Text

and Peach Bottom Lsro - Final Operating Exam (Sections a, B, and C) (Folder 3)
	ML102420261
Person / Time
Site:	Peach Bottom, Limerick
Issue date:	07/09/2010
From:	Dickenson R, Wasong A; Exelon Generation Co
To:	D'Antonio J; Operations Branch I
	Hansell S
Shared Package
ML092470056	List: IR 05000277/2010301; ML102150100; ML102150104; ML102150190; ML102420204; ML102420248; ML102420261; ML102460251; ML102520084;
References
	TAC U01795, TAC U01796
	Download: ML102420261 (184)
	v • d • e

Exelon Nuclear Job Performance Measure LSRO Only - FUEL HANDLING DIRECTOR TURNOVER CONDITIONS NOT MEETING TECHNICAL SPECIFICATION REQUIREMENTS JPM 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.1 05 (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 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 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 JPM.

12. When JPM is initially validated, sign and date ..IPM 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 6

NLSR02084 RevOOO REVISION RECORD (Summary)

1. Revision 00 NtA SIMULATOR SETUP INSTRUCTIONS

1. N/A 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 / Planned for next shift, including determination of Tech Spec compliance.

TASK STANDARD(S):

Determine the following Evolutions in Progress / 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 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.1 05 (when utilized for operator initial or continuing training) Page 3 of 6

NLSR02084 RevOOO JPM

SUMMARY

Operator's Name:,_ _ _ _ _ _ _ _ _ _ _Job

Title:

D SED D SM DSRO D STAliA ~ OTHER JPM

Title:

FUEL HANDLING DIRECTOR TURNOVER 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: DYes ~No SRO Only: ~Yes DNo Time Critical: DYes ~No Reference(s):

Procedure OP-AA-112-101 Rev: 6 Procedure OP-LG-112-101-F-11 Rev: -..!..-

Procedure Actual Testing Environment: Simulator D Control Room D In-Plant ~ Other Testing Method: D Simulate ~ Perform Estimated Time to Complete: 20 minutes Actual Time Used: minutes EVALUA"nON

SUMMARY

Were all the Critical Elements performed satisfactorily? DYes 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: 30.105 (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 ELEMENT STANDARD

~

en

-c(1) ...

E..Q (1) en z E §

)

ooz:.

CUE: Provide candidate with the Fuel Handling Director Turnover Checklist N/A AND Copy of Technical Specifications - -

1. Evolutions in Progress I Determine Movement of spent Planned for next shift: fuel in the Spent Fuel Pool cannot occur:

Current CCTAS is for Spent fuel pool transfers Tech Spec. 3.9.8 is not met as only 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

2 Evolutions in Progress I Determine Core Transfers Planned for next shift: cannot occur:

Core Transfers Tech Spec. 3.9.8 is not met as

water level is not 22 feet above the reactor pressu re vessel flange, Core Alterations cannot occur.

Tech Spec. 3.9.5 is not met as

Control Room communications is intermittent, Core Alterations cannot occur.

I 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 JPM JPM Stop Time: _ _ _ __

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

OP-LG-112-101-F-11 Exel n Revision #

Page 1 of 4 Nuclear FUEL HANDLING DIRECTOR SHIFT TURNOVER CHECKLIST NOTE: Complete this form at turnover Date:_ _-,-"M=M:..!!../.=.D.=.D~/y~Y,-_ _ _ _ _ _ _ _ __ Oncoming Shif(8) 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 Offgoing FHD Signature: __T:...::o::.!..m~S:.:..:.m~it~h_ _ _ _ _ _ _ _ __

SRRS: 30.105 (when utilized tor operator initial or continuing training)

OP-LG-112-101-F-11 Revision ##

Page 2 of 4

1. FHD Log and information on page 1 reviewed. 1. RAC

2. Fuel Floor local panel annunciators (both units) and Refuel Platform Interlock/Controls reviewed. 2. RAC

3. Status of work reviewed with Maint. Supervisor and RP Technician. 3. RAC

4. RP Drywell Control Point contacted and has verified access control to upper elevations is in place as required. 4. RAC RP Contacted: AI Senter

5. IF irradiated component transfers through cask pit will occur, RP has posted RB 313' areas as required. 5. RAC

6. Refueling Platform checkout per S97.1 .A is complete as required. 6. RAC

7. FHDs, Refuel Platform Operators (RPOs), and Spotters are qualified and completed all required reading. 7. RAC

8. Continuous communications established between Control Room and Refueling Platform during CORE ALTERATIONS. 8. RAC

9. FHD conducted a pre-evolution brief with refuel platform personnel. 9. RAC

10. Work environment assessed for error-free challenges; actions taken as necessary. 10. RAC (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. 11. RAC

12. CCTAS reviewed, and verified same title/rev. as Reactor Operator and Spotter copies. 12. RAC

13. IF not in use, THEN GE RCWP Jib Hoist Booms rotated away from RPV center. 13. RAC

14. Dedicated Spotter present when:

Fuel handling concurrent with Areva RCWP hoist installed OR Fuel handling concurrent with GE RCWP jib hoist load handling. 14. RAC

15. Auxiliary hoist jam blocks set properly during in-vessel maintenance. 15. RAC

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. 16. RAC

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. 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.105 (when utilized for operator initial or continuing training)

OP-LG-112-101-F-11 Revision ##

Page 3 of 4

18. RAC

19. Refueling Interlocks and Refuel Platform equipment operable as required by Tech Specs. ST 097 -630-1 (2) OR ST-6-107 -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 U-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-specific temperature specified by Reactor Engineering. 23. NOTE #1

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

25. RHR SOC flow:s 6000 gpm OR all In-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 NOTE # 2 "A" RHR in ADHR flow 5700 gpm

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

Oncoming FHD Signature: R. Nather Time: ####

SRRS; 3D.1 05 (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 CCTAS Instruction/Approval Page Core Component Transfer Authorization Sheet Page _:.--_ of 2 Unit LIMERICK GENERATING STATION Date MM/DDIYY 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, 8, C, D 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). SNM 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~F~o=u=s~t___________________ / __~M=M=/=D=D~/Y~Y~____

Preparer DATE

____~G~S~ni=de=rt~_________________ / ___=M=M~/=D=D~/Y~Y~____

Independent Reviewer DATE

_ _...:H..:-:-P...:::o~tt.::::;,;er:...--_ _ _ _ _ _ _ _ / _---'-'M=M"'-"/-=Dc.;;;D'-'-/Y...;...Y--'--_ _ _Distribution Legible YES Reactor Engineer DATE Return completed CCTAS (or a copy if original is contaminated) to Reactor Engineering.

Review of Completed Move Sheets: _____________ / _ _ _ _ _ __

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

NF-LG-31 0-2000 Revision ##

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 L2SPENT KK*158 SW LlSPENTT-58 SW 2 LY8488 L2SPENT KK156 SW L1SPENT U*57 SW 3 LY8811 L2SPENT KK-l54 SW LlSPENT U-56 SW 4 LYN091 L2SPENT KK-152 SW L1SPENT V-58 SW 5 LY8812 L2SPENT KK-150 SW L1SPENT V-56 SW 6 LY8813 L2SPENT KK148 SW L1SPENT W-58 SW 7 LYN104 L2SPENT KK146 SW L1SPENT W-57 SW 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:

SIIJIE or Instructor Date Reviewed By:

Operations Representative Date Approved By:

Training Department Date SRRS: 30.105 (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 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 "IPM 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.1 05 (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 !!2! 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 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 mrem/hr Worker 1 has 900 mrem accumulated dose on his Electronic Dosimeter from his first entry Worker 2 has 800 mrem accumulated dose on his Electronic Dosimeter from his first entry 1.5 total man-hrs are required to finish the work Work is to be performed on the Refuel Floor inside a quarantined area.

INITIATING CUES:

You are directed 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 TOTAL 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:

Any UNSAT requires written comments on respective step.

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

NLSR02701 Rev001

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.1 05 (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 STAliA I2J 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 I2J No SRO Only: I2JYes ONo Time Critical: OYes I2JNo Reference(s):

Procedure RP-M-460-002 Rev: --"'---

0 Procedure Rev:

Actual Testing Environment: 0 Simulator 0 Control Room 0 In-Plant I2J Other Testing Method: 0 Simulate I2J 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.1 05 (when utilized for operator initial or continuing training) Page 5 of 7

NLSR02701 Rev001 JPM Start Time: _ _ __

Ica emen t( S).In d'Icat ed b)y C nTIEl H*'" In Pe rformance Checkl'IS. t ELEMENT STANDARD l

e(

l-e(

tJ)

-e ..

(1),8 EE -I tJ) z E ::J

t 0

Oz (Cue: Provide copy of RP-AA N/A 460-002 and survey map)

1. Determine new Maximum N/A Stay Time for the required entry

! 2. For worker 1: I I

2.a Determine remaining Accum - Accum = Remain margin to the electronic Dose Dose Dose dosimeter accumulated Alarm Alarm does alarm setpoint by subtracting accumulated 1200 mr - 900 mr = 300 mr dose of 900 mr from accumulated dose alarm of 1200 mr to get remaining dose until alarm I

2.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 1300mr 1400 mr/hr = .75 hrs I Time (Worst Case) I

3. For worker 2: !

3.a Determine remaining Accum - Accum = Remain margin to the electronic Dose Dose Dose dosimeter accumulated Alarm Alarm does alarm setpoint Subtract accumulated 1200 mr- 800 mr = 400 mr dose of 800 mr from accumulated dose alarm of 1200 mr to get remaining dose until I

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

-1i NLSR02701 Rev001 ELEMENT STANDARD <t UJ s:: ....

G.\ G.\

E.Q EE UJ Z o :::J

J 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 400mr I 400 mr/hr ::;: 1.0 hrs Time (Worst Case) I

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 60 minutes 45 min + 60 min::;: 105 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 I

You have met the termination criteria for this JPM I

,-'PM Stop Time: _ _ _ __

SRRS: 3D.1 05 (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 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 mrem/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 mremlhr Worker 1 has 900 mrem accumulated dose on his Electronic Dosimeter from his first entry Worker 2 has 800 mrem accumulated dose on his Electronic Dosimeter from his first entry 1.5 total man-hrs are required to finish the work Work is to be performed on the Refuel Floor inside a quarantined area.

INITIATING CUES:

You are directed 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 TOTAL man-hrs SRRS: 30.105 (when utilized for operator initial or continuing training)

Attachment 1 - ARW Survey Form Page 1 of 1 RWP No. 10-55 Date: MM/DDIYY Time: #### Survey No.: 10-33 LOCATION: UNIT # 1 BLDG.: RX ELEV.: 352 AREA I LOCATION: RX 1 FUEL FLOOR (Le. room name/number)

WORK DESCRIPTION: Monorail Auxilia!y Hoist ReQair (Task being performed, work order #, etc.)

SURVEYED BY: R Smith I RS ARW SUPERVISOR: J Jones NOTIFIED: K. Anderson (Print name) I (Inits) (Supv of ARW performing survey) (RP Tech)

SERIAL CAL. DUE VALID SERIAL CAL. DUE VALID INSTRUMENT NO INSTRUMENT NO. YES NO NO. YES R02A ##-#### X RM-14 ##-#### X BETA GAMMA DISTANCE CONTAMINATION Ri ITEM I LOCATION (Circle one) ITEM I LOCATION dPm'l00cm~

mrad/hr mRlhr SMEAR#

A Work Area N/A 400 <1K 1 Laydown Area 0 ~ 30cm / GA I Low Dose Area N/A 50 - 2 Grapple <10K Cont. I 30cm / GA A

T 3 Laydown Area <2K NES Grapple Laydown Area I

0 4 N I 5

C)

I 6

~I Y/ct400 Grapple i r-Y/ 30 em 400 *1 7 i 8 I 9 10 I

0 11 12 Step-Off Pad 13 14 15

1. x-x-x = Radiological Boundary 20 SMEAR 3. <#/ # ~/yCONTACT 4. <#/ #: ~/y CONTACT All dose rates in mRlhr unless otherwise noted. #/ # ~/y @ 30 cm REMARKS: Surve:\l to sueeort Auxiliar'l Hoist Reeair REVIEWED BY: SWard DATE: MM/OOfYY y

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

Limerick Generating Station Job Performance Measure Fuel Movement in the Spent Fuel Pool, Hoist Jam Light Illuminates (LSRO performs as RPO)

(Alternate Path)

JPM Number: 2035 Revision Number: 002 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)

NLSROJPM2035 REV002.DOC JOB PERFORMANCE MEASlIRE 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. _ _

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 14

NLSROJPM2035 REV002.DOC 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.ooc

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: 30.105 (when utilized for operator initial or continuing training) Page 4 of 14

NLSROJPM2035 REV002.DOC 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 5 of 14

NLSROJPM2035 REV002.Doc Operator's Name: =-_ _ _ _ _ _ _ _ _Job

Title:

0 SED OSM OSRO ORO OSTAIIA 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: [2J Yes o No SRO Only:

[2J

[2J Yes o No Time Critical: DYes 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 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: 30.105 (when utilized for operator initial or continuing training) Page 6 of 14

NLSROJPM2035 REV002.DOC JPM Start Time: _ __

~TEP ELEMENT STANDARD I

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Provide candidate with a copy of S97.0.M

1. Obtain current revision of Current revision of S97.0.M 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.

I Instructor Note: If trainee asks about bridge movement in Semi-Auto vs. Manual, the initiating cue requires manual bridge operation.

2.

Pickup Location - Fuel Pool N/A I N/A

~.

Storage Rack or Cask Pit i N/A -

3. Spotter to RPO: "next location is _ -_ _ _"

RPO to Spotter: "understand, _ -_ _ _"

.§~otter 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 I 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 -

I L SRRS: 3D.1 05 (when utilized for operator initial or continuing training) Page 7 of 14

NLSROJPM2035 REV002.DOC STEP ELEMENT STANDARD I

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6. IF HMI screen is functional, THEN RPO, VERIFY the "Current Location" displayed on RPO, VERIFY the "Current HMI screen matches intended Location" displayed on HMI rack location.

screen matches intended rack location.

(CUE IF simulated: "Current Location" displayed matches intended rack location.) - - -

7. LOWER grapple until grapple is near bail.

Grapple lowered near bail.

(CUE IF simulated: Grapple has been lowered and is near the bail (180">> -

8. ENSURE grapple is open. Grapple open.

(CUE IF simulated: Grapple is Verify indicating light is NOT lit open)

Camera indicates grapple is I open. - - -

SRRS: 3D.1 05 (when utilized for operator initial or continuing training) Page 8 of 14

NLSROJPM2035 REV002.DOC

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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 NIA 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. N/A N/A I

SRRS: 3D.105 (when utilized for operator initial or continuing training) Page 9 of 14

NLSROJPM2035 REV002.DOC

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10. ROT ATE 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) - -

I -

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.DOC

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15. 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 N/A Pool Storage Rack

Grapple appears seated on bail handle using underwater camera for component seated in cask THEN DIRECT RPO to engage N/A . N/A I i grapple. -

16. , RPO, VERIFY the following

! N/A N/A N/A -

17.

SLACK CABLE Light is lit. Verifies SLACK CABLE light is lit.

(CUE IF simulated: Slack Cable Light is lit.) - - -

18.

Grapple is centered over bail Verifies SLACK CABLE light is handle. lit.

(CUE IF simulated: Grapple is I centered over bail handle.) - - -

19.

Hoist Position indication agrees Verifies hoist position is with Attachment 2 for item between 198" and 196".

seated in Fuel Pool Storage Rack. (Depending on calibration, Unit 1 is about 196"-197" and Unit 2

. (CUE IF simulated: Hoist is about 198")

I I Position indicates 197~ ,

1 SRRS: 30.105 (when utilized for operator initial or continuing training) Page 11 of 14

NLSROJPM2035 REV002.DOC STEP ELEMENT STANDARD I

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Grapple appears seated on ball N/A handle using underwater camera for component seated in cask. N/A N/A -

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). -

--24.

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

25.

Slowly RAISE load while ensuring FUEL LOADED Light is lit (fuel/dummy bundle only).

L (CUE IF simulated: If asked; I Fuel Loaded light is lit.)

ALTERNATE PATH STARTS HERE

/---!

SRRS: 3D.1 05 (when utilized for operator initial or continuing training) Page 12 of 14

NLSROJPM2035 REV002.DOC STEP ELEMENT STANDARD l-e:(

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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. I I

27. IF during hoist operation RPO immediately stops attempting to raise the bundle

a HOIST JAM light comes on, THEN movement shall be AND stopped immediately AND RPO immediately stops lowered until HOIST JAM attempting to raise the bundle Light goes out, THEN the Fuel Handling Director shall AND be stopped immediately RPO lowers the hoist until Hoist AND lowered until HOIST Jam light goes out, JAM Light goes out, THEN the Fuel Handling Director AND shall be contacted for The FHD is notified instruction.

Cue: After the candidate lowers the hoist, provide the following cue: liThe hoist Jam light is out."

1 (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 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.1 05 (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 Representative Date Approved By:

Training Department Date SRRS: 3D.1 05 (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 JPM using steps 9 and 12 below.

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

2. Knowledge and Abilities (K/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 / Instructor Date SME / Instructor Date SME / 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. Periorm 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 Periormance 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 periormance 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 periormance 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 periorm S97.0.M step 4.8.

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

Page 3 of 24

NLSR02083Revision 000 TASK 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.

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 ST ANDARD(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 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.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 [gJ 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: [gJ Yes D No SRO Only: [gJ Yes D No Time Critical: DYes [gJ No Reference(s):

Procedure _S;: : .9.: :,.7:. . ..:.:::,0.:.:..K:...-_ _ _ __ Rev: 14 Procedure _S==..97:...:.. =,0.:. :. ;.M=-=--_ _ _ __ Rev: 28 Actual Testing Environment: D Simulator D Control Room [gJ In-Plant D Other Testing Method: D Simulate [gJ Perform Estimated Time to Complete: 40 minutes Actual Time Used: minutes EVALUATION

SUMMARY

Were all the Critical Elements performed satisfactorily? D Yes 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

I\ILSR02083Revision 000 JPM Start Time: _.~_ _

Critical Element(s) indicated by "*,, in Performance Checklist.

-t:: ~ I, I- ~ G) G) ee Jle STEP ELEMENT STANDARD <C (/)

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)

OZ Provide candidate with a copy of S97.0.M

1. I Obtain current revision of Current revision of S97.0.M I 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 I I\J/A !

2.

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

3. Spotter to RPO: "next location is _ -_ _ _" I

, RPO to Spotter: "understand, _ -_ _ _"

I

S~otter 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 (CUE IF simulated: Refuel Component Move Sheet OR as I Platform is positioned over the directed by the evaluator.

dummy fuel bundle) - - -

I I

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 -

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

Page 7 of 24

NLSR02083Revision 000 I

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

Location" displayed matches intended rack location.) - - -

7. LOWER grapple until grapple is near bail.

(CUE IF simulated: Grapple Grapple lowered near bail.

i has been lowered and is near the bail (180">> - -

i

8. ENSURE grapple is open. Grapple open.

(CUE IF simulated: Grapple is Verify indicating Ught is NOT lit open)

Camera indicates grapple is open. - - -

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

Page 8 of 24

NLSR02083Revision 000 I

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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 I\J/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 SBG I with spacer buttons.

i CUE IF asked: There is no interference for this bundle. N/A N/A

10. ROTATE grapple as necessary to achieve grapple to bail alignment. Grapple rotated and aligned with bail.

. (CUE IF simulated: Grapple is i rotated and aligned with bail)

._M_

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

Page 9 of 24

NLSR02083Revision 000 STEP ELEMENT STANDARD l-e(

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11.

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

i CABLE Light is lit) -,

12.

FHD & Spotter, PERFORM Concurrent Verification of proper core component location AND orientation.

I\I/A (CUE IF simulated: Dummy bundle location and orientation concurrently verified by FHD & i i Spotter) N/A N/A -

I i

13. Spotter to FHD: "Location is -- "

FHD to Spotter: "agree, _ -_ _ _"

I Spotter to FHD: "correct" N/A N/A -

14. NOTE: The verifications in the following two steps may be N/A i

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: 30.105 (when utilized for operator initial or continuing training)

Page 10 of 24

NLSR02083Revision 000 STEP ELEMENT STANDARD

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15. 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 N/A Pool Storage Rack

Grapple appears seated on bail handle using underwater camera for component seated in cask i

THEN DIRECT RPO to i engage grapple. N/A N/A -

16. RPO, VERIFY the following I N/A N/A I N/A -

17.

SLACK CABLE Light is lit. Verifies SLACK CABLE light is lit.

, (CUE IF simulated: Slack Cable I Light is lit.) -

18.

Grapple is centered over bail Verifies SLACK CABLE light is handle. lit.

(CUE IF simulated: Grapple is centered over bail handle.) - - - i 19.

Hoist Position indication agrees Verifies hoist position is with Attachment 2 for item between 198" and 196".

seated in Fuel Pool Storage (Depending on calibration, Unit Rack.

1 is about 196"-197" and Unit 2 (CUE IF simulated: Hoist is about 198") i Position indicates 197") - -

20.

i Grapple appears seated on bail N/A I handle using underwater camera for component seated I

' in cask.

I I N/A I N/A -

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

Page 11 of 24

NLSR02083Revision 000 l l e: ...

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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"

25.

RPO to FHD: "correct" Slowly RAISE load while Slowly raise load

- -1 ensuring FUEL LOADED Light is lit (fuel/dummy bundle only).

(CUE IF simulated: If asked; Fuel Loaded light is lit.) - - -

I ALTERNATE PATH STARTS HERE NOTE: As part of the next step the candidate will assume the role of the FHD.

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

Page 12 of 24

NLSR02083Revision 000 STEP ELEMENT i

STANDARD I

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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 Per S97.0.M step 3.12.6, of the FHD. Student will reference S97.0.K

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 FAULT LOCKOUT.

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

I I -1 Note: The following steps are per S97.0.K 27.

I Obtain current revision of S97.0.K Cue: Once the trainee Current revision of S97.0.K demonstrates the ability to obtained.

locate the current revision of the i

procedure, provide him/her a copy. I 28.

Correct revision of procedure being used.

IN/A I

N/A ' N/A 1-

29. i i Procedure printed on white i I I paper. I N/A I N/A

N/A -I SRRS: 3D.1 05 (when utilized for operator initial or continuing training)

Page 13 of 24

NLSR02083Revision 000 I~

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30.

I I

Briefing performed as required.

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

31. To avoid extensive physical damage, slow OR Jog speed only shall be used in N/A !

I approaching any wall OR I i i

obstruction.

N/A N/A -

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 !

i N/A ' N/A -

I 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:

~2RESPONSETOSYSTEM FAULTS AND ALARMS. N/A 4.3 PLC OVERRIDE 4.5 BYPASSING A FAULTED ENCODER 4.6 RESETTING A DISABLED i

ENCODER i

4.7 CALIBRATING I ENCODER(S) 1N/A N/A i 1

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

Page 14 of 24

NLSR02083Revision 000

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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 N/A alarm condition occurs, the "System Fault Detected" red button will appear. Touching the "System Fault Detected" button displays the "SYSTEM N/A N/A -

FAULTS" screen.

37. NOTE:

2. Touching the "FAULT" OR "ALARM" button activated on N/A "SYSTEM FAULTS" screen displays popup screen !

i N/A

N/A i explaining the condition. !

38. Caution:

Troubleshooting system faults should not preclude taking N/A action to place the machine

. AND/OR associated load in a

N/A I\I/A i safe condition. ! !

39. To respond to a system fault/alarm condition, I\I/A I PERFORM the following: - - !

40.

VERIFY "System Fault Detected" button is illuminated Verifies "System Fault on Operator Touch Screen. Detected" button is illuminated on Operator Touch Screen.

(Cue: System Fault detected I button is illuminated} -

-I SRRS: 30.105 (when utilized for operator initial or continuing training)

Page 15 of 24

NLSR02083Revision 000

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41. NOTE:

Buttons on the SYSTEM FAULTS screen are designated as follows:

Normal condition: Green backlight. N/A Fault condition: Red backlight Alarm condition: Yellow backlight ~ N/A I N/A -!

42.

TOUCH "System Fault Detected" AND VERIFY "SYSTEM FAULT" screen appears with individual System Touches "System Fault faulValarm condition( s). Detected" and Verifies the fault is displayed.

(Cue:"System Fault" screen appears. (Show Applicant i

ATTACHMENT A>>) - -

i

43.

TOUCH the activated "FAULT/ALARM" button(s) AND VERIFY pop-up screen is Touches button for activated displayed explaining the fault and Verifies the condition. explanation of the fault (Cue: "System Fault indicates condition.

HOIST TUBE HANGUP (Show Applicant AlTACHMENT B>>) - -

44.

REFER to Appendices for REFER to APPENDIX 1 possible causes AND effects on LIMERICK REFUEL equipment AND potential follow PLATFORM FAULT i up actions for responding to the I

I faulValarm condition. RESPONSE TABLE I

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

Page 16 of 24

NLSR02083Revision 000 STEP ELEMENT STANDARD I I-

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45.

Review initiating conditions:

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

46.

I Review effect on equipment Hoist motion inhibited -

47.

1 Review POTENTIAL FOLLOW

. N/A 48.

UP ACTIONS 1 . IF picking up test weight IN/A I N/A - :.

I THEN RESET Fault per section N/A

N/A I N/A I

I 4.2 of this procedure.

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

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

~ I hoses have the proper

.~_ configuration and tension.) i- I I

NOTE. As part of the next step the candidate will resume the ro e of the RPO.

50. 3. CONFIRM that load indication is normal.

(Cue if simulated: Load gauge reads normal) Reads Load Gauge and identifies it is reading normal (Cue: For the purpose of this JPM, you are now performing

~__ ~role of the RPO).

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

Page 17 of 24

NLSR02083Revision 000 STEP ELEMENT STANDARD l-e:(

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

Attempt to clear fault by moving hoist using Travel Override.

Cue: The hoist raises and the hoist tube hangup fault has I cleared - - - I NOTE: The following steps are from S97.0.M 1

52.

Slowly RAISE load while ensuring FUEL LOADED Light is lit (fuel/dummy bundle only). Raises load slowly to normal-up I

(CUE IF simulated: Raised to Normal-Up} - - -

53.

NOTE:

1. IF operating in Automatic AND Quick Auto is enabled, THEN:

- 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 I INCREMENT AND require resetting. I N/A I N/A i-I SRRS: 3D.1 05 (when utilized for operator initial or continuing training)

Page 18 of 24

NLSR02083Revision 000

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STEP 54.

ELEMENT IF operating in Full Auto AND STANDARD l I

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use of QUICK AUTO is desired, N/A THEN PERFORM the following: N/A N/A -

55. . N/A N/A . N/A .

TOUCH "QUICK AUTO" 56.

TOUCH "AUTO RUN" I NJA N/A N/A -

57.

WHEN prompted, THEN N/A RELEASE joystick N/A . N/A i

58.

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) - - -

59.

GO TO appropriate "Release Location" section of this Trainee goes to Section 4.12 I procedure as directed by FHD. - I 60.

4.12 RELEASE LOCATION FUEL POOL STORAGE RACK N/A OR CASK PIT N/A N/A - I 61.

NOTE:

IF 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 i Shielded Canister (DSC) ilocation. N/A I N/A i -'----

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

Page 19 of 24

NLSR02083Revision 000

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62.

Spotter to FHD: "location is _ - - -"

FHD to Spotter: "agree, _ -_ _ _"

.I Spotter to FHD: "correct" - - -

63.

POSITION core component over desired location in accordance with Core Refuel Platform positioned over Component Move Sheet. location deSignated on the Core Component Move Sheet or as (Cue IF simulated: Refuel directed by the evaluator.

Platform is positioned over the release location) - - -

64.

NOTE:

The following step may be N/A performed anytime prior to !

component insertion in step 4.12.5. N/A I N/A I-I 65.

IF HMI screen is functional, THEN RPO, VERIFY the "Current Location" displayed on HMI screen matches intended Verifies the current location rack location. (ref. 5.32). matches the move sheet or instructions from evaluator.

(Cue IF simulated: Current location displayed matches the i intended rack location)

- 1 66.

Caution:

Grapple switch guard located on LH Controller side of grapple head interferes with adjacent seated DBG bail handle when N/A handled component's bail handle is perpendicular to DBG handle.

I (Cue IFsimulated: There is no I

interference. )

I N/A N/A -

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

Page 20 of 24

NLSR02083Revision 000 l- s:: '

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Caution:

Grapple guard can also interfere with Spent Fuel Pool N/A rack label pipe couplings.

(Cue IF simulated: There is no N/A N/A -

interference. )

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.) 1 - -

71.

NOTE:

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

-/

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

Page 21 of 24

NLSR02083Revision 000

.-------r-------.-------.----------~---.,._-~__._-__r--,

ELEMENT STANDARD

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FHD & Spotter, PERFORM Concurrent Verification of proper core component location AND orientation. N/A (Cue IF simulated: 4.12.4 is i complete, 10we~r~th:.:.ce~ho~i~st'1...._)_ _ . J ._ _ _ _ _ _ _ _ _ _ _ _+_-N-/A_+-N-/A_+------1 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 (Cue IF simulated: Slack Cable lit.

light is lit.) - I 75.

NOTE:

The verifications in the following NIA two steps may be performed in parallel. N/A N/A 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 with Attachment 2 for item N/A seated in Fuel Storage Rack, OR ISFSI cask.

THEN DIRECT RPO to release and raise grapple.

(Cue IF simulated: FHD directs I' N/A N/A i you to rais_e_.g",,--ra-Lip--,--ple_,)L-----I-----------------rl---I--~f_----_l I 77, l!PO, VERI FY_t_he_f_o_lIo_w_in~g_,__...l..-N_I_A_ __--_ _ _ _ _ .___._-L.I_N/_A----J:'--N_I_A---L-----l SRRS: 3D.1 05 (when utilized for operator initial or continuing training)

Page 22 of 24

NLSR02083Revision 000

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SLACK CABLE Light is lit (Cue IF simulated: Slack cable Verifies slack cable light lit.

light is lit.) - - -

79.

Component elevation appears equivalent to other stored components in the rack.

Verifies elevation is equivalent (Cue IF simulated: Component to other 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".) - - --I 81.

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

82.

THEN WHEN directed by FHD, RELEASE grapple.

Receives communication from FHD to release grapple.

(Cue IF simulated: FHD directs you to release grapple.) 1 I

83.

VERIFY grapple is "OPEN".

(Cue IF simulated: Grapple is Verifies grapple open.

open.) 1

- : - 1 84.

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

raising.) - -

I -I SRRS: 30.105 (when utilized for operator initial or continuing training)

Page 23 of 24

NLSR02083Revision 000

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85. RPO to FHD: "clear" FHD to RPO: "agree clear" RPO to FHD: "correct" - - -

86. FHD & RPO, PERFORM Peer Check that grapple is clear of component. Performs peer check with FHD that grapp Ie is clear.

(Cue IF simulated: I agree, grapple is clear.) - - - ..

You have met the termination criteria for this JPM CUE: I'd like you to raise the 9 rapple to Normal-up JPM Stop Time:

SRRS: 3D.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-1 06, 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: 30.105 (when utilized for operator initial or continuing training)

NLSR02083Revision 000 Attachment A SRRS: 3D.1 05 (when utilized for operator initial or continuing training)

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

Limerick Generating Station Job Performance Measure Install Rod Position 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: 3D.1 05 (when utilized for operator initial or continuing training)

NLSROJPM2029 REV005.DOC 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 J PM.

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 7

NLSROJPM2029 REV005.DOC REVISION RECORD (

SUMMARY

)

Rev 005, Updated based on procedure revision, new format no rev marks used 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 _ _ _ _to 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.DOC Operator's Name: _ _ _ _ _ _ _ _ _ _Job

Title:

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

Title:

Install Rod Position Test Box (LGS)

JPM Number: NLSROJPM2029 Revision Number: 005 Task Number and

Title:

234000-SL, Refuel Platform Surveillance Testing KIA Number and Importance: 214000 A4.01 3.2/3.3 Suggested Testing Environment: In-Plant Alternate Path: OYes ~No SRO Only: ~Yes ONo Time Critical: DYes ~l'Jo

References:

1. ST-6-097-630-*, Core Alteration Testing for Offloading, Shuffling and Reloading the Core Actual Testing Environment: D Simulator 0 Control Room 0 In-Plant D 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? 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: Oate _ __

SRRS: 3D.1 05 (when utilized for operator initial or continuing training) Page 4 of 7

NLSROJPM2029 REV005.DOC JPM Start Time: _ __

ELEMENT STANDARD SAT UNSAT Comment Number Evaluator notes:

Prior to each candidate starting JPM place single rod test box switch to position "02"

If candidate asks for a peer check, cue them that for the purposes of this JPM no peer check will be provided.

The Candidate can be directed to go to the Refuel floor to obtain a Single Rod Test Box.

If the box is stationed in the AER, the examiner can ask where the candidate would get the box, and provide it when appropriate.

N/A

1. Perform the following to N/A install test box in Auxiliary Equipment Room

2. REQUEST Reactor LSRO requests the Unit RO select rod Operator to select rod 38-59.

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.

SRRS: 30.105 (when utilized for operator initial or continuing training) Page 5 of 7

NLSROJPM2029 REV005.DOC ELEMENT STANDARD ISAT UNSAT comment' Number *I

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.

ROD SWITCH POSITION 38-59 00

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 ~O in the UP position.

8. Cable end 1,0 (Rod 34 N/A N/A

59) switch ~O in the UP

~osition.

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. I SRRS: 30.105 (when utilized for operator initial or continuing training) Page 6 of 7

NLSROJPM2029 REV005.DOC ELEMENT STANDARD SAT UNSAT Comment Number

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:

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 11 c. Overcore, Box Pc LEDs Overcore, Box Pc LEDs verified not are not Lit lit

. CUE: Overcore, Box Pc LEDs I 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. 8T-6-097-630-_ is in progress and has been completed through step _ _ __

INITIATING CUES:

You have been directed to directed you to perform 8T-6-097-630-_ step _ _ to install the Rod Position Test Box on Unit _ __

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

Exelon Nuclear Job Performance Measure LSRO Only - GP-13, CONTROL ROD DRIVE AND MAINTENANCE COORDINATION I ALTERNATE PATH - TWO CELL SEPARATION NOT ENSURED JPM Number: NLSR02087 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)

NLSR02087 RevOOO JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be petiormed 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. Petiormance 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 petiormance time is accurate

11. If the JPM cannot be petiormed 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.1 05 (when utilized for operator initial or continuing training) Page 2 of 5

NLSR02087 RevOOO REVISION RECORD (Summary)

1. Revision 00 N/A 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 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.

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.1 05 (when utilized for operator initial or continuing training) Page 3 of 5

NLSR02087 RevOOO JPM

SUMMARY

Operator's Name: Job

Title:

D SED SM DSRO D STAfIA [gI OTHER JPM

Title:

GP-13, CONTROL ROD DRIVE AND MAINTENANCE COORDINATION / ALTERNATE PATH -1WO CELL SEPARATION NOT ENSURED JPM Number: NLSR00287 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 [giNo SRO Only: [8JYes DNo Time Critical: DYes [8JNo Reference(s):

Procedure GP-13 Rev: 26

--=:.~-

-=~=-----------

Procedure __________ Rev:

Actual Testing Environment: D Simulator D Control Room Din-Plant [8J Other Testing Method: D Simulate [8J Perform Estimated Time to Complete: 20 minutes Actual Time Used: minutes EVALUATION

SUMMARY

Were all the Critical Elements performed satisfactorily? DYes DNo 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.105 (when utilized for operator initial or continuing training) Page 4 of 5

I'JLSR02087 RevOOO JPM Start Time: _ _ __

Critical Element s indicated b "*,, in Performance Checklist

f STEP. ELEMENT STANDARD ~

t/)

~

t/)

z 111 G)G)

E.D E

o o

E

J

Z i CUE: OUTAGE SERVICES 1.

Requests permission to remove I N/A NtA . I'JtA Control Rod Blade 22-27

2. 3.2.3 VERIFY that no CRD work is performed on the selected Review Attachment 3 to identify location AND that two cell CRB and CRD location separation exits between the CRD work location AND Determine Control Rod Blade surrounding work locations prior 22-27 cannot be removed and to CRB removal. inform Outages Services

3. CUE: This is OUTAGE ::t SERVICES I ~n~erstand we do NtA not have permission to remove i i

i Control Rod Blade 22-27 NtA NtA I

4. CUE: OUTAGE SERVICES Requests identification of all Control Rod Blades that can be NtA scheduled for replacement

. while Control Rod Drive 26-35 is removed NtA i NtA -

5. 3.2.3 VERIFY that no CRD work is performed on the selected Determine Control Rod Blade location AND that two cell 38-43 and 54-31 can be separation exits between the removed and inform Outages

CRD work location AND Services

~rrOUnding work locations prior i

~

to CRB removal.

i I L

~-------- 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 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 CCTAS.

The GP-13 Coordinator has requested you review the above request, and determine permissible actions.

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

Exelon Nuclear Job Performance Measure LSRO Only - Limerick, Movement of fuel from the fuel prep machine (Alternate Path, New Fuel Drops)

"IPM Number: NLSR02080 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)

NLSR020BORevision 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 identified.

2. Knowledge and Abilities (K/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 (*).

B. 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 ..IPM is initially validated, sign and date ..IPM cover page. Subsequent validations, sign and date below:

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

Page 2 of 12

NLSR02080Revision 000 REVISION RECORD (Summary)

1. Revision 00 NI A SIMULATOR SETUP INSTRUCTIONS

1. NI A 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 GGTAS 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 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.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 STAliA !:8J OTHER JPM

Title:

Movement of fuel from the fuel prep machine (Alternate Path, New Fuel Drops)

JPM Number: NLSR00280 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: !:8JYes 0 No SRO Only: !:8JYes ONo Time Critical: OYes !:8J No Reference( s):

Procedure _O.:..:...:N:......-1.:..:2::.::0~_ _ _ __ Rev: --:.-=---

19 Procedure _S::.9:<...7~...=.0=.:.;.M'_'___ _ _ __ Rev: --==---

28 Actual Testing Environment: 0 Simulator 0 Control Room !:8J 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: 3D.1 05 (when utilized for operator initial or continuing training)

Page 4 of 12

NLSR02080Revision 000 JPM Start Time: _ _ __

Critical Element(s) indicated by "*" in PerformanceChecklist.

STEP ELEMENT STANDARD l-e(

l-e(

tn e ...

Q) Q)

E,c E E tn Z o :::s

)

I 1 OZ i i 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 Verify fuel prep machine is fully carriage is fully LOWERED. lowered i CUE: Fuel Prep Machine (Note: Normally performed by !

Carriage is fully lowered NMD, not the LSRO) 1 - I

2. CAUTION:

Use extreme care to avoid entanglement of main mast or grappled fuel bundle with fuel N/A inspection and test equipment 1 located in the vicinity of the fuel

prep machines.

I- - -

i

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

1 CUE: The bridge is positioned i

over the fuel prep machine. .-

i i

4. LOWER grapple until grapple is near bail.

CUE: RPO directed to Lower RPO directed to Lower grapple the grapple until the grapple in until the grapple is near bail near the bail handle. The handle

grapple is lowered, and the

-1 I

encoder reads 157 inches SRRS: 3D.1 05 (when utilized for operator initial or continuing training)

Page 5 of 12

NLSR02080Revision 000 STEP ELEMENT STANDARD I I et en I

iTf et en z

~

(J)(J)

E~

. E:::J Oz

(.)

5. ENSURE grapple is open.

CUE: The grapple switch is in

Grapple Ensured open i RELEASE with no backlight -. I i

6. ROTATE grapple as necessary RPO directed to ROTATE to achieve grapple to bail grapple as necessary to alignment.

achieve grapple to bail CUE: The grapple head is alignment.

I aligned to the bail handle with a north east orientation - -

7. Slowly LOWER grapple until SLACK CABLE Light is lit.

RPO directed to Slowly LOWER CUE: RPO directed to Slowly grapple until SLACK CABLE LOWER grapple until SLACK Light is lit.

CABLE Ught is lit. The grapple is lowered the SLACK CABLE Light is lit - -

8. FHD & Spotter, PERFORM Concurrent Verification of proper core component location Spotter directed to PERFORM AND orientation. Verification of proper core component location AI\JD CUE: Spotter has verified The orientation.

bundle is in the North Fuel Prep Machine, and the bundle is oriented north east. Concurrent I

Verification is satisfied for this step of the JPM - -

I I

9. N/A . N/A FHD, VERIFY the following, N/A i 9.a

SLACK CABLE Ught is lit SLACK CABLE Light is verified CUE: SLACK CABLE Light is lit lit I

9.b

Grapple is centered over bail handle Grapple is verified centered I CUE: Grapple is centered over over the bail handle the bail handle I .. -..

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

Page 6 of 12

NLSR02080Revision 000 STEP ELEMENT STANDARD t

(f) t-(f)

Z

J

,~

CP CP E..Q E

Oz

~

(.)

9.c Hoist Position indication agrees with Attachment 2 for item seated in fuel prep machine. Hoist position verified i CUE: Hoist position indicates i 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 N/A machine.

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

. 167.5 inches -

! I I

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

engaged. - - -

12. FHD & RPO, PERFORM Peer Check that GRAPPLE ENGAGED Light is lit.

Grapple control switch verified CUE: RPO verifies Grapple to have green backlight lit engaged light is light, Peer Check is satisfied for this step of the JPM

~

I i_I __ -

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

Page 7 of 12

NLSR02080Revision 000

...C a G.I G.I STANDARD E..o ELEMENT EE o ::s OZ

13. Slowly RAISE load AND VERIFY FUEL LOADED Light is lit RPO directed to Slowly RAISE CUE: RPO is directed to Slowly load AND VERIFY FUEL Raises the bundle and verify LOADED Light is lit FUEL LOADED light is lit.

I 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 I following: !

17. NOTIFY Health Physics to evaluate radiological conditions.

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

I notified to evaluate radiological conditions.

I

18. NOTIFY Reactor Engineering.

I

! CUE: Reactor Engineering has Reactor Engineering notified been notified

.. ~

You have met the termination criteria for this JPM I

SRRS: 30.105 (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 FH-106 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 eeTAS SRRS: 3D.105 (when utilized for operator initial or continuing training)

TRANSFER AUTHORIZATION FOR FH-106 Page _1_ of_1 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 ##/##/## Reviewed By: TRAINING USE aNL Y 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: 3D.1 05 (when utilized for operator initial or continuing training)

TRANSFER AUTHORIZATION FOR FH-106 Page _1_ of _1 TRAINING USE ONLY #A## MV U# TRAINING USE ONLY RECORD TYPE #3B.108 Written By: TRAINING USE aNL Y Unit LIMERICK GENERATING STATION UNIT 2 Date ##/##/## Reviewed By: TRAINING USE aNL Y 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 L1 SPENT C-21 sw I--

I---- -

I - - - - >----

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

Exelon Nuclear Job Performance Measure LSRO Only - Limerick Emergency Classification (TIME CRITICAL)

JPM Number: NLSR02081 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)

NLSR020S1, Revision 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 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 (*).

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

Procedure EP-AA-100S 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 ..IPM.

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

SME / 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 6

NLSR02081, Revision 000 REVISION RECORD (Summary)

1. Revision 00 NIA 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.

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

Page 3 of 6

NLSR02081, Revision 000 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 ..IPM. 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 4 of 6

NLSR02081, Revision 000 JPM

SUMMARY

Operator's Name:,______________Job

Title:

O SED 0 SM OSRO o STAll A ~ OTHER

..IPM

Title:

SRO Only - Emergency Classification

..IPM 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 quiet area with appropriate Emergency Plan documents Alternate Path: OYes ~No SRO Only: ~Yes ONo Time Critical: ~Yes ONo Reference{s):

Procedure EP-AA-1008 Rev: 17 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: 3D.1 05 (when utilized for operator initial or continuing training)

Page 5 of 6

NLSR02081, Revision 000 JPM Start Time:

~l

....s::

I l- C1)

C1)

<C

~

JJ ELEMENT STANDARD CJ) E CJ) Z EE

> o ::J OZ

,..--- I I NOTE:

IF another SRO is requested to perform an independent Peer Check CUE: A Peer Check will not be provided for this JPM 1.

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

2.

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

- i -

3.

Determine the time the MA5 Threshold 1, was exceeded associated EAL Threshold at 0226 Value was exceeded i I i i i

You have met the termination criteria for this JPM I

JPM Stop Time: ___~~_

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

Page 6 of 6

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 SOC

"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 . .'PM 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 Threshold Value(s) was/were exceeded SRRS: 3D.105 (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 Representative Date Approved By:

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

NLSR02082Revision 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 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 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 J PM.

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 7

NLSR02082Revision 000 REVISION RECORD (Summary)

1. Revision 00 NtA SIMULATOR SETUP INSTRUCTIONS

1. NtA for In-plant TASK CONDITIONS:

Unit 1 is in OPCON 5 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 ..IPM. 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

NLSR02082Revision 000 JPM

SUMMARY

Operator's Name:,_ _ _ _ _ _ _ _ _ _ _ _Job

Title:

D SED 0 SM DSRO o STAll A IZl 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 [8JNo SRO Only: [8JYes DNo Time Critical: DYes IZlNo Reference( s):

Procedure _T..:...S=G:.....-4.:..:.:-:..1_______ Rev: 8 Procedure Rev:

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

SUMMARY

Were all the Critical Elements performed satisfactorily? DYes DNo 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.1 05 (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 STEP ELEMENT STANDARD t

<C t

<C

(/)

-I : ...

(I)

EJ:l CI)

(/) Z EE

) o: :s OZ I I LGS OPERATIONAL CONTINGENCY GUIDELINES TSG-4.1 ATTACHMENT 1 INTERNAL SPENT FUEL POOL MAKEUP STRATEGY Evaluator Note:

- Exam Key rings contain a Cat 198 Key, required to open cabinets.

- Storage cabinet on U1 North wall is behind the office hallway in a contaminated area.

- All actions will be simulated including entry into contaminated areas. I

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: 30.105 (when utilized for operator initial or continuing training)

Page 5 of 7

NLSR02082Revision 000

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

....oe( ....oe( s::: ...

CI) CI)

E.Q STEP ELEMENT STANDARD CJ)

CJ)

Z EE

I o :s OZ

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. N/A To obtain the 500 gpm makeup flow rate 2 - 3" hoses are required.

Two different hose routing options NOTE: Initial conditions direct are provided below. performance of OPTION 1 Refer to Figure 1 AND Figure 2 for "ADD Fire Water to spent fuel fire standpipe locations. pool using two (2) Fire System standpipes" 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)

N/A Fire System standpipes located I on refuel floor as follows:

- l - --

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 different fire standpipes Hoses routed from two different (Figures 1 and 2 show fire standpipes to Unit 1 fuel standpipe locations) pool

CUE: Hoses have been routed --

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

Page 6 of 7

NLSR02082Revision 000

---~--.

ELEMEN~I l- e II)

II) l-e:(

e:( E..Q

~ STANDARD UJ UJ Z EE

J o ::::s U Z 6 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 coupling from 1st selected fire Hose rem oved from standpipe standpipe valve. AND redu cing coupling removed f rom 1st standpipe CUE: Hose is removed from valve Standpipe, and coupling is removed from standpipe valve - - -

8 CONNECT 2 %" X 3" Storz adapter to fire standpipe valve AND CONNECT hose to Storz ada pter connected to fire adapter. standpipe valve and hose CUE: Storz adapter connected connected to adapter 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 i obtained the desired flow rate - - -I You have met the termmatlon criteria for this JPM JPM Stop Time: _ _ _ __

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

Page 7 of 7

TASK CONDITIONS:

Unit 1 is in OPCON 5 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.1 05 (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:_I_I_

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.DOC 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. _ _

Procedu re 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 JPM is initially validated, sign and date JPM cover page.

Subsequent validations, sign and date below:

SME I Instructor Date SME Ill1structor Date SME I Instructor Date SRRS: 3D.1 05 (when utilized for operator initial or continuing training) Page 2 of 10

NLSRO,JPM2086 REVOOO.ooc REVISION RECORD (

SUMMARY

)

Rev 000, N/A INITIAL CONDITIONS:

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 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 10

NLSROJPM2086 REVOOO.DOC 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 IR: 4.4 / 4.0 Suggested Testing Environment: In-Plant Alternate Path: OVes ~No SRO Only: ~Ves ONo Time Critical: OVes ~No

References:

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

2. Technical Specifications Actual Testing Environment: 0 Simulator 0 Control Room 0 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? 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.105 (when utilized for operator initial or continuing training) Page 4 of 10

NLSRO,JPM2086 REVOOO.DOC 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 ..IPM 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 Attachment 5 "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 Attachment 5 "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).

I SRRS: 3D.1 05 (when utilized for operator initial or continuing training) Page 5 of 10

NLSROJPM2086 REVOOO.DOC ELEMENT STANDARD SAT UNSAT Comment Number

3. NOTE: The following steps N/A N/A N/A place Refuel Outage Unit 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 N/A N/A N/A ARM's back to operate may 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.1 05 (when utilized for operator initial or continuing training) Page 6 of 10

NLSROJPM2086 REVOOO.DOC ELEMENT STANDARD SAT UNSAT Comment I Number

5. At Auxiliary Equipment Room Panel *OC605 PLACE: Mode Switch for ARM RIS30-M1-*K600, Steam Separator Area EI Mode Switch for ARM RIS30-M1 352, to the "OPERATE"

K600, Steam Separator Area EI position AND REMOVE 352, to the "OPERATE" position Blue Equipment Status Tag.

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-*K600, Steam Separator Area EI 352, Mode Switch for ARM RIS30-M1 placed "OPERATE" *K600, 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 Equipment Status Tag.

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

NLSROJPM2086 REVOOO.DOC 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 "OPERATE" position AND REMOVE Blue Equipment Status Tag.

CUE: IF 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 E1352, Mode Switch for ARM RIS33-M1 placed "OPERATE" *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 Take action to generate an IR, or broken component. 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 I I SRRS: 3D.1 05 (when utilized for operator initial or continuing training) Page 8 of 10

NLSROJPM2086 REvOOO.Doc ELEMENT STANDARD SAT UNSAT Comment Number

7. At Auxiliary Equipment Room Panel *OC605 PLACE: Mode Switch for ARM RIS 29-M1-*K600, D/W Head Laydown Area EI 352, to the "OPERATE" position AND REMOVE Blue Equipment Status Tag.

CUE: IF 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 Mode Switch for ARM RIS 29-M1-*K600, DIW Head Laydown Area EI 352, Mode Switch for ARM RIS29-M1 placed "OPERATE" *K600, Steam Separator Area EI 352, rotated to "OPERATE" CUE: Mode Switch is in "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. ARM reset pressed IF this occurs THEN the reset shall be pressed CUE: Amber HIGH light is NOT lit RO reports UNIT _

Refueling Area Hi Radiation Annuciator has cleared.

SRRS: 3D.1 05 (when utilized for operator initial or continuing training) Page 9 of 10

NLSROJPM2086 REVOOO.DOC ELEMENT STANDARD SAT UNSAT Comment I Number 7.c AND REMOVE Blue Equipment Status Tag.

Equipment Status Tag is CUE: Equipment Status Tag is removed removed

8. CUE: Refuel Floor coordinator Determine that failed ARM is a request you determine the Criticality monitor, and Technical Technical Specification Specification 3.3.7.1 is implications, if any, of the applicable.

failure of ARM RIS 33-M1

K600,. Pool Plug Laydown Determine that minimum channel Area EI352 operable requirement of 2 is met by remaining ARMS (Cue: You can stop here. You have met the termination criteria for this ...IPM.)

JPM Stop Time _ _

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

INITIAL CONDITIONS:

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.

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

EXELON NUCLEAR Nuclear Generation Group OJTITPE MATERIAL COVERSHEET TYPE: ~ JPM D QUALIFICATION MANUAL D OJT MODULE PROGRAM:* NLSRO Initial and NLSRO Requal CODE#: NLSRO-3069 COURSE: NLSRO REV#:: . 000 AUTHOR:. G. W. Zellmer TYPIST: gwz TITLE: . Bridge End Structure Panel Lineup APPROVALS: S:;.l? /0 Date

-(-/ ()

Date APPROVED FOR USE:

Date EFFECTIVE DATE: __<.::>_---0 _--,,-_ _. _....:.-0_ _

NAME: ISSUE DATE:

Last First M.1.

EMPLOYEE ID NO. COMPLETION DATE:

COMMENTS:

Training Review for Completeness: LMS CODE:

LMS ENTRY:

Sig natu re/Date NLSRO-3069 RevOOO Page 1 of 9

EXELON NUCLEAR PEACH BOrrOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE: Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR: 234000 NLSRO-3069 K/A: 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" 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 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.

NLSRO-3069 RevOOO Page 2 of9

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 the 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 / Checkout of Refueling Platform Bridge, Trolley, and Main Hoist for Operation'

3. 'Task Conditions / 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 I 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 I Unit 3) Refuel Platform Bridge 'End Structure' for operation using 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 1B.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 1B.1.C-2(3) step 4.2. The Control Room Supervisor gives you permission to operate the components identified in SO 1B.1.C-2(3) as necessary to place the Refuel Platform into alignment with step 4.2 of SO 1B.1.C-2(3).

NLSRO-3069 RevOOO Page 4 of 9

H. PERFORMANCE CHECKLIST 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)OS947A '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 liThe 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.)

NLSRO-3069 RevOOO Page 5 of 9

STEP STEP ACT STANDARD NO 3 Verify the 2(3)OS261A 'Mono Hoist S Verify the 2(3)OS261A 'Mono Hoist Disconnect Switch' is 'ON'. 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 S Operating handle of the 2(3)OS261A is the 2(3)OS261A Disconnect in the up moved from the 'Full Down - OFF' direction until handle is aligned with the position to the 'Full Up -- ON' position

'ON' position label.

(CUE: The component that you identified is in the condition that you described.)

5 Verify the CB-D 'Air Dryer Breaker' is S Verify the CB-D 'Air Dryer Breaker' toggle

'ON'. is in the 'ON' position.

(CUE: The CB-D 'Air Dryer Breaker' toggle is in the 'Full Up' position.)

6 Verify the CB-2 'GFI Outlet Breaker' is S Verify the CB-2 'GFI Outlet Breaker'

'ON'. 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 S Verify the CB-3 'GFI Outlet Breaker'

'ON', 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 S Verify the 2(3)OS261 B 'Air Compressor Disconnect Switch' is 'ON'. Disconnect Switch' is in the "ON" position.

(CUE: The 2(3)OS261B Disconnect

. Handle is in the 'Full Up' position.

NLSRO-3069 RevOOO Page 6 of 9

STEP STEP ACT STANDARD NO

9 Verify the 'Main Hoist Pneumatic Shut-Off S Verify the 'Main Hoist Pneumatic Shut-Off Valve' is OPEN. Valve' is OPEN (hand-wheel rotated in the fully counter-clockwise direction).

(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 % inch and resistance is felt; hand-wheel will not turn any further.")

10 Verify the 'Mono Hoist Pneumatic Shut- S Verify the 'Mono Hoist Pneumatic Shut-Off Valve' is OPEN. Off Valve' is OPEN (hand-wheel rotated in the fully counter-clockwise direction).

(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 % inch and resistance is felt; hand-wheel will not turn any further.")

I NLSRO-3069 RevOOO Page 7 of9

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 / 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 ..IPM 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.)

i Note to Evaluator As an Evaluator, ensure you have positive control of all exam material provided to the examinee

('Task Conditions I Prere~uisites & Initiating Cue' sheet' AND all procedures).

Under "ACT" P - must perform S - must simulate D - must discuss I. TE;RMINATING 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 I 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 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 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 perform 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 90f9

EXELON NUCLEAR Nuclear Generation Group OJT/TPE MATERIAL COVERSHEET TYPE: ~ JPM D QUALIFICATION MANUAL D OJT MODULE Limited Senior Reactor Operator .CODE ~:::.

-, ,"0 NLSRO-3068 LSRO Initial & LSRO Requalification

. G. W. Zellmer TYPist::* gwz TITLE::' , Drywell to Reactor Well Bellows Failure APPROVALS:

Date APPROVED FOR USE:

EFFECTIVE DATE: - - & - 'I 10 I 1° NAME: ISSUE DATE:

Last First M.I.

EMPLOYEE 10 NO. COMPLETION DATE:

COMMENTS:

Training Review for Completeness: LMS CODE:

LMS ENTRY:

SignaturelDate NLSR03068 RevOOO Page 1 of 16

EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE: Senior Reactor Operator I 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 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" 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 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.

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 I 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 I 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, Reactor 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 03 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 La 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 I PrereqUisites & Initiating Cue' sheet (Evaluator understands to specify the JPM 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 I Low Level.

NLSR03068 RevOOO Page 3 of 16

4. AO 10.4-2(3), Rev. 21 (20), Residual Heat 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.

8. ARC-BOP-1(2)OC222 B4 '1 (2)BT208 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. S51.8.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 are in progress (grapple change out is taking place).

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 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.

11. You (the Fuel Handling Director) and the NMD Reactor Services Foreman have radios set to the 'Operations' channel.

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 PaneI2(3)OC075.

NLSR03068 RevOOO Page 5 of 16

H. PERFORMANCE CHECKLIST STEP STEP ACT STANDARD NO Notes to Evaluator 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: "Horn noise has stopped and alarm light(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 / notifications in any order.

1 Locate the Fuel Pool System Panel P/ S 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] and state that "You hear the noise of an alarm horn.")

2 Identify alarm condition(s). S Identifies Alarm A-1 in alarm.

3 Obtain a copy of the Alarm Response P/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.)

NLSR03068 RevOOO Page 6 of 16

STEP STEP ACT STANDARD NO 4 Notify the Unit Reactor Operator that 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.

Note to evaluator - The*communications (Cue: Evaluator acknowledges the may be made using the radio or examinee's report.) telephone.

Notes to Evaluator A) At any time during this JPM, 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 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.") 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 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.") Note-This is the same cue as found in step 18.

5 Notify the LSRO (and/or NMD Reactor S Inform the LSRO (and/or NMD Reactor Services Foreman) of the "Seal Rupture Services Foreman) of the "Seal Rupture Drain High Flow" alarm. Drain High Flow" alarm.

(Cue: Evaluator acknowledges the examinee's report.)

(Cue: If the candidate asks for /checks Fuel Pool/ Reactor Cavity water level, then state that --"Fuel Pool water /

Reactor Cavity level is now at 232' 8".")

6 Notify the Reactor Operator that Fuel S Report any reduction in Reactor Cavity Pool/ Reactor Cavity water level is 232' water level to the Unit RO.

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.)

Immediately following report (or when candidate enters FH-74), 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 7 Identify alarm condition(s). P/D Identifies Alarm B-3 in alarm.

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 single 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

STEP STEP ACT STANDARD NO

11 Notify the Control Room that the currently S If level is low and RHR SDC - Fuel Pool operating RHR Pump ('A') must be to Reactor mode is in operation in immediately shutdown. accordance with AO 10.4-2(3), then immediately shutdown the running RHR (Cue: Evaluator acknowledges the Pump.

examinee's report and informs the examinee that the running RHR pump is being shutdown.)

Immediatelll following re~ortl then -

(Cue: Provide the examinee with the 2[3]OC075 Panel Conditions sheet #3

[Attachment #3].)

(Cue: If the candidate asks for Ichecks Fuel Pool I Reactor Cavity water level, then state that --"Fuel Pool water I Reactor Cavity level is now at 232' 4".")

12 Identify alarm condition(s). P/D Identifies Alarm B-1 in alarm.

13 Obtain a copy of the Alarm Response P/D Obtain a copy of ARC-2(3)OC075 B-1 Card ARC-2(3)OC075 B-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 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. S Visually check Fuel Pool level to determine if the alarm is due to high (Cue: If the candidate asks for Ichecks water level or low water level.

Fuel Pool I Reactor Cavity water level, then state that --"Fuel Pool water I Reactor Cavity level is now at 231' 10".")

NLSR03068 RevOOO Page 9 of 16

STEP STEP ACT STANDARD NO 15 Notify the Unit Reactor Operator that the S Notify the Unit Reactor Operator that the alarm "Fuel Storage Pool Low Level" is in alarm "Fuel Storage Pool Low Level" is in on the 2(3)OC075 Panel and that the Fuel and report current Spent Fuel Pool water Pool water level is at the 231' 10" mark level.

and going down.

(Cue: Evaluator acknowledges the examinee's report.)

16 Recommends entering the FH-74 S Recommend that FH-74 "Actions in "Actions in Response to an Unexpected Response to an Unexpected Loss of Fuel Loss of Fuel Pool, Reactor Cavity, or Pool, Reactor Cavity, or Equipment Equipment Storage Pool Water Inventory" Storage Pool Water Inventory" be procedure. implemented.

(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.")

I 17 Obtain a copy of the FH-74 procedure D Obtain a copy of the FH-74 procedure I from the EDMS system or other (CUE: When the examinee states that he controlled location.

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 S Notify Shift Management to enter ON-124 124 "Fuel Floor and Fuel Handling "Fuel Floor And Fuel Handling Problems".

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.") I!

NLSR03068 RevOOO Page 10 of 16

STEP STEP ACT STANDARD NO 19 Obtain a copy of the ON-124 procedure D Obtain a copy of the ON-124 procedure from the EDMS system or other (CUE: When the examinee states that he

controlled location.

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.)

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.

8) 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).

i NLSR03068 RevOOO Page 11 of 16

STEP STEP ACT STANDARD NO 22 Follow-up Question (Evaluator to ask the o Answer: The Limerick procedures examinee): "If you had similar conditions directions are similar. The Limerick ARC at Limerick unit 1 - Refueling Operations BOP-10C222 03 will direct the operator in progress and an ARC-BOP-10C222 03 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! FH-74 procedures at copy of the Limerick Procedure ARC PBAPS [not required for correct answer].)

BOP-10C222 03 '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 03 to the LSRO examinee.) words that are shown above.

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

B) The stop time for the JPM 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' sheet', ALL Attachments, AND procedures).

Under "ACT" P - must perform S - must simulate o - 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 JPM.

NLSR03068 RevOOO Page 12 of 16

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 are in progress (grapple change out is taking place).

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 lA' 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.

11. You (the Fuel Handling Director) and the NMD Reactor Services Foreman have radios set to the 'Operations' channel.

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.

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Attachment #1 - Panel 2(3)OC075 Panel Initial Indications (#1)

Flashin A B c SEAL RUPTURe: FUEL STORAGE FUEL 1 DRAIN POOL STORAGE POOL HIGH FLOW HIGH/LOW LEVEL HI RADIATION BELLOWS LEAK SKIMMER 2 HIGH FLOW SURGE TANK HIGH LEVEL SKIMMER GATE DRAIN SURGE TANK HIGH FLOW LOW LEVEL 3

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

LI-2(3)695 250 200 G G

'N FUEL POOL PUMP 150 100 G 0

'B' FUEL POOL PUMP 50 0

G G

'C' FUEL POOL PUMP SKIMMER SURGE TANK LEVEL G8 G0 ACK RESET TEST STOP AUTO 0

HIGH PRESSURE START CLOSE

\)

OPEN AO-2(3)698 000 DECON PUMP FUEL POOL MAKEUP NLSR03068 RevOOO Page 14 of 16

Attachment #2 - Panel 2(3)OG075 Panel Indications (#2)

A B c I

SEAL RUPTuRE FUEL STORAGE FUEL

DRAIN .... POOL STORAGE POOL 1

HIGH FlOW: HIGH/LOW LEVEL HI RADIATION I

i BELLOWS LEAK SKIMMER 2 HIGH FLOW SURGE TANK I FL HF:F, HIGH LEVEL

.~K.tylMEFf GATE DRAIN SURGI;TANK HIGH FLOW LOW:tEV!t:

3 i '\.

Flashmg LI-2(3}695

_ _ _250

_ _ _ 200

'A' FUEL POOL PUMP

_ _ _150

_ _ _100

'B' FUEL POOL PUMP

_ _ _50

'G' FUEL POOL PUMP SKIMMER SURGE TANK LEVEL G8 GG AGK RESET TEST STOP AUTO 0 START HIGH PRESSURE CLOSE

\)

OPEN AO-2(3)698 000 DEGON PUMP FUEL POOL MAKEUP NLSR03068 RevOOO Page 15 of 16

Attachment #3 - Panel 2(3)OG075 Panel Indications (#3)

A B ~

Flashing C SEAL RUPTURE> FUEL STORA1fe FUEL 1 DRAIN POOL> STORAGE POOL HIGHrLOW . HIGH/LOW LEVEL HI RADIATION BELLOWS LEAK SKIMMER 2 HIGH FLOW SURGE TANK I l i t~~ ;-,

HIGH LEVEL GATE DRAIN SKIMMER*

HIGH FLOW SURGE TANK 3 LOW LEVEL LI-2(3)695

_ _ _.250

_ _ _200

'A' FUEL POOL PUMP

_ _ _150

_ _ _100 G G

'B' FUEL POOL PUMP

_ _ _50

_ _.o

....,..~

G eG' FUEL POOL PUMP SKIMMER SURGE TANK LEVEL G8 00 AGK RESET TEST STOP AUTO

@ START HIGH PRESSURE AO-2(3)698 000 DEGON PUMP FUEL POOL MAKEUP NLSR03068 RevOOO Page 16 of 16

EXELON NUCLEAR Nuclear Generation Group OJT/TPE MATERIAL COVERSHEET TYPE: . ~ JPM D QUALIFICATION MANUAL D OJT MODULE PROGRAM: Limited Senior Reactor Operator CODE#: NLSRO-3066 COURSE:' LSRO Initial & LSRO Requalification REV#:: 000 AUTHOR: G. W. Zellmer TYPIST: .' gwz TITLE:. Transfer of Recently Irradiated Fuel - Alternate Path (Loss of SBGT)

APPROVALS:

Signature I TIlle W~t*~/,tseo Signaturmitle Date

Il-~(L;,

1 I J(j APPROVED FOR USE: o EFFECTIVE DATE: 7 I I I 10 NAME: ISSUE DATE:

Last First M.I.

EMPLOYEE 10 NO. COMPLETION DATE:

COMMENTS:

Training Review for Completeness: LMS CODE:

LMS ENTRY:

Signature/Date NLSR03066 Rev 000 Page 1 of 14

EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE: Senior Reactor Operator I Senior Reactor Operator - Limited (LSRO)

TASK-JPM DESIGNATOR: 234000-24 -- NLSR03066 KIA: 261000 A2.05 RO: 3.0 SRO: 3.1 TASK DESCRIPTION: Transfer of fuel within the reactor cavity, to the fuel pool, or from the fuel pool to the reactor cavity as the RPO 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" 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 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.

NLSR03066 Rev 000 Page 2 of 14

6. 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, procedures, and Prerequisites met if applicable).

7. 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.

8. 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 Operations Training Manager. If dummy fuel bundle is moved, then all required stations MUST be filled by qualified individuals.

9. Most ..IPMs 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.

10. 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).

11. 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 12 Minute Drill with the RPO (LSRO examinee) for this evolution. The Pre-Job Brief 12 Minute Drill are human performance tools that do NOT constitute inappropriate coaching or exam compromise.

12. 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).

NLSR03066 Rev 000 Page 3 of 14

B. TOOLS AND EQUIPMENT

1. Task Conditions 1 Prerequisites and Initiating Cue Sheet

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

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

4. Access to Unit 2(3) Tech Specs and Unit 2(3) Tech Spec Bases

5. Access to ST-0-09A-2 'SBGT Subsystem 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' C. REFERENCES

1. FH-6C Rev. 63 'Core Component Movement'

2. PBAPS Tech Specs Unit 2(3) [Rev. 275/279] and Bases

3. SO 18.1.A -2(3) Rev. 22 'Operation of Refueling Platform' procedure

4. ST-0-09A-325-2 Rev. 5 'SBGT Subsystem Operability Test'

5. FH-35 Rev 36 'Control of Material Movement In the Fuel Pool'

6. Limerick Unit 1 Tech Specs (Rev. 198)

7. Limerick procedure FH-105 Rev. 45 'Core Component Movement - Core Transfers' D. TASK STANDARD

1. Satisfactory task completion is indicated when the Dummy Fuel Bundle is re-seated in the Spent Fuel Pool.

2. Estimated time to complete: 25 minutes Non-Time Critical E. DIRECTIONS TO EXAMINEE When given the initiating cue, you (the Refuel Platform Operator [RPO]) are to continue transferring Recently Irradiated Fuel in accordance with the approved CCTAS. I will describe initial plant conditions and provide you access to the materials required to complete this task.

F. TASK CONDITIONS/PREREQUISITES

1. Refuel Bridge is removing Recently Irradiated Fuel Assemblies out of the Reactor and arranging the Irradiated Fuel Assemblies in the Spent Fuel Pool as directed by:

a. FH-6C Core Component Movement

b. SO 18.1.A -2(3) Operation of Refueling Platform

c. Core Component Transfer Authorization Sheet (CCTAS)

NLSR03066 Rev 000 Page 4 of 14

2. For the purpose of this evolution, you will treat the Dummy Fuel Bundle as jf it is a Fuel Assembly that has been recently irradiated (irradiated 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ago).

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

4. The auxiliary hoists are full up.

5. All of the applicable Prerequisites for procedure FH-35 AND FH6C have been completed for Dummy Bundle transfer (simulated Recently Irradiated Fuel Assembly) in the Spent Fuel Pool.

6. All applicable Prerequisites of procedure SO 18.1.A-2(3) have been completed for recently irradiated Fuel transfer in the Core and Spent Fuel Pool.

7. All applicable portions of SO 18.1.C-2(3) 'Electrical, Mechanical, and Pneumatic Alignment 1 Checkout of Refueling Platform' have been completed.

8. 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

1. The Fuel Handling Director directs you to perform the necessary steps to move the (Unit 21 Unit 3) Dummy Fuel Bundle (simulated Recently Irradiated Fuel Assembly) in accordance with the attached CCTAS and in accordance with SO 18.1.A-2(3). You will perform the next indicated step on the attached CCTAS. 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 Recently Irradiated Fuel.

3. You are to PERFORM this activity as the Refuel Platform Operator (RPO).

NLSR03066 Rev 000 Page 5 of 14

H. PERFORMANCE CHECKLIST STEP STEP ACT STANDARD NO Notes to Evaluator 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 Fuel, then the evaluator may state that an inadvertent criticality event occurred 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ago 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 with in progress procedures are currently in effect).

C) Provide a copy of SO 18.1.A-2(3) and a copy of the CCTAS for dummy bundle movement prior to starting JPM. IF this JPM is being administered immediately following NLSRO-3064, THEN the SO 18.1.A-2(3) and CCTAS given to the examinee for NLSRO-3064 JPM may be used by the examinee for this JPM (it may not be necessary to supply another SO 18.1.A-2(3) or CCTAS).

D) The examinee may validate any and all prerequisites associated with FH-6C / SO 18.1.A-2(3) /

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-2[3]).

E) 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.

F) This JPM may be started from the associated Refueling Platform.

G) 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).

H) The FHD must give a Pre-Job Brief /2 Minute Drill to the RPO (LSRO examinee) before the start of the JPM. IF this JPM is being administered immediately following the NLSRO-3064 JPM, THEN (At the FHD's discretion) the FHD's Pre-Job Brief /2 Minute Drill that was given as part of the NLSRO-3064 JPM may be applied to this JPM without being repeated; the start time for the JPM may be recorded here _ _ _ _ _ _ _ _ _ _ __

NLSR03066 Rev 000 Page 6 of 14

STEP STEP ACT STANDARD NO 1 Position Refuel Platform Mast over P The Refuel platform is positioned over the desired core component in accordance dummy fuel bundle.

with Core Component Transfer Authorization Sheet (CCTAS). Note to Evaluator - If this JPM is being performed immediately following NLSRO 3064, then this step may already have been performed and this step may be marked N/A

2 Lower hoist until grapple is near bail. P The hoist is lowered using the variable speed control, located on the right hand console until the hoist position indication is between 176 - 182 (approximately).

3 Verify grapple is open. P The backlight on the GRAPPLE ENGAGED switch is verified to be extinguished.

4 Rotate grapple as necessary to achieve P The mast is rotated so that the grapple is grapple to bail alignment aligned with the dummy fuel bundle bail handle.

5 Slowly lower hoist until SLACK CABLE P The hoist is slowly lowered down over the light is lit. bail of the dummy bundle.

The SLACK CABLE light, located on the left hand console is verified ON.

6 CONCURRENT VERIFICATION P Proper core component location and FHD and Spotter perform concurrent orientation concurrently verified.

verification of proper core component location and orientation. (This standard is N/A for the RPO unless the RPO is also acting as the Spotter)

Note to Evaluator The verifications in the following two steps may be performed in parallel.

7 FHD verify the following: N/A N/A NLSR03066 Rev 000 Page 7 of 14

STEP STEP ACT STANDARD NO 7a

SLACK CABLE light is lit N/A N/A 7b

Grapple is centered over bail N/A N/A handle 7c

Hoist position indication agrees N/A N/A with Attachment 9 for item seated in Fuel Pool Storage Rack 7d

THEN direct RPO to engage N/A N/A grapple (Cue: evaluator will have the FHD direct the examinee to engage the grapple.)

8 RPO verify the following: N/A See below 8a

SLACK CABLE light is lit P SLACK CABLE light is verified to be ON 8b

Grapple is centered over bail P Grapple is verified to be centered over handle the bail handle 8c

Hoist position indication agrees P Hoist position indication is verified to be in with Attachment 9 for item seated agreement with Attachment 9 (- 188")

in Fuel Pool Storage Rack (- 188")

8d

WHEN directed by FHD, engage P Grapple is engaged by using the Hoist grapple Control Station 9 FHD and RPO perform Peer Check that P GRAPPLE ENGAGED light is verified "GRAPPLE ENGAGED" light is lit (peer checked with FHD) to be 'ON'.

NLSR03066 Rev 000 Page 8 of 14

STEP STEP ACT STANDARD NO

10 Slowly raise load while verifying HOIST P The dummy fuel bundle is slowly raised LOADED light is lit. (using the Hoist Control Station) while ensuring the HOIST LOADED light is (CUE: When the Hoist Loaded indicating 'ON'.

light comes on [while the Fuel Assembly is being raised, Then to the examinee provide the following When the cue is given, then that marks

'The Fuel Handling Director notifies you the start of the Alternate Path.

that the ['A' & 'B' / 'B' & 'C'] Standby Gas Treatment System Fans both tripped during testing and neither fan can be started. The FHD is asking for your recommendations. It)

11 The examinee (RPO) stops raising the P FH-6C step 7.1.5 - [FHD] shall determine Dummy Fuel Bundle. the proper immediate corrective action if an abnormal event or instrument (CUE: If examinee recommends that the response occurs.

FHD stop movement of all Fuel, then acknowledge the recommendation.) FH-6C step 7.1.7 - [FHD] shall be responsible for review of the prerequisites (CUE: If examinee recommends that the to this procedure to assure that all FHD notify the control room / Reactor applicable prerequisites are met during Operators of the 'Stop Order' for Fuel core component movement.

Movement and/or the re-insertion of the Fuel Assembly, then acknowledge the FH-6C step 5.11 - SBGT system is in recommendation. ) compliance with the requirements of Tech Spec 3.6.4.3. (FH-35 steps 4.7 & 9.6)

(CUE: If the examinee recommends re inserting the Recently Irradiated Fuel Tech Spec 3.6.4.3 Condition 'E' (Two Assembly (Dummy Fuel Bundle) into it's SBGT subsystems inoperable during previous location, then acknowledge the movement of Recently Irradiated Fuel recommendation. ) assemblies in the Secondary Containment or during OPDRVs):

Required Action E.1 - Suspend

++++++++++++++++++++++++++++++ movement of Recently Irradiated Fuel When the examinee has completed their Assemblies in secondary containment recommendations, then the EVALUATOR (immediately) will notify the FHD that the FHD may now direct the examinee to re-insert and re- ~ . ~ This is NOT a CUE. The evaluator to seat the Recently Irradiated Fuel i let the actual FHD know that the JPM is Assembly (the Dummy Fuel Bundle). at the point to direct the examinee (now i

++++++++++++++++++++++++++++++ the acting RPO) to re-insert and re-seat the Dummy Fuel Bundle. II NLSR03066 Rev 000 Page 9 of 14

STEP STEP ACT STANDARD NO 12 FHD and Spotter perform Concurrent N/A N/A Verification of proper core component location and orientation (This standard is N/A for the examinee (RPO) unless the RPO is also acting as the Spotter) 13 Spotter and RPO discuss the 'Push' or P 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 (if prevent the channel fasteners from required) contacting the fuel rack (if required).

14 Lower hoist until component is seated P 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 to evaluator - This guidance is from the SO 18.1.A procedure at step 4.13.4.

I Note to Evaluator

The verifications in the following two steps may be performed in parallel (steps 15 & 16) .

15 FHD verify the following: N/A N/A 15a

SLACK CABLE light is lit N/A N/A 15b

Component elevation appears N/A N/A equivalent to other stored components in the rack 15c

Hoist position indication agrees N/A N/A with Attachment 9 for item seated in Fuel Pool Storage Rack 15d

THEN direct RPO to release N/A N/A grapple NLSR03066 Rev 000 Page 10 of 14

STEP STEP ACT STANDARD NO 16 RPO verify the following: PIS NIA 16a

SLACK CABLE light is lit P SLACK CABLE light is verified to be ON 16b

Component elevation appears P Bundle is verified to be at the same equivalent to other stored elevation as other fuel bundles in the components in the rack racks.

16c

Hoist position indication agrees P Hoist position indication is verified to be in with Attachment 9 for item seated agreement with Attachment 9 (-188 in Fuel Pool Storage Rack inches)

16d

THEN WHEN directed by FHD, P Grapple is released by using the Hoist release grapple 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.)

17 Verify grapple is open. P GRAPPLE ENGAGED light is verified to be 'OFF'.

18 Slowly raise hoist while verifying 'HOIST P The grapple is slowly raised while LOADED' light remains 'OFF'. verifying the 'HOIST LOADED' light remains 'OFF'.

19 Perform Peer Check with FHD to ensure P Verify Grapple is clear of core grapple is clear of core components. components.

20 Examinee (RPO) notifies the FHD that P Notify FHD of task completion.

the Recently Irradiated Fuel Assembly (Dummy Fuel Bundle) has been re-seated.

(CUE: Acknowledge the report.)

NLSR03066 Rev 000 Page 11 of 14

STEP STEP ACT STANDARD NO Notes to Evaluator A) The performance portion of this JPM is complete; Stop Time may be recorded here: _ _ __

8) The following questions are 'JPM follow-up questions' to be given to the examinee by the evaluator. JPM follow-up question Start Time may be recorded here: _ _ _ __

C) The follow-up questions do NOT have to be given immediately following the performance portion of this JPM. If the examinee is adequately sequestered, then these follow-up questions may be given AFTER leaving the Refuel Platform.

D) IF this JPM is being used for LSRO Initial training I testing, THEN ONLY the first two (2) follow-up questions are required to be asked (The third follow-u12 question is N/A for Initial training / testing).

21 (CUE: "In this situation [the 'A' & '8' / '8' D Engineering analysis for handling light

& 'C' Standby Gas Treatment System loads over Irradiated Fuel without fans not working], are there any Secondary Containment / S8GT (Table 2 restrictions on the Rad Protection of FH-6C and/or Table 1 of FH-35)

Technicians that are currently performing permits the use of Teletector survey a survey of the Fuel Pool using a instrument.

Teletector [a complete Fuel Pool survey-will measure radiological conditions in a/l Fuel Pool areas]").

(Cue: If examinee asks what the weight of the T eletector in use is, then reply.:...

"The Teletector weight is 8 Ibs.")

(CUE: If examinee asks for a copy of FH 6C or FH-35 procedures, Then provide the examinee with a copy of the

~ocedures.)

22 (CUE: "Are there any tech specs that D Tech Specs prohibits movement of apply to this situation [moving Recently Recently Irradiated Fuel without S8GT.

Irradiated Fuel Assemblies with the 'A' &

'8' / '8' & 'C' Standby Gas Treatment Tech Spec 3.6.4.3 Condition 'E' (Two System fans not working].")? S8GT subsystems inoperable during movement of Recently Irradiated Fuel (CUE: If examinee asks for a copy of assemblies in the Secondary Tech Specs, Then provide the examinee Containment or during OPDRVs):

with a copy of the appropriate Tech Specs. Required Action E.1 - Suspend movement of Recently Irradiated Fuel Assemblies in secondary containment (immediately) .

Note to Evaluator The following step ONLY applies if this JPM is being used for Requalification training (Le. step 23 I does NOT apply to Initial LSRO training / testing). .

NLSR03066 Rev 000 Page 12 of 14

STEP STEP ACT STANDARD NO 23 (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

~ 'If the above conditions occurred at SBGT subsystems) would also be Limerick Unit 1 [two of the three SBGT stopped at Limerick under these fans failed], would you make the same conditions (exact wording not required).

stop-work determinations that you just However, at Limerick, the loss of two made here at PBAPS (if not, how would SBGT fans will cause these actions to the determinations be different)?' apply to Both Limerick Unit 1 & Limerick Unit 2. At PBAPS, the loss of two SBGT (Cue: If the examinee asks to see any [or fans will ONLY cause these actions to all] of the below listed procedures, then apply to either Unit 2 OR Unit 3 provide the examinee with a copy of the (depending on which SBGT Fans have requested procedure(s): failed).

-Limerick Unit 1 Tech Specs

-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 (Le.

not just Recently Irradiated Fuel transfers ).

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 follow-up questions 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 determined which work must stop and addressed any applicable follow-up questions, then the evaluator may terminate the exercise.

NLSR03066 Rev 000 Page 13 of 14

Task Conditions / Prerequisites and Initiating Cue TASK CONDITIONS/PREREQUISITES

1. Refuel Bridge is removing Recently Irradiated Fuel Assemblies out of the Reactor and arranging the Irradiated Fuel Assemblies in the Spent Fuel Pool as directed by:

d. FH-6C Core Component Movement

e. SO 1B.1.A -2(3) Operation of Refueling Platform

f. Core Component Transfer Authorization Sheet (CCTAS)

2. For the purpose of this evolution, you will treat the Dummy Fuel Bundle as if it is a Fuel Assembly that has been recently irradiated (irradiated 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ago).

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

4. The auxiliary hoists are full up.

5. All of the applicable Prerequisites for procedure FH-35 AND FH6C have been completed for Dummy Bundle transfer (simulated Recently Irradiated Fuel Assembly) in the Spent Fuel Pool.

6. All applicable Prerequisites of procedure SO 18.1.A-2(3) have been completed for recently irradiated Fuel transfer in the Core and Spent Fuel Pool.

7. All applicable portions of SO 18.1.C-2(3) 'Electrical, Mechanical, and Pneumatic Alignment / Checkout of Refueling Platform' have been completed.

8. 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).

INITIATING CUE

1. The Fuel Handling Director directs you to perform the necessary steps to move the (Unit 2/ Unit 3) Dummy Fuel Bundle (Simulated Recently Irradiated Fuel Assembly) in accordance with the attached CCTAS and in accordance with SO 18.1.A-2(3). You will perform the next indicated step on the attached CCTAS. 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 Recently Irradiated Fuel.

3. You are to PERFORM this activity as the Refuel Platform Operator (RPO).

NLSR03066 Rev 000 Page 14 of 14

EXELON NUCLEAR Nuclear Generation Group OJTlTPE MATERIAL COVERSHEET

~ JPM D OJT MODULE

Limited Senior Reactor Operator NLSRO-3064 LSRO Initial & LSRO Requalification 000 G. W. Zellmer gwz

. Dummy Fuel Movement in the Spent Fuel Pool (PBAPS - Fire)

APPROVALS:

Date *

" '-8110 Date 7 I C Date APPROVED FOR USE: ro EFFECTIVE DATE: ,I ,__......:{-.:o_

NAME: ISSUE DATE:

Last First M.1.

EMPLOYEE ID NO. COMPLETION DATE:

COMMENTS:

Training Review for Completeness: LMS CODE:

LMS ENTRY:

Signature/Date NLSR03064 Rev 000 Page 1 14

EXELON NUCLEAR PEACH BOnOM ATOMIC 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-Plant" 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 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

6. 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, procedures, and Prerequisites met if applicable).

7. 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.

8. 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 JPM 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.

9. 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 Operations Training Manager. If dummy fuel bundle is moved, then all required stations MUST be filled by qualified individuals.

10. 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.

11. JPM paperwork that is used on the Refueling Bridge may be contaminated and not be available for record retention. Unless the ..IPM 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).

12. 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.

NLSR03064 Rev 000 Page 3 of 14

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. 22 'Operation of Refuel 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. #4 '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

E. 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 CCTAS and in accordance with SO 18.1.A-2(3). The Refuel Platform must be operated in the Manual mode. For the entire evolution, you will treat the Dummy Fuel Bundle 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 / 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 STEP STEP I 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 I SO 18.1.A I RWPs I 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 andlor 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 (Le. This is NOT coaching and it is NOT an exam compromise).

G) The FHD must give a Pre-Job Brief 12 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 .JPM 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 ENGAGED switch is verified to be extinguished.

I NLSR03064 Rev 000 Page 6 of 14

STEP STEP ACT STANDARD NO 4 Rotate grapple as necessary to achieve PIS The mast is rotated so that the grapple is grapple to bail alignment aligned with the dummy fuel bundle bail handle.

5 Slowly lower hoist until SLACK CABLE PIS The hoist is slowly lowered down over the light is lil. bail of the dummy bundle.

The SLACK CABLE light, located on the left hand console is verified ON.

6 CONCURRENT VERIFICATION PIS Proper core component location and FHD and Spotter perform concurrent verification orientation concurrently verified.

of proper core component location and orientation.

(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: N/A N/A 7a

SLACK CABLE light is lit N/A N/A 7b

Grapple is centered over bail N/A N/A handle 7c

Hoist position indication agrees N/A N/A with Attachment 9 for item seated in Fuel Pool Storage Rack 7d

THEN direct RPO to engage N/A N/A grapple (Cue: evaluator will have the FHD direct the examinee to engage the grapple.)

8 RPO verify the following: N/A See below I

NLSR03064 Rev 000 Page 7 of 14

STEP STEP ACT STANDARD NO Sa

SLACK CABLE light is lit PIS SLACK CABLE light is verified to be ON Sb

Grapple is centered over bail PIS Grapple is verified to be centered over handle the bail handle Sc

Hoist position indication agrees PIS Hoist position indication is verified to be in with Attachment 9 for item seated agreement with Attachment 9 in Fuel Pool Storage Rack

Sd

WHEN directed by FHD, engage PIS Grapple is engaged by using the Hoist grapple Control Station 9 FHD and RPO perform Peer Check that PIS GRAPPLE ENGAGED light is verified "GRAPPLE ENGAGED" light is lit (peer checked with FHD) to be 'ON'.

10 Slowly raise load while verifying HOIST PIS The dummy fuel bundle is slowly raised LOADED light is lit (fuel only). (using the Hoist Control Station) while ensuring the HOIST LOADED light is

'ON'.

11 Continue raising until grapple is fully PIS Continue raising the grapple to the full up raised, THEN verify Grapple NORMAL position and verify that the Grapple UP light is lit. NORMAL UP light is 'ON'.

Notes to Evaluator A) The following steps are contained in procedure SO 1S.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.

i NLSR03064 Rev 000 Page 8 of 14

STEP STEP ACT STANDARD NO Position core component over desired The platform is positioned so that the

12 location in accordance with Core PIS dummy fuel bundle is hanging over the Component Transfer Authorization Sheet correct spent fuel pool storage location (CCTAS). (per CCTAS)

(Cue: AFTER the Refuel Platform Trolley is over the 'MOVED TO' location on the CCTAS, Then provide The following "An 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 I 3 ] 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.)

L Notes to Evaluator I FHD A) 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 ANDIOR the Fuel Handling Director (FHD).

B) If the examinee asks the FHD for direction (i.e. 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 [FHD may ask the examinee 'what they think the crew should do']).

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 N/A 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 I 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) .

i 17 FHD verify the following: N/A N/A 17a

SLACK CABLE light is lit N/A N/A 17b

Component elevation appears N/A N/A equivalent to other stored components in the rack NLSR03064 Rev 000 Page 10 of 14

STEP STEP ACT STANDARD NO 17c

Hoist position indication agrees NIA NIA with Attachment 9 for item seated in Fuel Pool Storage Rack 17d

THEN direct RPO to release NIA NIA grapple 18 RPO verify the following: PIS NIA i

18a

SLACK CABLE light is lit I PIS SLACK CABLE light is verified to be ON 18b

Component elevation appears PIS Bundle is verified to be at the same equivalent to other stored elevation as other fuel bundles in the components in the rack racks.

18c

Hoist position indication agrees PIS Hoist position indication is verified to be in with Attachment 9 for item seated agreement with Attachment 9 (-188 in Fuel Pool Storage Rack . inches) 18d

THEN WHEN directed by FHD, PIS Grapple is released by using the Hoist release grapple 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 i be 'OFF'.

20 Slowly raise hoist while verifying 'HOIST PIS The grapple is slowly raised while LOADED' light remains 'OFF'. verifying the 'HOIST LOADED' light remains 'OFF'.

21 Perform Peer Check with FHD to ensure PIS Verify Grapple is clear of core grapple is clear of core components. 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).

Notes to Evaluator A) Ideally, the below two steps will NOT be performed. The Evaluator should terminate the "IPM 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 Evaluator A) If at any time, the examinee attempts to perform the second CCTAS move (as directed by the initiating cue), then that action constitutes a failure 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 JPM (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 evacuate the Refuel Floor, then the evaluator may terminate the performance portion of the JPM 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

STEP STEP ACT STANDARD NO 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 Note 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 ..IPM.

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 questions, then the evaluator may terminate the JPM.

NLSR03064 Rev 000 Page 13 of 14

TASK CONDITIONS I PREREQUISITES AND INITIATING CUE TASK CONDITIONS/PREREQUISrrES

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.

INITIATING CUE

1. The Fuel Handling Director directs you to perform the necessary steps to move the (Unit 2 I 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

EXELON NUCLEAR Nuclear Generation Group OJT/TPE MATERIAL COVERSHEET TYPE: ~ JPM D QUALIFICATION MANUAL D OJT MODULE PROGRAM: Limited Senior Reactor Operator CODE#: NLSRO-3065 COURSE: LSRO Initial & LSRO Requalification REV#:: . 000 AUTHOR: G. W. Zellmer TYPIST: gwz I TiTlE: Fuel Support Piece Removal using FSP Grapple (Alternate Path due to Fault Lockout)

APPROVALS:

~Signature'l Title Date I

/ VJI1.Id,nwt. s/z. ftt-j/d Dale 5/~f'D Dale

,-U-'(V Dale APPROVED FOR USE: b Date

{., I Iv I {O NAME: ISSUE DATE:

Last First M.1.

EMPLOYEE ID NO. COMPLETION DATE:

COMMENTS:

I Training Review for Completeness: LMS CODE:

LMS ENTRY:

Signature/Date NLSR03065 Rev 000 Page 1 of 16

EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE: Senior Reactor Operator I 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-Plant" 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 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.

NLSR03065 Rev 000 Page 2 of 16

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

B. 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 1B.1.A-2(3) 'Operation of 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 1B.1.A-2(3) Rev 22 '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 I 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 of 16

6. The CCTAS is approved (current step is provided - see below).

I I STEP NO.

COMPONENT SERIAL NO.

MOVED FROM ORIENT MOVE TO ORIENT FHD RPO CRO CO~~~TE I DATE I TIME i ABCDEFGH I 86 SUP PC I 30-31 I SW P SPENT NONE N/A L I I

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.

11. You (the FHD) have a complete Refuel Platform crew available to you, including the RPO which is stationed at the Monorail Hoist Pendant Control.

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 STEP 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 ..IPM include JPM pages 12,13,14,15, and 16.

8) A Copy of M-C-741-301 and SO 1B.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 JPM 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 ..IPM start time may be recorded here

1 Direct the RPO to 'ENGAGE' the FSP S RPO is directed to "ENGAGE" the Grapple. Monorail FSP Grapple.

(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 Direct the RPO to 'Lower hoist until S RPO is directed to lower the grapple grapple enters top guide, then ensure while maintaining the proper Grapple grapple is oriented properly to align with orientation (Southwest).

anti-rotation pin at corner of control cell (Southwest)' . Note -- If any system or equipment required to perform work becomes (CUE: The grapple starts to lower but inoperable or malfunctions, stop after the grapple travels two (2) feet in the operations until the required system or down direction, the grapple motion equipment is returned to service (step abruptly stops followed by a report from 3.2.7 of M-C-741-301).

the RPO that an 'Interlock Status Display Annunciator' is currently up and indicates *********************************************

a 'Fault Lockout' condition. The Refuel Note -- Start Of Alternate Path Platform will NOT respond to controls.) *********************************************

(CUE: Provide the examinee with a copy of the 'Interlock Status Display' [page 11 ].)

NLSR03065 Rev 000 Page 5 of 16

STEP STEP ACT STANDARD NO 3 Notify Control Room of the 'Fault Lockout' S When operating equipment, If it does not condition. perform as expected, then place the equipment in a safe condition and inform (CUE: Acknowledge the report of the Shift Management.

'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 Direct the RPO to 'depress the Refuel S RPO is direct to depress the Refuel Platform 'START' pushbutton'. Platform "START" pushbutton (to resume Platform operation).

(CUE: "Refuel Platform 'START' pushbutton is depressed; all Refuel Note to Evaluator - Start pushbutton Bridge indications are as expected [as must be pressed to resume platform they were before the Fault Lockout operation after 'Fault Condition is cleared condition - Monorail Hoist is two [2] feet (SO 18 .1.A-2[3] Att. 1).

lower than the normal full up position].")

(CUE: If examinee request maintenance Note -- End Of Alternate Path to perform a checkout I diagnostic of the *********************************************

Bridge functions, then provide the examinee with the following "Maintenance determines that all Bridge functions are operating normally.")

NLSR03065 Rev 000 Page 6 of 16

STEP STEP ACT STANDARD NO

5 Direct RPO to 'lower hoist until grapple S RPO is directed to lower the grapple enters top guide, then ensure grapple is while maintaining the proper Grapple oriented properly to align with anti- orientation (Southwest).

rotation pin at corner of control cell (Southwest orientation),. Note to Evaluator - This step is completing what the examinee started in (Cue: The component that you identified step 2 (but was NOT able to complete is in the condition that you just due to the Fault Lockout).

described.)

(CUE: If examinee directs hoist 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 Direct the RPO to 'continue to lower S RPO is directed to lower the Monorail grapple through top guide to just above Grapple UNTIL the grapple is just above the FSP'. the FSP.

(Cue: The component that you identified is in the condition that you just described.)

Direct the RPO to ensure the 'RELEASE' RPO is directed to verify the "RELEASE"

7 push-button on the Monorail Hoist S push-button is depressed on the Hoist pendant control is actuated.. pendant control (to release the FSP Grapple),

(CUE: The component that you identified is in the condition that you just described.)

8 Direct the RPO to 'lower the FSP Grapple S RPO is directed to lower the FSP Grapple fully onto the FSP'. fully onto the FSP.

(Cue: The component that you identified is in the condition that you just described. )

NLSR03065 Rev 000 Page 7 of 16

STEP STEP I ACT STANDARD NO 9 Direct the RPO to 'Pull down on and hold S RPO is directed to pull down on and hold air hoses to verify there is no tension in air hoses to verify there is no tension in hoses'. the hoses.

(Cue: The component that you identified is in the condition that you just described.)

10 Direct the RPO to 'actuate the S RPO is directed to depress the Monorail "ENGAGE" push-button on the Monorail Hoist Pendant Control "ENGAGE" push-hoist pendant control and pause a button and pause for 10 seconds.

minimum of 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 before going on to the next described.) step OR the examinee must verbally state that at least 10 seconds must pass before manually lifting the FSP grapple.

11 Direct the RPO to manually lift the FSP S RPO is directed to manually lift the FSP grapple enough to take weight of the Grapple and verify the load indicator on FSP. the Monorail Hoist Pendant Control is greater than 100 Ibs and less than or (Cue: "The component that you identified equal to 165 Ibs.

is in the condition that you just described. !

The RPO reRorts that the load indicator on the Monorail Hoist Pendant Control indicates 160.")

12 Direct the RPO to 'bump the Hoist up S RPO is directed to raise the FSP Grapple approximately 6 inches'. approximately 6 inches.

(Cue: The component that you identified is in the condition that you just described. )

(Cue: If examinee asks the indication on the load indicator, then "The load indicator on the Monorail Hoist Pendant Control reads 160.")

NLSR03065 Rev 000 Page 8 of 16

STEP STEP ACT STANDARD NO

13 Direct the RPO to 'raise the FSP through S RPO is directed to raise the FSP through top guide and above the core'. the top guide and above the core.

(CUE: FSP is through the top guide and Note to Evaluator - It is permissible for above the core.) this completes the this action to be done in a series of steps.

simulated portion of the JPM. There may be follow up question(s) that need to be addressed.)

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 The following step ONLY applies for Requal Examinations (i.e. 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-741-301, 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.

NLSR03065 Rev 000 Page 9 of 16

STEP STEP ACT STANDARD NO 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.

8) 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 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 STATUS DISPLAY ----'

I BRIDGE POS I ITROLLEY POS I 30.00 31.00 FUEL ROD BLK ROD BLK BRIDGE BRIDGE HOIST INTERLK INTERLK REVERSE REVERSE INTERLK #1 #2 STOP #1 STOP #2 BACKUP SAFETY TEST HOIST TRAVEL IN LMIT INTERLK PROG MONO FRAME HOIST HOIST INTERLK INTERLK NLSR03065 Rev 000 Page 11 of 16

TASK CONDITONS I PREREQUISITES AND INITIATING CUE TASK CONDITIONS/PREREQUISITES

1. Fuel shuffle part 1 has been completed on PBAPS Unit _ (Unit 21 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).

STEP NO.

, COMPONENT SERIAL NO.

I MOVED FROM I ORIENT MOVE TO ORIENT! FHD RPO eRO I

I WRNM COUNTRATE i DATE I TIME !

I ABCDEFGH 86 SUP pc I 30-31 I sw P SPENT NONE I I N/A I I I

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.

11. You (the FHD) have a complete Refuel Platform crew available to you, including the RPO which is stationed at the Monorail Hoist Pendant Control.

INITIATING CUE The Control Room Supervisor directs you (as the Fuel Handling Director [FHDJ) 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

f :1

':::,.\

-r -,

I i I,

\1, 1,1 I, '

]0 11 :

oe III, II*

1).1 i, i Ii CJ I Ij 01 I] 11 1 : [ 1"1 C! I l 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 (Hoist Raising Direction)

FSP Lift*: 160

CRB Lift: 300 (Mark N/A if using NES Combined Grapple)

FSP + CRB Lift: N/A

~----------------

(Combined Grapple only)

Grapple Empty: _ _1_00 _ _ _ _ __

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

INDICATED WEIGHTS DURING CRB EXCHANGE Attachment 11 Page 1 of 1 NLSR03065 Rev 000 Page 15 of 16

STu:;,

Orientation Aid GUSSE T (aligned with anti-rotation pin)

S? AC E,R

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8ASE PLATE FUEL SUPPOI'IT GRAPPLE GRID GUIDE and Orientation Aid NLSR03065 Rev 000 Page 16 of 16

v t e Letter Sequence 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]

ML102420261

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