ML102420261
| ML102420261 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom, Limerick  |
| Issue date: | 07/09/2010 |
| From: | Dickenson R, Wasong A J Exelon Generation Co |
| To: | D'Antonio J M Operations Branch I |
| Hansell S | |
| Shared Package | |
| ML092470056 | List: |
| References | |
| TAC U01795, TAC U01796 | |
| Download: ML102420261 (184) | |
Text
Exelon Job Performance LSRO Only -FUEL HANDLING DIRECTOR TURNOVER CONDITIONS MEETING TECHNICAL SPECIFICATION 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. Task description and number, JPM description and number are identified. Knowledge and Abilities (KIA) references are included. Performance location specified. (in-plant, control room, simulator, or other) Initial setup conditions are identified. Initiating cues (and terminating cues if required) are properly identified. Task standards identified and verified by SME review. Critical steps meet the criteria for critical steps and are identified with an asterisk (*). 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: Verify cues both verbal and visual are free of conflict. Verify performance time is accurate If the JPM cannot be performed as written with proper responses, then revise the JPM. When JPM is initially validated, sign and date ..IPM cover page. Subsequent validations, sign and date below: SME I Date SME I Date SME I Date SRRS: 3D.1 05 (when utilized for operator initial or continuing Page 2 of 6 NLSR02084 RevOOO REVISION RECORD (Summary) Revision 00 Nt A SIMULATOR SETUP INSTRUCTIONS 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 Review completed Fuel Handling Director Shift Turnover Checklist prior to taking 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 Page 3 of 6 NLSR02084 RevOOO JPM
SUMMARY
Operator's Name:,___________
Job Title:D SED D SM DSRO D ST AliA 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 SRO Only:
DNo Time Critical:
DYes 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: ______________________________ 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.
c ... -<< (1) (1) << E..Q en STANDARD STEP ELEMENT E §en z :::) oz:o . CUE: Provide candidate with the Fuel Handling Director Turnover Checklist N/A AND Copy of
--*1. Determine Movement of Planned for next Evolutions in Progress I fuel in the Spent Fuel Pool cannot occur:Current CCTAS is Spent fuel pool 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 Planned for next cannot occur: Tech Spec. 3.9.8 is not met as Core Transfers
- 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. SRRS: 3D.105 (when utilized for operator initial or continuing Page 5 of 6 I NLSR02084 RevOOO *3. Control Rod withdrawal to support uncoupling:
Determine Control Rod 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 Review completed Fuel Handling Director Shift Turnover Checklist prior to taking 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 Revision #Exel n Page 1 of 4 Nuclear FUEL HANDLING DIRECTOR SHIFT TURNOVER CHECKLIST NOTE: Complete this form at turnover Date:__
__________ 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:
__
__________ SRRS: 30.105 (when utilized tor operator initial or continuing training)
Revision ## Page 2 of 4 FHD Log and information on page 1 reviewed.
- 1. RAC Fuel Floor local panel annunciators (both units) and Refuel Platform Interlock/Controls reviewed.
- 2. RAC Status of work reviewed with Maint. Supervisor and RP Technician.
- 3. RAC RP Drywell Control Point contacted and has verified access control to upper elevations is in place as required.
- 4. RAC RP Contacted:
AI Senter IF irradiated component transfers through cask pit will occur, RP has posted RB 313' areas as required.
- 5. RAC Refueling Platform checkout per S97.1 .A is complete as required.
- 6. RAC FHDs, Refuel Platform Operators (RPOs), and Spotters are qualified and completed all required reading. 7. RAC Continuous communications established between Control Room and Refueling Platform during CORE ALTERATIONS.
- 8. RAC FHD conducted a pre-evolution brief with refuel platform personnel.
- 9. RAC 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) An RP qualified person is present on the Refuel Floor for any work in fuel pool, Reactor cavity, or equipment pit. 11. RAC CCTAS reviewed, and verified same title/rev.
as Reactor Operator and Spotter copies. 12. RAC IF not in use, THEN GE RCWP Jib Hoist Booms rotated away from RPV center. 13. RAC 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 Auxiliary hoist jam blocks set properly during in-vessel maintenance.
- 15. RAC 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 Fuel Floor permanent ARMs, temporary ARM(s) if required, and Refuel Platform ARM(s) indicate on scale. Refuel Platform rad monitor audible alarm check
- 17. RAC 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. *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 RAC Refueling Interlocks and Refuel Platform equipment operable as required by Tech Specs. ST 097 -630-1 (2) OR ST 107 -633-1 (2) . 19. RAC Reactor Mode switch locked in REFUEL position.
- 20. RAC All control rods are fully inserted and indicate full in as required by Tech Specs. 21. RAC 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 Moderator temperature?:
68° F OR a lower cycle-specific temperature specified by Reactor Engineering.
- 23. NOTE #1 Both Recirc pumps secured OR allin-core Instruments supported.
- 25. NOTE #2 LCO, PLCO, prior shift ops narrative log entries reviewed.
- 26. RAC 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. SRMs are operable as required by Tech Spec 3.9.2. (Circle operable SRMs ABC D). 28. RAC 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 *Main Control Room Emergency Fresh Air Supply System instrumentation operable.
- 30. *SBGTS operable as required by Tech Specs. 31. RAC *Secondary Containment, SCIVs AND instrumentation Refuel Area HVAC is in service with operable ventilation exhaust OR Standby Gas Treatment is in service to the Refuel Area. 32. ECCS operable as required by Tech Specs. 33. RAC *Electrical systems AND instrumentation operable as required by Specs. 34. RHR method(s) set per Tech Spec requirements.
- 35. RAC 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. Time: #### SRRS; 3D.1 05 (when utilized for operator initial or continuing training)
NF-LG-31 0-2000 Revision ## Page 1 Of 2 ATTACHMENT "Sample" CCTAS Instruction/Approval Page 1 of 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 (Rev.#)
__ This CCTAS provides the moves necessary to Fuel bundles within the U1 Spent Fuel Pool This CCTAS assumes that SRM A, 8, C, D are in service. Emergency Setdown Location This CCTAS must be used in conjunction with appropriate maintenance procedures. This CCTAS must be used in conjunction with appropriate fuel handling procedures. All changes to this CCTAS must be made in accordance with procedure NF-AA-309. This CCTAS involves the transfer of Special Nuclear Material (SNM). SNM transfers shall be controlled in accordance with procedure NF-AA-300. Reactor Engineer contact: H Potter X#### List pen and ink revisions and affected pages here: ____
___________________
/ __
____ Preparer DATE ____
_________________
/ __
____ Independent Reviewer DATE __
________/ _---'-'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 CCT AS 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 NO. 1 COMPONENT SERIAL NO. LY8487 MOVE FROM L2SPENT KK*158 ORIENT SW MOVE TO L lSPENTT-58 ORIENT SW SW SW SW SW SW FHD RPO DATE TIME 2 3 4 5 6 LY8488 LY8811 LYN091 LY8812 LY8813 L2SPENT KK156 L2SPENT KK-l54 L2SPENT KK-152 L2SPENT KK-150 L2SPENT KK148 SW SW SW SW SW L 1SPENT U*57 L lSPENT U-56 L 1 SPENT V-58 L 1 SPENT V-56 L 1 SPENT W-58 7 LYN104 L2SPENT KK146 SW L 1 SPENT W-57 SW SRRS: 30.105 (when utilized for operator initial or continuing training)
Exelon Job Performance Calculate Stay JPM Number:
Revision Number: 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. Task description and number, JPM description and number are identified. Knowledge and Abilities (KIA) references are included. Performance location specified. (in-plant, control room, simulator, or other) Initial setup conditions are identified. Initiating cues (and terminating cues if required) are properly identified. Task standards identified and verified by SME review. Critical steps meet the criteria for critical steps and are identified with an asterisk (*). Verify the procedure(s) referenced by this .JPM reflects the current revision:
Procedure
________ Rev: Procedure Procedure
________
Rev: Verify cues both verbal and visual are free of conflict. Verify performance time is accurate If the "IPM cannot be performed as written with proper responses, then revise the JPM. When JPM is initially validated, sign and date JPM cover page. Subsequent validations, sign and date below: SME /
Date SME /
Date SME /
Date SRRS: 3D.1 05 (when utilized for operator initial or continuing Page 2 of 7 NLSR02701 Rev001 REVISION RECORD (Summary) 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 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 is to be performed on the Refuel Floor inside a quarantined INITIATING CUES: You are directed to determine: Maximum Stay Times (Worst Case) to reach the Electronic Dosimeter accumulated dose alarms for worker 1 and worker 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 UNSA T requires written comments on respective step. SRRS: 3D.1 05 (when utilized for operator initial or continuing 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 ST AliA 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: 0Procedure 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: EVALUATION Were all the Critical Elements performed satisfactorily?
OYes The operator's performance was evaluated against contained within this JPM and has been determined to be: o Satisfactory 0
Evaluator's Name: ______________________________ 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: ___C TIEl t( ). d' t d b )y H*'" P n Ica emen S In Ica e In e ormance Ch ec kl'IS.t -l-e (1),8.. e(tJ)e( E E -I STANDARD ELEMENT tJ) z E ::J ::t Oz 0 N/A (Cue: Provide copy of 460-002 and survey map) N/A 1. Determine new Maximum Stay Time for the required entry !2. For worker 1 : I I *2.a Determine remaining Accum -Accum = margin to the Dose Dose Dose dosimeter accumulated Alarm Alarm does alarm setpoint by 1200 mr -900 mr = 300 mr subtracting dose of 900 mr accumulated dose of 1200 mr to remaining dose *2.b Divide remaining Remain I Effective
= to alarm by the 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 1200 mr-800 mr = 400 mr Subtract dose of 800 mr accumulated dose of 1200 mr to remaining dose I alarm i I SRRS: 3D.1 05 (when utilized for operator initial or continuing training)
Page 6 of 7 NLSR02701 Rev001 -1i<t UJ STANDARD ELEMENT UJ Z ::J , s:: .... G.\ G.\E.QE E o :::J OZ *3.b Divide remaining margin to alarm by the effective Dose Rate in work area to get Maximum Stay Time (Worst Case) Calculate if man-hrs are exceeded: Add worker 1 Maximum Stay Time of 45 minutes to worker 2 Maximum Stay Time of 60 minutes *4.b Determine work can be competed due to combined stay time greater than the required Remain I Effective
- Max Margin Dose Stay Alarm Rate Time 400mr I 400 mr/hr
- :;: 1.0 hrs I Worker + Worker::;:
Total 1 Stay 2 Stay Stay Time Time Time 45 min + 60 min::;: 105 min Determine work can be completed 1.5 man-hrs I You have met the termination criteria for this JPM ,-'PM Stop Time: _____ SRRS: 3D.1 05 (when utilized for operator initial or continuing Page 7 of 7 I 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 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 is to be performed on the Refuel Floor inside a quarantined INITIATING CUES: You are directed to determine: Maximum Stay Times (Worst Case) to reach the Electronic Dosimeter accumulated dose alarms for worker 1 and worker 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)
Att ac h ment 1 -ARW S urvey F orm 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. YES NO INSTRUMENT NO. YES NO R02A ##-#### X RM-14 ##-#### X Ri ITEM I LOCATION BETA GAMMA DISTANCE CONTAMINATION mrad/hr mRlhr (Circle one) SMEAR# ITEM I LOCATION A Work Area N/A 400 <1K 0 30cm / GA 1 Laydown Area I Low Dose Area N/A 50 -2 Grapple <10K A Cont. I 30cm / GA T NES Grapple Laydown Area 3 Laydown Area <2K I 0 4 N I C) 5 Y/ct400 I 6 *1 Grapple i 7 r-Y / 30 em 400 i 8 I 9 0 I 10 11 12 Step-Off Pad 13 14 15 1. x-x-x = Radiological Boundary 20 SMEAR 3. <#/ #
- 4. <#/ #: CONTACT All dose rates in mRlhr unless otherwise noted. #/ # @ 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 Hoist Jam Light (LSRO performs as (Alternate 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. Task description and number, JPM description and number are identified. Knowledge and Abilities (KIA) references are included. Performance location specified. (in-plant, control room, or simulator) Initial setup conditions are identified. Initiating and terminating cues are properly identified. Task standards identified and verified by SME review. Critical steps meet the criteria for critical steps and are identified with an asterisk (*). Verify the procedure referenced by this JPM matches the most current revision of that procedure:
Procedure Rev. __ Rev. __Procedure Rev. __ 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 Date SME I Date SME I Date SRRS: 3D.1 05 (when utilized for operator initial or continuing Page 2 of 14 NLSROJPM2035 REVISION RECORD (
SUMMARY
)
Rev 002, updated based on procedure rev. Format updated no rev markers used TRAINEE BRIEFING Perform PJB lAW HU-AA-1211. Ensure Roles and Responsibilities are covered Ensure trainee understands that in order to examine requirements of the LSRO program, they may be asked to switch roles during the JPM. Ensure Safety is covered Ensure Human Performance Fundamentals are covered. BRIDGE SETUP INSTRUCTIONS ENSURE there is NO conflict with scheduled Refuel Floor and/or Fuel Pool work. ENSURE personnel required for performance of S97.0.M are in attendance. PERFORM PREREQUISITES of S97.0.M. Bridge operation will be in Manual. ENSURE there is NO potential for contact with the Auxiliary Platform during performance of any section of this procedure. PERFORM the applicable sections of S97.1.A. PERFORM FH-106. PERFORM PRECAUTIONS of S97.0.M. 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 Page 3 of 14 NLSROJPM2035 REV002.ooc All of the Prerequisites and Precautions of procedure S97.0.M have been completed. 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. 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. Refuel Floor Secondary Containment is not required. The fuel prep machine is operable and visually verified full down. INITIAL CONDITIONS: 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. Prerequisites of S97.0.M have been met. All encoders are enabled for the bridge, trolley and hoist. This JPM is written from the standpoint that the LSRO is operating the refuel platform as RPO. Refuel Floor Secondary Containment is not required. There are NO irradiated components grappled to any refueling platform hoist. The Aux Hoists are full up with no tools attached. 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. All Prerequisites of FH-106, Core Component and Irradiated Item Movement-No Core Transfer, are complete as applicable.
INITIATING CUES: 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. You are to PERFORM (simulate if Refuel Platform is not operable) this activity as the Refuel Platform Operator. 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 Page 4 of 14 NLSROJPM2035 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 OSRO OSM 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 Yes o No Time Critical:
DYes [2J S97.1.A, Electrical, Mechanical, and Pneumatic Alignment/Checkout of Refueling Platform Bridge, Trolley, and Main Hoist for Operation FH-106, Core Component and Irradiated Item Movement -No Core Transfer S97.0.M, Refueling Platform Operation Actual Testing Environment:
0 Simulator 0 Control Room 0 In-Plant 0 Testing Method: 0 Simulate 0 Estimated Time to Complete:
20 minutes Actual Time Used: 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 I NLSROJPM2035 REV002.DOC JPM Start Time: ___ <C STANDARD ELEMENT U) I . .Provide candidate with a copy of S97.0.M Current revision of S97.0.M Obtain current revision of 1. S97.0.M obtained. <C U) Z ;:) e ... CD CD E.D E E o ::::I OZ 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 I initiating cue requires manual bridge operation.
Pickup Location -Fuel Pool N/A I 2. N/A Storage Rack or Cask Pit N/A -.__. i Spotter to RPO: "next location is _-___" 3. RPO to Spotter: "understand, _-___" --
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 I dummy fuel --N/A 5. NOTE: The following step be performed anytime prior setting grapple on bail in step N/A N/A -I L SRRS: 3D.1 05 (when utilized for operator initial or continuing training)
Page 7 of 14 NLSROJPM2035 STEP ELEMENT STANDARD << (J) << (J) Z ::l -e: ... C1) C1)E..Q E E o :::J OZ 6. 7. 8. IF HMI screen is functional, THEN RPO, VERIFY the "Current Location" displayed on HMI screen matches intended rack location. (CUE IF simulated: "Current Location" displayed matches intended rack location.)
LOWER grapple until grapple is near bail. (CUE IF simulated:
Grapple has been lowered and is near the bail (180">> ENSURE grapple is open. (CUE IF simulated:
Grapple is open) RPO, VERIFY the "Current Location" displayed on HMI screen matches intended rack location.
Grapple lowered near bail. Grapple open. Verify indicating light is NOT lit Camera indicates grapple is I open. -------SRRS: 3D.1 05 (when utilized for operator initial or continuing training)
Page 8 of 14 NLSROJPM2035 ELEMENT CAUTION 9. Grapple switch guard located on LH Controller side of grapple head interferes with adjacent DBG bail handle when pickup component's bail handle is between the DBG legs and pickup component's bail handle is perpendicular to DBG handle. Grapple guard can also interfere with Spent Fuel Pool rack label pipe couplings.
Contact of grapple guard can cause permanent damage to proximity switch electric cable causing refuel platform to be inoperable.
Maintain switch guard away from adjacent seated DBG bail handle OR rack label pipe couplings.
SBG bail handle will always be perpendicular to DBG bail handle in core. Therefore, for pickup of SBG's in pool, mast must be oriented with switch guard opposite corner of SBG with spacer buttons. CUE IF asked: There is no interference for this bundle. STANDARD NI A l-c:c (/)(/) Z ::;:) N/A N/A e a.. CI) CI)E.o E E o ::::I OZ SRRS: 3D.105 (when utilized for operator initial or continuing training)
Page 9 of 14 I
---NLSROJPM2035
-. ....c: G) G)e.Q (/)STANDARD ELEMENT STEP e e (/) Z o :::s;:) OZ 10. ROT ATE grapple as to achieve grapple to Grapple rotated and aligned with (CUE IF simulated:
Grapple rotated and aligned with ---11. Slowly LOWER grapple until SLACK CABLE Light is lit. Grapple is lowered, SLACK CABLE Light is lit. (CUE IF simulated: . CABLE Light is ---I 12. FHD & Spotter, Concurrent Verification proper core component AND N/A (CUE IF simulated: bundle location and concurrently verified by FHD , Spotter) N/A N/A -13. Spotter to FHD: "Location is _-___" FHD to Spotter: "agree, -" Spotter to FHD: "correct" N/A N/A -' 14. NOTE: The verifications in the following two steps may be performed in 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 I NLSROJPM2035 <C STANDARD ELEMENT§!Ef en FHD, VERIFY the following, SLACK CABLE Light is lit Grapple is centered over bail handle Hoist Position indication agrees with Attachment 2 for item seated in Fuel Pool Storage Rack Grapple appears seated on bail handle using underwater camera for component seated in cask THEN DIRECT RPO to engage i grapple. <C en Z :::) e: ... CI) CI)e.Q e e o ::s OZ N/A N/A . N/A -16. 17. 18. , RPO, VERIFY the following SLACK CABLE Light is lit. (CUE IF simulated:
Slack Cable Light is lit.) Grapple is centered over bail handle. ! N/A Verifies SLACK CABLE light is lit. Verifies SLACK CABLE light is lit. N/A -N/A ---(CUE IF simulated:
Grapple is I centered over bail handle.) ---19. Hoist Position indication agrees with Attachment 2 for item seated in Fuel Pool Storage Rack. . (CUE IF simulated:
Hoist I Position indicates Verifies hoist position is between 198" and 196". (Depending on calibration, Unit 1 is about 196"-197" and Unit 2 is about 198") , SRRS: 30.105 (when utilized for operator initial or continuing Page 11 of 14 I NLSROJPM2035 e :r...l-CI) CI)oe(soC (/)oe(ELEMENT STANDARD STEP (/) S §z ::::) Oz I 0 20. Grapple appears seated on ball handle using camera for component in N/A N/A -21. Grapple is ENGAGE (CUE IF simulated: grapple is THEN WHEN directed by FHD, --22. FHD to RPO: "engage RPO to FHD: "understand, engage FHD to RPO:
--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). (CUE IF simulated: If asked; L 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 STEP ELEMENT 26. After the candidate starts raising the bundle, provide the STANDARD -s:: -l-CI) CI)e:( e oC l-CJ)e:( e e CJ) Z o :::s:::l OZ 1 . STOP raising the hoist 2. We are simulating that the hoist has automatically stopped moving. 3. The HOIST LOADED HOIST JAM lights are Cue If asked: Hoist load cell . indicates 1190 Ibs. I I 27. IF during hoist operation
- a HOIST JAM light comes on, THEN movement shall be stopped immediately AND lowered until HOIST JAM Light goes out, THEN the Fuel Handling Director shall be stopped immediately AND lowered until HOIST JAM Light goes out, THEN the Fuel Handling Director shall be contacted for instruction.
Cue: After the candidate lowers the hoist, provide the following cue: liThe hoist Jam light is out." RPO immediately stops attempting to raise the bundle AND RPO immediately stops attempting to raise the bundle AND RPO lowers the hoist until Hoist Jam light goes out, AND The FHD is notified 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 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. Prerequisites of S97.0.M have been met. All encoders are enabled for the bridge, trolley and hoist. This JPM is written from the standpoint that the LSRO is operating the refuel platform as RPO. Refuel Floor Secondary Containment is not required. There are NO irradiated components grappled to any refueling platform hoist. The Aux Hoists are full up with no tools attached. 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. All Prerequisites of FH-106, Core Component and Irradiated Item Movement-No Core Transfer, are complete as applicable.
INITIATING CUES: 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. You are to PERFORM (simulate if Refuel Platform is not operable) this activity as the Refuel Platform Operator. 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. Task description and number, JPM description and number are identified. Knowledge and Abilities (K/ A) references are included. Performance location specified. (in-plant, control room, simulator, or other) Initial setup conditions are identified. Initiating cues (and terminating cues if required) are properly identified. Task standards identified and verified by SME review. Critical steps meet the criteria for critical steps and are identified with an asterisk (*). Verify the procedure(s) referenced by this JPM reflects the current revision:
Procedure S97.0.K Rev: Procedure S97.0.M Rev: Verify cues both verbal and visual are free of conflict. Verify performance time is accurate If the JPM cannot be performed as written with proper responses, then revise the JPM. When .JPM is initially validated, sign and date JPM cover page. Subsequent validations, sign and date below: SME /
Date SME /
Date SME /
Date SRRS: 30.105 (when utilized for operator initial or continUing training)
Page 2 of 24 NLSR02083Revision 000 REVISION RECORD (Summary) Revision 00 N/ A TRAINEE BRIEFING Periorm PJB lAW HU-AA-1211. Ensure Roles and Responsibilities are covered Ensure trainee understands that in order to examine requirements of the LSRO program, they may be asked to switch roles during the JPM. Ensure Safety is covered Ensure Human Periormance Fundamentals are covered. BRIDGE SETUP INSTRUCTIONS ENSURE there is NO conflict with scheduled Refuel Floor and/or Fuel Pool work. ENSURE personnel required for periormance of S97.0.M are in attendance. PERFORM PREREQUISITES of S97.0.M. Bridge operation will be in Manual. ENSURE there is NO potential for contact with the Auxiliary Platform during periormance of any section of this procedure. PERFORM the applicable sections of S97.1.A. PERFORM FH-106. PERFORM PRECAUTIONS of S97.0.M. 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: 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. Prerequisites of S97.0.M have been met. All encoders are enabled for the bridge, trolley and hoist. This JPM is written from the standpoint that the LSRO is operating the refuel platform as RPO. Refuel Floor Secondary Containment is not required. There are NO irradiated components grappled to any refueling platform hoist. The Aux Hoists are full up with no tools attached. 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. All Prerequisites of FH-106, Core Component and Irradiated Item Movement -No Core Transfer, are complete as applicable.
INITIATING CUES: 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. You are to PERFORM (simulate if Refuel Platform is not operable) this activity as the Refuel Platform Operator. You are to perform Bridge Moves in Manual. TASK ST ANDARD(S): 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: _________________ Evaluator's Signature:
______________
_ Date: _____SRRS: 3D.1 05 (when utilized for operator initial or continuing Page 6 of 24 I\ILSR02083Revision 000 JPM Start Time: __ Critical Element(s) indicated by "*,, in Performance Checklist.
-t:: I , G) G)I-e Jl (/)<C STEP ELEMENT STANDARD e e (/) Z o :::s;::) OZ Provide candidate with a copy of S97.0.M I Obtain current revision of Current revision of S97.0.M 1. obtained.
-I S97.0.M --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.
I !Pickup Location -Fuel Pool I\J/A 2. Storage Rack or Cask Pit I N/A N/A -, Spotter to RPO: "next location is _-___" 3. I , RPO to Spotter: "understand, _-___" I
- to RPO: "correct" *4. POSITION Refuel Platform Mast over desired core Refuel Platform positioned component in accordance dummy fuel bundle at Core Component Move designated on the Core Component Move Sheet OR as (CUE IF simulated:
Refuel directed by the evaluator. Platform is positioned over dummy fuel ---I I 5. NOTE: The following step may be performed anytime prior , setting grapple on
- bail in step N/A -SRRS: 30.105 (when utilized for operator initial or continuing training)
Page 7 of 24 NLSR02083Revision 000 e ... -(U (U<< E.c (f)<<STANDARD ELEMENT STEP E E (f) Z o ::J::J .Oz IF HMI screen is THEN RPO, VERIFY "Current Location" displayed 6. RPO, VERIFY the "Current HMI screen matches intended Location" displayed on HMI rack location.
screen matches intended rack i location.(CUE IF simulated:
Location" displayed intended rack
---*7. LOWER grapple until grapple near Grapple lowered near (CUE IF simulated: i has been lowered and is the bail --i 8. ENSURE grapple is open. Grapple (CUE IF simulated:
Grapple Verify indicating Ught is NOT
- Camera indicates grapple is open. ---i SRRS: 3D.1 05 (when utilized for operator initial or continuing training)
Page 8 of 24 NLSR02083Revision 000 c ... -I CD CD c( E.!l U)c(STANDARD ELEMENT STEP E E U) Z o :::J:J U Z CAUTION 9. Grapple switch guard on LH Controller side of head interferes with DBG bail handle when component's bail handle between the DBG legs pickup component's bail is perpendicular to DBG Grapple guard can interfere with Spent Fuel rack label pipe Contact of grapple guard cause permanent damage proximity switch electric I\J/A causing refuel platform to be inoperable.
Maintain switch guard from adjacent seated DBG handle OR rack label SBG bail handle will always perpendicular to DBG handle in core. Therefore, pickup of SBG's in pool, must be oriented with guard opposite corner of 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 Grapple rotated and with . (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 i i NLSR02083Revision 000 STEP ELEMENT *11. Slowly LOWER grapple until SLACK CABLE Light is lit. (CUE IF simulated:
SLACK i CABLE Light is lit) 12. FHD &Spotter, PERFORM Concurrent Verification of proper core component location AND orientation. (CUE IF simulated:
Dummy bundle location and orientation STANDARD Grapple is lowered, SLACK CABLE Light is lit. I\I/A s:: -l-CJ.) CJ.)e(l-E.Q tJ) tJ) e( EE z o :::::J (J Z::::;) concurrently verified by FHD & i N/A N/A Spotter)i -I 13. Spotter to FHD: "Location is --" i 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 performed in parallel.
N/A N/A Note to the Steps 4.8.8 (for the FHD and Spotter) and 4.8.9 (for the RPO) of the procedure have the actions and they may be performed in parallel.
This JPM is evaluating the After the verifications are a cue needs to be given to direct the RPO to engage the SRRS: 30.105 (when utilized for operator initial or continuing training)
Page 10 of 24 NLSR02083Revision 000 ..-.--... I: ... -(I) (I)e..Q U)c(ELEMENT STANDARD STEP ee, U) Z . 0 ::::J.:l Z'(J I 15. FHD, VERIFY the following, SLACK CABLE Light is lit Grapple is centered bail Hoist Position agrees with Attachment for item seated in N/A Pool Storage Rack Grapple appears on bail handle underwater camera component seated in i i THEN DIRECT RPO to N/A N/A engage grapple. -16. RPO, VERIFY the following N/A I N/A I -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 lit. (CUE IF simulated:
Grapple is centered over bail handle.) i---19. Hoist Position indication agrees Verifies hoist position with Attachment 2 for between 198" and seated in Fuel Pool ! (Depending on calibration, Unit Rack. 1 is about 196"-197" and Unit (CUE IF simulated: is about 198") Position indicates --20. N/A i Grapple appears seated on bail I handle using camera for component ' in I N/A I N/A -I I SRRS: 30.105 (when utilized for operator initial or continuing training)
Page 11 of 24 NLSR02083Revision 000 e: -(1) (1)<< E.Q Cf)ELEMENT STANDARD I STEP I I Cf) E E Z o ::J::::;) OZ i *21. Grapple is ENGAGE (CUE IF simulated: grapple is THEN WHEN directed by FHD, ---22. FHD to RPO: "engage RPO to FHD: "understand, engage FHD to RPO:
---23. FHD & RPO, PERFORM Peer Verify GRAPPLE Check that Light is ENGAGED Light is (CUE IF simulated: GRAPPLE ENGAGED Light --I 24. RPO to FHD: "engaged light FHD to RPO: "agree, engaged light RPO to FHD:
-*25. Slowly RAISE load while Slowly raise ensuring FUEL LOADED is lit (fuel/dummy bundle (CUE IF simulated:
If asked; Fuel Loaded light is lit.) ---I ALTERNATE PATH STARTS NOTE: As part of the next step the candidate will assume the role of the -"" SRRS: 3D.1 05 (when utilized for operator initial or continuing training)
Page 12 of 24 NLSR02083Revision 000 <en E E STEP ELEMENT STANDARD <en z E ::s fiI! :::::J Oz U i i ! 26. WHEN HOIST POSITION indicates between 100" and 50", THEN, CUE: 1 . STOP raising the hoist 2. We are simulating that hoist has automatically 3. For the purpose of this you are now performing the Per S97.0.M step of the Student will reference S97.0.K 3. PAR representative that a hoist tube hang-up is likely cause of the hoist 4. IF requested, screen RIGHT (interlock status) displaying a FAULT
- 5. IF requested, screen on (HMI) indicates a red fault detected button is lit. I Note: The following steps are per S97.0.K I 27. Obtain current revision Cue: Once the trainee Current revision of S97.0.K demonstrates the ability to obtained.
locate the current revision of the procedure, provide him/her a copy. I -! 28. Correct revision of procedure IN/A 'being used. N/A I i 29. i Procedure printed on white i I paper. I N/A I N/A * --N/A 1-N/A -I SRRS: 3D.1 05 (when utilized for operator initial or continuing training)
Page 13 of 24 i I NLSR02083Revision 000 c ...(J) (J)<C E,c tJ) EE I STEP I ELEMENT I STANDARD . <C I tJ) Z o ::s::J OZ i I 30. Briefing performed as required.
N/A I Cue: If asked; brief was ---performed during the job PJB. ! 31. To avoid extensive damage, slow OR Jog only shall be used N/A ! i I approaching any wall OR N/A I N/A i -obstruction.
- 32. NOTE: ConditionaIIF
... THEN that are not applicable steps to be skipped N/A . direction of the IF .. THEN shall be marked N/A N/A ' ! N/A -initialed.
i I 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. NOTE: 35. The performance steps of this procedure are into the following that may be N/A FAULTS AND ALARMS. 4.3 PLC OVERRIDE 4.5 BYPASSING A 4.6 RESETTING A DISABLED i ENCODER 4.7 CALIBRATING N/A i 1 i N/A I ENCODER(S) SRRS: 3D.1 05 (when utilized for operator initial or continuing training)
Page 14 of 24 NLSR02083Revision 000 c: ... -CI) CI)<<e.Q<n<<ELEMENT STANDARD I§TEP z<n e I :::J IOZ.0 I i 36. NOTE: 1. The PLC monitors faults AND alarms. "System Fault Screen" button indicates operation (no faults/alarms the system). When a fault alarm condition occurs, "System Fault Detected" button will appear. Touching "System Fault Detected" displays the N/A N/A -FAULTS" screen. 37. NOTE: 2. Touching the "FAULT" "ALARM" button activated N/A"SYSTEM FAULTS" displays popup i N/A
- N/A i ! !explaining the condition.
- 38. Caution: Troubleshooting system should not preclude N/A action to place the . AND/OR associated load in
- N/A I\I/A !!i safe condition.
- 39. To respond to a system I fault/alarm condition, I\I/A ! --PERFORM the following:
- 40. VERIFY "System Detected" button is Verifies "System on Operator Touch Detected" button is illuminated on Operator Touch Screen. (Cue: System Fault detected -button is illuminated} -II SRRS: 30.105 (when utilized for operator initial or continuing training)
Page 15 of 24 NLSR02083Revision 000 .... e ...l-Q) Q)<< E.Q tJ)STANDARD STEP ELEMENT E E tJ) Z I 0 :l::l OZ I 41. NOTE: Buttons on the FAULTS screen are as Normal condition: N/A Fault condition:
Red Alarm condition: backlight N/A I N/A -! *42. TOUCH "System Fault Detected" AND VERIFY "SYSTEM FAUL T" screen appears with individual System faulValarm condition( s). (Cue:"System Fault" screen appears. (Show Applicant ATTACHMENT A>>) i *43. TOUCH the activated "FAULT/ALARM" button(s)
AND VERIFY pop-up screen is displayed explaining the condition. (Cue: "System Fault indicates HOIST TUBE HANGUP (Show Applicant AlTACHMENT B>>) 44. REFER to Appendices for possible causes AND effects on equipment AND potential follow i up actions for responding to the I faulValarm condition.
Touches "System Fault Detected" and Verifies the fault is displayed.
i --Touches button for activated fault and Verifies the explanation of the fault condition.
--REFER to APPENDIX 1 LIMERICK PLATFORM I RESPONSE TABLE SRRS: 3D.1 05 (when utilized for operator initial or continuing training)
Page 16 of 24 NLSR02083Revision 000 I-<C STANDARD I <C I en ELEMENT STEP lij en z ::> oz* I (.) I 45. Review initiating conditions:
1.Hoist hang up detected 2.Hoist was not moving transition zone AND did Reviews maintain a stable load (Cue if simulated:
Hoist indication reads -46. Hoist motion inhibited I Review effect on equipment
-47. 1 Review POTENTIAL FOLLOW . N/A UP ACTIONS I N/A I N/A -:. 48. 1 . IF picking up test THEN RESET Fault per I N/A I : N/A I N/A I 4.2 of this procedure.
- 49. 2. CHECK cables and hose proper config. and Verifies cables and hoses (Cue: The PAR proper configuration has verified the cables 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 indication is (Cue if simulated:
Load reads (Cue: For the purpose of this JPM, you are now performing __
of the RPO). Reads Load Gauge and identifies it is reading normal 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:( fJ) I l-e:( fJ) Z ::J -e: ... CI) CI)E.o EE o ::::I OZ *51. 4. IF no problem is detected, CLEAR fault by moving hoist using Travel Override.
Cue: The hoist raises and the hoist tube hangup fault has I cleared Attempt to clear fault by moving hoist using Travel Override.
---I NOTE: The following steps are from S97.0.M I *52. 53. Slowly RAISE load while ensuring FUEL LOADED Light is lit (fuel/dummy bundle only). (CUE IF simulated:
Raised to Normal-Up}
NOTE: Raises load slowly to normal-up
---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 be terminated.
N/A 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 1 NLSR02083Revision 000 c:: l-CI) CI)E.c (/)<C STANDARD ELEMENT STEP E E (/) Z o ::::> OZ 54. IF operating in Full Auto AND use of QUICK AUTO is desired, THEN PERFORM the N/A N/A -55. N/A . N/A .TOUCH "QUICK AUTO" . N/A 56. I NJA N/A N/A TOUCH "AUTO RUN" -57. WHEN prompted, THEN N/A i N/A . N/A RELEASE joystick CONTINUE raising until is fully raised, THEN NORMAL UP Light is Slowly raise to (CUE IF simulated:
Raised
---59. GO TO appropriate "Release Location" section of this Trainee goes to Section 4.12 I I procedure as directed by FHD. ---60. 4.12 RELEASE FUEL POOL STORAGE OR CASK N/A N/A -61. NOTE: I F a fuel assembly is transferred to the Cask Pit loading into a Dry Canister, AND platform is operating in Automatic mode, THEN N/A platform will automatically with the bundle centered the Cask. At that point, positioning of the fuel bundle necessary to properly locate bundle in the desired Shielded Canister N/A N/A ilocation.
i SRRS: 3D.105 (when utilized for operator initial or continuing training)
Page 19 of 24 I i I
---I NLSR02083Revision 000 e::: ...l-Q) Q)<C I-e.a en<CSTANDARD STEP I e §z en oz::J 0 I 62. Spotter to FHD: "location is _---" FHD to Spotter: "agree, _-___" . Spotter to FHD: "correct" --I POSITION core component over desired location Refuel Platform positioned accordance with location deSignated on the Component Move Component Move Sheet or (Cue IF simulated: directed by the Platform is positioned over release location)
---64. NOTE: The following step may be N/A performed anytime prior to ! component insertion in step N/A I N/A I-I 4.12.5. 65. IF HMI screen is THEN RPO, VERIFY "Current Location" displayed Verifies the current location HMI screen matches matches the move sheet rack location. (ref. instructions from (Cue IF simulated: location displayed matches the i intended rack location)
-66. Caution: Grapple switch guard on LH Controller side of head interferes with seated DBG bail handle N/A handled component's handle is perpendicular to (Cue IFsimulated:
There is interference. N/A N/A -I SRRS: 3D.1 05 (when utilized for operator initial or continuing training)
Page 20 of 24 NLSR02083Revision 000 STEP ELEMENT 67. Caution: Grapple guard can also interfere with Spent Fuel Pool rack label pipe couplings. (Cue IF simulated:
There is no interference. ) 68. Caution: Contact of grapple guard can cause permanent damage to proximity switch electric cable causing refuel platform to be inoperable. (Cue IF simulated:
There is no interference.)
l-e:{STANDARD UJ N/A N/A N/A ...... s:: l-CP CP e:{ e,OI g e ::J:;:) OZ , N/A -N/A: 69. *70. 71. Caution: Maintain switch guard away from adjacent seated DBG bail handle OR rack label pipe couplings. (Cue IF simulated:
There is no interference.}
ROT ATE core component as necessary to achieve proper orientation. (Cue IF simulated:
Component rotated.)
N/A N/A NOTE: Component may be inserted into the fuel rack, up to hoist position "30", in parallel with i verification of core component I location and orientation.
I N/A N/A N/A -N/A -: -SRRS: 3D.105 (when utilized for operator initial or continuing training)
Page 21 of 24 L NLSR02083Revision 000 t:: ... -(1) (1)e.o STANDARD ELEMENT e e o :J OZ 72. FHD & Spotter, PERFORM Concurrent Verification of proper core component location AND orientation.
N/A (Cue IF simulated:
4.12.4 is i complete,
_ _.J.___________
_+_-N-/A_+-N-/A_+------1
- 73. FHD to RPO: "lower RPO to FHD: "understand, lower FHD to RPO:
---, *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 NI A 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 you to rais_e_.g",,--ra-Lip--,--ple_,
I 77, l!PO, VERI __...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 i NLSR02083Revision 000 ....c: << CI) CI) E,c U)<<STEP ELEMENT STANDARD E E U) Z o :J::;, OZ I 1 78. SLACK CABLE Light is Verifies slack cable light (Cue IF simulated:
Slack light is ---79. Component elevation appears equivalent to other stored components in the Verifies elevation is (Cue IF simulated:
to other components in appears at the same as other components in ---80. Hoist Position indication with Attachment 2 for seated in Fuel Storage Hoist Position indicates OR ISFSI (Cue IF simulated:
- position indicates ----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 Receives communication FHD to release (Cue IF simulated:
FHD you to release 1 --.--. 83. VERIFY grapple is Verifies grapple (Cue IF simulated:
Grapple
- I 1 -:-1 84. Slowly RAISE grapple verifying FUEL Slowly raises grapple remains verifies fuel loaded light remains NOT lit. (Cue IF simulated:
Grapple *
--SRRS: 30.105 (when utilized for operator initial or continuing training)
Page 23 of 24 I -I NLSR02083Revision 000 tJ) Z ::;) ----.. --ELEMENT RPO to FHD: "clear" FHD to RPO: "agree clear" RPO to FHD: "correct" FHD & RPO, PERFORM Peer Check that grapple is clear of component. (Cue IF simulated:
I agree, grapple is clear.) .-.--.--.-.
STANDARD peer check with FHD Performs that grapp Ie is clear. You have met the termination criteria for this JPM CUE: I'd like you to raise the 9 rapple to Normal-up
- 85. 86. ....r: ... Q) Q)e.Q e e o :;, OZ JPM Stop Time: SRRS: 3D.105 (when utilized for operator initial or continuing training)
Page 24 of 24 NLSR02083Revision 000 INITIAL CONDITIONS: 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. Prerequisites of S97.0.M have been met. All encoders are enabled for the bridge, trolley and hoist. This JPM is written from the standpoint that the LSRO is operating the refuel platform as RPO. Refuel Floor Secondary Containment is not required. There are NO irradiated components grappled to any refueling platform hoist. The Aux Hoists are full up with no tools attached. 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. All Prerequisites of FH-1 06, Core Component and I rradiated Item Movement -No Core Transfer, are complete as applicable.
INITIATING CUES: 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. You are to PERFORM (simulate if Refuel Platform is not operable) this activity as the Refuel Platform Operator. 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 Install Rod Position Test Box 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. Task description and number, JPM description and number are identified. Knowledge and Abilities (KIA) references are included. Performance location specified. (in-plant, control room, or simulator) Initial setup conditions are identified. Initiating and terminating cues are properly identified. Task standards identified and verified by SME review. Critical steps meet the criteria for critical steps and are identified with an asterisk (*). Verify the procedure referenced by this JPM matches the most current revision of that procedure:
Procedure Rev. __
Rev.
Rev. __ Verify cues both verbal and visual are free of conflict.
- 10. Verify performance time is accurate 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 Date SME I Date SME I Date SRRS: 30.105 (when utilized for operator initial or continuing Page 2 of 7 NLSROJPM2029 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 Operator's Name: __________
Job Title: 0 SED 0 SM OSRO 0 RO o ST AliA 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 SRO Only:
ONo Time Critical:
DYes
References:
- 1. ST-6-097-630-*, Core Alteration Testing for Offloading, Shuffling and Reloading the Core Testing Environment:
D Simulator 0 Control Room 0 In-Plant D Testing Method: Simulate 0 Estimated Time to Complete:
20 minutes Actual Time Used:
EVALUATION Were all the Critical Elements performed satisfactorily?
o Yes 0 The operator's performance was evaluated against the standards contained in this JPM, and been determined to be: 0 Satisfactory 0
Comments:________________________
_ Evaluator's Name: ______________Evaluator's Signature:
Oate __SRRS: 3D.1 05 (when utilized for operator initial or continuing training)
Page 4 of 7 NLSROJPM2029 JPM Start Time: ___ ELEMENT STANDARD SAT UNSAT Comment Number Evaluator notes:
- 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.
- 1. Perform the following to install test box in Auxiliary Equipment Room N/A N/A 2. REQUEST Reactor Operator to select rod 38-59. CUE: Unit RO reports that rod 38-59 is selected.
LSRO requests the Unit RO select rod 38-59. 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 I NLSROJPM2029 UNSAT STANDARD I SAT ELEMENT comment' Number
- IF using single rod test Single Rod Test box switch moved box, THEN position test box as OTHERWISE ENTER N/A. ROD 38-59 00 N/A N/AIF using 4-rod test box, THEN POSITION test box switches as follows, OTHERWISE ENTER N/A. N/A N/A 6. All test box switches initially in the DOWN position.
N/A N/ACable end 1,0 (Rod 59) switch in the UP position.
N/A N/ACable end 1 ,0 (Rod 59) switch in the UP Test box cannon+ plug cable to connector 63 at panel *OC615 B). CONNECT test box Test box group cannon plug is connected to 63. SRRS: 30.105 (when utilized for operator initial or continuing Page 6 of 7 I NLSROJPM2029 ELEMENT STANDARD SAT UNSAT Comment Number 10. REQUEST Reactor Operator to verify that indicated position of rods 38-59 AND 34-59 is 00 on the 4 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. Reactor Operator Requested to verify that indicated position of rods 38-59 AND 34-59 is 00 on the 4 rod display. OR PMS Control Rod Position Screen. 11. VERIFY the following at panel *OC616 Activity Control No's 1 AND 2: N/A N/A 11a. Rods Not Full In, Box FI LEDs are not Lit CUE: Rods Not Full In, Box FI LEDs are not Lit Rods Not Full In, Box FI LEDs are verified not lit 11b. Grapple Load, Box PG LEDs are not Lit CUE: Grapple Load, Box PG LEDs are not Lit Grapple Load, Box PG LEDs verified not lit 11 c. Overcore, Box Pc LEDs are not Lit . CUE: Overcore, Box Pc LEDs I are not Lit Overcore, Box Pc LEDs verified 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. Task description and number, JPM description and number are identified. Knowledge and Abilities (KIA) references are included. Petiormance location specified. (in-plant, control room, simulator, or other) Initial setup conditions are identified. Initiating cues (and terminating cues if required) are properly identified. Task standards identified and verified by SME review. Critical steps meet the criteria for critical steps and are identified with an asterisk (*). Verify the procedure(s) referenced by this JPM reflects the current revision:
Procedure Rev: Procedure Rev: Procedure
________ Procedure Verify cues both verbal and visual are free of conflict. Verify petiormance time is accurate If the JPM cannot be petiormed as written with proper responses, then revise the JPM. When JPM is initially validated, sign and date JPM cover page. Subsequent validations, sign and date below: SME /
Date SME /
Date SME /
Date SRRS: 3D.1 05 (when utilized for operator initial or continuing Page 2 of 5 NLSR02087 RevOOO REVISION RECORD (Summary) Revision 00 N/A SIMULATOR SETUP INSTRUCTIONS N/A TASK CONDITIONS:
Unit 1 is in OPCON 5 GP-13, Control Rod Drive/ Control Rod Blade Outage Maintenance Coordination is in progress: 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 Control Rod Blade Shuffle/Replacement is in progress per Section 3.2 "CRB SHUFFLE! REPLACEMENT ONLY", and Attachment 2 (page 1 of 6) 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 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 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 Testing Method: D Simulate [8J Estimated Time to Complete:
20 minutes Actual Time Used: EVALUATION Were all the Critical Elements performed satisfactorily?
DYes The operator's performance was evaluated against contained within this JPM and has been determined to be: D Satisfactory D
Comments:______________________________Evaluator's Name: ________________ 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
- f G)G)<< E.D t/)STANDARD STEP. ELEMENT E 111 t/) z E ::J *::>> o Z i o
- CUE: OUTAGE Requests permission to remove IControl Rod Blade 1. NtA . I'JtA ! *2. 3.2.3 VERIFY that no CRD is performed on the 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 surrounding work locations 22-27 cannot be removed to CRB inform Outages Services i i 3. CUE: This is OUTAGE ::t SERVICES I we do not have permission to remove Control Rod Blade NtA NtA I 4. CUE: OUTAGE Requests identification of Control Rod Blades that can NtA scheduled for . while Control Rod Drive : is removed NtA NtA i -*5. 3.2.3 VERIFY that no CRD is performed on the 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 i work locations prior to CRB removal. i I. .LYou have met the termination criteria for this JPMJPM 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: 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 Control Rod Blade Shuffle/Replacement is in progress per Section 3.2 "CRB SHUFFLE/ REPLACEMENT ONLY", and Attachment 2 (page 1 of 6) 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. Task description and number, JPM description and number are identified. Knowledge and Abilities (K/ A) references are included. Performance location specified. (in-plant, control room, simulator, or other) Initial setup conditions are identified. Initiating cues (and terminating cues if required) are properly identified. Task standards identified and verified by SME review. Critical steps meet the criteria for critical steps and are identified with an asterisk (*). Verify the procedure(s) referenced by this JPM reflects the current revision:
Procedure ON-120 Rev: Procedure S97.0.M Rev: Verify cues both verbal and visual are free of conflict. Verify performance time is accurate If the .JPM cannot be performed as written with proper responses, then revise the JPM. When ..IPM is initially validated, sign and date ..IPM cover page. Subsequent validations, sign and date below: SME /
Date SME /
Date SME /
Date SRRS: 3D.1 05 (when utilized for operator initial or continuing training)
Page 2 of 12 NLSR02080Revision 000 REVISION RECORD (Summary) Revision 00 NI A SIMULATOR SETUP INSTRUCTIONS NI A for In plant TASK CONDITIONS: New Fuel Receipt is in progress A New Fuel Bundle is ready for pickup in the Unit _North fuel preparation machine and release in the spent fuel pool Prerequisites of S97.0.M have been met The refueling platform is in operation and positioned over the fuel preparation machine 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 GGT AS 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 ST AliA !: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
_____ Rev: 19 Procedure
...=.0=.:.;.M'_'__
_____ Rev: 28Actual 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: EVALUATION Were all the Critical Elements performed satisfactorily?
DYes The operator's performance was evaluated against contained within this JPM and has been determined to be: o Satisfactory 0
Comments:_______________________________Evaluator's Name: _________________ 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.
e ... -l-Q) Q)e(l-E,c e( tn ELEMENT STANDARD STEP E E Z tn o :::s::)1 OZ I 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 Verify fuel prep machine is carriage is fully
- 1. VERIFY Fuel Prep Machine lowered !(Note: Normally performed by i CUE: Fuel Prep Machine NMD, not the LSRO)
- Carriage is fully lowered I-2. CAUTION: Use extreme care to avoid entanglement of main mast or N/A grappled fuel bundle with fuel inspection and test equipment 1 I-located in the vicinity of the fuel -i* prep machines. Carefully POSITION Platform Mast over fuel machine in accordance The bridge is positioned over Core Component Move Sheet. the fuel prep machine. 1 CUE: The bridge is positioned
.-i i* over the fuel prep machine. i *4. LOWER grapple until grapple near RPO directed to Lower CUE: RPO directed to Lower until the grapple is near bail the grapple until the grapple in handle near the bail handle.
- grapple is lowered, and : encoder reads 157 :-1 I SRRS: 3D.1 05 (when utilized for operator initial or continuing training)
Page 5 of 12 NLSR02080Revision 000 I I iTfet (J)(J) STEP ELEMENT STANDARD et en E en z . 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 CUE: Spotter has verified The component location AI\JD orientation.
bundle is in the North Fuel Prep Machine, and the bundle is oriented north east. Concurrent I Verification is satisfied for this I step of the JPM --I *9. FHD, VERIFY the following, N/A N/A . N/A i 9.a
- SLACK CABLE Ught is lit SLACK CABLE Light is verified I CUE: SLACK CABLE Light is lit lit 9.b
- Grapple is centered over bail handle Grapple is verified centered I CUE: Grapple is centered over over the bail handle I -I !the bail handle I i .. -.. SRRS: 3D.105 (when utilized for operator initial or continuing training)
Page 6 of 9.c i NLSR02080Revision 000 STANDARD STEP ELEMENT Hoist Position indication with Attachment 2 for seated in fuel prep Hoist position verified i CUE: Hoist position indicates 167.5 inches 10. RPO, VERIFY the following,
- SLACK CABLE Light is lit
- Grapple is centered over
- Hoist Position agrees with Attachment 2 N/A item seated in fuel prep machine. CUE: RPO verified: CABLE Light is lit, Grapple centered over the bail and Hoist position . 167.5 inches ! I t-CP CP<< E..Q (f) << (f) Z E :J (.)Oz i ------I *11. THEN WHEN directed by FHD, ENGAGE grapple FHD Directs RPO to ENGAGE CUE: RPO is directed to . engage grapple. Grapple : engaged. ---12. FHD &RPO, PERFORM Check that ENGAGED Light is Grapple control switch verified CUE: RPO verifies Grapple to have green backlight engaged light is light, Check is satisfied for this of the JPM i_I __ -SRRS: 3D.1 05 (when utilized for operator initial or continuing training)
Page 7 of 12 NLSR02080Revision 000 ...C G.I G.I E..o STANDARD ELEMENT E E o ::s OZ
- 13. Slowly RAISE load VERIFY FUEL LOADED Light RPO directed to Slowly RAISE load AND VERIFY FUEL CUE: RPO is directed to LOADED Light is Raises the bundle and FUEL LOADED light is I Bundle is slowly being 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 Assembly, exit S97.0.M enter CUE, If Asked: No Fuel ARM are in alarm No fuel was ---15. Obtain copy of ON-120, Fuel Procedure ON-120 Obtained Handling Problems -Procedure
- 16. Refer to section for: IF a fuel bundle OR new Fuel (Pin) is dropped or N/A AND no other symptoms present THEN PERFORM I following:
! 17. NOTIFY Health Physics to evaluate radiological Health Physics notified CUE: Health Physics has evaluate radiological I notified to evaluate I 18. NOTIFY Reactor Engineering.
I Reactor Engineering notified CUE: Reactor Engineering been
! ..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: New Fuel Receipt is in progress A New Fuel Bundle is ready for pickup in the Unit _North fuel preparation machine and release in the spent fuel pool All prerequisites are complete, with FH-106 and S97.0.M in progress The refueling platform is in operation and positioned over the fuel preparation machine 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 eeT AS SRRS: 3D.105 (when utilized for operator initial or continuing training)
TRANSFER AUTHORIZATION FOR FH-106 TRAINING USE ONLY RECORD TYPE #3B.1 08 Unit LIMERICK GENERATING STATION UNIT 1 Date ##/##/## Title TRAINING CCTAS Page _1_ of_1 #A## MV U# TRAINING USE ONLY Written By: TRAINING USE aNL Y Reviewed By: TRAINING USE aNL Y Authorized By: TRAINING USE aNL Y STEP NO. COMPONENT MOVE FROM ORIENT MOVE TO SERIAL NO. 1 LYN521 NFPM NE L2SPENT C-21 ORIENT FHD sw -RPO CRO DATE TIME -. SRRS: 3D.1 05 (when utilized for operator initial or continuing training)
TRANSFER AUTHORIZATION FOR FH-106 TRAINING USE ONLY RECORD TYPE #3B.108 Unit LIMERICK GENERATING STATION UNIT 2 Date ##/##/## Title TRAINING CCTAS Page _1_ of _1 #A## MV U# TRAINING USE ONLY Written By: TRAINING USE aNL Y Reviewed By: TRAINING USE aNL Y Authorized By: TRAINING USE aNL Y STEP NO. COMPONENT MOVE FROM ORIENT MOVE TO SERIAL NO. 1 LYN521 NFPM NE L1 SPENT C-21 I-----ORIENT FHD sw RPO CRO DATE TIME 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. Task description and number, JPM description and number are identified. Knowledge and Abilities (KIA) references are included. Performance location specified. (in-plant, control room, simulator, or other) Initial setup conditions are identified. Initiating cues (and terminating cues if required) are properly identified. Task standards identified and verified by SME review. Critical steps meet the criteria for critical steps and are identified with an asterisk (*). Verify the procedure(s) referenced by this JPM reflects the current revision:
Procedure EP-AA-100S Rev: Procedure EP-AA-111 Rev: Verify cues both verbal and visual are free of conflict. Verify performance time is accurate If the JPM cannot be performed as written with proper responses, then revise the ..IPM. When JPM is initially validated, sign and date JPM cover page. Subsequent validations, sign and date below: SME /
Date SME I Date SME I 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 NI A SIMULATOR SETUP INSTRUCTIONS This JPM can be performed in any quiet area 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 coolant temperature 167 of
- Secondary Containment Closure is not established
- 3. The following sequence of events occurs: "28" RHR Pump trips. Restart attempts are unsuccessful "28" Reactor Recirculation Pump is started. Reactor coolant temperature is 195°F and rising. Cause of "28" RHR Pump trip identified as breaker fault. The breaker will be swapped out. Reactor coolant temperature is 201°F and rising. "28" RHR Pump restarted.
Reactor coolant temperature is 225°F and going down. INITIATING CUE This task is Time Critical This JPM will start when you tell the evaluator that you are aware of task conditions and are ready to begin. The starting time will be 0323. 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 SRO Only:
ONo Time Critical:
ONo Reference{s):
Procedure EP-AA-1008 Rev: 17 Procedure EP-AA-111 Rev: 15Actual 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: EVALUATION Were all the Critical Elements performed satisfactorily?
DYes The operator's performance was evaluated against contained within this JPM and has been determined to be: o Satisfactory 0
Evaluator's Name: _______________________ 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: ELEMENTI ,..---I I IF another SRO is requested to perform an independent Peer CUE: A Peer Check will not be provided for this .... l-s:: ... C1) C1) <C E JJ STANDARD CJ) E E CJ) Z :::> o ::J OZ 1. Review the Initiating Conditions EAL Matrix( s) used to classify applicable to the operating mode event *2. Determine Threshold Value has been met or exceeded, Determine Alert initiating 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 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 INITIAL CONDITIONS:
- 1. Unit 1 is at 100% power 2. Unit 2 plant conditions are as follows:
- Day 4 of refueling outage
- Reactor coolant temperature 167 of
- Secondary Containment Closure is not established
- 3. The following sequence of events occurs: "28" RHR Pump trips. Restart attempts are unsuccessful "28" Reactor Recirculation Pump is started. Reactor coolant temperature is 195°F and rising. Cause of "28" RHR Pump trip identified as breaker fault. The breaker will be swapped out. Reactor coolant temperature is 201°F and rising. "28" RHR Pump restarted.
Reactor coolant temperature is 225°F and going down. INITIATING CUE: This ...'PM will start when you tell the evaluator that you are aware of task conditions and are ready to begin. No prior classifications or notifications have been made. You are required to: Make the highest classification based on the given plant conditions AND 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. Task description and number, JPM description and number are identified. Knowledge and Abilities (KIA) references are included. Performance location specified. (in-plant, control room, simulator, or other) Initial setup conditions are identified. Initiating cues (and terminating cues if required) are properly identified. Task standards identified and verified by SME review. Critical steps meet the criteria for critical steps and are identified with an asterisk (*). Verify the procedure(s) referenced by this JPM reflects the current revision:
Procedure TSG-4.1 Procedure
_______Rev: Verify cues both verbal and visual are free of conflict. Verify performance time is accurate If the ,JPM cannot be performed as written with proper responses, then revise the J PM. When JPM is initially validated, sign and date JPM cover page. Subsequent validations, sign and date below: SME I Date SME I Date SME I Date SRRS: 30.105 (when utilized for operator initial or continuing training)
Page 2 of 7 NLSR02082Revision 000 REVISION RECORD (Summary)
- 1. Revision 00 Nt A SIMULATOR SETUP INSTRUCTIONS
- 1. Nt A 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 ST ANDARD(S):
1 st 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: ___________________ Evaluator's Signature:
_________________
_ Date: ____SRRS: 3D.1 05 (when utilized for operator initial or continuing training)
Page 4 of 7 STEP ELEMENT STANDARD I <C (/) <C (/) Z ::;) -I: ... (I) CI)EJ:l E E o ::s OZ LGS OPERATIONAL CONTINGENCY GUIDELINES TSG-4.1 ATTACHMENT 1 INTERNAL SPENT FUEL POOL MAKEUP STRATEGY I 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. 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 ---NLSR02082Revision 000 JPM Start Time: ___ Critical Element(s) indicated by "*,, in Performance Checklist SRRS: 30.105 (when utilized for operator initial or continuing training)
Page 5 of 7 I
NLSR02082Revision 000 ..
STEP ELEMENT 3. NOTE: 400 ft of 3" hose is staged in each cabinet, one along the north wall of the Unit 1 fuel floor behind the reactor services office AND the second near the PCMs on the east end of the Unit 2 refuel floor. To obtain the 500 gpm makeup flow rate 2 -3" hoses are required.
Two different hose routing options are provided below. Refer to Figure 1 AND Figure 2 for fire standpipe locations.
IF hose on refuel floor is inaccessible, additional 3" hose can be obtained from the B.5.b Hose Trailer. 4. OPTION 1-ADD Fire Water to spent fuel pool using two (2) Fire System standpipes located I on refuel floor as follows: STANDARD -_.. N/A NOTE: Initial conditions direct performance of OPTION "ADD Fire Water to spent fuel pool using two (2) Fire System standpipes" N/A s::: ... -.... CI) CI)oe(.... E.Q CJ)oe( E E CJ) Z o :s:::::I OZ ----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 (Figures 1 and 2 show standpipe locations)
- CUE: Hoses have been routed Hoses routed from two different fire standpipes to Unit 1 fuel pool SRRS: 30.105 (when utilized for operator initial or continuing training)
Page 6 of 7
--6 NLSR02082Revision 000
-e l-II) II)e:(l-E..Q e:( UJ STANDARDE E UJ Z o ::::s:J Z U 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 ---REMOVE existing hose at fire standpipe AND reducing Hose rem o ved from standpipe coupling from 1 st selected fire AND redu c ing coupling standpipe valve. removed f r om 1 st standpipe CUE: Hose is removed from valve Standpipe, and coupling is removed from standpipe valve ---_. CONNECT 2 %" X 3" Storz adapter to fire standpipe valve AND CONNECT hose to Storz ada p ter connected to fire adapter. standpipe valve and hose connected to adapter CUE: Storz adapter connected to fire standpipe valve and hose connected to adapter --*9 Slowly OPEN 1 ST 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 Refuel Floor ARM Return to 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. Task description and number, JPM description and number are identified. Knowledge and Abilities (KIA) references are included. Performance location specified. (in-plant, control room, or simulator) Initial setup conditions are identified. Initiating and terminating cues are properly identified. Task standards identified and verified by SME review. Critical steps meet the criteria for critical steps and are identified with an asterisk (*). Verify the procedure referenced by this JPM matches the most current revision of that procedure:
Procedure Rev. __ Procedu re Rev. Procedure Rev. 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 Date SME Date SME I Date SRRS: 3D.1 05 (when utilized for operator initial or continuing Page 2 of 10 NLSRO,JPM2086 REVOOO.ooc REVISION RECORD (
SUMMARY
)
Rev 000, N/A INITIAL CONDITIONS: Unit _ Reactor pressure vessel disassembly is in progress per M-041-200 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. 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 Page 3 of 10
NLSROJPM2086 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 KIA Number and Importance:
272000 G2.1.30 IR: 4.4 / Suggested Testing Environment:
Alternate Path: OVes SRO Only:
ONo Time Critical:
OVes
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 Testing Method: Simulate 0 Estimated Time to Complete:
20 minutes Actual Time Used:
EVALUATION Were all the Critical Elements performed satisfactorily?
o Yes 0 The operator's performance was evaluated against the standards contained in this .JPM, and been determined to be: 0 Satisfactory 0
Evaluator's Name: _____________________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 wo uld 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 on the equipment when the candidate identifies a ARM to be If the candidate asks for a Peer Check, inform them: "For the purposes of this ..IPM no Peer will be
- 3. If step 4C of this JPM is to be performed in the AER, a Copy of Unit Technical Specification be 1 . Obtain current revision of M-Current revision of M-041-200 041-200 Attachment 5 "REFUEL FLOOR Cue: Once the trainee demonstrates the ability to ARM RETURN TO SERVICE" obtained locate the current revision of the procedure, provide him/her a copy of Attachment 5 "REFUEL FLOOR ARM RETURN
- 2. NOTE: This activity returns N/A N/A N/A three (3) fuel floor ARMs to service (2 of which are Criticality Monitors).
SRRS: 3D.1 05 (when utilized for operator initial or continuing training)
Page 5 of 10 I NLSROJPM2086 SAT STANDARD UNSAT Comment Number ELEMENT 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 *K600,. Pool Plug Laydown Area EI 352 AND ARM RIS 29-M1-*K600, DIW Laydown Area EI 352 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 cause a spike and a set pOint alarm. For reason the operator shall in constant with the outage unit Operator while placing switches to the position.
IF this THEN the reset shall pressed SRRS: 3D.1 05 (when utilized for operator initial or continuing training)
Page 6 of 10 NLSROJPM2086 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 352, to the "OPERATE" position AND REMOVE Blue Equipment Status Tag. Mode Switch for ARM *K600, Steam Separator Area EI 352, to the "OPERATE" position AND REMOVE Blue Equipment 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 Status Tag. *5.a Mode Switch for ARM RIS30-M1-*K600, Steam Separator Area EI 352, Mode Switch for ARM 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 ELEMENT 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 STANDARD SAT UNSAT Comment Number *6.a Mode Switch for ARM ARM RIS 33-M1-*K600, Pool Plug Laydown Area E1352, placed "OPERATE" CUE: -Mode Switch will NOT rotate to "OPERATE" -White LOW light is lit. Mode Switch for ARM *K600, Steam Separator Area EI 352, rotated to "OPERATE *6.b Take action to identify broken component.
CUE: Actions have been taken to address Failed ARM IF Asked if task should be completed:
CUE: You are directed to continue with remaining ARM Take action to generate an IR, or contact Personnel contacted regarding failed 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 CUE: Mode Switch for ARM RIS 29-M1-*K600, DIW Head Laydown Area EI 352, placed "OPERATE" Mode Switch is in "OPERATE" Mode Switch for ARM *K600, Steam Separator Area EI 352, rotated to "OPERATE" Amber HIGH light is lit RO reports UNIT _ Refueling Area Hi Radiation Annuciator has be received When Mode switch in operate *7.b From CAUTION: Placement of the ARM's back to operate may cause a spike and a high set point alarm. IF this occurs THEN the reset shall be pressed ARM reset pressed CUE: Amber HIGH light is NOT lit RO reports UNIT _ Refueling Area Hi Radiation Annuciator has cleared. SRRS: 3D.1 05 (when utilized for operator initial or continuing training)
Page 9 of 10 NLSROJPM2086 ELEMENT I STANDARD SAT UNSAT Comment Number 7.c AND REMOVE Blue Equipment Status Tag. CUE: Equipment Status Tag is removed Equipment Status Tag is removed *8. CUE: Refuel Floor coordinator request you determine the Technical Specification implications, if any, of the failure of ARM RIS *K600,. Pool Plug Laydown Area EI352 Determine that failed ARM is a Criticality monitor, and Technical Specification 3.3.7.1 is applicable.
Determine that minimum channel 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 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. 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 Generation OJTITPE MATERIAL COVERSHEET TYPE: JPM QUALIFICATION MANUAL OJT MODULE D D NLSRO-3069 PROGRAM:*
NLSRO Initial and NLSRO Requal CODE#: REV#:: . 000 COURSE: NLSRO gwz TYPIST: AUTHOR:. G. W. Zellmer TITLE: . Bridge End Structure Panel Lineup APPROVALS:
S:;.l? /0 APPROVED FOR USE: EFFECTIVE DATE: __<.::>_---0
_--,,-__._....:.-0__ Date -(-/ () Date Date NAME: ISSUE DATE: Last First M.1. EMPLOYEE ID NO. COMPLETION DATE:
Training Review for Completeness:
LMS CODE: LMS ENTRY: Sig natu re/Date NLSRO-3069 RevOOO Page 1 of 9 EXELON PEACH BOrrOM ATOMIC POWER JOB PERFORMANCE POSITION TITLE: Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR:
234000-11
-NLSRO-3069 234000K5.01 RO: 2.9 SRO: 3.4 TASK DESCRIPTION:
Refuel Platform Pre Operational Checkoff List NOTES TO EVALUATOR: 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. System cues included in the performance checklist are to be provided to the examinee when no system response is available. JPM Performance "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). When performing "In-Plant" JPMs, no equipment will be operated without Shift Management approval. Satisfactory performance of this JPM is accomplished if: The task standard is met. JPM completion time requirement is met. 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. For time critical JPMs, completion within the estimated time (listed in paragraph 0.2) is required. The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee.
NLSRO-3069 Page 2 of9 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). 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. TOOLS AND EQUIPMENT Access to PBAPS procedure SO 18.1.C-2(3)
'Electrical, Mechanical, and Pneumatic Alignment
/ Checkout of Refueling Platform Access to Limerick procedure S97.1.A 'Electrical, Mechanical, and Pneumatic Alignment
/ Checkout of Refueling Platform Bridge, Trolley, and Main Hoist for Operation' 'Task Conditions
/ Prerequisites
&Initiating Cue' sheet REFERENCES SO 18.1.C-2(3)
Rev. 2; Electrical, Mechanical And Pneumatic Alignment/Checkout Of Refueling Platform S97 .1.A Rev. 21 'Electrical, Mechanical, and Pneumatic Alignment I Checkout of Refueling Platform Bridge, Trolley, and Main Hoist for Operation. TASK STANDARD Satisfactory task completion is indicated when SO 18.1.C-2(3) section 4.2 'Bridge End Structure Panel Lineup' is complete. Estimated time to complete:
20 minutes Non-Time Critical 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 Page 3 of 9 TASK CONDITIONS/PREREQUISITES The Refuel Platform is being returned to service following maintenance. 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. 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. INITIATING CUE The Control Room Supervisor directs you to perform the (Unit 2 / Unit 3) Refuel Bridge End Structure Panel Lineup in accordance with SO 1B.1.C-2(3) step 4.2. The Room Supervisor gives you permission to operate the components identified in SO as necessary to place the Refuel Platform into alignment with step 4.2 of SO NLSRO-3069 Page 4 of 9 H. PERFORMANCE STEP NO STEP ACT STANDARD Notes to Evaluator A In addition to the Task Conditions/Prerequisites and Initiating Cue Sheet, the examinee should also be given a copy of SO 18.1.C-2 or SO 18.1.C-3 as appropriate.
B. Evaluator may record the JPM start time here: 1 Verify the 2(3)OS947 A 'Main Disconnect Switch' is 'ON'. (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. 2[3].") S Verify the 2(3)OS947 A 'Main Disconnect Switch' is in the "ON" position.
- 2 Examinee moves the operating handle of the 2(3)OS947A in the up direction until handle is aligned with the 'ON' position label. (CUE: The component that you identified is in the condition that you described.)
S Operating handle of the 2(3)OS947A is moved from the 'Full Down -OFF' position to the 'Full Up --ON' position NLSRO-3069 RevOOO Page 5 of 9 STEP STEP NO 3 Verify the 2(3)OS261A
'Mono Hoist Disconnect Switch' is 'ON'. (CUE: The Disconnect 2(3)OS261A Disconnect Handle is in the 'Full Down' position.)
- 4 Examinee moves the operating handle of the 2(3)OS261A Disconnect in the up direction until handle is aligned with the 'ON' position label. (CUE: The component that you identified is in the condition that you described.)
5 Verify the CB-D 'Air Dryer Breaker' (CUE: The CB-D 'Air Dryer toggle is in the 'Full Up' 6 Verify the CB-2 'GFI Outlet Breaker' is 'ON'. (CUE: CB-2 'GFI Outlet Breaker' toggle is in the 'Full Up' position.)
7 Verify the CB-3 'GFI Outlet Breaker' is 'ON', (CUE: CB-2 'GFI Outlet Breaker' toggle is in the 'Full Up' position.)
8 Verify the 2(3)OS261 B 'Air Compressor Disconnect Switch' is 'ON'. (CUE: The 2(3)OS261B Disconnect . Handle is in the 'Full Up' position.
ACT S STANDARD Verify the 2(3)OS261A
'Mono Hoist Disconnect Switch' is in the 'ON' position.
S Operating handle of the 2(3)OS261A is moved from the 'Full Down -OFF' position to the 'Full Up --ON' position S Verify the CB-D 'Air Dryer Breaker' toggle is in the 'ON' position.
S Verify the CB-2 'GFI Outlet Breaker' toggle is in the 'ON' position.
S Verify the CB-3 'GFI Outlet Breaker' toggle is in the 'ON' position.
S Verify the 2(3)OS261 B 'Air Compressor Disconnect Switch' is in the "ON" position.
NLSRO-3069 RevOOO Page 6 of 9 STEP ACT STANDARD STEP NO *9 Verify the
'Main Hoist Pneumatic Valve' is (CUE: If the examinee attempting to operate the 'Main hand-wheel in the clockwise THEN provide the "The hand-wheel will not (CUE: When the examinee operating the hand-wheel for the Hoist' in the counter-clockwise THEN provide the following "The hand-wheel rotates in the clockwise direction until the moves away from the valve body % and resistance is felt; hand-wheel will turn any
- 10 Verify the 'Mono Hoist Pneumatic Shut-Off Valve' is OPEN. (CUE: If the examinee describes attempting to operate the 'Mono Hoist' hand-wheel in the clockwise direction, THEN provide the "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
'The hand-wheel rotates in the clockwise direction until the hand-wheel moves away from the valve body % inch and resistance is felt; hand-wheel will not turn any further.") Verify the 'Main Hoist Pneumatic Shut-Off Valve' is OPEN (hand-wheel rotated in the fully counter-clockwise direction).
Verify the 'Mono Hoist Pneumatic Shut-Off Valve' is OPEN (hand-wheel rotated in the fully counter-clockwise direction).
NLSRO-3069 RevOOO Page 7 of9 I STEP NO STEP ACT STANDARD 11 Notify the Control Room Supervisor that the Refuel Platform Bridge End Structure Panel Lineup has been completed in accordance with SO 18.1.C-2(3) step 4.2. (CUE: Acknowledge the report.) S Notify the Control Room Supervisor of task completion.
Note: Notification may be simulated as in-person or via radio / phone. 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: (CUE: If you were performing the Refuel Platform 'Bridge' End Structure Electrical Lineup at Limerick (S97.1.A section 4.3), Then what would be different between the actions you just performed I simulated here and what you would expect to do at Limerick?)
If the examinee asks for a copy of S97 .1.A, then provide the following: (CUE: Give the examinee a copy of S97.1.A.)
D The Bridge End Structure Panel Lineup verifications at PBAPS and at Limerick are similar. However, other than different models of equipment that would be actuated, the Bridge Structure End Panel Lineup verifications at Limerick include a check for each phase of the Bridge Surge Suppressor.
i Note to Evaluator
-The answer to the follow up question does not have to be answered by the trainee using the exact words that are shown above. Note to Evaluator As an Evaluator, ensure you have positive control of all exam material provided to the examinee ('Task Conditions I
& Initiating Cue' sheet' AND all procedures).
Under P -must S -must D -must 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 Page 8 of 9 Task Conditions I Prerequisites
& Initiating TASK CONDITIONS/PREREQUISITES The Refuel Platform is being returned to service following maintenance. 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. 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 Bridge End Structure Panel Lineup in accordance with SO 18.1.C-2(3) step 4.2. The Room Supervisor gives you permission to operate the components identified in SO as necessary to place the Refuel Platform into alignment with step 4.2 of SO NLSRO-3069 Page 90f9 EXELON Nuclear Generation OJT/TPE MATERIAL COVERSHEET TYPE: JPM D QUALIFICATION MANUAL D OJT MODULE Limited Senior Reactor Operator .CODE NLSRO-3068
-, ,"0 LSRO Initial & LSRO Requalification . G. W. Zellmer TYPist::*
gwz TITLE::' , Drywell to Reactor Well Bellows Failure APPROVALS:
Date APPROVED FOR USE: EFFECTIVE DATE: & I 1 0 I 1°---' NAME: ISSUE DATE: Last First M.I. EMPLOYEE 10 NO. COMPLETION DATE:
Training Review for Completeness:
LMS CODE: LMS ENTRY: SignaturelDate NLSR03068 RevOOO Page 1 of 16 EXELON PEACH BOTTOM ATOMIC POWER JOB PERFORMANCE 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 NOTES TO EVALUATOR: 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. System cues included in the performance checklist are to be provided to the examinee when no system response is available. JPM Performance "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). When performing "In-Plant" JPMs, no equipment will be operated without Shift Management approval. Satisfactory performance of this JPM is accomplished if: The task standard is met. JPM completion time requirement is met. 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. For time critical ..IPMs, completion within the estimated time (listed in paragraph 0.2) is required. The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee. 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 Page 2 of 16 B. TOOLS AND Access to either the 20C075 Panel OR the 30C075 Panel. Access to the PBAPS Alarm Response Procedure ARC-2(3)OC075 A-1 Seal Rupture Drain High Flow. Access to the PBAPS Alarm Response Procedure ARC-2(3)OC075 B-3 Skimmer Surge Tank Low Level. Access to the PBAPS Alarm Response Procedure ARC-2(3)OC075 B-1 Fuel Storage Pool High I Low Level. Access to the PBAPS Abnormal Operating Procedure AO 10.4-2(3)
Residual Heat Removal System -Fuel Pool to Reactor Mode. 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. Access to the PBAPS ON-124 'Fuel Floor and Fuel Handling Problems' procedure. Access to the Limerick Annunciator Response Procedure ARC-BOP-1 (2)OC222 03 Reactor Well Seal Rupture Drain Hi Flow. Access to the Limerick Annunciator Response Procedure ARC-BOP-1(2)OC222 B4 1 (2)BT20B Skimmer Surge Tank La Level. Access to the Limerick system procedure S53.3.A Direct Makeup to Fuel Storage Pool. Access to the Limerick System procedure S53.3.G Skimmer Surge Makeup and Letdown. Access to Limerick General Procedure GP-6.1 Shutdown Operations
-Refueling Core Alternation, and Core Off-Loading. Access to the Limerick System Procedure S51.B.L RHR Alternate Decay Heat Removal Startup and Shutdown. Task Conditions I PrereqUisites
& Initiating Cue' sheet (Evaluator understands to specify the JPM for either PBAPS Unit 2 or Unit 3. REFERENCES
- 1. ARC-2(3)OC075 A-1 Rev. 2, Seal Rupture Drain High Flow. ARC-2(3)OC075 B-3, Rev. 2, Skimmer Surge Tank Low Level. ARC-2(3)OC075 B-1 Rev. 2, Fuel Storage Pool High I Low Level. NLSR03068 Page 3 of 16 AO 10.4-2(3), Rev. 21 (20), Residual Heat Removal System -Fuel Pool to Reactor Mode. FH-74, Rev. 6, Actions in Response to an Unexpected Loss of Fuel Pool, Reactor Cavity, or Equipment Storage Pool Water Inventory. ON-124 Rev. 14 'Fuel Floor and Fuel Handling Problems' procedure. ARC-BOP-1(2)OC222 D3 'Reactor Well Seal Rupture Drain Hi Flow' Revision O. ARC-BOP-1(2)OC222 B4 '1 (2)BT208 Skimmer Surge Tank Lo Level' Revision 1. S53.3.A Direct Makeup to Fuel Storage Pool Revision 17. S53.3.G Skimmer Surge Makeup and Letdown Revision 22. GP-6.1 Shutdown Operations
-Refueling Core Alternation, and Core Off-Loading Revision 20 (Unit 1) / Revision 23 (Unit 2). S51.8.L RHR Alternate Decay Heat Removal Startup and Shutdown Revision 15. TASK STANDARD 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. Estimated time to complete:
20 minutes Non-Time Critical 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. TASK CONDITIONS/PREREQUISITES Reactor is in MODE 5. Fuel Pool Gates to the Reactor Cavity are removed. Fuel Pool water level is 232' 10" Refueling Operations are in progress (grapple change out is taking place). NLSR03068 Page 4 of 16 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. The 'A' RHR Pump is the ONLY available Pump for Shutdown Cooling I Injection. The Fuel Pool Cooling system has been shutdown. The Reactor Water Clean Up System has been shutdown. I&C has just been dispatched to investigate the loss of camera functions on the Refuel Floor. The overhead crane is NOT in use. 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 PaneI2(3)OC075.
NLSR03068 Page 5 of 16 H. PERFORMANCE STEP STEP ACT STANDARD NO Notes to Evaluator 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).) 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)".) JPM start time may be recorded here: _____________
_ 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 Page 6 of 16 STEP STEP ACT STANDARD NO 4 Notify the Unit Reactor Operator that alarm "Seal Rupture Drain High Flow" is in on the 2(3)OC075 Panel. S Inform the Unit Reactor Operator that the alarm "Seal Rupture Drain High Flow" is in. Note to evaluator
-The*communications (Cue: Evaluator acknowledges the examinee's report.) may be made using the radio or 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 (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 Fuel Pool/ Reactor Cavity water then state that --"Fuel Pool water Reactor Cavity level is now at 232' 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 examinee's report AND inform examinee that Equipment Operators been dispatched and the Operators will perform ALL water additions and ALL required Immediately following report (or candidate enters FH-74), then (Cue: Provide the examinee with 2[3]OC075 Panel Conditions sheet [Attachment NLSR03068 RevOOO Page 7 of 16 STEP NO STEP ACT STANDARD 7 Identify alarm condition(s).
P/D Identifies Alarm B-3 in alarm. 8 Obtain a copy of the Alarm Response Card ARC-2(3)OC075 B-3 (Cue: If examinee does NOT use the alarm response procedure located in the ARC Book (at the Panel), then the evaluator may provide the examinee with a copy of ARC-2[3]OC075 B-3 AFTER the examinee discusses the method for obtaining the procedure from the EDMS system or other controlled location.)
P/D Obtain a copy of ARC-2(3)OC075 B-3 from the ARC book at the Panel or from the EDMS system or other controlled location.
9 Identifies Level indicator LI-2(3)695 indicates pegged low << 0 inches). S Verify that a "Low Level" condition is 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 alarm "Skimmer Surge Tank Low Level" is in on the 2(3)OC075 Panel and that the Skimmer Surge Tank water level is 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.) S Inform the Unit Reactor Operator that the alarm "Skimmer Surge Tank Low Level" is in and report the indicated level on 2(3)695. NLSR03068 RevOOO Page 8 of 16 STEP NO STEP ACT STANDARD *11 Notify the Control Room that the currently operating RHR Pump ('A') must be immediately shutdown. (Cue: Evaluator acknowledges the examinee's report and informs the examinee that the running RHR pump is being shutdown.)
Immediatelll following 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".") S If level is low and RHR SDC -Fuel Pool to Reactor mode is in operation in accordance with AO 10.4-2(3), then immediately shutdown the running RHR Pump. 12 Identify alarm condition(s).
P/D Identifies Alarm B-1 in alarm. 13 Obtain a copy of the Alarm Response Card ARC-2(3)OC075 B-1 (Cue: If examinee does NOT use the alarm response procedure located in the ARC Book (at the Panel), then the evaluator may provide the examinee with a copy of ARC-2[3]OC075 B-1 AFTER the examinee discusses the method for obtaining the procedure from the EDMS system or other controlled location.)
P/D Obtain a copy of ARC-2(3)OC075 B-1 from the ARC book at the Panel or from the EDMS system or other controlled location.
14 Visually check Fuel Pool water level. (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 231' 10".") S Visually check Fuel Pool level to determine if the alarm is due to high water level or low water level. NLSR03068 RevOOO Page 9 of 16 15 16 17 18 STANDARD ACT STEP Notify the Unit Reactor Operator that the alarm "Fuel Storage Pool Low Level" is in on the 2(3)OC075 Panel and that the Fuel Pool water level is at the 231' 10" mark and going down. (Cue: Evaluator acknowledges the examinee's report.) Recommends entering the FH-74 "Actions in Response to an Unexpected Loss of Fuel Pool, Reactor Cavity, or Equipment Storage Pool Water Inventory" procedure. (CUE: Acknowledge the recommendation to enter the FH-74 procedure AND state "The Control Room Supervisor directs you to evaluate the Refuel Floor conditions and execute the Refuel Floor portions of the FH-74 procedure.")
Obtain a copy of the FH-74 procedure (CUE: When the examinee states that he would find a copy of the procedure in the Refuel Floor Office area, or on the Refuel Platform, or from the EDMS system, then provide the examinee with a copy of the FH-74 procedure.)
Notifies Shift Management to enter 124 "Fuel Floor and Fuel Handling Problems". (CUE: Acknowledge the recommendation to enter the ON-124 procedure AND state "The Control Room Supervisor directs you to evaluate the Refuel Floor conditions and execute the Refuel Floor portions of the ON-124 procedure.")
Notify the Unit Reactor Operator that the alarm "Fuel Storage Pool Low Level" is in and report current Spent Fuel Pool water level. S Recommend that FH-74 "Actions in Response to an Unexpected Loss of Fuel Pool, Reactor Cavity, or Equipment Storage Pool Water Inventory" be implemented.
S Obtain a copy of the FH-74 procedure from the EDMS system or other controlled location.
D Notify Shift Management to enter ON-124 "Fuel Floor And Fuel Handling Problems".
S I! NLSR03068 RevOOO Page 10 of 16 I I STEP STEP NO Obtain a copy of the ON-124 procedure 19 (CUE: When the examinee states that he would find a copy of the procedure in the Refuel Floor Office area, or on the Refuel Platform, or from the EDMS system, then provide the examinee with a copy of the ON-124 procedure.)
Notify Rad Protection to continuously evaluate radiological conditions on the Fuel Floor and recommend evacuation or allowance to continue with steps 20 (CUE: Rad Pro Technician acknowledges your direction and begins surveys.)
- 21 Direct all personnel non-essential for placing the Fuel Floor in a radiologically safe condition to immediately evacuate the Fuel Floor. STANDARD ACT Obtain a copy of the ON-124 procedure from the EDMS system or other D
- controlled location.
S Notify Radiation Protection to continuously evaluate radiological conditions on the Fuel Floor and recommend evacuation or allowance to continue with the remaining procedural steps. S All personnel not essential to place the Refueling Floor in a radiologically safe condition shall immediately evacuate the Fuel Floor. Notes to Evaluator 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).
NLSR03068 Page 11 of 16 i STEP NO STEP ACT STANDARD 22 Follow-up Question (Evaluator to ask the examinee): "If you had similar conditions at Limerick unit 1 -Refueling Operations in progress and an ARC-BOP-10C222 03 'Reactor Well Seal Rupture Drain Hi Flow' alarm in concurrent with Reactor Cavity water level going down, then how would your actions be different than what you just demonstrated here? If the LSRO examinee wants to see a copy of the Limerick Procedure BOP-10C222 03 'Reactor Well Seal Rupture Drain Hi Flow' alarm response card, then: (CUE: Present a copy of 10C222 03 to the LSRO examinee.)
o Answer: The Limerick procedures directions are similar. The Limerick BOP-10C222 03 will direct the operator to verify operation of the inflatable Reactor Well seals. The PBAPS Seals are NOT inflatable and therefore there are no directions to verify seal operability. (Examinee may include that the ON-120 procedure would be entered at Limerick vice the ON-124! FH-74 procedures at PBAPS [not required for correct answer].)
Note to Evaluator
-The answer to the follow up question does not have to be answered by the trainee using the exact 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 P -must S -must o -must 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 Page 12 of 16 TASK CONDITIONS
& PREREQUISITES Reactor is in MODE 5. Fuel Pool Gates to the Reactor Cavity are removed. Fuel Pool water level is 232' 10" Refueling Operations are in progress (grapple change out is taking place). 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. The lA' RHR Pump is the ONLY available Pump for Shutdown Cooling I Injection. The Fuel Pool Cooling system has been shutdown. The Reactor Water Clean Up System has been shutdown. I&C has just been dispatched to investigate the loss of camera functions on the Refuel Floor. The overhead crane is NOT in use. 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.
NLSR03068 Page 13 of 16 Attachment
- 1 -Panel 2(3)OC075 Panel Initial Indications
(#1) SEAL RUPTURe: FUEL STORAGE FUEL DRAIN POOL STORAGE POOL HIGH FLOW HIGH/LOW LEVEL HI RADIATION BELLOWS LEAK SKIMMER HIGH FLOW SURGE TANK HIGH LEVEL SKIMMER GATE DRAIN SURGE TANK HIGH FLOW Flashin A 1 2 3 LI-2(3)695 250 200 150 100 50 0 LOW LEVEL '-------------'---------'-----
---...B G 'N FUEL POOL PUMP G 0 'B' FUEL POOL PUMP G 'C' FUEL POOL PUMP SKIMMER TANK ACK RESET TEST G8 G0 AUTO CLOSE OPEN STOP 0 START \) 000 HIGH PRESSURE AO-2(3)698 DECON PUMP FUEL POOL MAKEUP NLSR03068 RevOOO Page 14 of 16 Attachment
- 2 -Panel 2(3)OG075 Panel Indications
(#2) A B 1 2 3 ___200 ___150 ___100 ___50 SKIMMER TANK STOP HIGH DEGON CLOSE OPEN FUEL POOL SEAL RUPTuRE FUEL STORAGE *DRAIN .... POOL HIGH FlOW: HIGH/LOW LEVEL I i BELLOWS LEAK SKIMMER HIGH FLOW SURGE TANK HIGH LEVEL GATE DRAIN SURGI;TANK HIGH FLOW LOW:tEV!t:
i '\. Flashmg LI-2(3}695
___250 I FUEL STORAGE POOL HI RADIATION I FL HF:F, 'A' FUEL POOL PUMP 'B' FUEL POOL PUMP 'G' FUEL POOL PUMP AGK RESET TEST NLSR03068 RevOOO Page 15 of 16 Attachment
- 3 -Panel 2(3)OG075 Panel Indications A B Flashing 1 2 3
___.250 ___200 ___150 ___100 ___50
__.o SKIMMER TANK SEAL RUPTURE> FUEL STORA1fe FUEL POOL>DRAIN STORAGE POOL HIGHrLOW . HIGH/LOW LEVEL HI RADIATION SKIMMER BELLOWS LEAK I SURGE TANK i ;-, HIGH FLOW l HIGH LEVEL SKIMMER*GATE DRAIN SURGE TANK HIGH FLOW LOW LEVEL AUTO STOP @START 'A' FUEL POOL PUMP G G 'B' FUEL POOL PUMP G eG' FUEL POOL PUMP AGK RESET TEST HIGH PRESSURE AO-2(3)698 DEGON PUMP FUEL POOL MAKEUP NLSR03068 RevOOO Page 16 of 16 EXELON Nuclear Generation 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 Signaturmitle Date
- 1 I J (j APPROVED FOR USE: o EFFECTIVE DATE: 7 I I I 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 PEACH BOTTOM ATOMIC POWER JOB PERFORMANCE 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 NOTES TO EVALUATOR: 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. System cues included in the performance checklist are to be provided to the examinee when no system response is available. JPM Performance "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). When performing "In-Plant" JPMs, no equipment will be operated without Shift Management approval. Satisfactory performance of this JPM is accomplished if: The task standard is met. JPM completion time requirement is met. 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. For time critical JPMs, completion within the estimated time (listed in paragraph 0.2) is required. The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee.
NLSR03066 Rev Page 2 of 14
- 6. 7. 8. 9. 10. 11. 12. Verify the prerequisites of FH-35 and SO 18.1.A-2(3) are satisfied AND permission is obtained from Shift Supervision to perform dummy fuel bundle moves BEFORE the JPM begins (evaluator).
The evaluator must indicate on the 'Task Conditions/Prerequisites
& Initiating Cue' sheet which unit is to be used for the JPM (and have the appropriate CCTAS, procedures, and Prerequisites met if applicable).
This JPM may be used for PBAPS Unit 2 or Unit 3. However, the evaluator must make certain that all prerequisites and approvals are obtained on the unit that is going to be used prior to starting this JPM. 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.
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.
JPM paperwork that is used on the Refueling Bridge may be contaminated and not be available for record retention.
Unless the JPM Pre-job brief determines otherwise, if JPM material used on the Refueling Bridge becomes contaminated, then, it is acceptable for the JPM evaluator to transfer JPM notes/scores to a JPM summary sheet and destroy original JPM paperwork (AFTER accounting for ALL exam material).
The DA is in charge of all evolutions on that occur on the Refuel Platform.
It is required that the DA perform a Pre-Job Brief 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.
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).
Page 3 of 14 NLSR03066 Rev 000 B. C. D. E. F. TOOLS AND EQUIPMENT Task Conditions 1 Prerequisites and Initiating Cue Sheet Access to FH-6C 'Core Component Movement' procedure Access to SO 18.1.A -2(3) 'Operation of Refueling Platform' procedure Access to Unit 2(3) Tech Specs and Unit 2(3) Tech Spec Bases Access to ST-0-09A-2
'SBGT Subsystem Operability Test' Access to FH-35 'Control of Material Movement In the Fuel Pool' Access to Limerick Unit 1 Tech Specs Access to Limerick Procedure FH-105 'Core Component Movement -Core Transfers' REFERENCES FH-6C Rev. 63 'Core Component Movement' PBAPS Tech Specs Unit 2(3) [Rev. 275/279] and Bases SO 18.1.A -2(3) Rev. 22 'Operation of Refueling Platform' procedure ST-0-09A-325-2 Rev. 5 'SBGT Subsystem Operability Test' FH-35 Rev 36 'Control of Material Movement In the Fuel Pool' Limerick Unit 1 Tech Specs (Rev. 198) Limerick procedure FH-105 Rev. 45 'Core Component Movement -Core Transfers' TASK STANDARD Satisfactory task completion is indicated when the Dummy Fuel Bundle is re-seated in the Spent Fuel Pool. Estimated time to complete:
25 minutes Non-Time Critical 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. TASK CONDITIONS/PREREQUISITES 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) Page 4 of 14 NLSR03066 Rev 000 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 <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> ago). There are NO irradiated components grappled to any Refuel Platform Hoist. The auxiliary hoists are full up. 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. 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. All applicable portions of SO 18.1.C-2(3)
'Electrical, Mechanical, and Pneumatic Alignment 1 Checkout of Refueling Platform' have been completed. 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 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. , For the entire evolution, you will treat the Dummy Fuel Bundle as if the Dummy Fuel Bundle is actual Recently Irradiated Fuel. You are to PERFORM this activity as the Refuel Platform Operator (RPO). NLSR03066 Rev Page 5 of 14 H. PERFORMANCE STEP NO STEP ACT STANDARD 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 <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 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 NO 1 STEP ACT STANDARD Position Refuel Platform Mast over desired core component in accordance with Core Component Transfer Authorization Sheet (CCTAS). P The Refuel platform is positioned over the dummy fuel bundle. Note to Evaluator
-If this JPM is being performed immediately following 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 grapple to bail alignment P The mast is rotated so that the grapple is aligned with the dummy fuel bundle bail handle. *5 Slowly lower hoist until SLACK CABLE light is lit. P The hoist is slowly lowered down over the bail of the dummy bundle. The SLACK CABLE light, located on the left hand console is verified ON. 6 CONCURRENT VERIFICATION FHD and Spotter perform concurrent verification of proper core component location and orientation.
P Proper core component location and orientation concurrently verified. (This standard is N/A for the RPO unless the RPO is also acting as the Spotter) Note 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 NO STEP ACT STANDARD 7a
- SLACK CABLE light is lit N/A N/A 7b
- Grapple is centered over bail handle N/A N/A 7c
- Hoist position indication agrees with Attachment 9 for item seated in Fuel Pool Storage Rack N/A N/A 7d
- THEN direct RPO to engage grapple N/A N/A (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 handle P Grapple is verified to be centered over the bail handle 8c
- Hoist position indication agrees with Attachment 9 for item seated in Fuel Pool Storage Rack (-188") P Hoist position indication is verified to be in agreement with Attachment 9 (-188") *8d
- WHEN directed by FHD, engage grapple P Grapple is engaged by using the Hoist Control Station 9 FHD and RPO perform Peer Check that "GRAPPLE ENGAGED" light is lit P GRAPPLE ENGAGED light is verified (peer checked with FHD) to be 'ON'. NLSR03066 Rev 000 Page 8 of 14 STANDARD STEP ACT STEP NO *10 Slowly raise load while verifying HOIST LOADED light is lit. (CUE: When the Hoist Loaded indicating light comes on [while the Fuel Assembly is being raised, Then to the examinee provide the following 'The Fuel Handling Director notifies you 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 Dummy Fuel Bundle. (CUE: If examinee recommends that the FHD stop movement of all Fuel, then acknowledge the recommendation.) (CUE: If examinee recommends that the FHD notify the control room / Reactor Operators of the 'Stop Order' for Fuel Movement and/or the re-insertion of the Fuel Assembly, then acknowledge the recommendation. ) (CUE: If the examinee recommends inserting the Recently Irradiated Fuel Assembly (Dummy Fuel Bundle) into it's previous location, then acknowledge the recommendation. ) ++++++++++++++++++++++++++++++
When the examinee has completed their recommendations, then the EVALUATOR will notify the FHD that the FHD may now direct the examinee to re-insert and re-seat the Recently Irradiated Fuel Assembly (the Dummy Fuel Bundle). ++++++++++++++++++++++++++++++
The dummy fuel bundle is slowly raised (using the Hoist Control Station) while ensuring the HOIST LOADED light is 'ON'. P **********************************************
When the cue is given, then that marks the start of the Alternate Path. **********************************************
FH-6C step 7.1.5 -[FHD] shall determine the proper immediate corrective action if an abnormal event or instrument response occurs. P FH-6C step 7.1.7 -[FHD] shall be responsible for review of the prerequisites to this procedure to assure that all applicable prerequisites are met during core component movement.
FH-6C step 5.11 -SBGT system is in compliance with the requirements of Tech Spec 3.6.4.3. (FH-35 steps 4.7 &9.6) Tech Spec 3.6.4.3 Condition
'E' (Two SBGT subsystems inoperable during movement of Recently Irradiated Fuel assemblies in the Secondary Containment or during OPDRVs): Required Action E.1 -Suspend movement of Recently Irradiated Fuel Assemblies in secondary containment (immediately) . This is NOT a CUE. The evaluator to i let the actual FHD know that the JPM is 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 ACT STEP STEP N/A N/A 12 FHD and Spotter perform Concurrent 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) Fuel Assembly may need to be either 'Pull' (twist left I twist right) motion P 13 Spotter and RPO discuss the 'Push' or 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).
The dummy fuel bundle is lowered (using and the 'SLACK CABLE' light is lit. *14 P Lower hoist until component is seated 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) .
- N/A 15 N/A FHD verify the following:
N/A N/A 15a
- SLACK CABLE light is lit N/A 15b N/A* Component elevation appears equivalent to other components in the 15c N/A N/A* Hoist position indication agrees with Attachment 9 for item in Fuel Pool Storage N/A N/A 15d
- THEN direct RPO to release grapple NLSR03066 Rev 000 Page 10 of 14 STEP NO STEP ACT STANDARD 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 equivalent to other stored components in the rack P Bundle is verified to be at the same elevation as other fuel bundles in the racks. 16c
- Hoist position indication agrees with Attachment 9 for item seated in Fuel Pool Storage Rack P Hoist position indication is verified to be in agreement with Attachment 9 (-188 inches) *16d
- THEN WHEN directed by FHD, release grapple P Grapple is released by using the Hoist Control Station If necessary, the Evaluator will ask the FHD to direct the examinee to release the grapple. (This is a possible cue for the FHD -NOT a cue for the examinee.)
17 Verify grapple is open. P GRAPPLE ENGAGED light is verified to be 'OFF'. 18 Slowly raise hoist while verifying
'HOIST LOADED' light remains 'OFF'. P The grapple is slowly raised while verifying the 'HOIST LOADED' light remains 'OFF'. 19 Perform Peer Check with FHD to ensure grapple is clear of core components.
P Verify Grapple is clear of core components.
20 Examinee (RPO) notifies the FHD that the Recently Irradiated Fuel Assembly (Dummy Fuel Bundle) has been re-seated. (CUE: Acknowledge the report.) P Notify FHD of task completion.
NLSR03066 Rev 000 Page 11 of 14
22 STEP STEP ACT STANDARD NO Notes to Evaluator The performance portion of this JPM is complete; Stop Time may be recorded here: ____ 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: _____ 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. 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 6C or FH-35 procedures, Then provide the examinee with a copy of the (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 Page 12 of 14 STEP NO STEP ACT STANDARD 23 (Cue: After the above actions are complete, then ask the following question 'If the above conditions occurred at Limerick Unit 1 [two of the three SBGT fans failed], would you make the same stop-work determinations that you just made here at PBAPS (if not, how would the determinations be different)?' (Cue: If the examinee asks to see any [or all] of the below listed procedures, then provide the examinee with a copy of the requested procedure(s): -Limerick Unit 1 Tech Specs -FH-105 P All of the above work that was stopped due to the loss of the SBGT system (both SBGT subsystems) would also be stopped at Limerick under these conditions (exact wording not required).
However, at Limerick, the loss of two SBGT fans will cause these actions to apply to Both Limerick Unit 1 & Limerick Unit 2. At PBAPS, the loss of two SBGT fans will ONLY cause these actions to apply to either Unit 2 OR Unit 3 (depending on which SBGT Fans have failed). 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 P -must S -must D-must 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 Page 13 of 14 Task Conditions
/ Prerequisites and Initiating Cue TASK CONDITIONS/PREREQUISITES 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) 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 <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> ago). There are NO irradiated components grappled to any Refuel Platform Hoist. The auxiliary hoists are full up. 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. 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. All applicable portions of SO 18.1.C-2(3)
'Electrical, Mechanical, and Pneumatic Alignment
/ Checkout of Refueling Platform' have been completed. 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 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. For the entire evolution, you will treat the Dummy Fuel Bundle as if the Dummy Fuel Bundle is actual Recently Irradiated Fuel. You are to PERFORM this activity as the Refuel Platform Operator (RPO). NLSR03066 Rev Page 14 of 14
. EXELON Nuclear Generation OJTlTPE MATERIAL COVERSHEET D OJT MODULE JPM ; 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:
EFFECTIVE DATE: ,I ,__......:{-.:o_
Date * " '-8110 Date 7 I C Date ro APPROVED FOR NAME: ISSUE DATE: Last First M.1. EMPLOYEE ID NO. COMPLETION DATE:
Training Review for Completeness:
LMS CODE: LMS ENTRY: Signature/Date NLSR03064 Rev 000 Page 1 14 EXELON PEACH BOnOM ATOMIC POWER JOB PERFORMANCE 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 NOTES TO EVALUATOR: 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. System cues included in the performance checklist are to be provided to the examinee when no system response is available. JPM Performance "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). When performing "In-Plant" JPMs, no equipment will be operated without Shift Management approval. Satisfactory performance of this JPM is accomplished if: The task standard is met. JPM completion time requirement is met. 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. For time critical JPMs, completion within the estimated time (listed in paragraph 0.2) is required. The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee.
NLSR03064 Rev Page 2 of 14
- 6. 7. 8. 9. 10. 11. 12. Verify the prerequisites of FH-35 and SO 18.1.A-2(3) are satisfied AND permission is obtained from Shift Supervision to perform dummy fuel bundle moves BEFORE the JPM begins (evaluator).
The evaluator must indicate on the 'Task Conditions/Prerequisites
& Initiating Cue' sheet which unit is to be used for the JPM (and have the appropriate CCTAS, procedures, and Prerequisites met if applicable).
This JPM may be used for PBAPS Unit 2 or Unit 3. However, the evaluator must make certain that all prerequisites and approvals are obtained on the unit that is going to be used prior to starting this JPM. This JPM is designed to have the examinee move the dummy fuel bundle using the Refuel Platform in 'manual' mode. However, if this JPM is performed in conjunction with loading the appropriate move sequence [section 4.5 of SO 18.1.A-2(3}], then this JPM may be performed with Refuel Platform set up for 'Semi-Automatic Operation' (section 4.6 of SO 18.1.A-2(3).
Regardless of how the Refuel Platform is moved, this 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.
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.
Most JPMs that involve the use of Concurrent Verification or Peer Checks are performed with the Concurrent Verification
/ Peer Checks being simulated (not leading the examinee).
This .JPM is different because an actual component is being moved in the Fuel Storage Pool. Therefore, all required verifications and checks will be performed per procedure.
Any errors by the examinee discovered during a Concurrent Verification
/ Peer Check will be documented by the JPM evaluator.
JPM paperwork that is used on the Refueling Bridge may be contaminated and not be available for record retention.
Unless the ..I PM Pre-job brief determines otherwise, if JPM material used on the Refueling Bridge becomes contaminated, then, it is acceptable for the JPM evaluator to transfer JPM notes/scores to a JPM summary sheet and destroy original JPM paperwork (AFTER accounting for ALL exam material).
The DA is in charge of all evolutions on that occur on the Refuel Platform.
It is required that the DA perform a Pre-Job Brief /2 Minute Drill with the RPO (LSRO examinee) for this evolution.
The Pre-Job Brief /2 Minute Drill are human performance tools that do NOT constitute inappropriate coaching or exam compromise.
Page 3 of 14 N LSR03064 Rev 000 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). TOOLS AND EQUIPMENT Unit 2 or Unit 3 Refueling Bridge accessible. HP coverage provided for the Dummy Fuel Bundle move (including RWP). Reactor Services support to provide: FHD and a Spotter Applicable portions of FH-35 completed (and documented) Refuel Bridge checked out in accordance with SO 18.1.C-2(3) Work Order C0222751 may be used as a reference for coordinating the support needed to move the Dummy Fuel Bundle in the Fuel Pool. Reactor Engineers to develop the CCTAS as required (three hard copies of the CCTAS are required). REFERENCES FH-35 Revision #36 'Control of Material Movement in the Fuel Pool' SO 18.1.A-2(3)
Rev. 22 'Operation of Refuel Platform' SO 18.2.A-2(3)
Rev. 3 'Shutdown of Refueling Platform' ON-114 Rev. 17 'Actual Fire Reported in the Power Block, Diesel Generator Building, Emergency Pump, Inner Screen or Emergency Cooling Tower Structures' Limerick Procedure S97.0.M Rev. 25 'Refueling Platform Operation' OU-AB-4001 Rev. #4 'BWR Fuel Handling Practices' TASK STANDARD 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 2(3). (NOTE -Evaluator must specify which PBAPS unit to perform/simulate the JPM.) Estimated time to complete:
40 minutes Non-Time Critical NLSR03064 Rev Page 4 of 14 DIRECTIONS TO EXAMINEE When given the initiating cue, perform the necessary steps to move the (Unit 2/ Unit 3) Dummy Fuel Bundle in accordance with the attached 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. TASK CONDITIONS/PREREQUISITES There are NO irradiated components grappled to any Refuel Platform Hoist. The auxiliary hoists are full up. All of the applicable Prerequisites for procedure FH-35 have been completed for Dummy Bundle transfer in the Spent Fuel Pool. All applicable Prerequisites of procedure SO 18.1.A-2(3) have been completed for Dummy Bundle transfer in the Spent Fuel Pool. All applicable portions of SO 18.1.C-2(3)
'Electrical, Mechanical, and Pneumatic Alignment
/ Checkout of Refueling Platform' have been completed. INITIATING CUE 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. 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 this activity as the Refuel Platform Operator.
NLSR03064 Rev Page 5 of 14
H. PERFORMANCE STANDARD STEP I ACT NO Notes to Evaluator A) Provide a copy of SO 18.1.A-2(3) and a copy of the CCT AS for dummy bundle movement prior to starting JPM. 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. JPM may be started from the associated Refueling Platform. 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). 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 . *1 Position Refuel Platform Mast over desired core component in accordance with Core Component Transfer Authorization Sheet (CCTAS). PIS The Refuel platform is positioned over the dummy fuel bundle. *2 Lower hoist until grapple is near bail. PIS 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. I PIS The backlight on the GRAPPLE ENGAGED switch is verified to be extinguished.
NLSR03064 Rev Page 6 of 14 7 STEP NO STEP ACT STANDARD 4 Rotate grapple as necessary to achieve grapple to bail alignment PIS The mast is rotated so that the grapple is aligned with the dummy fuel bundle bail handle. *5 Slowly lower hoist until SLACK CABLE light is lil. PIS The hoist is slowly lowered down over the bail of the dummy bundle. The SLACK CABLE light, located on the left hand console is verified ON. 6 CONCURRENT VERIFICATION FHD and Spotter perform concurrent verification of proper core component location and orientation.
PIS Proper core component location and orientation concurrently verified. (This standard is N/A for the RPO unless the RPO is also acting as the Spotter) NOTE The verifications in the following two steps may be performed in parallel.
FHD verify the following:
7a
- SLACK CABLE light is lit 7b Grapple is centered over bail handle 7c Hoist position indication agrees with Attachment 9 for item seated in Fuel Pool Storage Rack 7d THEN direct RPO to engage grapple (Cue: evaluator will have the FHD direct the examinee to engage the grapple.)
N/A N/A N/A N/A N/A N/A ! N/A N/A N/A N/A ! RPO verify the following:
See below 8 N/A I NLSR03064 Rev Page 7 of 14 STEP NO STEP ACT STANDARD Sa
- SLACK CABLE light is lit PIS SLACK CABLE light is verified to be ON Sb
- Grapple is centered over bail handle PIS Grapple is verified to be centered over the bail handle Sc *Sd
- Hoist position indication agrees with Attachment 9 for item seated in Fuel Pool Storage Rack
- WHEN directed by FHD, engage grapple PIS PIS Hoist position indication is verified to be in agreement with Attachment 9 ..Grapple is engaged by using the Hoist Control Station 9 FHD and RPO perform Peer Check that "GRAPPLE ENGAGED" light is lit PIS GRAPPLE ENGAGED light is verified (peer checked with FHD) to be 'ON'. *10 Slowly raise load while verifying HOIST LOADED light is lit (fuel only). PIS The dummy fuel bundle is slowly raised (using the Hoist Control Station) while ensuring the HOIST LOADED light is 'ON'. *11 Continue raising until grapple is fully raised, THEN verify Grapple NORMAL UP light is lit. PIS Continue raising the grapple to the full up position and verify that the Grapple NORMAL UP light is 'ON'. i 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. NLSR03064 Rev 000 Page 8 of 14 STEP STEP NO Position core component over location in accordance with Core Component Transfer Authorization Sheet (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 ACT PIS STANDARD The platform is positioned so that the dummy fuel bundle is hanging over the correct spent fuel pool storage location (per CCTAS) 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). 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']). 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). 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.
PIS The mast is rotated so that the dummy achieve proper orientation.
- 13 Rotate core component as necessary to fuel bundle is properly oriented (per CCTAS as appropriate).
NLSR03064 Rev Page 9 of 14 STEP STEP ACT STANDARD NO Notes to Evaluator 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 14 Verification of proper core component location and orientation 15 Spotter and RPO discuss the 'Push' or 'Pull' (twist left I twist right) motion required for seating the Fuel Assembly *16 Lower hoist until component is seated and the 'SLACK CABLE' light is lit. PIS PIS PIS Proper core component location orientation concurrently (This standard is N/A for the RPO unless the RPO is also acting as the Spotter) Fuel Assembly may need to be either pushed or pulled while being seated to . prevent the channel fasteners from I contacting the fuel rack. The dummy fuel bundle is lowered the Hoist Control Station) until component is seated and the CABLE light is
!
- The verifications in the following two steps may be performed in parallel (steps 17 & 18) . ! FHD verify the following:
17a SLACK CABLE light is lit 17b Component elevation appears equivalent to other stored components in the rack NLSR03064 Rev Page 10 of 14 i 17 STEP ACT STEP NIA NIA 17c
- Hoist position indication agrees with Attachment 9 for item in Fuel Pool Storage NIA 17d NIA* THEN direct RPO to release grapple NIA 18 RPO verify the following:
PIS i SLACK CABLE light is verified to be ON 18a
- SLACK CABLE light is lit I PIS 18b Bundle is verified to be at the same equivalent to other stored PIS* Component elevation appears elevation as other fuel bundles in the components in the rack racks. 18c PIS Hoist position indication is verified to be in with Attachment 9 for item seated
- Hoist position indication agrees agreement with Attachment 9 (-188 in Fuel Pool Storage Rack . inches) 18d PIS Grapple is released by using the Hoist release grapple
- THEN WHEN directed by FHD, 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 NO STEP ACT STANDARD 22 Verify completion of component transfer on CCTAS (as required N/A ). N/A 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. 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 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 Start/Stop Station. *24 Evacuate the Refuel Floor. S S The large red 'STOP' push button located on the Start/Stop Station is momentarily depressed.
The examinee evacuates the Refuel Platform and Refuel Floor. Notes to Evaluator 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). 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). 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 Page 12 of 14 STEP NO STEP ACT STANDARD 25 Follow-up Question (Evaluator to ask the examinee): (CUE: If you were moving a Limerick D The answer to the question is: The actions performed here for an evacuation due to a fire are the same that would be done at Limerick.
While there are minor Fuel Bundle [from one location in the Limerick Fuel Storage Pool to another location in the Limerick Fuel Storage Pool] and an announcement was made to evacuate the Refuel Floor due to a fire, how would the actions you just performed I simulated here be different if you were differences in the bridge controls between PBAPS and Limerick, in both places, the Refuel Platform must be in a 'safe' condition prior to evacuating (no irradiated fuel hanging from the Refuel Platform.
at Limerick [on a Limerick Refuel Platform])?
Note to Evaluator
-If the examinee asks for a copy of the Limerick Procedure
'S97.0.M 'Refueling Platform Operation', then: (CUE: Provide examinee with a copy of S97.0.M) Note to Evaluator
-The answer to the follow up question does not have to be answered by the trainee using the exact words that are shown above. Notes to Evaluator A) After the examinee has answered all 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 P -must S -must D-must I. TERMINATING CUE When the examinee has answered all follow-up questions, then the evaluator may terminate the JPM. NLSR03064 Rev Page 13 of 14 TASK CONDITIONS I PREREQUISITES AND INITIATING TASK CONDITIONS/PREREQUISrrES There are NO irradiated components grappled to any Refuel Platform Hoist. The auxiliary hoists are full up. All of the applicable Prerequisites for procedure FH-35 have been completed for Dummy Bundle transfer in the Spent Fuel Pool. All applicable Prerequisites of procedure SO 18.1.A-2(3) have been completed for Dummy Bundle transfer in the Spent Fuel Pool. 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 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. 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 this activity as the Refuel Platform Operator.
NLSR03064 Rev Page 14 of 14 EXELON NUCLEAR Nuclear Generation OJT/TPE MATERIAL 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:
Title Date I /
s/z. ftt-j/d Dale 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:
Training Review for Completeness:
LMS CODE: LMS ENTRY: Signature/Date
-I NLSR03065 Rev 000 Page 1 of 16 EXELON PEACH BOTTOM ATOMIC POWER JOB PERFORMANCE 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 . NOTES TO EVALUATOR: 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. System cues included in the performance checklist are to be provided to the examinee when no system response is available. JPM Performance "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). When performing "In-Plant" JPMs, no equipment will be operated without Shift Management approval. Satisfactory performance of this JPM is accomplished if: The task standard is met. JPM completion time requirement is met. 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. For time critical JPMs, completion within the estimated time (listed in paragraph 0.2) is required. The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee.
NLSR03065 Rev Page 2 of 16 Though not required, this JPM is designed to be given on the Refuel Floor and associated areas. TOOLS AND EQUIPMENT Copy of 'Conditions
/ Prerequisites And Initiating Cue' sheet Access to M-C-741-301
'Control Rod Blade, FSP And Control Rod Guide Tube Removal And Installation' Access to SO 1B.1.A-2(3)
'Operation of Refueling Platform' Access to S97.0.M 'Refueling Platform Operation' REFERENCES M-C-741-301 Rev. 26 'Control Rod Blade, FSP And Control Rod Guide Tube Removal And Installation' SO 1B.1.A-2(3)
Rev 22 'Operation of Refueling Platform' S97.0.M Rev. 27 'Refueling Platform Operation' TASK STANDARD Satisfactory task completion is indicated when the FSP is raised through the Top Guide. Estimated time to complete:
20 minutes Non-Time Critical 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. TASK CONDITIONS/PREREQUISITES Fuel shuffle part 1 has been completed on PBAPS Unit _ (Unit 2 I Unit 3). Control Cell 30-31 is having the Fuel Support Piece (FSP) removed using the PBAPS FSP Grapple & Grid Guide connected to the Monorail Hoist. Core Configuration is shown on the attached core view. The Reactor Cavity Work Platform (RCWP) is NOT installed. M-C-741-301 Attachment 11 is provided and was filled in when the first FSP replacements occurred (previous shift). NLSR03065 Rev Page 3 of 16
- 6. The CCTAS is approved (current step is provided -see below). I STEP CRO *
- I COMPONENT MOVED ORIENT MOVE ORIENT FHD RPO I DATE I TIME i NO. SERIAL NO. FROM TO 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. 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. 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). The Monorail Hoist is positioned over the Core at location 30-31. 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 [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 Page 4 of 16 H. PERFORMANCE Notes to ACT STEP STEP 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. 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 RPO is directed to "ENGAGE" the Grapple. Direct the RPO to 'ENGAGE' the FSP S Monorail FSP Grapple. (Cue: The component that you is in the condition that you (Cue: If asked for camera view, provide "No camera view is
- 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 anti-rotation pin at corner of control (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 the RPO that an 'Interlock Status *********************************************
Annunciator' is currently up and a 'Fault Lockout' condition.
The Note --Start Of Alternate Path *********************************************
Platform will NOT respond to controls.) (CUE: Provide the examinee with a of the 'Interlock Status Display' 11 NLSR03065 Rev Page 5 of 16 STEP NO STEP ACT STANDARD 3 Notify Control Room of the 'Fault Lockout' condition. (CUE: Acknowledge the report of the 'Fault Lockout' condition AND provide the following report "One of the OEM technicians (Original Equipment Manufacturer's technicians) opened a trolley deck cabinet door. The trolley deck cabinet doors are now closed AND the 'Fault Lockout' annunciator is clear. If there are NO other abnormal conditions present, then Shift Management is directing you to reset the P.L.C. AND to continue with the FSP Removal.)
S When operating equipment, If it does not perform as expected, then place the equipment in a safe condition and inform Shift Management.
- 4 Direct the RPO to 'depress the Refuel Platform 'START' pushbutton'. (CUE: "Refuel Platform 'START' pushbutton is depressed; all Refuel Bridge indications are as expected [as they were before the Fault Lockout condition
-Monorail Hoist is two [2] feet lower than the normal full up position].") (CUE: If examinee request maintenance to perform a checkout I diagnostic of the Bridge functions, then provide the examinee with the "Maintenance determines that all Bridge functions are operating normally.")
S RPO is direct to depress the Refuel Platform "START" pushbutton (to resume Platform operation).
Note to Evaluator
-Start pushbutton must be pressed to resume platform operation after 'Fault Condition is cleared (SO 18 .1.A-2[3]
Att. 1). *********************************************
Note --End Of Alternate Path *********************************************
NLSR03065 Rev 000 Page 6 of 16 STEP NO STEP *5 Direct RPO to 'lower hoist until grapple enters top guide, then ensure grapple is oriented properly to align with anti-rotation pin at corner of control cell (Southwest orientation),. (Cue: The component that you identified is in the condition that you just 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 grapple through top guide to just above the FSP'. (Cue: The component that you identified is in the condition that you just described.)
- 7 Direct the RPO to ensure the 'RELEASE' push-button on the Monorail Hoist pendant control is actuated.. (CUE: The component that you identified is in the condition that you just described.)
- 8 Direct the RPO to 'lower the FSP Grapple fully onto the FSP'. (Cue: The component that you identified is in the condition that you just described. ) ACT S STANDARD RPO is directed to lower the grapple while maintaining the proper Grapple orientation (Southwest).
Note to Evaluator
-This step is completing what the examinee started in step 2 (but was NOT able to complete due to the Fault Lockout).
S RPO is directed to lower the Monorail Grapple UNTIL the grapple is just above the FSP. S RPO is directed to verify the "RELEASE" push-button is depressed on the Hoist pendant control (to release the FSP Grapple), S RPO is directed to lower the FSP Grapple fully onto the FSP. NLSR03065 Rev 000 Page 7 of 16 STEP NO STEP I ACT 9 Direct the RPO to 'Pull down on and hold air hoses to verify there is no tension in hoses'. S (Cue: The component that you identified is in the condition that you just described.)
- 10 Direct the RPO to 'actuate the "ENGAGE" push-button on the Monorail hoist pendant control and pause a minimum of 10 seconds to allow air cylinders to stroke'. S (Cue: The component that you identified is in the condition that you just described.)
11 Direct the RPO to manually lift the FSP grapple enough to take weight of the FSP. S (Cue: "The component that you identified 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 approximately 6 inches'. S (Cue: The component that you identified is in the condition that you just described. ) (Cue: If examinee asks the indication on the load indicator, "The load indicator on the Monorail Hoist Pendant Control reads 160.")
RPO is directed to pull down on and hold air hoses to verify there is no tension in the hoses. RPO is directed to depress the Monorail Hoist Pendant Control "ENGAGE" push-button and pause for 10 seconds. Note to Evaluator
-For the examinee to obtain credit for this critical task, the examinee must EITHER pause at least 10 seconds before going on to the next step OR the examinee must verbally state that at least 10 seconds must pass before manually lifting the FSP grapple. RPO is directed to manually lift the FSP Grapple and verify the load indicator on the Monorail Hoist Pendant Control is greater than 100 Ibs and less than or equal to 165 Ibs. ! RPO is directed to raise the FSP Grapple approximately 6 inches. NLSR03065 Rev 000 Page 8 of 16 STEP NO STEP ACT STANDARD *13 Direct the RPO to 'raise the FSP through top guide and above the core'. (CUE: FSP is through the top guide and above the core.) this completes the simulated portion of the JPM. There may be follow up question(s) that need to be addressed.)
S RPO is directed to raise the FSP through the top guide and above the core. Note to Evaluator
-It is permissible for this action to be done in a series of steps. 14 Notify Control Room Supervisor that the FSP at Core location 30-31 has been removed in accordance with 301 up to and including step 5.3.16. (CUE: Acknowledge the report and end the performance portion of this JPM.) S Notify Supervisor of task completion.
Note to Evaluator The following step ONL Y applies for Requal Examinations (i.e. Step 15 is NOT applicable to Initial Exams). 15 (Cue: "If you were removing a Fuel Support Piece (FSP) at Limerick using C-741-301, how would your actions at Limerick be different than the actions that you just simulated here?") (CUE: If the examinee asks to see a copy of the Limerick procedure S97.0.M, then provide the examinee with a copy of the S97.0.M procedure AND re-read the follow up question to the examinee [if necessary].)
S Answer: The actions would be similar. At Limerick, there is a different style FSP grapple that is used and therefore, no need to "ENGAGE" the empty grapple while the grapple is going through the top guide. Also, at Limerick, the opening of the trolley deck cabinet doors do NOT cause a Fault Lockout condition of the Refuel Platform.
Note to Evaluator
-The answer to the 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 NO STEP ACT STANDARD 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 P -must S -must D-must 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 Page 10 of 16 Interlock Status INTERLOCK STATUS DISPLAY ----' I BRIDGE POS I I TROLLEY POS I 30.00 31.00 FUEL HOIST INTERLK ROD BLK ROD BLK BRIDGE BRIDGE INTERLK INTERLK REVERSE REVERSE #1 #2 STOP #1 STOP #2 BACKUP SAFETY TEST HOIST IN TRAVEL LMIT PROG INTERLK FRAME HOIST INTERLK NLSR03065 Rev 000 Page 11 of 16 TASK CONDITONS I PREREQUISITES AND INITIATING CUE TASK CONDITIONS/PREREQUISITES Fuel shuffle part 1 has been completed on PBAPS Unit _ (Unit 21 Unit 3). Control Cell 30-31 is having the Fuel Support Piece (FSP) removed using the PBAPS FSP Grapple & Grid Guide connected to the Monorail Hoist. Core Configuration is shown on the attached core view. The Reactor Cavity Work Platform (RCWP) is NOT installed. M-C-741-301 Attachment 11 is provided and was filled in when the first FSP replacements occurred (previous shift). The CCTAS is approved (current step is provided -see below). STEP NO. 86 , COMPONENT I MOVED I ORIENT ORIENT! I WRNM i DATE I TIME !MOVE FHD RPO eRO ! COUNTRATE SERIAL NO. FROM TO I I ABCDEFGH 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. 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. 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) The Monorail Hoist is positioned over the Core at location 30-31. 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 Page 12 of 16 CORE VIEW (FROM NLSR03065 Rev 000 Page 13 of
':::,.\ ]0 oe 1).1 CJ I Ij 01 I] 11 1 : [ 1"1 C! I l PBAPS CORE MAP f :1 , , , , -r -, I i , I, \1, 1,1 I, ' 11 : III, II* i, i Ii 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 160
- CRB (Mark N/A if using NES Combined Grapple)
- 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 Attachment 11 Page 1 of 1 NLSR03065 Rev Page 15 of 16 STu:;, GUSSE T S? AC E,R .TYPICAL Of 61 GUIDE TUBE ----"'-1 II OF Orientation Aid (aligned with anti-rotation pin) GuSSE T 8ASE PLATE FUEL SUPPOI'IT GRAPPLE GRID GUIDE and Orientation Aid NLSR03065 Rev 000 Page 16 of 16