failed ARM address Failed ARM IF Asked if task should be completed: CUE: You are directed to continue with remaining ARM SRRS: 3D.1 05 (when utilized for operator initial or continuing training) Page 8 of 10

NLSROJPM2086 REVOOO ELEMENT STANDARD SAT UNSAT Comment Number

7.

At Auxiliary Equipment Room Panel *OC605 PLACE: Mode Switch for ARM RIS 29-M1-*K600, DIW Head Laydown Area EI 352, to the "OPERATE" position AND REMOVE Blue Equipment Status Tag. CUE: I F Candidate is at correct ARM: -ARM mode switch is in "ZERO" position -White LOW light is lit. -There is a Blue Equipment status tag on that ARM

7.a CUE:

Mode Switch for ARM RIS 29-M1-*K600, DIW Head Laydown Area EI 352, placed "OPERATE" Mode Switch is in "OPERATE" Mode Switch for ARM RIS29-M1

K600, Steam Separator Area EI 352, rotated to "OPERATE" Amber HIGH light is lit RO reports UNIT _

Refueling Area Hi Radiation Annuciator has be received When Mode switch in operate

7.b From CAUTION: Placement of the ARM's back to operate may cause a spike and a high set point alarm.

IF this occurs THEN the reset shall be pressed ARM reset pressed CUE: Amber HIGH light is NOT lit RO reports UNIT_ Refueling Area Hi Radiation Annuciator has cleared. SRRS: 3D.105 (when utilized for operator initial or continuing training) Page 9 of 10

NLSRO...IPM2086 REVOOO ELEMENT STANDARD SAT UNSAT Comment l\\Jumber 7.c AND REMOVE Blue Equipment Status Tag. CUE: Equipment Status Tag is Equipmont Status Tag is Ir9moved removed

8. CUE: Refuel Floor coordinator Determine that failed ARM is a request you determine the Technical Specification implications, if any, of the failure of ARM RIS 33-M1 Criticality monitor, and Technical Specification 3.3.7.1 is applicable.
K600,. Pool Plug Laydown Area EI352 Determine that minimum channel operable requirement of 2 is met by remainin~1 ARMS (Cue: You can stop here. You have met the termination criteria for this JPM.)

JPM Stop Time ___ SRRS: 3D.1 05 (when utilized for operator initial or continuing training) Page 10 of 10

INITIAL CONOn"IONS:

1.

Unit _ Reactor pressure vessel disassembly is in progress per M-041-200

2.

The Steam Separator has been placed in the equipment pool, Shift Management permission to return Refuel Floor ARMs to service per M-041-200 Attachment 5 has been obtained.

3.

Unit RO communication is established INn"IATING CUES: You have been directed to perform M-041-200 Attachment 5, "REFUEL FLOOR ARM RETURN TO SERVICE" to return Unit Refuel Floor ARM to service. SRRS: 3D.105 (when utilized for operator initial or continuing training)

Limerick Generating Station Job Performance Measure Install Rod Positiotn Test Box (LGS) JPM Number: 2029 Revision Number: 005 Date: Developed By: Instructor Date Validated By: SME or Instructor Date Review By: Operations Representative Date Approved By: Training Department Date SRRS: 30.105 (when utilized for operator initial or continuin~1 training)

NLSROJPM2029 REV005 JOB PERFORMANCE MEASUFtE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 9 and 12 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, or simulator)

4. Initial setup conditions are identified.

5. Initiating and terminating cues 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. Verify the procedure referenced by this JPM matches the most current revision of that procedure:

Procedure Rev. __ Procedure ________ Rev. __ Procedure _________ Rev. __

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

10. Verify performance time is accurate

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

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

Subsequent validations, sign and date below: SME I Instructor Date SME I Instructor Date SIVIE I Instructor Date SRRS: 3D.105 (when utilized for operator initial or continuing training) Page 2 of 7

NLSROJPM2029 REV005 REVISION RECORD (

SUMMARY

) Rev 005, Updated based on procedure revision, new format no rev marks used INITIAL CONDn"IONS:

1.

ST-6-097-630-_ is in progress and has bt~en completed through step ____ INITIATING CUES: You have been directed to directed you to pHrform ST-6-097-630-step ____. install the Rod Position Test Box on Unit __ TASK STANDARD: Test Box Cable connected at AER panel, activity controls numbers verified. 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 SRRS: 30.105 (when utilized for operator initial or continuing training) Page 3 of 7

NLSROJPM2029 REV005 Operator's Name: __________J.ob

Title:

D SED D SM DSRO D RO D STAlIA D OTHER JPM

Title:

Install Rod Position Test Box (LGS) JPM Number: NLSROJPM2029 Revision Number: 005 Task Number and

Title:

234000-8L, Refuel Platform Surveillance Testing KIA Number and Importance: 214000 A4.01 3.2/3.3 Suggested Testing Environment: In-Plant Alternate Path: DYes [ZINo SRO Only: [ZIYes ONo Time Critical: DYes [ZINo

References:

1. ST-6-097-630-*, Core Alteration Testing for Offloading, Shuffling and Reloading the Core Actual Testing Environment: D Simulator D Control Room Din-Plant D Other Testing Method:

[ZI Simulate D Perform Estimated Time to Complete: 20 minutes Actual Time Used: _minutes EVALUATION

SUMMARY

Were all the Critical Elements performed satisfactorily? Q Yes Q No The operator's performance was evaluated against the standards contained in this..IPM, and has been determined to be: Q Satisfactory Q Unsatisfactory Comments: Evaluator's Name: _____________________{Print) Evaluator's Signature: Date ----- SRRS: 30.105 (when utilized for operator initial or continuing training) Page 4 of 7

NLSROJPM2029 REV005 JPM Start Time: ___ ELEMENT STANDARD SAT UNSAT Comment Number Evaluator note: Prior to each candidate stating JPM place single rod test box switch to position Evaluator note: If candidate asks for a peer check, cue them that for the purposes of this JPM

1.

ill be provided. Perform the following to install test box in NIA N/A Auxiliary Equipment Room

2.

REQUEST Reactor Operator to select rod 38-59. LSRO requests the Unit RO select rod 38-59. CUE: Unit RO reports that rod 38-59 is selected. Evaluator Note: - The front of the cabinet reads *OC615 (BAY A) the back of the cabinet reads *OC615 (BAY B) the cabinet should be entered from the back. - The cannon plug connections are labeled at the bottom of each connection point.

3.

DISCONNECT four rod Four rod group J38-63 cannon plug is group J38-63 at panel disconnected.

OC615 (BAY B).

CUE: Four rod group cannon plug J38-63 is disconnected.

4.

IF using single rod test Single Rod Test box switch moved to box, THEN POSITION position "00". test box as follows, OTHERWISE ENTER N/A. SWITCH POSITION 38-59 00 SRRS: 3D.1 05 (when utilized for operator initial or continuing training) Page 5 of 7

NLSRO..IPM2029 REV005 ELEMENT STANDARD SAT UNSAT Comment Number

5.

IF using 4-rod test box, N/A N/A THEN POSITION test box switches as follows, OTHERWISE ENTER N/A.

6.

All test box switches N/A N/A initially in the DOWN position.

7.

Cable end 1,0 (Rod 38-N/A N/A

59) switch "00" in the UP position.

8.

Cable end 1,0 (Rod 34-N/A N/A

59) switch "00" in the UP position.

9.

CONNECT test box Test box cannon+ plug connected. cable to connector J38 63 at panel *OC615 (Bay B). CUE: Test box group cannon plug is connected to J38

63.

10.

REQUEST Reactor Reactor Operator Requested to Operator to verify that verify that indicated position of rods indicated position of rods 38-59 AND 34-59 is 00 on the 4 rod 38-59 display. OR PMS Control Rod AND 34-59 is 00 on the 4 Position Screen. rod display. OR PMS Control Rod Position Screen. CUE: Reactor Operator has verified that indicated position of rods 38-59 AND 34-59 is 00 on the 4 rod display.

11.

VERIFY the following at N/A N/A panel *OC616 Activity Control No's 1 AND 2: SRRS: 3D.1 05 (when utilized for operator initial or continuing training) Page 6 of 7 I

NLSROJPM2029 REV005 ELEMENT STANDARD SAT UNSAT Comment Number 11a. Rods Not Full In, Box FI Rods Not Full In, Box FI LEDs are LEDs are not Lit verified not lit CUE: Rods Not Full In, Box FI LEDs are not Lit 11b. Grapple Load, Box PG Grapple Load, Box PG LEDs LEDs are not Lit verified not lit CUE: Grapple Load, Box PG LEDs are not Lit 11c. Overcore, Box Pc LEDs Overcore, Box Pc LEDs verified not are not Lit lit CUE: Overcore, Box Pc LEDs are not Lit (Cue: You can stop here. You have met the termination criteria for this JPM.) JPM Stop Time ___ SRRS: 30.105 (when utilized for operator initial or continuing training) Page 7 of 7

INITIAL CONDITIONS:

1.

ST 097 -630-_ is in progress and has been completed through step ____ INITIATING CUES: You have been directed to directed you to perform ST-6-097-630-_ step ____ install the Rod Position Test Box on Unit ___ SRRS: 3D.105 (when utilized for operator initial or continuing training)

Exelon Nuclear Job Performance Measure LSRO Only - Limerick, Movement ()f fuel 'from the fuel prep machine (Alternate Path, New Fuel Drops) JPM Number: NLSR02080 Revision Number: 000 Date: Developed By: D. M Monahan Instructor Date Val idated By: SME or Instructor Date Reviewed By: Operations RE~presentative Date Approved By: Training D,epartment Date SRRS: 3D.1 05 (when utilized for operator initial or continuing training)

NLSR02080Revision 000 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 and 12 below.

1.

Task description and number,,JPM description and number are identi'fied.

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.

Verify the procedure(s) referenced by this JPM reflects the current revision: Procedure ON-120 Rev: __ Procedure S97.0.M Rev: -

9.

Verify cues both verbal and visual are free of conflict.

10. Verify performance time is accurate

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

12. 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 SRRS: 3D.105 (when utilized for operator initial or continuing training) Page 2 of 12

NLSR02080Revision 000 REVISION RECORD (Summary)

1. Revision 00 Nt A SIMULATOR SETUP INSTRUCTIONS

1. NtA for In plant TASK CONDITIONS:

1. New Fuel Receipt is in progress

2. A New Fuel Bundle is ready for pickup in the Unit _North fuel preparation machine and release in the spent fuel pool

3. Prerequisites of S97.0.M have been met

4. The refueling platform is in operation and positioned over the fuel preparation machine

5. GE personnel are stationed at the fuel preparation machine INITIATING CUES:

You are the Fuel Handling Director and have been directed to perform the fuel transfer listed in the attached CeTAS TASK STANDARD(S): ON-120 has been entered for new fuel bundle or New Fuel Rod (pin) Dropped or Damaged AND no other symptoms present:

Health Physics has been notified to evaluate radiological condiions
Reactor Engineering has been notified Information for Evaluator's Use:

Any UNSAT requires written comments on respectivH step. Denotes critical steps Number any comments in the "Comment Number" c()lumn 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 SRRS: 3D.1 05 (when utilized for operator initial or continuing training) Page 3 of 12

NLSR02080Revision 000 JPM

SUMMARY

Operator's Name:___________Job

Title:

O SED 0 SM OSRO o ST AliA ~ OTHER JPM

Title:

Movement of fuel from the fuel prep machine (Alternate Path, New Fuel Drops) ..IPM Number: I\\ILSR00280 Revision Number: 000 Task Number and

Title:

295023-2, Perform Actions for Dropped or Damaged Fuel KIA Number and Importance: 295023, AA2.04 RO: 3.4 SRO: 4.1 Suggested Testing Environment: Refuel Platform Alternate Path: ~Yes ONo SRO Only: ~Yes ONo Time Critical: DYes ~No Reference( s): Procedure _O=.:...,:N'--1:..:2=0______ Rev: 19 Procedure _S=97:...:..:;:.0:.:.,:.M:.!..-_____ Rev:

28=--

Actual Testing Environment: 0 Simulator 0 Control Room ~ In-Plant 0 Other Testing Method: ~ Simulate 0 Perform Estimated Time to Complete: 20 minutes Actual Time Used: minutes EVALUATION

SUMMARY

Were all the Critical Elements performed satisfactorily? DYes ONo The operator's performance was evaluated against standards contained within this JPM and has been determined to be: o Satisfactory 0 Unsatisfactory Comments:______________._________________ Evaluator's Name: _________________ (Print) Evaluator's Signature: __________, Date: _____ SRRS: 30.105 (when utilized for operator initial or continuing training) Page 4 of 12

NLSR02080Revision 000 JPM Start Time: ____ Critical Element(s) indicated by"*" in Performance Checklist. STEP ELEMENT STANDARD I <C I <C z c... (1)1: EE E:;s Oz 0 Evaluator note: Give the following to the candidate at the start of the JPM:

UNIT specific CCTAS
S97.0.M, "Refuel Platform Operation" S97.0.M Section 4.10, Pickup Location - Fuel Preparation Machine

1.

VERIFY Fuel Prep Machine carriage is fully LOWERED. CUE: Fuel Prep Machine Carriage is fully lowered

2.

CAUTION: Use extreme care to avoid entanglement of main mast or grappled fuel bundle with fuel inspection and test equipment located in the vicinity of the fuel prep machines. I

3.

Carefully POSITION Refuel Platform Mast over fuel prep machine in accordance with Core Component Move Sheet. CUE: The bridge is positioned over the fuel prep machine.

4.

LOWER grapple until grapple is near bail. CUE: RPO directed to Lower the grapple until the grapple in near the bail handle. The grapple is lowered, and the encoder reads 157 inches I Verify fuel prep machine is fully lowered (Note: Normally performed by NMO, not the LSRO) N/A The bridge is positioned over the 'fuel prep machine. RPO directed to Lower grapple until the grapple is near bail handle SRRS: 3D.105 (when utilized for operator initial or continuing training) Page 5 of 12

NLSR020S0Revision 000 STEP ELEMENT

5.

ENSURE grapple is open. CUE: The grapple switch is in RELEASE with no backlight

6.

ROT ATE grapple as necessary to achieve grapple to bail alignment. CUE: The grapple head is aligned to the bail handle with a north east orientation

7.

Slowly LOWER grapple until SLACK CABLE Light is lit. CUE: RPO directed to Slowly LOWER grapple until SLACK CABLE Light is lit. The grapple is lowered the SLACK CABLE Light is lit S. FHD &Spotter, PERFORM Concurrent Verification of proper core component location AND orientation. CUE: Spotter has verified The bundle is in the North Fuel Prep Machine, and the bundle is oriented north east. Concurrent Verification is satisfied for this step of the JPM

9.

FHD, VERIFY the following, 9.a

SLACK CABLE Light is lit CUE: SLACK CABLE Light is lit 9.b
Grapple is centered over bail handle CUE: Grapple is centered over the bail handle c...

t-G>! STANDARD <C tn E E tn Z E ::s

l Oz 0

Grapple Ensured open RPO directed to ROTATE grapple as necessary to achievl3 grapple to bail alignment. RPO directed to Slowly LOWER grapple until SLACK CABLE Light is lit. Spotter directed to PERFORM Verification of proper core component location AND orientation. N/A N/A N/A SLACK CABLE Light is verified lit Grapple is verified centered over the bail handle SRRS: 3D.105 (when utilized for operator initial or continuing training) Page 6 of 12

NLSR02080Revision 000 I S"rEP ELEMENT 9.c Hoist Position indication agrees with Attachment 2 for item seated in fuel prep machine. CUE: Hoist position indicates 167.5 inches

10.

RPO, VERIFY the following,

SLACK CABLE Light is lit
Grapple is centered over bail handle
Hoist Position indication agrees with Attachment 2 for item seated in fuel prep machine.

CUE: RPO verified: SLACK CABLE Light is lit, Grapple is centered over the bail handle, and Hoist position indicates 167.5 inches

11.

THEN WHEN directed by FHD, ENGAGE grapple CUE: RPO is directed to engage grapple. Grapple is engaged.

12.

FHD & RPO, PERFORM Peer Check that GRAPPLE ENGAGED Light is lit. CUE: RPO verifies Grapple engaged light is light, Peer Check is satisfied for this step of the JPM STANDARD Hoist position verified N/A FHD Directs RPO to ENGAGE grapple Grapple control switch verified to have green backlight lit e Ii... l-CD CD oCt !¢ en E.D E E en Z o :::J

)

OZ i I SRRS: 30.105 (when utilized for operator initial or continuing training) Page 7 of 12

NLSR02080Revision 000 c:.. Q) Q) t- ~ e.o U) STEP ELEMENT STANDARD c( U) Z E e o:::J

J OZ

13.

Slowly RAISE load AND VERIFY FUEL LOADED Light is lit RPO directed to Slowly RAISE load AND VERIFY FUEL CUE: RPO is directed to Slowly LOADED Light is lit Raises the bundle and verify FUEL LOADED light is lit. Bundle is slowly being raised. Alternate Path Starts Here CUE: You feel a vibration of the refuel platform structure, and observe the fuel assembly dropping. Next to the fuel prep machine, and landing on the fuel pool liner.

14.

Recognize Dropped New Fuel Assembly, exit S97.0.M and enter ON-120 CUE, If Asked: No Fuel Floor ARM are in alarm No Irradiated fuel was damaged

15.

Obtain copy of ON-120, Fuel Procedure ON-120 Obtained Handling Problems - Procedure

16.

Refer to section for: IF a new fuel bundle OR new Fuel Rod (Pin) is dropped or damaged N/A AND no other symptoms are present THEN PERFORM the following:

17.

NOTIFY Health Physics to evaluate radiological conditions. Health Physics notified to CUE: Health Physics has been evaluate radiological conditions. notified to evaluate radiological conditions.

18.

NOTIFY Reactor Engineering. Reactor Engineering notified CUE: Reactor Engineering has been notified You have met the termination criteria for this JPM SRRS: 3D.1 05 (when utilized for operator initial or continuing training) Page 8 of 12

NLSR02080Revision 000 JPM Stop Time: SRRS: 30.105 (when utilized for operator initial or continuing training) Page 9 of 12

NLSR02080Revision 000 TASK CONDITIONS:

1. New Fuel Receipt is in progress

2. A New Fuel Bundle is ready for pickup in the Unit _North fuel preparation machine and release in the spent fuel pool

3. All prerequisites are complete, with FHM106 and S97.0.M in progress

4. The refueling platform is in operation and positioned over the fuel preparation machine

5. GE personnel are stationed at the fuel preparation machine INITIATING CUES:

You are the Fuel Handling Director and have been directed to perform the fuel transfer listed in the attached CCT AS SRRS: 30.105 (when utilized for operator initial or continuing training)

TRANSf.......1 AUTHORIZATION FOR FH-106 Page _1_ of _' TRAINING USE ONLY

A## MV U# TRAINING USE ONLY RECORD TYPE #3B.1 08 Written By: TRAINING USE aNL Y Unit LIMERICK GENERATING STATION UNIT 1 Date ##1##1##

Reviewed By: TRAINING USE aNLY Title TRAINING CCTAS Authorized By: TRAINING USE aNL Y ~~~~~~- STEP NO. COMPONENT MOVE FROM ORIENT MOVE TO ORIENT FHD RPO CRO DATE TIME SERIAL NO. 1 LYN521 NFPM NE L2SPENT C-21 sw SRRS: 30.105 (when utilized for operator initial or continuing training)

TRANS~.... I-{ AUTHORIZATION FOR FH-106 Page _1_ of _. TRAINING USE ONLY

A## MV U# TRAINING USE ONLY RECORD TYPE #3B.1 08 Written By: TRAINING USE ONLY Unit LIMERICK GENERATING STATION UNIT 2 Date ##/##/##

Reviewed By: TRAINING USE ONLY Title TRAINING CCTAS Authorized By: TRAINING USE ONLY STEP NO. COMPONENT MOVE FROM ORIENT MOVE TO ORIENT FHD RPO CRO DATE TIME SERIAL NO. 1 LYN521 NFPM NE USPENT C-21 SW SRRS: 3D.1 05 (when utilized for operator initial or continuing training)

Exelon Nuclear Job Performance Measure LSRO Only - Limerick, Spent Fuel Pool Makeup using Fire System standpipes (TSG-4.1) JPM Number: NLSR02082 Revision Number: 000 Date: _____ Developed By: D. M Monahan Instructor Date Validated By: SME or Instructor Date Reviewed By: Operations RElpresentative Date Approved By: Training Department Date SRRS: 30.105 (when utilized for operator initial or continuing training)

NLSR02082Revision 000 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NO"rE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM usin~~ steps 9 and 12 below.

1.

Task description and number,..IPM 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.

Verify the procedure(s) referenced by this..IPM reflects the current revision: Procedure TSG-4.1 Rev: Procedure Rev: -

9.

Verify cues both verbal and visual are free of conflict.

10. Verify performance time is accurate

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

12. When JPM is initially validated, sign and date JPM cover page. Subsequent validations, sign and date below:

SME I Instructor Date SME !Instructor Date SME !Instructor Date SRRS: 30.105 (when utilized for operator initial or continuing training) Page 2 of 7

NLSR02082Revision 000 REVISION RECORD (Summary)

1. Revision 00 NI A SIMULATOR SETUP INSTRUCTIONS

1. N/A for In-plant TASK CONDITIONS:

Unit 1 is in OPCON 4 Fuel Pool Gates are installed An earthquake results in the a Loss of Offsite Power, NO Unit 1 Diesels are running As a result of the earthquake a small leak has developed in the Unit 1 Fuel Pool The Diesel Driven Fire Pump is running Health Physics is monitoring Radiological conditions on the Refuel Floor INITIATING CUES: You are directed to supply an internal 500 gpm makeup source to the UNIT 1 Spent Fuel Pool from the fire system using: TSG 4.1 "LIMERICK GENERATING STATION OPERATIONAL CONTINGENCY GUIDELINES", Attachment 1 "INTERNAL SPENT FUEL POOL MAKEUP STRATEGY". OPTION 1- "ADD Fire Water to spent fuel pool using two (2) Fire System standpipes" TASK STANDARD(S): 1st Refuel Floor Fire Protection System Standpipe valves opened with flow directed into the Unit 1 Fuel pool. 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 al)ceptable 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 SRRS: 3D.105 (when utilized for operator initial or continuing training) Page 3 of 7

NLSR02082Revision 000 JPM

SUMMARY

Operator's Name:.___________,lob

Title:

O SED 0 SM OSRO D STAliA IZI OTHER JPM

Title:

Limerick, Spent Fuel Pool Makeup using Fire System standpipes (TSG-4.1) JPM Number: NLSR00282 Revision Number: 000 Task Number and

Title:

295023-1, Perform Actions to respond to unexpected loss of level in the spent fuel pool, reactor cavity, and the equipment pit KIA Number and Importance: 295023, AA2.02 RO: 3.4 SRO: 3.7 Suggested Testing Environment: Refuel Platform Alternate Path: DYes IZINo SRO Only: IZIYes ONo Time Critical: DYes [gJNo Reference(s): Procedure _T...:...S=G:....-4..:...:.~1______ Rev:-1L__ Procedure ___________ Rev: _____ Actual Testing Environment: 0 Simulator 0 Control Room [gJln-Plant 0 Other Testing Method: IZI Simulate 0 Perform Estimated Time to Complete: 20 minutes Actual Time Used: minutes EVALUATION

SUMMARY

Were all the Critical Elements performed satisfactorily? DYes ONo The operator's performance was evaluated against standards contained within this JPM and has been determined to be: o Satisfactory 0 Unsatisfactory Comments:--------------------------------------------------- Evaluator's Name: ______________________ (Print) Evaluator's Signature: ___________________ Date: ______ SRRS: 30.105 (when utilized for operator initial or continuing training) Page 4 of 7

NLSR02082Revision 000 JPM Start Time: ____ Critical Element(s) indicated by "*,, in Performance Checklist. c... !;( - CD CD §!5f ELEMENT STANDARD !;( tJ) e.Q tJ) e e Z o :s

l OZ LGS OPERATIONAL CONTINGENCY GUIDELINES TSG-4.1 AnACHMENT 1 INTERNAL SPENT FUEL POOL MAKEUP STRATEGY Evaluator Note:

- Exam Key rings contain a Cat 198 Key, required to open cabinets. - Storage cabinet on U 1 North wall is behind the office hallway in a contaminated area. - All actions will be simulated including entry into contaminated areas.

1.

This guidance can be used to supply an internal 500 gpm N/A makeup source to the spent fuel pool from the fire system.

2.

WARNING: Radiological conditions and plant damage state must be considered when selecting fire systems standpipes to be used for this strategy. N/A IF Asked: CUE: Health Physics reports Radiation levels are normal SRRS: 3D.105 (when utilized for operator initial or continuing training) Page 5 of 7

NLSR02082Revision 000 STEP ELEMENT

3.

NOTE: 400 ft of 3" hose is staged in each cabinet, one along the north wall of the Unit 1 fuel floor behind the reactor services office AND the second near the PCMs on the east end of the Unit 2 refuel floor. To obtain the 500 gpm makeup flow rate 2 - 3" hoses are required. Two different hose routing options are provided below. Refer to Figure 1 AND Figure 2 for fire standpipe locations. IF hose on refuel floor is inaccessible, additional 3" hose can be obtained from the B.5.b Hose Trailer.

4.

OPTION 1-ADD Fire Water to spent fuel pool using two (2) Fire System standpipes located on refuel floor as follows: c... CI)~ I- ~ STANDARD <C (/) EE (/) z E j ~ Oz 0 NIA NOTE: Initial conditions direct performance of OPTION 1 "ADD Fire Water to spent fuel pool using two (2) Fire System standpipes" NIA Evaluator Note Cue the Candidate: - Access to the cabinet on the North Wall of Unit 1 is not accessible due to equipment damage from the earthquake. - For the purposes of this JPM you are not expected to enter any Contaminated areas. Simulate the performance of these steps using equipment found outside Contaminated areas.

5.

ROUTE fire hoses from affected spent fuel pool to two Hoses routed from two different different fire standpipes fire standpipes to Unit 1 fuel (Figures 1 and 2 show pool standpipe locations) CUE: Hoses have been routed SRRS: 3D.105 (when utilized for operator initial or continuing ttraining) Page 6 of 7

I 6 NLSR02082Revision 000 e:: " l-G) G) I-e.Q STEP ELEMENT STANDARD <n e e <n Z o :::J

)

(Jz SECURE hose ends at rail to spent fuel pool at floor elevation using ty-wraps staged in the Hose ends secured at rail to storage cabinets. spent fuel pool using ty-wraps CUE: Hose ends are ty-wraped to fuel pool rail

7 REMOVE existing hose at fire standpipe AND reducing Hose removed from standpipe coupling from 1st selected fire AND reducing coupling standpipe valve.

removed from 1st standpipe CUE: Hose is removed from valve Standpipe, and coupling is removed from standpipe valve

8 CONNECT 2 Y2" X 3" Storz adapter to fire standpipe valve AND CONNECT hose to Storz adapter connected to fire adapter.

standpipe valve and hose connected to adapter CUE: Storz adapter connected to fire standpipe valve and hose connected to adapter

9 Slowly OPEN 1ST standpipe valve to obtain desired flow rate.

Standpipe slowly opened after 20 seconds Cue: You have obtained the desired flow rate You have met the termination,criteria for this JPM JPM Stop Time: _____ SRRS: 3D.105 (when utilized for operator initial or continuing training) Page 7 of 7

TASK CONDITIONS: Unit 1 is in OPCON 4 Fuel Pool Gates are installed An earthquake results in the a Loss of Offsite Power, NO Unit 1 Diesels are running As a result of the earthquake a small leak has developed in the Unit 1 Fuel Pool The Diesel Driven Fire Pump is running Health Physics is monitoring Radiological conditions on the Refuel Floor INITIATING CUES: You are directed to supply an internal 500 gpm makeup source to the UNIT 1 Spent Fuel Pool from the fire system using: TSG 4.1 "LIMERICK GENERATING STATION OPERATIONAL CONTINGENCY GUIDELINES", Attachment 1 "INTERNAL SPENT FUEL POOL MAKEUP STRATEGY". OPTION 1- "ADD Fire Water to spent fuel pool using two (2) Fire System standpipes" SRRS: 3D.105 (when utilized for operator initial or continuing training)

Exelon Nuclear Job Performance Measure LSRO Only - Limerick Enlergency Classification (TIME CRITICAL) ,"'PM Number: NLSR02081 Revision Number: 000 Date: Developed By: D. M Monahan Instructor Date Validated By: SM E or Instructor Date Reviewed By: Operations Representative Date Approved By: Training Department Date SRRS: 30.105 (when utilized for operator initial or continuing training)

LLOJPM0131, Revision 001 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 and 12 below.

1.

Task description and number,..IPM 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 idenUfied.

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.

Verify the procedure(s) referenced by this JPM reflects the current revision: Procedure EP-AA-1008 Rev: - Procedure EP-AA-111 Rev: -

9.

Verify cues both verbal and visual are free of conflict.

10. Verify performance time is accurate

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

12. 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 SRRS: 30.105 (when utilized for operator initial or continuing! training) Page 2 of 2

LLOJPM0131, Revision 001 REVISION RECORD (Summary)

1. Revision 00 N/ A SIMULATOR SETUP INSTRUCTIONS

1. This JPM can be performed in any quiet area

2. Provided appropriate Emergency Plan documents INITIAL CONDITIONS

1.

Unit 1 is at 100% power

2.

Unit 2 plant conditions are as follows:

Day 4 of refueling outage
Reactor cavity is flooded to + 494"
"28" RHR is in SDC
"2A" RHR heat exchanger out-of-service
Reactor coolant temperature 167 of
Secondary Containment Closure is not established

3.

The following sequence of events occurs: 0200 "28" RHR Pump trips. Restart attempts are unsuccessful 0215 "28" Reactor Recirculation Pump is started. Reactor coolant temperature is 195°F and rising. 0226 Cause of "28" RHR Pump trip identified as breaker fault. The breaker will be swapped out. Reactor coolant temperature is 201°F and rising. 0238 "28" RHR Pump restarted. Reactor coolant temperature is 225°F and going down. INn"IATING CUE This task is Time Critical

1. This JPM will start when you tell the evaluator that you are aware of task conditions and are ready to begin. The starting time will be 0323.

2. No prior classifications or notifications have been made. You are required to:

Make the highest classification based on the given plant conditions AND
Determine the time the associated EAL Threshold Value(s) was/were exceeded SRRS: 30.105 (when utilized for operator initial or continuing training)

Page 3 of 3

LLOJPM0131, Revision 001 TASK STANDARD(S): Trainee makes the highest classification and determines the time the threshold was exceeded in the appropriate time. 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 SRRS: 3D.105 (when utilized for operator initial or continuing training) Page 4 of 4

LLOJPM0131, Revision 001 JPM

SUMMARY

Operator's Name: ___________Job

Title:

O SED 0 SM OSRO o STAliA ~ OTHER JPM

Title:

SRO Only - Emergency Classification JPM Number: NLSR02081 Revision Number: 000 Task Number and

Title:

295023-6, Determine Emergency Classification relative to fuel handling and storage KIA Number and Importance: 2.4.41 RO: 2.9 SRO: 4.6 Suggested Testing Environment: Simulator or guiet area with appropriate Emergency Plan documents Alternate Path: DYes ~No SRO Only: ~Yes ONo Time Critical: ~Yes ONo Reference(s): Procedure EP-AA-1008 Rev: --.11___ Procedure EP-AA-111 Rev: 15 ~""'--- Actual Testing Environment: 0 Simulator 0 Control Room 0 In-Plant ~ Other Testing Method: 0 Simulate ~ Perform Estimated Time to Complete: 10 minutes Actual Time Used: minutes EVALUATION

SUMMARY

Were all the Critical Elements performed satisfactorily? DYes ONo The operator's performance was evaluated against standards contained within this JPM and has been determined to be: o Satisfactory 0 Unsatisfactory Comments:_______________________________________________________________ Evaluator's Name: ________________________ (Print) Evaluator's Signature:, ___________ Date: ______ SRRS: 30.105 (when utilized for operator initial or continuing training) Page 5 of 5

LLO..IPM0131, Revision 001 JPM Start Time: ____ STEP ELEMENT STANDARD ~ en ~ en z

l -

cr... CD! E E E ::s oz 0 NOTE: IF another SRO is requested to perform an independent Peer Check CUE: A Peer Check will !!.Q! be provided for this JPM

1.

Review the Initiating Conditions applicable to the operating mode EAL Matrix(s) used to classify event

2.

Determine Threshold Value has been met or exceeded, Determine Alert initiating conditions have been exceeded MA5 Threshold 1

3.

Determine the time the associated EAL Threshold Value was exceeded MAS Threshold 1, was exceeded at 0226 You have met the termination criteria for this JPM JPM Stop Time: SRRS: 30.105 (when utilized for operator initial or continuing training) Page 6 of 6

LLOJPM0131, Revision 001 INITIAL CONDITIONS: 1. Unit 1 is at 100% power

2.

Unit 2 plant conditions are as follows:

Day 4 of refueling outage
Reactor cavity is flooded to + 494"
"28" RHR is in SDC
"2A" RHR heat exchanger out-of-service
Reactor coolant temperature 167 of
Secondary Containment Closure is not established

3.

The following sequence of events occurs: 0200 "28" RHR Pump trips. Restart attempts are unsuccessful 0215 "28" Reactor Recirculation Pump is started. Reactor coolant temperature is 195°F and rising. 0226 Cause of "28" RHR Pump trip identified as breaker fault. The breaker will be swapped out. Reactor coolant temperature is 201°F and rising. 0238 "28" RHR Pump restarted. Reactor coolant temperature is 225°F and going down. INITIATING CUE:

1. This JPM will start when you tell the evaluator that you are aware of task conditions and are ready to begin.

2. No prior classifications or notifications have been made. You are required to:

Make the highest classification based on the given plant conditions AND
Determine the time the associated EAL ThrE~shold Value(s) was/were exceeded SRRS: 30.105 (when utilized for operator initial or continuing training)

EXELON NUCL.EAR Nuclear Generiition Group OJTrrPE MATERIAI_ COVERSHEET ~ ..IPM QUALIFICATION MANUAL OJTMODULE NLSRO Initial and NLSRO Requal NLSRO 00 G. W. Zellmer Bridge End Structure Panel Lineup APPROVALS: Signature I Title Date Signature I Title Date Signature I Title Date Signature I Title Date \\PPROVED FOR USE: Signature I Title Date EFFECTIVE DATE: __----' ___---'___ NAME: ISSUE DATE: Last First M.I. EMPLOYEE 10 NO. COMPLETION DATE: COMMENTS: Training Review for Completeness: LMSCODE: LMS ENTRY: Signature/Date NLSRO-3069 RevOOO Page 1 of 9

-'.'~--'--------~-'I <<,~ _______ __________ EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE: Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR: 234000 NLSRO-~1069 KIA: 234000K5.01 RO: 2.9 SRO: 3.4 TASK DESCRIPTION: Refuel Platform Pre Operational Checkoff List A. NOTES TO EVALUATOR:

1.

An asterisk (*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.

2.

System cues included in the performance checklist are to be provided to the examinee when no system response is available.

3.

JPM Performance

a.

"Control Room" JPMs are designed to be performed in the simulator. If a "Control Room" JPM is to be performed in the Control Room all perform steps (P) shall be simulated (S).

b.

When performing "In-Plant"..IPlVls, no equipment will be operated without Shift Management approval.

4.

Satisfactory performance of this JPM is accomplished if:

a.

The task standard is met.

b.

..IPM completion time requirement is met.

1)

For non-time critical JPMs, completion within double the estimated time (listed in paragraph 0.2) iis acceptable provided the evaluator determines that the progress to completion is acceptable.

2)

For time critical JPMs, completion within the estimated time (listed in paragraph D.2) is required.

5.

The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee. NLSRO-3069 RevOOO Page 2 of 9

6.

Evaluator(s) must be particularly cognizant of the potential for a foreign material event (FME) to occur. Beside the need for exam security (maintaining control of the JPM and associated exam paperwork), there is a risk for the evaluator to lose control of paper and/or pens (refer to issue 01001205).

7.

This JPM is designed to be given on th,e Refuel Floor (either Unit 2 or Unit 3). This JPM may be performed on the Refuel Platform. B. TOOLS AND EQUIPMENT

1.

Access to PBAPS procedure SO 18.1.C-2(3) 'Electrical, Mechanical, and Pneumatic Alignment / Checkout of Refueling Platform

2.

Access to Limerick procedure S97.1.A 'Electrical, Mechanical, and Pneumatic Alignment I Checkout of Refueling Platform Bridge, Trolley, and Main Hoist for Operation'

3.

'Task Conditions I Prerequisites & Initiating Cue' sheet C. REFERENCES

1.

SO 18.1.C-2(3) Rev. 2; Electrical, Mechanical And Pneumatic Alignment/Checkout Of Refueling Platform

2.

S97.1.A Rev. 21 'Electrical, Mechanical, and Pneumatic Alignment / Checkout of Refueling Platform Bridge, Trolley, and Main Hoist for Operation. D. TASK STANDARD

1.

Satisfactory task completion is indicated when SO 18.1.C-2(3) section 4.2 'Bridge End Structure Panel Lineup' is complete.

2.

Estimated time to complete: 20 minutes Non-Time Critical E. DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to align the (Unit 2/ Unit 3) Refuel Platform Bridge 'End Structure' for operation IJsing appropriate procedures. I will describe initial plant conditions and provide you access to the materials required to complete this task. NLSRO-3069 RevOOO Page 3 of 9

F. TASK CONDITIONS/PREREQUISITES 1. The Refuel Platform is being returned to service following maintenance.

2.

The Refuel Platform clearances have been removed by operations; tags were removed with the equipment out of service so the system operating procedures would be used to lineup the Refuel Platform.

3.

All SO 18.1.C-2(3) 'Electrical, Mechanical, and Pneumatic Alignment / Checkout of Refueling Platform' procedure prerequisites and precautions are met and step 4.1 is complete. G. INITIATING CUE The Control Room Supervisor directs you to perform the (Unit 2/ Unit 3) Refuel Platform Bridge End Structure Panel Lineup in accordance with SO 18.1.C-2(3) step 4.2. The Control Room Supervisor gives you permission to operate the components identified in SO 18.1.C-2(3) as necessary to place the Refuel Platform into alignment with step 4.2 of SO 18.1.C-2(3). NLSRO-3069 RevOOO Page 4 of 9

_rt H. PERFORMANCE CHECKLIST II STEP STEP ACT STANDARD NO Notes to Evaluator A. In addition to the Task Conditions/Prerequisites and Initiating Cue Sheet, the examinee should also be given a copy of SO 18.1.C-2 or SO 18.1.C-3 as appropriate. B. Evaluator may record the JPM start time here: 1 Verify the 2(3)OS947 A 'Main Disconnect S Verify the 2(3)OS947A 'Main Disconnect Switch' is 'ON'. Switch' is in the "ON" position. (CUE: The Disconnect 2(3)OS947A Disconnect Handle is in the 'Full Down' position.) (CUE: If the examinee reports to the Control Room Supervisor that while performing SO 18.1.C-2[3] an unexpected condition occurred [component not in position as stated in the procedure], Then provide the following "The Refuel Platform is being returned to service following maintenance via the system operating procedures, you have permission to operate the components identified in SO 18.1.C-2[3] as necessary to place the Refuel Platform into alignment with step 4.2 of SO 18.1.C 2[3].")

2 Examinee moves the operating handle of S

Operating handle of the 2(3)OS947A is the 2(3)OS947A in the up direction until moved from the 'Full Down - OFF' handle is aligned with the 'ON' position position to the 'Full Up -- ON' position label. (CUE: The component that you identified is in the condition that you described.) II I NLSRO-3069 RevOOO Page 5 of 9

_..-IlIfIlII. rtr STEP NO STEP ACT STANDARD 3 Verify the 2(3)OS261 A 'Mono Hoist Disconnect Switch' is 'ON'. S Verify the 2(3)OS261 A 'Mono Hoist Disconnect Switch' is in the 'ON' position. (CUE: The Disconnect 2(3)OS261A Disconnect Handle is in the 'Full Down' position.)

4 Examinee moves the operating handle of the 2(3)OS261 A Disconnect in the up direction until handle is aligned with the

'ON' position label. S Operating handle of the 2(3)OS261 A is moved from the 'Full Down - OFF' position to the 'Full Up -- ON' position (CUE: The component that you identified is in the condition that you described.) 5 Verify the CB-D 'Air Dryer Breaker' is 'ON'. (CUE: The CB-D 'Air Dryer Breaker' toggle is in the 'Full Up' position.) S Verify the CB-D 'Air Dryer Breaker' toggle is in the 'ON' position. 6 Verify the CB-2 'GFI Outlet Breaker' is 'ON'. S Verify the CB-2 'GFI Outlet Breaker' toggle is in the 'ON' position. (CUE: CB-2 'GFI Outlet Breaker' toggle is in the 'Full Up' position.) 7 Verify the CB-3 'GFI Outlet Breaker' is 'ON'. S Verify the CB-3 'GFI Outlet Breaker' toggle is in the 'ON' position. (CUE: CB-2 'GFI Outlet Breaker' toggle is in the 'Full Up' position.) 8 Verify the 2(3)OS261 B 'Air Compressor Disconnect Switch' is 'ON'. S Verify the 2(3)OS261 B 'Air Compressor Disconnect Switch' is in the "ON" position. (CUE: The 2(3)OS261 B Disconnect Handle is in the 'Full Up' pOSition. II NLSRO-3069 RevOOO Page 6 of 9

STEP STEP NO

9 Verify the 'Main Hoist Pneumatic Shut-Off Valve' is OPEN.

(CUE: If the examinee describes attempting to operate the 'Main Hoist' hand-wheel in the clockwise direction, THEN provide the following "The hand-wheel will not rotate.") (CUE: When the examinee describes operating the hand-wheel for the 'Main Hoist' in the counter-clockwise direction, THEN provide the following "The hand-wheel rotates in the counter clockwise direction until the hand-wheel moves away from the valve body Y2 inch and resistance is felt; hand-wheel will not turn any further.")

10 Verify the 'Mono Hoist Pneumatic Shut-Off Valve' is OPEN.

(CUE: If the examinee describes attempting to operate the 'Mono Hoist' hand-wheel in the clockwise direction, THEN provide the following "The hand-wheel will not rotate.") (CUE: When the examinee describes operating the hand-wheel for the 'Mono Hoist' in the counter-clockwise direction, THEN provide the following "The hand-wheel rotates in the counter clockwise direction until the hand-wheel moves away from the valve body Y2 inch and resistance is felt; hand-wheel will not turn any further.") ACT STANDARD S Verify the 'Main Hoist Pneumatic Shut-Off Valve' is OPEN (hand-wheel rotated in the fully counter-clockwise direction). S Verify the 'Mono Hoist Pneumatic Shut-Off Valve' is OPEN (hand-wheel rotated in the fully counter-clockwise direction). NLSRO-3069 RevOOO Page 7 of 9 II

STEP STEP ACT STANDARD NO 11 Notify the Control Room Supervisor that S Notify the Control Room Supervisor of the Refuel Platform Bridge End Structure task completion. Panel Lineup has been completed in accordance with SO 18.1.C-2(3} step 4.2. Note: Notification may be simulated as in-person or via radio I phone. (CUE: Acknowledge the report.) NOTES to Evaluator A. When the examinee has completed SO 18.1.C-2(3} step 4.2, then the evaluator may terminate the JPM. (CUE: You may stop here; you have met the termination criteria for this JPM.) B. JPM stop time may be recorded here. ____._____ C. If this JPM is being performed as part of Initial LSRO training/testing, then this JPM is complete and the next step (step 12) may be marked as 'N/A'. If this JPM is being performed as part of LSRO REQUAL, then the next step MUST be completed. 12 Follow-up Question: D The Bridge End Structure Panel Lineup verifications at PBAPS and at Limerick (CUE: If you were performing the Refuel are similar. However, other than different Platform 'Bridge' End Structure Electrical models of equipment that would be Lineup at Limerick (S97.1.A section 4.3), actuated, the Bridge Structure End Panel Then what would be different between the Lineup verifications at Limerick include a actions you just performed I simulated check for each phase of the Bridge Surge here and what you would expect to do at Suppressor. Limerick?) Note to Evaluator - The answer to the If the examinee asks for a copy of follow up question does not have to be S97.1.A, then provide the following: answered by the trainee using the exact (CUE: Give the examinee a copy of words that are shown above. S97.1.A.) Note to Evaluator As an Evaluator, ensure you have positive control of all exam material provided to the examinee ('Task Conditions I Prerequisites & Initiating Cue' sheet' AND all procedures). Under "ACT" P - must perform S - must simulate D - must discuss I. TERMINATING CUE When the examinee has completed SO 18.1.C**2(3) step 4.2 'Bridge End Structure Panel Lineup', the Control Room Supervisor should be informed. The evaluator will then terminate the exercise. NLSRO-3069 RevOOO Page 8 of 9

Task Conditions / Prerequisites &Initiating Cue TASK CONDITIONS/PREREQUISITES

1.

The Refuel Platform is being returned to service following maintenance.

2.

The Refuel Platform clearances have been removed by operations; tags were removed with the equipment out of service so thl9 system operating procedures would be used to lineup the Refuel Platform.

3.

All SO 18.1.C-2(3) 'Electrical, Mechanical, and Pneumatic Alignment I Checkout of Refueling Platform' procedure prerequisites and precautions are met and step 4.1 is complete. INITIATING CUE The Control Room Supervisor directs you to p,erform the (Unit 2 I Unit 3) Refuel Platform Bridge End Structure Panel Lineup in accordance with SO 18.1.C-2(3) step 4.2. The Control Room Supervisor gives you permission to operate the components identified in SO 18.1.C-2(3) as necessary to place the Refuel Platform into alignment with step 4.2 of SO 18.1.C-2(3). NLSRO-3069 RevOOO Page 9 of 9

EXELON NUCLEAR Nuclear Generation Group OJTITPE MATERIAl. COVERSHEET JPM QUALIFICATION MANUAL D Limited Senior Reactor Operator LSRO Initial & LSRO Requalification Drywell to Reactor Well Bellows Failure APPROVALS: Signature / Title Signature I Title Signature / Title Signature I Title ,PPROVED FOR USE: Signature I Title EFFECTIVE DATE: __----' __----! ___ NAME: ISSUE DATE: Last First M.I. EMPLOYEE ID NO. COMPLETION DATE: COMMENTS: Training Review for Completeness: LMSCODE: LMS ENTRY: Signature/Date OJT MODULE NLSRO-3068 000 gwz Date Date Date Date Date NLSR03068 RevOOO Page 1 of 16

tJ wt.,. EXELON NUCLEAR PEACH BonOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE: Senior Reactor Operator / Senior Reactor Operator - Limited (LSRO) TASK-JPM DESIGNATOR: B2-3 -- NLSR03054 KIA: 233000 K1.02 RO: 2.9 SRO: 3.0 TASK DESCRIPTION: Respond to alarms on the fuel floor panel *OC222 & *OC075 A. NOTES TO EVALUATOR:

1.

An asterisk (*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed Gorrectly will prevent the system from functioning properly or prevent successful task completion.

2.

System cues included in the performance checklist are to be provided to the examinee when no system response is available.

3.

JPM Performance

a.

"Control Room" JPMs are designed 10 be performed in the simulator. If a "Control Room" JPM is to be performed in the Control Room all perform steps (P) shall be simulated (S).

b.

When performing "In-Planf' "IPlVls, no equipment will be operated without Shift Management approval.

4.

Satisfactory performance of this JPM is accomplished if:

a.

The task standard is met.

b.

JPM completion time requirement is met.

1)

For non-time critical JPMs, completion within double the estimated time (listed in paragraph 0.2) iis acceptable provided the evaluator determines that the progress to completion is acceptable.

2)

For time critical JPMs, completion within the estimated time (listed in paragraph 0.2) is required.

5.

The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee.

6.

Although not required, this JPM is designed to be given on the Unit 2 or Unit 3 Refuel Floor (the evaluator to make the appropriate annotations on the 'Task Conditions and Prerequisites / Initiating Cue' sheet and attachments). NLSR03068 RevOOO Page 2 of 16

B. TOOLS AND EQUIPMENT 1. Access to either the 20C075 Panel OR the :30C075 Panel.

2.

Access to the PBAPS Alarm Response Procedure ARC-2(3)OC075 A-1 Seal Rupture Drain High Flow.

3.

Access to the PBAPS Alarm Response Procedure ARC-2(3)OC075 B-3 Skimmer Surge Tank Low Level.

4.

Access to the PBAPS Alarm Response Procedure ARC-2(3)OC075 B-1 Fuel Storage Pool High / Low Level.

5.

Access to the PBAPS Abnormal Operating Procedure AO 10.4-2(3) Residual Heat Removal System - Fuel Pool to Reactor Mode.

6.

Access to the PBAPS Fuel Handling Procedure FH-74 Actions in Response to an Unexpected Loss of Fuel Pool, ReactOir Cavity, or Equipment Storage Pool Water Inventory.

7.

Access to the PBAPS ON-124 'Fuel Floor and Fuel Handling Problems' procedure. B. Access to the Limerick Annunciator Response Procedure ARC-BOP-1 (2)OC222 D3 Reactor Well Seal Rupture Drain Hi Flow.

9.

Access to the Limerick Annunciator Response Procedure ARC-BOP-1 (2)OC222 B4 1 (2)BT20B Skimmer Surge Tank Lo Level.

10.

Access to the Limerick system procedure S53.3.A Direct Makeup to Fuel Storage Pool.

11.

Access to the Limerick System procedure S53.3.G Skimmer Surge Makeup and Letdown.

12.

Access to Limerick General Procedure GP-6.1 Shutdown Operations - Refueling Core Alternation, and Core Off-Loading.

13.

Access to the Limerick System Procedure S51.B.L RHR Alternate Decay Heat Removal Startup and Shutdown.

14.

'Task Conditions / Prerequisites & Initiating Cue' sheet (Evaluator understands to specify the..IPM for either PBAPS Unit 2 or Unit 3. C. REFERENCES

1.

ARC-2(3)OC075 A-1 Rev. 2, Seal Rupture Drain High Flow.

2.

ARC-2(3)OC075 B-3, Rev. 2, Skimmer Surge Tank Low Level.

3.

ARC-2(3)OC075 B-1 Rev. 2, Fuel Storage Pool High / Low Level. NLSR03068 RevOOO Page 3 of 16

4.

AO 10.4-2(3), Rev. 21 (20), Residual Ht3at Removal System - Fuel Pool to Reactor Mode.

5.

FH-74, Rev. 6, Actions in Response to an Unexpected Loss of Fuel Pool, Reactor Cavity, or Equipment Storage Pool Water Inventory.

6.

ON-124 Rev. 14 'Fuel Floor and Fuel Handling Problems' procedure.

7.

ARC-BOP-1 (2)OC222 D3 'Reactor Well Seal Rupture Drain Hi Flow' Revision O. S. ARC-BOP-1(2)OC222 B4 '1 (2)BT20S Skimmer Surge Tank Lo Level' Revision 1.

9.

S53.3.A Direct Makeup to Fuel Storage Pool Revision 17.

10.

S53.3.G Skimmer Surge Makeup and Letdown Revision 22.

11.

GP-6.1 Shutdown Operations - Refueling Core Alternation, and Core Off-Loading Revision 20 (Unit 1) / Revision 23 (Unit 2).

12.

S51.S. L RHR Alternate Decay Heat Removal Startup and Shutdown Revision 15. D. TASK STANDARD

1.

Satisfactory task completion is indicated when the examinee has notified the Control Room to shut down the 'A' RHR Pump and directed non-essential personnel to evacuate the Refuel Floor, then the evaluator may terminate the JPM.

2.

Estimated time to complete: 20 minutes Non-Time Critical E. DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to continuously monitor the Unit 2(3) Skimmer Surge Tank level until the remote monitoring can be restored in accordance with AO 10.4-2(3) step 3.10(3.12) and to respond to any local Fuel Pool alarm condition(s) on the Fuel Pool System Panel 2(3)OC075. I will describe initial plant conditions and provide you access to the materials required to complete this task. F. TASK CONDITIONS/PREREQUISITES

1.

Reactor is in MODE 5.

2.

Fuel Pool Gates to the Reactor Cavity are removed.

3.

Fuel Pool water level is 232' 10"

4.

Refueling Operations have been suspended to allow for grapple change out. NLSR03068 RevOOO Page 4 of 16

5.

The Residual Heat Removal System is currently removing decay heat from the reactor in accordance with AO 10.4-2(3) Residual Heat Removal System - Fuel Pool to Reactor Mode using the 'A' RHR Pump.

6.

The 'A' RHR Pump is the ONLY available Pump for Shutdown Cooling / Injection.

7.

The Fuel Pool Cooling system has been shutdown.

8.

The Reactor Water Clean Up System ~las been shutdown.

9.

I&C has just been dispatched to investiigate the loss of camera functions on the Refuel Floor.

10.

The overhead crane is NOT in use. G. INITIATING CUE The Control Room Supervisor directs you (thE) current Fuel Handling Director) to continuously monitor the Unit 2(3) Skimmer Surge Tank level until the remote monitoring can be restored in accordance with AO 10.4-2(3) step 3.10 (3.12:) and to respond to any local Fuel Pool alarm condition(s) on the Fuel Pool System Panel 2(3)OC075. NLSR03068 RevOOO Page 5 of 16

¢ _,_. H. PERFORMANCE CHECKLIST ,,:)1t:P STEP I'...... STANDARD NO Notes to Eva.luator A) Before the start of the JPM, If the examinee asks to see a copy of AO 10.4-2(3), then (Cue: After the examinee describes how they would obtain a copy of AO 10.4-2(3), provide the examinee with a copy of AO 10.4-2(3).) B) At any time during this JPM that an alarm condition is indicated on the 2{3}OC075 Panel (alarm annunciator flashing), IF the examinee momentarily depresses the 2(3)OC075 Panel Alarm Acknowledge push-button, then provide the following cue: (Cue: Alarm annunciator(s) is/are no longer flashing - indicated alarm light{s) is/are lit [steady].) C) JPM start time may be recorded here: ______________ D) The examinee may perform the below listed communications / noti'fications in any order. 1 Locate the Fuel Pool System Panel PIS 2(3)OC075 Panel is located on the Refuel 2(3)OC075 Floor - General Area (elevation 234') (Cue: When examinee has located the 2[3]OC075 Panel, provide the examinee with the 2[3]OC075 Panel Conditions sheet #1 [Attachment #1 ].) 2 Identify alarm condition(s). S Identifies Alarm A-1 in alarm. 3 Obtain a copy of the Alarm Response P I D Obtain a copy of ARC-2(3)OC075 A-1 Card ARC-2(3)OC075 A-1 from the ARC book at the Panel or from the EDMS system or other controlled (Cue: If examinee does NOT use the location. alarm response procedure located in the ARC Book (at the Panel), then the evaluator may provide the examinee with a copy of ARC-2[3]OC075 A-1 AFTER the examinee discusses the method for obtaining the procedure from the EDMS system or other controlled location.) II NLSR03068 RevOOO Page 6 of 16

STANDARD ~ S~rg' I STEP IACT ~"";'4~-+-N-o-t-ify-th-e-U-n-i-t-R-e-ac-t-o-rO-p-e-ra-to-r-t-ha-t--+ S Inform the Unit Reactor Operator that the alarm "Seal Rupture Drain High Flow" is alarm "Seal Rupture Drain High Flow" is in on the 2(3)OC075 Panel. in. (Cue: Evaluator acknowledges the Note to evaluator - The communications examinee's report.) may be made using the radio or telephone. Notes to Evaluator A) At any time during this "IPM, the examinee enters OR recommends entering/performing the FH-74 'Actions in Response to an Unexpected Loss of Fuel Pool, Reactor Cavity, or Equipment Storage Pool Water Inventory' procedure, then provide the following - (CUE: Acknowledge the recommendation to !nter the FH-74 procedure AND state "The Control Room Supervisor directs you to evaluate the Refuel Floor conditions and execute the Refuel Floor portions of the FH-74 procedure.") Note-This is the same cue as found in step 16.

8) At any time during this JPM, the examinee enters OR recommends entering/performing the ON-124 'Fuel Floor and Fuel Handling Problems' procedure, then provide the following-(CUE: Acknowledge the recommendation to !nter the OI\\J-124 procedure AND state "The Control Room Supervisor directs you to evaluate the Refuel Floor conditions and execute the Refuel Floor portions of the ON-124 procedurE~.") Note-This is the same cue as found in step 18.

5 Notify the LSRO (and/or NMD Reactor Services Foreman) of the "Seal Rupture Drain High Flow" alarm. S Inform the LSRO (and/or NMD Reactor Services Foreman) of the "Seal Rupture Drain High Flow" alarm. (Cue: Evaluator acknowledges the examinee's report.) 6 (Cue: Inform the examinee that Fuel Pool water level is now at 232' 8" going down.) Notify the Reactor Operator that Fuel Pool/Reactor Cavity water level is 232' 8" going down. (Cue: Evaluator acknowledges the examinee's report AND inform the examinee that Equipment Operators have been dispatched and the Equipment Operators will perform ALL make-up water additions and ALL required valve line-ups.) S Report any reduction in Reactor Cavity water level to the Unit RO. Note to evaluator - The examinee may notify the FHD to cease Refueling Operations. This is acceptable. II Immediately following report. then - (Cue: Provide the examinee with the 2[3]OC075 Panel Conditions sheet #2 [Attachment #2].) NLSR03068 RevOOO Page 7 of 16

STEP STEP ACT STANDARD NO Identify alarm condition(s). P/D Identifies Alarm B-3 in alarm. 7 8 Obtain a copy of the Alarm Response P/D Obtain a copy of ARC-2(3)OC075 B-3 Card ARC-2(3)OC075 B-3 from the ARC book at the Panel or from the EDMS system or other controlled (Cue: If examinee does NOT use the location. alarm response procedure located in the ARC Book (at the Panel), then the evaluator may provide the examinee with a copy of ARC-2[3]OC075 B-3 AFTER the examinee discusses the method for obtaining the procedure from the EDMS system or other controlled location.) 9 Identifies Level indicator LI-2(3)695 S Verify that a "Low Level" condition is indicates pegged low << 0 inches). indicated on LI-2(3)695 located on the 20C075 Panel. Note to Evaluator Steps 10 and 11 (below) may be done through a sin~~le communication with the Control Room. 10 Notify the Unit Reactor Operator that the S Inform the Unit Reactor Operator that the alarm "Skimmer Surge Tank Low Level" alarm "Skimmer Surge Tank Low Level" is in on the 2(3)OC075 Panel and that the is in and report the indicated level on LI-Skimmer Surge Tank water level is 2(3)695. pegged low << 0 inches). (Cue: Evaluator acknowledges the examinee's report and informs the examinee that an Equipment Operator has been dispatched to add make-up water to the Skimmer Surge Tanks.) NLSR03068 RevOOO Page 8 of 16

______________________o_________________________________________________au______ STEP STANDARD ~

11 Notify the Control Room that the currently operating RHR Pump ('A') must be immediately shutdown.

(Cue: Evaluator acknowledges the examinee's report and informs the examinee that the running RHR pump is being shutdown.) Immediatel~ following re12ort3 then - (Cue: Inform the examinee that Fuel Pool water Level is 232' 4" going down AND provide the examinee with the 2[3]OC075 Panel Conditions sheet #3 [Attachment

3].)

12 Identify alarm condition(s). 13 Obtain a copy of the Alarm Response Card ARC-2(3)OC075 B-1 (Cue: If examinee does NOT use the alarm response procedure located in the ARC Book (at the Panel), then the evaluator may provide the examinee with a copy of ARC-2[3]OC075 B-1 AFTER the examinee discusses the method for obtaining the procedure from the EDMS system or other controlled location.) 14 Visually check Fuel Pool water level. (Cue: Fuel Pool water level is at 231' 10" and going down.) 15 Notify the Unit Reactor Operator that the alarm "Fuel Storage Pool Low Level" is in on the 2(3)OC075 Panel and that the Fuel Pool water level is at the 231' 10" mark and going down. (Cue: Evaluator acknowledges the II examinee's report.) NLSR03068 RevOOO S If level is low and RHR SOC - Fuel Pool to Reactor mode is in operation in accordance with AO 10.4-2(3), then immediately shutdown the running RHR Pump. PID Identifies Alarm 8-1 in alarm. PID Obtain a copy of ARC-2(3)OC075 8-1 from the ARC book at the Panel or from the EDMS system or other controlled location. S Visually check Fuel Pool level to determine if the alarm is due to high water level or low water level. S Notify the Unit Reactor Operator that the alarm "Fuel Storage Pool Low Level" is in and report current Spent Fuel Pool water level. Page 9 of 16

STEP ACT STANDARD ~ II 16 Recommends entering the FH-74 "Actions in Response to an Unexpected Loss of Fuel Pool, Reactor Cavity, or Equipment Storage Pool Water Inventory" procedure. (CUE: Acknowledge the recommendation to enter the FH-74 procedure AND state "The Control Room Supervisor directs you to evaluate the Refuel Floor conditions and execute the Refuel Floor portions of the FH-74 procedure.") 17 Obtain a copy of the FH-74 procedure (CUE: When the examinee states that he would 'find a copy of the procedure in the Refuel Floor Office area, or on the Refuel Platform, or from the EDMS system, then provide the examinee with a copy of the FH-74 procedure.) 18 Notifies Shift Management to enter ON 124 "Fuel Floor and Fuel Handling Problems". (CUE: Acknowledge the recommendation to enter the ON-124 procedure AND state "The Control Room Supervisor directs you to evaluate the Refuel Floor conditions and execute the Refuel Floor portions of the ON-124 procedure.") 19 Obtain a copy of the ON-124 procedure (CUE: When the examinee states that he would find a copy of the procedure in the Refuel Floor Office area, or on the Refuel Platform, or from the EDMS system, then provide the examinee with a copy of the ON-124 procedure.) II NLSR03068 RevOOO S Recommend that FH-74 "Actions in Response to an Unexpected Loss of Fuel Pool, Reactor Cavity, or Equipment Storage Pool Water Inventory" be implemented. D Obtain a copy of the FH-74 procedure from the EDMS system or other controlled location. S Notify Shift Management to enter ON-124 "Fuel Floor And Fuel Handling Problems". D Obtain a copy of the ON-124 procedure from the EDMS system or other controlled location. Page 10 of 16

STEP STEP ACT STANDARD NO 20 Notify Rad Protection to continuously S Notify Radiation Protection to evaluate radiological conditions on the continuously evaluate radiological Fuel Floor and recommend evacuation or conditions on the Fuel Floor and allowance to continue with steps recommend evacuation or allowance to continue with the remaining procedural (CUE: Rad Pro Technician steps. acknowledges your direction and begins surveys.)

21 Direct all personnel non-essential for S

All personnel not essential to place the placing the Fuel Floor in a radiologically Refueling Floor in a radiologically safe safe condition to immediately evacuate condition shall immediately evacuate the the Fuel Floor. Fuel Floor. Notes to Evaluator A) Satisfactory task completion is indicated when the examinee has notified the Control Room to shut down the 'A' RHR Pump and directed non-essential personnel to evacuate the Refuel Floor, then the evaluator may terminate the JPM.

3) The below step ONLY applies if this JPM is being used for LSRO Requal training I testing (i.e. The below step is N/A for LSRO initial training I testing).

22 Follow-up Question (Evaluator to ask the D Answer: The Limerick procedures examinee): "If you had similar conditions directions are Similar. The Limerick ARC-at Limerick unit 1 - Refueling Operations BOP-10C222 D3 will direct the operator in progress and an ARC-BOP-10C222 D3 to verify operation of the inflatable 'Reactor Well Seal Rupture Drain Hi Flow' Reactor Well seals. The PBAPS Seals alarm in concurrent with Reactor Cavity are NOT inflatable and therefore there water level going down, then how would are no directions to verify seal operability. your actions be different than what you just demonstrated here? (Examinee may include that the ON-120 procedure would be entered at Limerick If the LSRO examinee wants to see a vice the ON-124 I FH-74 procedures at copy of the Limerick Procedure ARC-PBAPS [not required for correct answer].) BOP-10C222 D3 'Reactor Well Seal Rupture Drain Hi Flow' alarm response Note to Evaluator - The answer to the card, then: follow up question does not have to be (CUE: Present a copy of ARC-BOP-answered by the trainee using the exact 10C222 D3 to the LSRO examinee.) words that are shown above. NLSR03068 RevOOO Page 11 of 16

STEP STEP ACT STANDARD NO Notes to Evaluator A) Satisfactory task completion is indicated when the examinee has notified the Control Room to shut down the 'A' RHR Pump and directed non~essential personnel to evacuate the Refuel Floor, then the evaluator may terminate the JPM.

8) The stop time for the..IPM may be entered here:. ___________

C) As an evaluator, ensure you have positive control of all exam material provided to the examinee ('Task Conditions / Prerequisites & Initiating Cue' she'et', ALL Attachments, AND procedures). Under "ACT" P ~ must perform S ~ must simulate D - must discuss I. TERMINATING CUE When the examinee has notified the Control Room to shut down the 'A' RHR Pump and directed non-essential personnel to evacuate the Refuel Floor, then the evaluator may terminate the..IPM. NLSR03068 RevOOO Page 12 of 16

__________________________________________________,_____w__________________ TASK CONDITIONS & PREREQUISITES

1.

Reactor is in MODE 5.

2.

Fuel Pool Gates to the Reactor Cavity are removed.

3.

Fuel Pool water level is 232' 10"

4.

Refueling Operations have been suspended to allow for grapple change out.

5.

The Residual Heat Removal System is currently removing decay heat from the reactor in accordance with AO 10.4-2(3) Residual Heat Removal System - Fuel Pool to Reactor Mode using the 'A' RHR Pump.

6.

The 'A' RHR Pump is the ONLY available Pump for Shutdown Cooling I Injection.

7.

The Fuel Pool Cooling system has been shutdown.

8.

The Reactor Water Clean Up System has been shutdown.

9.

I&C has just been dispatched to investigate the loss of camera functions on the Refuel Floor.

10.

The overhead crane is NOT in use. INITIATING CUE The Control Room Supervisor directs you (the current Fuel Handling Director) to continuously monitor the Unit 2(3) Skimmer Surge Tank level until the remote monitoring can be restored in accordance with AO 10.4-2(3) step 3.10 (3.12) and to respond to any local Fuel Pool alarm condition(s) on the Fuel Pool System Panel 2(3)OC075. NLSR03068 ReVOOO Page 13 of 16

Attachment #1 - Panel 2(3)OC075 Panel Initial Indications (#1) B FUEL STORAGE POOL 1 HIGH/LOW LEVEL BELLOWS LEAK SKIMMER 2 HIGH FLOW SURGE TANK HIGH LEVEL. SKIMMER GATE DRAIN SURGE TANI< HIGH FLOW LOW LEVEL 3 LI-2(3)695 250 200 150 100 50 0 SKIMMER SURGE TANK LEVEL o AUTO CLOSE OPEN STOP START c FUEL STORAGE POOL HI RADIATION FLASHER G 'A' FUEL POOL PUMP G 'B' FUEL POOL PUMP G 'C' FUEL POOL PUMP ACK RESET TEST 00 HIGH PRESSURE AO-2(3}698 DECON PUMP FUEL POOL MAKEUP NLSR03068 RevOOO Page 14 of 16

______________ ________..m___ W_ __ Attachment #2 - PaneI2(3)OC075 Panel Indications (#2) A B FUEL STORAGE POOL 1 HIGH/LOW LEVEL BELLOWS LEAK SKIMMER 2 HIGH FLOW SURGE TANK HIGH LEVEl. GATE DRAIN HIGH FLOW 3 LI-2(3)695 ___ 50 ___ 00 ___50 IE:,.-_O SKIMMER SURGE TANK LEVEL o AUTO CLOSE OPEN STOP START I c FUEL STORAGE POOL HI RADIATION FLASHER 'A' FUEL POOL PUMP G 'B' FUEL POOL PUMP 'C' FUEL POOL PUMP ACK RESET TEST o HIGH PRESSURE AO-2(3)698 DECON PUMP FUEL POOL MAKEUP NLSR03068 RevOOO Page 15 of 16

Attachment #3 - PaneI2(3)OC075 Panel Indications (#3) Flashing C 1 FUEL STORAGE POOL HI RADIATION 2 BELLOWS LEAK HIGH FLOW FLASHER 3 GATE DRAIN HIGH FLOW LI-2(3)695 ___,250 ___,200 ___150 'A' FUEL POOL PUMP ___100 ___,50 'B' FUEL POOL PUMP -=:-~__o 'e' FUEL POOL PUMP SKIMMER SURGE TANK LEVEL 8 AUTO CLOSE STOP I START OPEN AeK o RESET TEST HIGH PRESSURE AO-2(3)698 DEeON PUMP FUEL POOL MAKEUP NLSR03068 RevOOO Page 16 of 16

..~ EXELON NUCLEAR Nuclear Generation Group OJTITPE MATERIAL COVERSHEET ~ JPM QUALIFICATION MANUAL OJT MODULE D D Limited Senior Reactor Operator NLSRO-3065 LSRO Initial & LSRO Requalification 000 G. W. Zellmer gwz Fuel Support Piece Removal using FSP Grapple (Alternate Path due to Fault Lockout) APPROVALS: Signature I Title Date Signature / Title Date Signature / Title Date Signature I Title Date \\PPROVED FOR USE: Signature I Title Date EFFECTIVE DATE: __---' ___' ___ NAME: ISSUE DATE: Last First M.I. EMPLOYEE 10 NO. COMPLETION DATE: COMMENTS: Training Review for Completeness: LMSCODE: LMS ENTRY: Signature/Date NLSR03065 Rev 000 Page 1 of 16

___ _____0.__,____________________ EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE: Senior Reactor Operator / Senior Reactor Operator - Limited (LSRO) TASK-JPM DESIGNATOR: 234000-19 -- NLSR03065 KIA: 234000 K3.04 RO: 2.9 SRO: 3.8 TASK DESCRIPTION: Direct actions for installation and removal of FSPs & CRBs A. NOTES TO EVALUATOR:

1.

An asterisk (*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.

2.

System cues included in the performance checklist are to be provided to the examinee when no system response is available.

3.

JPM Performance

a.

"Control Room" JPMs are designed to be performed in the simulator..If a "Control Room" JPM is to be performed in the Control Room all perform steps (P) shall be simulated (S).

b.

When performing "In-Planf' JPMs, no eqUipment will be operated without Shift Management approval.

4.

Satisfactory performance of this JPM is accomplished if:

a.

The task standard is met.

b.

JPM completion time requirement is met.

1)

For non-time critical JPMs, completion within double the estimated time (listed in paragraph D.2) is acceptable provided the evaluator determines that the progress to completion is acceptable.

2)

For time critical JPMs, completion within the estimated time (listed in paragraph 0.2) is required.

5.

The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee. NLSR03065 Rev 000 Page 2 of 16

_________________j_______ j _t___

6.

Though not required, this JPM is designed to be given on the Refuel Floor and associated areas. TOOLS AND EQUIPMENT

1.

Copy of 'Conditions / Prerequisites And Initiating Cue' sheet

2.

Access to M-C-741-301 'Control Rod Blade, FSP And Control Rod Guide Tube Removal And Installation'

3.

Access to SO 18.1.A-2(3) 'Operation olf Refueling Platform'

4.

Access to S97.0.M 'Refueling Platform Operation' C. REFERENCES

1.

M-C-741-301 Rev. 26 'Control Rod Blade, FSP And Control Rod Guide Tube Removal And Installation'

2.

SO 18.1.A-2(3) Rev 21 'Operation of Refueling Platform'

3.

S97.0.M Rev. 27 'Refueling Platform Operation' D. TASK STANDARD

1.

Satisfactory task completion is indicated when the FSP is raised through the Top Guide.

2.

Estimated time to complete: 20 minutes Non-Time Critical E. DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to continue Fuel Support Piece (FSP) removal at core location 30-31 per M-C-741-301 step 5.3.5 using appropriate procedures. I will describe initial plant conditions and provide you access to the materials required to complete this task. F. TASK CONDITIONS/PREREQUISITES

1.

Fuel shuffle part 1 has been completed on PBAPS Unit (Unit 2/ Unit 3).

2.

Control Cell 30-31 is having the Fuel Support Piece (FSP) removed using the PBAPS FSP Grapple & Grid Guide connected to the Monorail Hoist.

3.

Core Configuration is shown on the attached core view.

4.

The Reactor Cavity Work Platform (RCWP) is NOT installed.

5.

M-C-741-301 Attachment 11 is provided and was filled in when the first FSP replacements occurred (previous shift). NLSR03065 Rev 000 Page 3 0116

6.

The CCTAS is approved (current step is provided - see below). WRNM STEP COMPONENT MOVED ORIENT MOVE ORIENT FHD RPO CRO DATE TIME COUNTRATE NO. SERIAL NO. FROM TO ABCDEFGH 86 SUP PC 30-31 SW P _SPENT NONE......-_....._

7.

All prerequisites for FSP replacement are met, and M-C-741-301 steps 5.3.1 through 5.3.4 have been completed for core location 30-31.

8.

All procedure FH-6C, GP-26, and SO 18.1.A-2(3) prerequisites and associated steps are complete for the FSP replacement at core location 30-31.

9.

The FSP Grapple is currently empty (re!leased) and is positioned at the 'Full up position' (the Monorail Hoist Pemdant Control indicates a load of 100 Ibs).

10.

The Monorail Hoist is positioned over the Gore at location 30-31. G. INITIATING CUE The Control Room Supervisor directs you (as the Fuel Handling Director [FHD]) to continue the FSP removal at core location 30-31 in accordance with M-C-741-301 steps 5.3.5 through and including step 5.3.16. NLSR03065 Rev 000 Page 4 of 16

H. PERFORMANCE CHECKLIST 3TEP STEP ACT STANDARD NO Notes to Evaluator A) The 'Task Conditions / Prerequisites & Initiating Cue' sheets that are given to the examinee prior to the start of the JPM include JPM pages 12, 13, 14, 15, and 16. B) A Copy of M-C-741-301 and SO 18.1.A-2(3) procedures is to be given to the examinee with the 'Task Conditions / Prerequisites & Initiating Cue' sheets (evaluator to select the appropriate Unit 2 or Unit 3 procedure). C) If the examinee asks to review the FH-6C and/or GP-26 procedures, it is within the scope of this ..IPM for the evaluator to provide a copy of these procedures to the examinee. D) The examinee (as the FHD) will either perform (simulate) or direct that the following steps be taken. E) The JPM start time may be recorded here

1 Depress "ENGAGE" push-button on the S

The Grapple "ENGAGE" push-button is hoist pendant control. depressed on the Monorail Pendant Control (Cue: The component that you identified is in the condition that you described.) (Cue: If asked for camera view, then provide "No camera view is available.")

2 Lower hoist until grapple enters top guide, S

Grapple "LOWER" push-button on the then ensure grapple is oriented properly Monorail Hoist Pendant Control is to align with anti-rotation pin at corner of depressed. The 'Anti-Rotation' pin on the control cell (Southwest) Grapple is verified to have a Southwest orientation (CUE: The grapple starts to lower but after the grapple travels two (2) feet in the Note -- If any system or equipment down direction, the grapple motion required to perform work becomes abruptly stops followed by a report from inoperable or malfunctions, stop the RPO that an 'Interlock Status Display operations until the required system or Annunciator' is currently up and indicates eqUipment is returned to service (step a 'Fault Lockout' condition. The Refuel 3.2.7 of M-C-741-301). Platform will NOT respond to controls.) (CUE: Provide the examinee with a copy Note -- Start Of Alternate Path of the 'Interlock Status Display' [page 11 J.) NLSR03065 Rev 000 Page 5 of 16 II

,____________,__________,___________________w, 3 STEP STEP ACT STANDARD NO Notify Control Room of the 'Fault Lockout' condition. (CUE: Acknowledge the report of the 'Fault Lockout' condition AND provide the following report ~ "One of the OEM technicians (Original Equipment Manufacturer's technicians) opened a trolley deck cabinet door. The trolley deck cabinet doors are now closed AND the 'Fault Lockout' annunciator is clear. If there are NO other abnormal conditions present, then Shift Management is directing you to reset the P.L.C. AND to continue with the FSP Removal.)

4 Refuel Platform 'START' pushbutton depressed.

(CUE: Refuel Platform 'START' pushbutton is depressed; all Refuel Bridge indications are as expected [as they were before the Fault Lockout condition - Monorail Hoist is two [2] feet lower than the normal full up position].) (CUE: If examinee request maintenance to perform a checkout / diagnostic of the Bridge functions, then provide the examinee with the following "Maintenance determines that all Bridge functions are operating normally.") S When operating equipment, If it does not perform as expected, then place the equipment in a safe condition and inform Shift Management. S Refuel Platform "START" pushbutton is depressed. Note to Evaluator - Start pushbutton must be pressed to resume platform operation after 'Fault Condition is cleared (SO 18.1.A-2[3] Att. 1). Note -- End Of Alternate Path II I NLSR03065 Rev 000 Page 6 of 16

STEP ACT STANDARD

5 Lower hoist until grapple enters top guide, S

Grapple "LOWER" push-button on the then ensure grapple is oriented properly Monorail Hoist Pendant Control is to align with anti-rotation pin at corner of depressed. The Orientation Aid on the control cell (Southwest orientation) Grid Guide is veri'fied to have a Southwest orientation (Cue: The component that you identified is in the condition that you just Note to Evaluator - This step is described.) completing what the examinee started in step 3 (but was NOT able to complete (CUE: If examinee directs hoist due to the Fault Lockout). movement WITHOUT directing the 'START' pushbutton to be depressed (step 5), then provide the examinee with the following - "Hoist and Bridge will NOT move")

6 Continue to lower grapple through top S

Grapple "LOWER" push-button (on the guide to just above the FSP Monorail Hoist Pendant Control) is depressed and held UNTIL the grapple is (Cue: The component that you identified just above the FSP (then the "LOWER" is in the condition that you just push-button is released). described.) Ensure pendant 'RELEASE' push-button Monorail Hoist Pendant Control

7 is actuated.

S "ENGAGE" push-button is depressed. (CUE: The component that you identified is in the condition that you just described.)

8 Lower FSP grapple fully onto the FSP.

S Grapple "LOWER" push-button (on the Monorail Hoist Pendant Control) is (Cue: The component that you identified depressed and held UNTIL the grapple is in the condition that you just cable is slack (then the "LOWER" push described.) button is released). 9 Pull down on and hold air hoses to verify S Air hoses are pulled to verify that the there is no tension in hoses hoses are in a 'slack' condition (no tension). (Cue: The component that you identified is in the condition that you just described.) II I I NLSR03065 Rev 000 Page 7 of 16

STEP STEP ACT STANDARD NO

10 Actuate "ENGAGE" push-button on hoist S

The Monorail Hoist Pendant Control pendant control and pause a minimum of "ENGAGE" push-button is depressed. 10 seconds to allow air cylinders to stroke. Note to Evaluator - For the examinee to obtain credit for this critical task, the (Cue: The component that you identified examinee must EITHER pause at least is in the condition that you just 10 seconds between simulating described.) depressing the 'ENGAGE' push-button and manually lifting the FSP grapple OR the examinee must verbally state that at least 10 seconds must pass before manually lifting the FSP grapple. 11 Verify FSP is captured by the FSP S FSP grapple cable is manually lifted and grapple by manually lifting the FSP the load indicator on the Monorail Hoist grapple enough to take weight of FSP. Pendant Control is verified to be greater than 100 Ibs and less than or equal to (Cue: The component that you identified 1651bs. is in the condition that you just described. The load indicator on the Monorail Hoist Pendant Control is 160.)

12 Bump Hoist up approximately 6 inches.

S Grapple "RAISE" push-button (on the Monorail Hoist Pendant Control) is (Cue: The component that you identified depressed and held UNTIL the grapple is in the condition that you just cable rises about 6 inches and then the described.) "RAISE" push-button is released. (Cue: If examinee asks the indication on the load indicator, then "The load indicator on the Monorail Hoist Pendant Control reads 160.")

13 Raise FSP through top guide and above S

Grapple "RAISE" push-button (on the core. Monorail Hoist Pendant Control) is depressed and held UNTIL the grapple (CUE: FSP is through the top guide and rises to the grapple normal up position above the core.) this completes the marked by tape on the cable (more than simulated portion of the JPM. There may or equal to 9 feet of water above grapple) be follow up question(s) that need to be then the "RAISE" push-button is released. addressed.) Note to Evaluator - It is permissible for II this action to be done in a series of steps. NLSR03065 Rev 000 Page 8 of 16

STEP STEP ACT STANDARD NO 14 Notify Control Room Supervisor that the S Notify Supervisor of task completion. FSP at Core location 30-31 has been removed in accordance with M-C-741 301 up to and including step 5.3.16. (CUE: Acknowledge the report and end the performance portion of this JPM.) Note to Evaluator A) The following step ONLY applies for Requal Examinations (Le. Step 15 is NOT applicable to Initial Exams). 15 (Cue: "If you were removing a Fuel S Answer: The actions would be similar. At Support Piece (FSP) at Limerick using M Limerick, there is a different style FSP C-7 41-301, how would your actions at grapple that is used and therefore, no Limerick be different than the actions that need to "ENGAGE" the empty grapple you just simulated here?") while the grapple is going through the top guide. Also, at Limerick, the opening of (CUE: If the examinee asks to see a the trolley deck cabinet doors do NOT copy of the Limerick procedure S97.0.M, cause a Fault Lockout condition of the then provide the examinee with a copy of Refuel Platform. the S97.0.M procedure AND re-read the follow up question to the examinee [if Note to Evaluator - The answer to the necessary]. ) follow up question does not have to be answered by the trainee using the exact words that are shown above. Notes to Evaluator A) After the examinee has answered all follow-up questions, the evaluator may terminate this JPM. The end time for the JPM may be recorded here. ________ B) As an evaluator, ensure you have positive control of all exam material provided to the examinee ('Task Conditions / Prerequisites & Initiating Cue' sheet' AND procedures). NLSR03065 Rev 000 Page 9 of 16

Under "ACT" p. must perform S

must simulate D* must discuss I.

TERMINATING CUE When the FSP has been raised and the examinee has answered applicable follow up question(s), then the JPM may be terminated. NLSR03065 Rev 000 Page 10 of 16

Interlock Status Display INTERLOCK STA-rUS DISPLAY I BRIDGE POS I 30.00 FUEL ROD BLK ROD BLK HOIST INTERLK INTEF~LK INTERLK

1
2 BACKUP SAFETY HOIST TRAVEL LMIT INTERLK MONO FRAME HOIST HOIST INTERLK INTERLK TROLLEY pos 31.00 BRIDGE BRIDGE REVERSE REVERSE STOP
1 STOP #2 TEST IN PROG NLSR03065 Rev 000 Page 11 of 16

a TASK CONDITONS I PREREQUISITES AND INITIATING CUE (ASK CONDITIONS/PREREQUISITES

1.

Fuel shuffle part 1 has been completed on PBAPS Unit _ (Unit 2/ Unit 3).

2.

Control Cell 30-31 is having the Fuel Support Piece (FSP) removed using the PBAPS FSP Grapple & Grid Guide connected to the Monorail Hoist.

3.

Core Configuration is shown on the attached core view.

4.

The Reactor Cavity Work Platform (RCWP) is NOT installed.

5.

M-C-741-301 Attachment 11 is provided and was filled in when the first FSP replacements occurred (previous shift).

6.

The CCTAS is approved (current step is provided - see below). WRNM STEP COMPONENT MOVED ORIENT MOVE ORIENT FHD RPO CRO DATE TIME COUNTAATE NO. SERIAL NO. FROM TO ABCDEFGH 86 SUP PC 30-31 SW P _SPENT NONE --~--

7.

All prerequisites for FSP replacement are met, and M-C-741-301 steps 5.3.1 through 5.3.4 have been completed for core location 30-31.

8.

All procedure FH-6C, GP-26, and SO 18.1.A-2(3) prerequisites and associated steps are complete for the FSP replacement at core location 30-31.

9.

The FSP Grapple is currently empty (released) and is positioned at the 'Full up position' (the Monorail Hoist Pendant Control indicates a load of 100 Ibs)

10.

The Monorail Hoist is positioned over the Core at location 30-31. INITIATING CUE The Control Room Supervisor directs you (as the Fuel Handling Director [FHD]) to continue the FSP removal at core location 30-31 in accordance with M-C-741-301 steps 5.3.5 through and including step 5.3.16. NLSR03065 Rev 000 Page 12 of 16

wi CORE VIEW (FROM TOP) NLSR03065 Rev 000 Page 13 of 16

PBAPS CORE MAP NLSR03065 Rev 000 Page 14 of 16

M-C-741-301 Rev. 26 Page 79 of 85 WEIGHT INDICATIONS DURING CRB EXCHANGE (Haist Raising Direction)

FSP Lift*:

160

CRB Lift:

(Mark N/A if using NES Combined Grapple) ) FSP + CRB Lift: r~/A

~-.-~--------------

(Combined Grapple only)

Grapple Empty:

100

When using NES Cornbined Grapple, FSP only weight can only be detected within approx. the first 3 inches of grapple motion.

INDICATED WEIGHTS DURING CRB EXCHANGE 1 Page 1 of 1 NLSR03065 Rev 000 Page 15 of 16

STU:::* CUSSE T AUXILIARY HOIST CABLE SPACER ,T'r' PICAL OF oj GUIOE TUBE ----""'"1 I I OF ~1 BME PLAn: FUEL. SUPPORT GRAPPLE Orientation Aid (aligned with anti-rotation pin) GRID GUIDE and Orientation Aid NlSR03065 Rev 000 Page 16 of 16

EXELON NUCLEAR Nuclear Generation Group OJTITPE MATERIAL COVERSHEET __________-._--'----.. -.--------------'.'.2;----------------------- ~ JPM QUALIFICATION MANUAL OJT MODULE D D Limited Senior Reactor Operator NLSRO-3066 LSRO Initial & LSRO Requalification 000 G. W. Zellmer gwz Transfer of Recently Irradiated Fuel - Alternate Path (Loss of SSGT) APPROVALS: Signature / Title Date Signature / Title Date Signature I Title Date Signature I Title Date . "PPROVED FOR USE: Signalture I Title Date EFFECTIVE DATE: ___.-1__----'1___ NAME: ISSUE DATE: Last First M.1. EMPLOYEE ID NO. COMPLETION DATE: COMMENTS: Training Review for Completeness: LMSCODE: LMS ENTRY: Signature/Date NLSR03066 Rev 000 Page 1 of 11

....,________,.........trt C1 EXELOI\\J NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE: Senior Reactor Operator / Senior Reactor Operator - Limited (LSRO) TASK-JPM DESIGNATOR: 234000-21 -- NLSR0306i KIA: 261000 A2.0S RO: 3.0 SRO: 3.1 TASK DESCRIPTION: Direct Transfer of fuel from the reactor cavity to the fuel pool A. NOTES TO EVALUATOR:

1.

An asterisk (*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.

2.

System cues included in the performance checklist are to be provided to the examinee when no system response is available.

3.

JPM Performance

a.

"Control Room" JPMs are designed to be performed in the simulator. If a "Control Room" JPM is to be performed in the Control Room all perform steps (P) shall be simulated (S).

b.

When performing "In-Plant"..IPMs, no equipment will be operated without Shift Management approval.

4.

Satisfactory performance of this JPM is accomplished if:

a.

The task standard is met.

b.

JPM completion time requirement is met.

1)

For non-time critica.l JPMs, completion within double the estimated time (listed in paragraph 0.2) is acceptable provided the evaluator determines that the progress to completion is acceptable.

2)

For time critical..IPMs, completion within the estimated time (listed in paragraph 0.2) is required. S. The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee.

6.

Though not required, this JPM is designed to be given on the Refuel Floor and associated areas. NLSR03066 Rev 000 Page 2 of 11

tt ___________ B. C. D. E. F. TOOLS AND EQUIPIVIENT

1.

Task Conditions / Prerequisites and Initiating Cue Sheet

2.

Access to FH-6C 'Core Component Movement' procedure

3.

Access to SO 18.1.A -3 'Operation of Befueling Platform' procedure

4.

Access to Unit 3 Tech Specs and Unit a TeGh Spec Bases

5.

Access to ST-0-09A-2 'SBGT SubsystHm Operability Test'

6.

Access to FH-35 'Control of Material Movement In the Fuel Pool'

7.

Access to Limerick Unit 1 Tech Specs

8.

Access to Limerick Procedure FH-105 'CorE~ Component Movement - Core Transfers' REFERENCES

1.

FH-6C Rev. 63 'Core Component MovElment'

2.

PBAPS Unit 3 Tech Specs Unit 3 [Rev. 276] and Bases

3.

SO 18.1.A-3 Rev. 21 'Operation of Refueling Platform' procedure

4.

ST-0-09A-2 Rev. 5 'SBGT Subsystem Operability Test'

5.

FH-35 Rev 35 'Control of Material MovE~ment In the Fuel Pool'

6.

Limerick Unit 1 Tech Specs (Rev. 197)

7.

Limerick procedure FH-105 Rev. 44 'Core Component Movement-Core Transfers' TASK STANDARD

1.

Satisfactory task completion is indicated when the Fuel Assembly Y JT709 is seated in the Spent Fuel Pool and all movement of RI~cently Irradiated Fuel is stopped.

2.

Estimated time to complete: 20 minutes Non-Time Critical DIRECTIONS TO EXAMINEE When given the initiating cue, as the Refuel Platform on-duty Fuel Handling Director (FHD) you are to continue transferring Recently Irradiated FW31 out of the PBAPS Unit 3 Reactor Cavity and into the Unit 3 Spent Fuel Pool in accordance with the approved CCTAS. I will describe initial plant conditions and provide you access to the materials required to complete this task. TASK CONDITIONS/PREREQUISITES

1.

Refuel Bridge is removing Recently IrradiatE~d Fuel Assemblies out of the Reactor as directed by:

a. FH-6C Core Component Movement

b. SO 18.1.A -3 Operation of Refueling Platform Page 3 of 11 NLSR03066 Rev 000

,--"'-~,~----------------------------------------------?-----------

2.

Current approved Core Component Transfer Authorization Sheet (CCT AS) steps are as shown below: STEP NO. COMPONENT SERIAL NO. MOVEO FROM ORIENT MOVE TO ORIENT FHD RPO CRO WRNMCOUNTRATE ASCOEFGH DATE TIME 86 YJT709 P3CORE 03-38 SW P3SPENT G-16 SW 87 YJZ393 P3CORE 15-44 SE P3SPENTX-60 SW

3.

CCT AS step #86 is the current step:

a. Main Hoist is at the 'Normal Full-Up' position

b. Refuel Platform (Main Hoist) is over Unit 3 Core at location 03-38

c. SO 18.1.A-3 steps 4.9.1 AND 4.9.2 havEI just been completed

4.

Rad Protection Technicians are currently performing a survey of the Fuel Pool using a Teletector (complete Fuel Pool survey - will measure radiological conditions in all Fuel Pool areas). G. INITIATING CUE The Control Room Supervisor directs you (as the Fuel Handling Director) to continue to move Recently Irradiated Fuel out of the Unit 3 Reactor Cavity in accordance with the CCTAS. NLSR03066 Rev 000 Page 4 of 11

II if f r f N<C P--::L H. PERFORMANCE CHECKLIST STEP STEP ACT STANDARD NO NOTES A) If PRIOR to the JPM start (before examinee is given the Initiating Cue), the examinee questions how it is possible to be moving Recently Irradiated FUE~I, then the evaluator may state that an inadvertent criticality event occurred 8 hours a!Jo due to simultaneous HCU Blocking evolutions concurrent with a failure of the CRD Hydraulic System (SEN 264). If the question is asked AFTER the Initiating Cue is given, then the evaluator may NOT provide an answer to the question until after the JPM is complete (the question / answer has no bearing on the examinee's ability to perform the task). B) If at any time during this JPM the examinee asks if there are any 'special' engineering analyses in effect, then the evaluator should provide the following - (Cue: Only those engineering analyses associated wilth in progress procedures are currently in effect). C) The J PM start time may be recorded here ______

1.

The examinee obtains a copy of any (or P/SI Procedures may be obtained from all) of the following procedures: D controlled copy locations (Control Room, SO 18.1.A-3 Operation of Refueling Radwaste, Fuel Bridge) or from the Platform EDMS system. The EDMS system is FH-6C 'Core Component Movement accessed via the Exelon Intranet. The Core Transfers' EDMS system is launched and the user FH-35 'Control of Material Movement In then signs onto the system. The the Fuel Pool' procedure is selected using any number Unit 3 Tech Specs of search criteria. Once EDMS has Unit 3 Tech Spec Bases selected the procedure, double clicking on the selected procedure will bring up a (Cue: When the examinee calls up an copy of the latest revision for review electronic version of any of the above and/or printing. procedures, then hand them a hard copy of the appropriate procedure/procedures [latest revision]). NOTE: If EDMS is not available I not being used, then a discussion of how to obtain the procedure is satisfactory and the above 'Cue' may be followed. NLSR03066 Rev 000 Page 5 of 11 II

STEP NO STEP

2 FHD directs the RPO to lower the hoist until the grapple is near the bail handle of Fuel Assembly Y JT709.

(CUE: RPO reports that the Grapple is just above the bail handle of Fuel Assembly YJT709.) 3 FHD directs the RPO to verify the Grapple is open. (CUE: The RPO reports that the Grapple has been verified to be OPEN.) 4 FHD directs the RPO to rotate the grapple as necessary to achieve the proper grapple to bail alignment (with a Southwest orientation). (CUE: The RPO reports that the grapple and Fuel Assembly bail handle are properly aligned [with a Southwest orientation]. )

5 FHD directs the RPO to slowly lower the hoist until the 'Slack Cable' light is lit.

(CUE: RPO reports that the Hoist has been lowered and the 'Slack Cable' light is lit. 6 CONCURRENT VERIFICATION FHD and Spotter perform concurrent veri'fication of proper core component location and orientation. (CUE: Spotter reports that the core location is 03-38 and that the grapple has an orientation of Southwest.) II NLSR03066 Rev 000 ACT STANDARD S The hoist is lowered using the variable speed control, located on the right hand console until the Grapple is just above the Fuel Assembly bail handle. S The backlight on the GRAPPLE ENGAGED switch is verified to be extinguished. S The mast is rotated so that the grapple is aligned with the Fuel Assembly bail handle (with a Southwest orientation). S The hoist is slowly lowered down over the bail of the dummy bundle. The 'Slack Cable' light (located on the left hand console) is verified ON. S Proper core component location and orientation concurrently verified. Page 6 of 11

STEP STEP NO 7 FHD verifies the following: - 'Slack Cable' light is lit -Grapple is centered over bail handle -Hoist position reads 549 (CUE: RPO reports checking the same indications that the FHD has -the 'Slack Cable' light is lit -Grapple is centered over bail handle -Hoist position indicates properly at 549.)

8 FHD directs RPO to engage the Grapple.

(CUE: RPO reports that the Grapple is engaged.) 9 FHD and RPO perform peer check that 'Grapple Engaged' light is lit. (CUE: RPO reports checking the same indications that the FHD has - the 'Grapple Engaged' light is lit.)

10 FHD directs RPO to slowly raise Fuel Assembly while verifying 'Hoist Loaded' light is lit.

(CUE: RPO reports that the fuel assembly is rising slowly and the 'Hoist Loaded' light is lit.) Immediatel~ following the above cue Qrovide the examinee with the following cue. (Cue: "The Control Room Supervisor notifies you that during the performance of the Standby Gas Treatment System testing, both the 'B' and the 'C' SBGT fan motors tripped and neither motor can be started. The Control Room Supervisor directs you to control the evolutions on the Unit 3 Refuel Floor in accordance II with procedures and Unit 3 Tech Specs.") NLSR03066 Rev 000 ACT STANDARD S FHD verifies the following: - 'Slack Cable' light is lit -Grapple is centered over bail handle -Hoist position reads - 549 S Grapple is engaged by using the HOist Control Station. S 'Grapple Engaged' light is verified (peer checked with FHD) to be 'ON'. S The Fuel Assembly is slowly raised (using the Hoist Control Station) while ensuring the 'Hoist Loaded' light is 'ON'. Start of Alternate Path Page 7 of 11

__ ______ ________________________________t_t_____________ STEP ACT STANDARD ~

11 The examinee (FHD) directs that S

FH-6C step 7.1.5 [FHD] shall determine movement of Recently Irradiated Fuel the proper immediate corrective action if Assemblies stop. an abnormal event or instrument response occurs... (CUE: RPO reports that the Fuel FH-6C step 7.1.7 [FHD] shall be Assembly is stationary at a Hoist position responsible for review of the prerequisites of 500.) to this procedure to assure that all applicable prerequisites are met during (CUE: If examinee notifies the control core component movement. room / Reactor Operators of the 'Stop Order' for Fuel Movement and/or the Tech Spec 3.6.4.3 Condition 'E' (Two insertion of the Fuel Assembly at core SBGT subsystems inoperable during location 03-38, then acknowledge the movement of Recently Irradiated Fuel report.) assemblies in the Secondary Containment or during OPDRVs): Required Action E.1 - Suspend movement of Recently Irradiated Fuel Assemblies in secondary containment (immediately)

12 FHD directs the RPO to lower the hoist S

Lower hoist until component is seated until the Fuel Assembly is seated and the and 'Slack Cable' light is lit. 'Slack Cable' light is lit. Note to evaluator - This guidance is from (CUE: RPO reports that the Fuel the SO 18.1.A-3 procedure starting at Assembly has been seated in core step 4.14.7. location 03-38 and the 'Slack Cable' light is lit.) 13 FHD verifies the following: S FHD (and RPO) verify -'Slack Cable' light is lit -Slack Cable' light lit -Hoist position reads 549 -Hoist position reads 549 -Fuel Assembly elevation appears -Fuel Assembly elevation appears equivalent to adjacent Fuel equivalent to adjacent Fuel Assemblies Assemblies (CUE: RPO reports checking the same indications that the FHD has -'Slack Cable' light is lit -Hoist position reads 549 -Fuel Assembly elevation appears equivalent to adjacent Fuel Assembliesl II I

==================~----~~~----:--===========----------------~

NLSR03066 Rev 000 Page 8 of 11

,~.......-.------------ _.

,---,---~...-'-'.~~.'. STEP STEP ACr= STANDARD NO

14 FHD directs the RPO to release the Grapple S

Grapple is released by using the Hoist Control Station. (CUE: RPO reports that the grapple is OPEN.)

15 FHD directs the RPO to slowly raise the S

The grapple is slowly raised while hoist while verifying the 'Hoist Loaded' verifying the 'Hoist Loaded' light remains light remains 'OFF'. 'OFF'. (CUE: RPO reports that the Hoist is rising and the 'Hoist Loaded' light is NOT lit.) 16 FHD and the RPO perform peer check S FHD and the RPO perform peer check that the grapple is clear of core that the Grapple is clear of core components. components. (CUE: RPO reports that the grapple is clear of all core components.) 17 The examinee directs that the Fuel Pool S Engineering analysis for handling light survey may continue. loads over Irradiated Fuel without Secondary Containment / SBGT (Table 2 (Cue: If examinee asks what the weight of FH-6C and/or Table 1 of FH-35) of the Teletector in use is, then reply - permits use of Teletector survey "The Teletector wejght is 8 Ibs.") instrument. Notes to Evaluator A) If the examinee determines that movement of Recently Irradiated Fuel should stop solely due to the pre-requisites of FH-6C (i.e. examinee does not consult or refer to Tech Specs), Then ask the examinee this follow-up question - (Cue: "Is there a PBAPS Unit 3 Tech Spec which also directs that Recently Irradiated Fuel movement must stop?") For answer, refer to step 11 B) If the examinee does NOT address the Fuel Pool Survey activity, then ask the examinee this follow-up question - (Cue: "Is the Fuel Pool Survey activity required to stop?) For answer, refer to step 17 ';) The following step ONLY applies if this JPM is being used for Requalification training (Le. step 18 does NOT apply to Initial LSRO training / testing). NLSR03066 Rev 000 Page 9 of 11 II

STEP STEP ACT STANDARD NO 18 (Cue: After the above actions are P All of the above work that was stopped complete, then ask the following question due to the loss of the SBGT system (both 7 'If the above conditions occurred at SBGT subsystems) would also be Limerick Unit 1, would you make the stopped at Limerick under these same stop-work determinations that you conditions (exact wording not required). just made here at PBAPS (if not, how However, at Limerick, the loss of two would the determinations be different)?' SBGT fans will cause these actions to apply to Both Limerick Unit 1 & Limerick (Cue: If the examinee asks to see any [or Unit 2. At PBAPS, the loss of two SBGT all] of the below listed procedures, then fans will OI\\lLY cause these actions to provide the examinee with a copy of the apply to either Unit 2 OR Unit 3 requested procedure(s): (depending on which SBGT Fans have

Limerick Unit 1 Tech Specs failed).
FH*105 Limerick Unit 1 Tech Specs Limiting Condition for Operation spec 3.6.5.3 Action 'b' 'With both standby gas treatment subsystems inoperable, if in progress, suspend handling of irradiated fuel in the secondary containment, Core Alterations or operations with the potential for draining the reactor vessel.

Note - Not required to be stated by the examinee (but provided here as a reference to the evaluator), at Limerick the same jobs would be stopped even if ONLY 'Irradiated Fuel' was involved (i.e. not just Recently Irradiated Fuel transfers ). l\\Iotes to Evaluator A) After the examinee has answered all follow-up questions, the evaluator may terminate this JPM. The end time for the JPM may be recorded here. ________ B) As an evaluator, ensure you have positive control of all exam material provided to the examinee ('Task Conditions I Prerequisites & Initiating Cue' sheElt' AND procedures). Under "ACT" P - must perform S - must simulate D-must discuss I. TERMINATING CUE When the examinee has determined which work must stop and addressed any applicable follow-up questions, then the evaluator may terminate the exercise. NLSR03066 Rev 000 Page 10 of 11

Task Conditions / Prerequisites and Initiating Cue _____----*'",--,,----------------~ F. TASK CONDITIONS/PREREQUISITES

1.

Refuel Bridge is removing Recently Irradiated Fuel Assemblies out of the Reactor as directed by:

a. FH-6C Core Component Movement

b. SO 18.1.A -3 Operation of Refueling Platform

2.

Current approved Core Component Transfer Authorization Sheet (CCTAS) steps are as shown below: STEP COMPONENT MOVED FROM ORIENT MOVE TO

ORIENT FHD RPO CRO WRNMCOUNTFIATE DATE TIME NO.

SERIAL NO. ABCDEFGH 86 Y JT709 P3CORE 03-38 SW P3SPENT G-16 87 YJZ393 P3CORE 15-44 SE P3SPENTX-60 S'vV

3.

CCT AS step #86 is the current step:

a. Main Hoist is at the 'Normal Full-Up' position

b. Refuel Platform (Main Hoist) is over Unit 3 Core at location 03-38

c. SO 18.1.A-3 steps 4.9.1 AND 4.9.2 have just been completed

4.

Rad Protection Technicians are currently performing a sUNey of the Fuel Pool using a Teletector (complete Fuel Pool sUNey - will measure radiological conditions in all Fuel Pool areas). G. 1I\\lITIATING CUE The Control Room SupeNisor directs you (as the Fuel Handling Director) to continue to move Recently Irradiated Fuel out of the Unit 3 Reactor Cavity in accordance with the CCTAS. NLSR03066 Rev 000 Page 11 of 11

EXELON NUCLEAR Nuclear Generation Group OJTITPE MATERIAL. COVERSHEET JPM QUALIFICATION MANUAL O..IT MODULE D D Limited Senior Reactor Operator LSRO Initial & LSRO Requalification 00 wz Dummy Fuel Movement in the Spent Fuel Pool (PBAPS - Fire) APPROVALS: Signature I Title Date Signature I Title Date Signature I Title Date Signature I Title Date ,PPROVED FOR USE: Signature I Title Date EFFECTIVE DATE: __-----'I __--',___ NAME: ISSUE DATE: Last First M.I. EMPLOYEE ID NO. COMPLETION DATE: COMMENTS: Training Review for Completeness: LMSCODE: LMS ENTRY: Signature/Date NLSR03064 Rev 000 Page 1 of 14

~~----------------'--...~------------------------.---------~'

EXELON NUCLEAR PEACH BOTTOM ATOMliC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE: Senior Reactor Operator I Senior Reactor Operator - Limited (LSRO) TASK-JPM DESIGNATOR: 295023-9 -- NLSR03064 KIA: 600000 AA2.16 RO: 3.0 SRO: 3.5 TASK DESCRIPTION: Actions in the event of a fire A. NOTES TO EVALUATOR:

1.

An asterisk (*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.

2.

System cues included in the performance checklist are to be provided to the examinee when no system response is available.

3.

JPM Performance

a.

"Control Room" JPMs are designed to be performed in the simulator. If a "Control Room" JPM is to be performed in the Control Room all perform steps (P) shall be simulated (S).

b.

When performing "In-Planf' JPMs, no equipment will be operated without Shift Management approval.

4.

Satisfactory performance of this JPM is accomplished if:

a.

The task standard is met.

b.

JPM completion time requirement is met.

1)

For non-time critica.l JPMs, completion within double the estimated time (listed in paragraph 0.2) is acceptable provided the evaluator determines that the progress to completion is acceptable.

2)

For time critical JPMs, completion within the estimated time (listed in paragraph 0.2) is required.

5.

The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee. NLSR03064 Rev 000 Page 2 of 14

______________________________________________________ _____________________W__

6.

7.

8.

9.

10.

11.

12.

Verify the prerequisites of FH-35 and SO 18.1.A-2(3) are satisfied AND permission is obtained from Shift Supervision to perform dummy fuel bundle moves BEFORE the JPM begins (evaluator). The evaluator must indicate on the 'Task Conditions/Prerequisites & Initiating Cue' sheet which unit is to be used for the JPM (and have the appropriate CCTAS, procedulres, and Prerequisites met if applicable). This JPM may be used for PBAPS Unit 2 or Unit 3. However, the evaluator must make certain that all prerequisites and approvals are obtained on the unit that is going to be used prior to starting this JPM. This JPM is designed to have the examinee move the dummy fuel bundle using the Refuel Platform in 'manual' mode. However, if this JPM is performed in conjunction with loading the appropriate move sequence [section 4.5 of SO 18.1.A-2(3)], then this JPM may be performed with Refuel Platform set up for 'Semi-Automatic Operation' (section 4.6 of SO 18.1.A-2(3). Regardless of how the Refuel Platform is moved, this..IPM is evaluating the trainee to the standards of SO 18.1.A-2{3) sections 4.8 and 4.13. The evaluator MUST clearly identify to the examinee the expectation to move the Refuel Platform either manually or with the Refuel Platform set up for 'Semi-Automatic Operation. The design activity level for this JPM is 'PERFORMED' (P). It is an expectation that the LSROs will use the Refuel Platform to move a dummy fuel bundle for evaluation. However, setting up the Refuel Platform for operation requires coordination between Reactor Services, Radiation Protection, Reactor Engineers, and Shift Operations, as well as requiring multiple Refuel Platform subsystems to be working correctly. Therefore, the activity level for this JPM is deSignated as Perform/Simulate (P/S) to provide a POSSIBLE contingency for the infrequent condition that despite proper planning, actual Refuel Bridge operation is precluded. Use of simulate for this JPM requires the approval of the PBAPS Op~3rati()ns Training Manager. If dummy fuel bundle is moved, then all required stations MUST be filled by qualified individuals. Most JPMs that involve the use of Concurrent Verification or Peer Checks are performed with the Concurrent Verification / Peer Checks being simulated (not leading the examinee). This JPM is different because an actual component is being moved in the Fuel Storage Pool. Therefore, all required verifications and checks will be performed per procedure. Any errors by the examinee discovered during a Concurrent Verification / Peer Check will be documented by the JPM evaluator. JPM paperwork that is used on the Refueling Bridge may be contaminated and not be available for record retention. Unless the JPM Pre-job brief determines otherwise, if JPM material used on the Refueling Bridge becomes contaminated, then, it is acceptable for the JPM evaluator to transfer JPM notes/scores to a JPM summary sheet and destroy original JPM paperwork (AFTER accounting for ALL exam material). The DA is in charge of all evolutions on that occur on the Refuel Platform. It is required that the DA perform a Pre-Job Brief /2 Minute Drill with the RPO (LSRO examinee) for this evolution. The Pre-Job Brief / 2 Minute Drill are human performance tools that do NOT constitute inappropriate coaching or exam compromise. Page 3 of 14 NLSR03064 Rev 000

13.

Evaluator(s) must be particularly cognizant of the potential for a foreign material event (FME) to occur. Beside the need for exam security (maintaining control of the JPM and associated exam paperwork), there is a risk for the evaluator to lose control of paper and/or pens (refer to issue 01001205). B. TOOLS AND EQUIPMENT

1.

Unit 2 or Unit 3 Refueling Bridge accessible.

2.

HP coverage provided for the Dummy Fuel Bundle move (including RWP).

3.

Reactor Services support to provide:

a. FHD and a Spotter

b. Applicable portions of FH-35 completed (and documented)

c. Refuel Bridge checked out in accordance with SO 18.1.C-2(3)

d. Work Order C0222751 may be used as a reference for coordinating the support needed to move the Dummy Fuel Bundle in the Fuel Pool.

4.

Reactor Engineers to develop the CCTAS as required (three hard copies of the CCTAS are required). C. REFERENCES

1.

FH-35 Revision #36 'Control of Material Movement in the Fuel Pool'

2.

SO 18.1.A-2(3) Rev. 21 'Operation of RI3fuei Platform'

3.

SO 18.2.A-2(3) Rev. 3 'Shutdown of Refueling Platform'

4.

ON-114 Rev. 17 'Actual Fire Reported in the Power Block, Diesel Generator Building, Emergency Pump, Inner Screen or Emergency Cooling Tower Structures'

5.

Limerick Procedure S97.0.M Rev. 25 'Refueling Platform Operation'

6.

OU-AB-4001 Rev. #3 'BWR Fuel Handling Practices' D. TASK STANDARD 1. Satisfactory task completion is indicated when the Dummy Fuel Bundle is moved from one location in the Fuel Pool to another in accordance with the CCTAS and SO 18.1.A 2(3). (NOTE - Evaluator must specify which PBAPS unit to perform/simulate the JPM.)

2.

Estimated time to complete: 40 minutes Non-Time Critical NLSR03064 Rev 000 Page 4 of 14

DIRECTIONS TO EXAMINEE When given the initiating cue, perform the necessary steps to move the (Unit 2/ Unit 3) Dummy Fuel Bundle in accordance with the attached CCT AS and in accordance with SO 18.1.A-2(3). The Refuel Platform must be op'3rated in the Manual mode. For the entire evolution, you will treat the Dummy Fuel Bundlle as if the Dummy Fuel Bundle is actual irradiated fuel. You are to perform the NEXT two (2) CCTAS moves. You are to PERFORM this activity as the Refuel Platform Operator. F. TASK CONDITIONS/PREREQUISITES

1.

There are NO irradiated components grappled to any Refuel Platform Hoist.

2.

The auxiliary hoists are full up.

3.

All of the applicable Prerequisites for procedure FH-35 have been completed for Dummy Bundle transfer in the Spent Fuel Pool.

4.

All applicable Prerequisites of procedure SO 18.1.A-2(3) have been completed for Dummy Bundle transfer in the Spent Fuel Pool.

5.

All applicable portions of SO 18.1.C-2(3) 'Electrical, Mechanical, and Pneumatic Alignment I Checkout of Refueling Platform" have been completed. G. INITIATING CUE

1.

The Fuel Handling Director directs you to perform the necessary steps to move the (Unit 2/ Unit 3) Dummy Fuel Bundle in accordance with the attached CCTAS and in accordance with SO 18.1.A-2(3). You will perform the NEXT two (2) CCTAS moves. The Refuel Platform must be operated in the Manual mode.

2.

For the entire evolution, you will treat the Dummy Fuel Bundle as if the Dummy Fuel Bundle is actual irradiated fuel.

3.

You are to PERFORM this activity as the Refuel Platform Operator. NLSR03064 Rev 000 Page 5 of 14

H. PERFORMANCE CHECKLIST U STEP STEP ACT STANDARD NO Notes to Evaluator A) Provide a copy of SO 18.1.A-2(3) and a copy of the CCTAS for dummy bundle movement prior to starting JPM. B) The following steps are contained in procedure SO 18.1.A-2(3), section 4.8 (Pickup Location - Fuel Pool Storage Rack) C) The examinee may validate any and all prerequisites associated with FH-35 / SO 18.1.A / RWPs / FME plans including verifying that Shift Operations has given permission for the move and verifying Refuel Platform Computer log in (step 4.1 of SO 18.1.A). D) Examinee is permitted to communicate with the FHD and/or Spotter in order to 'setup' for task, concurrent verifications, and documentation on the CCTAS. FHD and Spotter are NOT to lead the examinee in performing the task. E) JPM may be started from the associated Refueling Platform. F) The examinee may request permission to pick up the dummy fuel bundle as a 'Hard Pick'. The FHD evaluating the move as a 'Hard Pick' and giving permission to grapple the dummy fuel bundle as a 'Hard Pick' is acceptable and expected (i.e. This is NOT coaching and it is NOT an exam compromise). G) The FHD must give a Pre-Job Brief I 2 Minute Drill to the RPO (LSRO examinee) before the start of the JPM. After the FHD's Pre-Job Brief 12 Minute Drill, the start time for the..IPM may be recorded here ______-'--______ Position Refuel Platform Mast over The Refuel platform is positioned over the

1 desired core component in accordance PIS dummy fuel bundle.

with Core Component Transfer Authorization Sheet (CCTAS). Lower hoist until grapple is near bail. The hoist is lowered using the variable

2 PIS speed control, located on the right hand console until the hoist position indication is between 176 - 182 (approximately).

3 Verify grapple is open. PIS The backlight on the GRAPPLE ENGAG ED switch is verified to be extinguished. NLSR03064 Rev 000 Page 6 of 14 II

'.-.--------------------------------------------.----------.~

STEP STEP NO 4 Rotate grapple as necessary to achieve grapple to bail alignment

5 Slowly lower hoist until SLACK CABLE light is lit.

6 CONCU RRENT VERI FICA-nON FHD and Spotter perform concurrent verification of proper core component location and orientation. ACT STANDARD PIS The mast is rotated so that the grapple is aligned with the dummy fuel bundle bail handle. PIS The hoist is slowly lowered down over the bail of the dummy bundle. The SLACK CABLE light, located on the left hand console is verified ON. PIS Proper core component location and orientation concurrently verified. (This standard is N/A for the RPO unless the RPO is also acting as the Spotter) NOTE The verifications in the following two steps may be performed in parallel. 7 FHD verify the following: 7a

SLACK CABLE light is lit 7b
Grapple is centered over bail handle 7c
Hoist pOSition indication agrees with Attachment 9 for item seated in Fuel Pool Storage Rack 7d
THEN direct RPO to engage grapple (Cue: evaluator will have the FHD direct the examinee to engage the grapple.)

II 8 RPO verify the following: N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A I N/A See below NLSR03064 Rev 000 Page 7 of 14

9 STEP STEP NO 8a

SLACK CABLE light is lit 8b
Grapple is centered over bail handle 8c
Hoist position indication agrees with Attachment 9 for item seated in Fuel Pool Storage Rack
8d
WHEN directed by FHD, engage grapple FHD and RPO perform Peer Check that "GRAPPLE ENGAGED" light is lit
10 Slowly raise load while verifying HOIST LOADED light is lit (fuel only).
11 Continue raising until grapple is fully raised, THEN verify Grapple NORMAL UP light is lit.

ACT STANDARD PIS SLACK CABLE light is verified to be ON PIS Grapple is verified to be centered over the bail handle PIS Hoist position indication is verified to be in agreement with Attachment 9 PIS Grapple is engaged by using the Hoist Control Station PIS GRAPPLE ENGAGED light is verified (peer checked with FHD) to be 'ON'. PIS The dummy fuel bundle is slowly raised (using the Hoist Control Station) while ensuring the HOIST LOADED light is 'ON'. PIS Continue raising the grapple to the full up position and verify that the Grapple NORMAL UP light is 'ON'. Notes to Evaluator A) The following steps are contained in procedure SO 18.1.A-2{3), section 4.13 "Set down Location - Fuel Pool" B} JPM steps 12 & 13 shall be concurrently verified by the Fuel handling Director (FHD) and Refuel Platform Operator (RPO) or Spotter. NLSR03064 Rev 000 Page 8 of 14 II

STEP STEP ACT STANDARD NO

12 Position core component over desired location in accordance with Core Component Transfer Authorization Sheet (CCTAS).

PIS The platform is positioned so that the dummy fuel bundle is hanging over the correct spent fuel pool storage location (per CCTAS) (Cue: The following announcement is heard over the plant page - "Attention all personnel, attention all personnel a fire hazard exists in the Unit 2/3 Reactor Building AND Refuel Floor. All personnel evacuate the Unit [2 13] Reactor Building AND Refuel Floor by the nearest exit and assemble outside of the Unit 3 Turbine Building.) (Cue: Evaluator will repeat the above cue.) Notes to Evaluator I FHD l\\) The Refuel Platform FHD must be briefed BEFORE the start of the JPM to expect the 'announcement' of the fire AND to expect the possibility that the examinee will ask the FHD for clarifying instructions. The below cues are for both the Evaluator AI\\ID/OR the Fuel Handling Director (FHD). B) If the examinee asks the FHD for direction (Le. should we evacuate now?), then the FHD will provide the following CUE to the examinee (Cue: When the equipment is in a safe condition, then evacuate the Refuel Floor). C) If the examinee asks the Evaluator for direction (Le. simulating contacting the control room I SSV and asking if the Refuel Floor should be evacuated now?), then the evaluator will provide the following CUE to the examinee (Cue: When the equipment is in a safe condition, then evacuate the Refuel Floor). D) If the examinee asks whether or not the Refuel Platform is in a 'safe' condition, then the ONLY acceptable cue is (even if cue was previously given) 'When the equipment is in a safe condition, then evacuate the Refuel Floor). In other words, the examinee MUST determine that the Fuel Bundle must be seated BEFORE the Refuel Platform may be considered in a 'safe' condition.

13 Rotate core component as necessary to PIS The mast is rotated so that the dummy achieve proper orientation.

fuel bundle is properly oriented (per CCTAS as appropriate). NLSR03064 Rev 000 Page 9 of 14

STEP STEP ACT STANDARD NO Notes to Evaluator A) At any time during this JPM, IF the examinee asks if there are any indications of smoke or fire, then provide the following cue: (Cue: There is an acrid odor in the air, however, there is no visible smoke and no visible sign of flames.) B) Component may be inserted into the fuel rack up to hoist position 25", in parallel with verification of core component location and orientation. FHD and Spotter perform Concurrent Proper core component location and 14 Verification of proper core component PIS orientation concurrently verified. location and orientation (This standard is NIA for the RPO unless the RPO is also acting as the Spotter) 15 Spotter and RPO discuss the 'Push' or PIS Fuel Assembly may need to be either 'Pull' (twist left I twist right) motion pushed or pulled while being seated to required for seating the Fuel Assembly prevent the channel fasteners from contacting the fuel rack.

16 Lower hoist until component is seated PIS The dummy fuel bundle is lowered (using and the 'SLACK CABLE' light is lit.

the Hoist Control Station) until the component is seated and the SLACK CABLE light is energized. NOTE

The verifications in the following two steps may be performed in parallel (steps 17 & 18).

______________..9___________ STEP NO STEP ACT STANDARD 17c

Hoist position indication agrees with Attachment 9 for item seated in Fuel Pool Storage Rack NIA NIA 17d
THEN direct RPO to release grapple NIA NIA 18 RPO verify the following:

PIS NIA 18a

SLACK CABLE light is lit PIS SLACK CABLE light is verified to be ON 18b
Component elevation appears equivalent to other stored components in the rack PIS Bundle is verified to be at the same elevation as other fuel bundles in the racks.

18c

Hoist position indication agrees with Attachment 9 for item seated in Fuel Pool Storage Rack PIS Hoist position indication is verified to be in agreement with Attachment 9 (-188 inches)
18d
THEN WHEN directed by FHD, release grapple PIS Grapple is released by using the Hoist Control Station If necessary, the Evaluator will ask the FHD to direct the examinee to release the grapple. (This is a possible cue for the FHD - NOT a cue for the examinee.)

19 Verify grapple is open. PIS GRAPPLE ENGAGED light is verified to be 'OFF'. 20 Slowly raise hoist while verifying 'HOIST LOADED' light remains 'OFF'. PIS The grapple is slowly raised while verifying the 'HOIST LOADED' light remains 'OFF'. II 21 Perform Peer Check with FHD to ensure grapple is clear of core components. PIS Verify Grapple is clear of core components. NLSR03064 Rev 000 Page 11 of 14

STEP STEP ACT STANDARD NO 22 Verify completion of component N/A N/A transfer on CCTAS (as required). l\\Jotes to Evaluator A) Ideally, the below two steps will NOT be performed. The Evaluator should terminate the JPM when the examinee has made it clear that their intention is to evacuate the Refuel Floor. B) If the "STOP" push button is depressed (step 23 below), then the Evaluator should be aware that the only consequence to step #23 being performed is that the Refuel Platform will need to be re started before this JPM is re-performed. C) The next step is directed out of procedure SO 18.'1.A step 3.24 and SO 18.2.A (Short Term SID). 23 Depress the "STOP" push button at the S The large red 'STOP' push button located Start/Stop Station. on the Start/Stop Station is momentarily depressed.

24 Evacuate the Refuel Floor.

S The examinee evacuates the Refuel Platform and Refuel Floor. Notes to Evalua.tor A) If at any time, the examinee attempts to perform tine second CCTAS move (as directed by the initiating cue), then that action constitutes a failurl3 of this JPM (Not evacuating as soon as the Refuel Platform is in a safe condition). B) If at any time, the examinee attempts to evacuate the Refuel Floor with the Dummy Fuel Bundle hanging from the Refuel Platform (Dummy Fuel Bundle NOT seated), then that action constitutes a failure of this...IPM (Not identifying the necessary conditions for placing the Refuel Platform in a safe condition). C) The following step ONLY applies for Requal Examinations (Step 25 is NOT applicable to Initial Exams). D) When the examinee expresses their intention to e~vacuate the Refuel Floor, then the evaluator may terminate the performance portion of the...IPM and continue with the next step (if applicable): (CUE: "You may stop here, you have met the termination criteria for the performance portion of this JPM") NLSR03064 Rev 000 Page 12 of 14 II

_________________ _p. IrsTEP STEP ACT STANDARD II NO II 25 D The answer to the question is: The Follow-up Question (Evaluator to ask the actions performed here for an evacuation examinee): due to a fire are the same that would be (CUE: If you were moving a Limerick done at Limerick. While there are minor Fuel Bundle [from one location in the differences in the bridge controls between Limerick Fuel Storage Pool to another PBAPS and Limerick, in both places, the location in the Limerick Fuel Storage Refuel Platform must be in a 'safe' Pool] and an announcement was made to condition prior to evacuating (no evacuate the Refuel Floor due to a fire, irradiated fuel hanging from the Refuel how would the actions you just performed Platform. I simulated here be different if you were at Limerick [on a Limerick Refuel Note to Evaluator - The answer to the Platform])? follow up question does not have to be answered by the trainee using the exact l\\Jote to Evaluator -If the examinee asks words that are shown above. for a copy of the Limerick Procedure 'S97.0.M 'Refueling Platform Operation', then: (CUE: Provide examinee with a copy of S97.0.M) Notes to Evaluator A) After the examinee has answered all required follow-up questions, the evaluator may terminate this JPM. The end time for the JPM may be recorded here. ________ B) As an evaluator, ensure you have positive control of all exam material provided to the examinee ('Task Conditions I Prerequisites & Initiating Cue' sheet' AND procedures). Under "ACT" P - must perform S - must simulate D-must discuss I. TERMINATING CUE When the examinee has answered all follow-up qUElstions, then the evaluator may terminate the JPM. NLSR03064 Rev 000 Page 13 of 14

TASK CONDITIONS / PREREQUISITES AND INITIATING CUE TASK CONDITIONS/PREREQUISITES 1. There are NO irradiated components grappled to any Refuel Platform Hoist.

2.

The auxiliary hoists are full up.

3.

All of the applicable Prerequisites for procedure FH-35 have been completed for Dummy Bundle transfer in the Spent Fuel Pool.

4.

All applicable Prerequisites of procedure SO 18.1.A-2(3) have been completed for Dummy Bundle transfer in the Spent Fuel Pool.

5.

All applicable portions of SO 18.1.C-2(a) 'Electrical, Mechanical, and Pneumatic Alignment I Checkout of Refueling Platform' have been completed. INITIATING CUE 1. The Fuel Handling Director directs you to perform the necessary steps to move the (Unit 2 / Unit 3) Dummy Fuel Bundle in accordance with the attached CCTAS and in accordance with SO 18.1.A-2(3}. You are to perform the NEXT two (2) CCTAS moves. The Refuel Platform must be operated in the Manual mode.

2.

For the entire evolution, you will treat the Dummy Fuel Bundle as if the Dummy Fuel Bundle is actual irradiated fuel.

3.

You are to PERFORM this activity as the Refuel Platform Operator. NLSR03064 Rev 000 Page 14 of 14}}

v t e Letter Sequence Draft Other
TAC:U01795, (Open) TAC:U01796, (Open)
Initiation Acceptance... Administration Questions Answers Results Approval... Other: ML102420204, ML102420248, ML102420261, ML102520084, ML110390528
MONTHYEAR2010-07-01 [Table View]

ML102150190

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