ML021710133

Final - Lsro Section B Operating (Limerick Category B)

ML021710133
Person / Time
Site:	Peach Bottom, Limerick
Issue date:	05/24/2002
From:	Wasong A Exelon Nuclear
To:	Conte R NRC/RGN-I/DRS/OSB
References
-nr, 50-277/02301, 50-278/02301, 50-352/02301, 50-353/02301
Download: ML021710133 (305)

Text

EXELON NUCLEAR TITLE: Movement of the Dummy Fuel Bundle in the Spent Fuel Pool TASK PERFORMED BY: EVALUATOR:

EVALUATOR SIGNATURE: DATE:

DIRECTIONS TO EVALUATOR:

NOTE: When used as an exam item for initial LSRO candidates, a qualified LSRO/DA and RPO are required on the bridge to ensure correct Double Verification. Initial LSRO candidates will be acting as platform operator during most of the exam, and as FHD when addressing the CCTAS revision. This exam exercise will require the candidate to perform the first check as the RPO, with the qualified Fuel Handling Director performing the second check. In addition, the second qualified operator will perform a double verification.

NRC examiners will generally limit themselves to observing and will not provide direction or cueing to the candidate because actual equipment will be manipulated. Pre-brief the qualified FHD that he or she is the accountable individual who is responsible for equipment safety, personal safety, and reactivity controls during operation by the candidate. The FHD is expected to maintain constant attention on bridge and mast operation such that intervention is possible prior to any misoperation or contact with obstructions.

As a minimum, this includes (1) immediately stopping the bridge if a CCTAS error is committed or if unsafe bridge operation is taking place (2) restoring to starting conditions between each JPM, (3) collecting and returning the CCTAS signed final copies, and-(4) shutting down the refueling platform after the exams. The qualified FHD will. interact with the candidate in as realistic a fashion as practicable in an exam setting. The FHD will not provide cues other than specified, and should concur with all verifications up to the pbint just prior to a misoperation.

The qualified Operator should perform startup and checkout of the refueling platform and have on-hand the marked up copies of the procedures for review by the candidates. The actual CCTAS and bridge operating procedure in-use will be on the refuel platform.

The support of and coordination with the following is necessary to permit the conduct of the JPM:

1. NMD to schedule bridge availability and provide qualified operators

2. Operations for Refuel Floor Secondary Containment Integrity if required

3. Reactor Engineering for CCTAS generation

4. Health Physics for Refuel Floor and RWP support. The grappling and movement of components may require use of the refuel floor RWP in lieu of the work group standing RWP. Ensure a HP briefing is received prior to the exam.

Page 3 of 14 L&.S JPM I.1.dOc L(GS. JI-'M doc Page 3 of 14

EXELON NUCLEAR EVALUATION METHOD:

PERFORM EVALUATION LOCATION:

Refuel Platform APPROXIMATE COMPLETION TIME:

Completion lime: 60 minutes IMPORTANCE RATING(S): SYSTEM NUMBER(S):

3.5 2.2.28 Generic

REFERENCES:

1. FH-1 06, Rev 24, CORE COMPONENT AND IRRADIATED ITEM MOVEMENT - NO CORE TRANSFER

2. $97.0.M, Rev 12, OPERATION OF THE REFUELING PLATFORM

3. $97.1.A REV 12, ELECTRICAL, MECHANICAL, AND PNEUMATIC ALIGNMENT/CHECKOUT OF REFUELING PLATFORM, BRIDGE, TROLLEY, AND MAIN HOIST FOR OPERATION

4. RE-C-40, Rev 9, CORE COMPONENT TRANSFER AUTHORIZATION SHEET GENERATION AND ADMINISTRATION

/

TASK STANDARD(S):

Dummy fuel bundle transferred lAW the attached CCTAS and associated procedures Page 4 of 14 LGS JPM 1.dac LGS JPM I. doc Page 4.of 14

EXELON NUCLEAR TASK CONDITIONS:

1. Secondary containment integrity is established

2. The Unit __ refuel platform is ready for operation per S97.0.M and $97.1.A

3. FH-106 prerequisites are complete

4. Reactor Engineering has required a CCTAS for the movement of the dummy fuel bundle. The CCTAS has been provided to you.

5. Shift supervision permission has been obtained to operate the refueling platform INITIATING CUES:

You are directed by shift supervision to transfer the dummy fuel bundle in the Unit spent fuel pool per the attached CCTAS. You are expected to perform the actions of the Platform Operator and to perform actual operation of the equipment, rather than a simulation.

Page 5 of 14 LGS* JPM 1.doc L(3SJI-'M 1. doe Page 5 of 14

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

PERFORMANCE CHECKLIST:

The qualified LSRO will have completed portions of the following procedures to allow actual use of the refuel platform. These copies will be signed off and should remain on or near the refuel platform.

The candidate may wish to review the signoffs.

1. FH-106, CORE COMPONENT AND IRRADIATED ITEM MOVEMENT- NO CORE TRANSFER

2. $97.1.A, ELECTRICAL, MECHANICAL, AND PNEUMATIC ALIGNMENT/CHECKOUT OF REFUELING PLATFORM, BRIDGE, TROLLEY, AND MAIN HOIST FOR OPERATION Ensure a blank copy of the approved CCTAS is on the FHD desk. Ensure S97.0.M is available in the binders located at the FHD desk.

STEP STANDARD SAT/UNSAT Bundle Pickup per S97.0.M

1. *Position Refuel Platform Mast over Bridge, and Trolley controls manipulated the desired core component in until the mast is positioned over the accordance with the CCTAS dummy bundle (Evaluator Note: Small adjustments in position may be required once the grapple is near the bundle)

2. Lower grapple until grapple is 6 to 12 Grapple 6 to 12 inches above DUMMY inches above bail bundle bail handle.

Hoist encoder reads between following values:

Unit 1-178" and 186 Unit 2- 182" and 190"

• Critical value is at least 174, or grapple will not open in the next step

3. Ensure grapple is open Grapple is open as indicated by lack of green backlighting on grapple control rocker switch (green=closed; out=open)

4. Rotate grapple as necessary to Grapple is aligned with bail. Verify using achieve grapple to bail alignment mast camera.

LOS JPM 1.doc JPM I. Page 6 of 14 LGS doc Page 6 of 14

I ýEXELON NUCLEAR STEP STANDARD SAT/UNSAT

5. *Slowly lower grapple until SLACK Grapple is lowered until red SLACK CABLE light is lit CABLE lamp is lit with grapple being seated on the dummy bundle bail handle

6. Verify proper core component location Grapple is on the dummy bundle in the and orientation correct fuel pool location. The bundle Although is step channel fastener is oriented per the important, itis non- CCTAS (use mast video image and.

critical for this JPM compass rose painted on refuel bridge because the bundle will deckplates. The mast image is of the already be aligned correctly. It would have comer of the bundle CLOSEST to the been critical ifthis were operator. (If you cannot see the channel an alternate path JPM with the bundle found fastener, then the bundle is oriented in rotated atthis point. the same compass direction as the operator is facing when holding the mast handles)

7. Verify the following then notify the N/A N/A FHD of grapple position:

a. Grapple is centered over the Grapple is landed and centered on the bail handle DUMMY bundle bail handle.

Video image will be similar to the image below.

When properly landed, only the comer of the bundle is visible, with a symmetric, eveA appearance.

Image is looking almost straight down toward top of bundle. The shiny portion is the grapple and the dark portion is the bundle FHD is notified that grapple is centered on the bundle LGS JPMJPM I. 1.doc Page 7 of 14 LGS doc Page 7 of 14

I I EXELON NUCLEAR I STEP STANDARD SAT/UNSAT

b. Hoist position agrees with Hoist encoder (bottom LED display in values listed in Attachment 2 front of RPO console) reads:

for item seated in the Fuel Unit 1:190" to 192" Storage Pool Rack Unit 2: 194" to 196" FHD is notified that the hoist position is correct

c. Grapple appears seated on N/A N/A bail handle using underwater camera for component seated (Not in the cask) in the cask

8. *When directed by the FHD, then Grapple control switch actuated to engage the grapple and verify grapple ENGAGE engaged light is lit Green backlighting on grapple switch lit FHD CUE:,"Engage the grapple"

9. *When directed by the FHD, then RAISE actuated on grapple console slowly raise load while ensuring Red HOIST Loaded lamp lit on hoist HOIST LOADED light is lit cnoeISp console FHD CUE: "Raise the bundle"

10. *Continue raising until grapple is fully Green NORMAL UP lamp received on raised then verify NORMAL UP lamp hoist console is lit

11. Go to appropriate "Release Location" Move to Section 4.5, "Release Location section of this procedure as directed Fuel Pool Storage Rack or Cask Pit" by the FHD l4oc Page 8 of 14 LGS JPM I.

LOS JPM doc Page 8 of 14

EXELON NUCLEAR, STEP STANDARD SAT/UNSAT Bundle Drop-off Attempted per S97.0.M

12. *Position core component over Operate bridge and trolley controls to desired location in accordance with position the mast over the target location the Core Component Transfer on the CCTAS Authorization Sheet (CCTAS) Stop component transfer when FHD CUE: (After the bridge is driven to obstruction is cued the drop-off location):

"The fuel rack target location is obstructed by some plastic packing material and does not appear to allow bundle insertion" Alternate Path - CCTAS Step Cannot be Completed (FH-106 and RE-C-40)

Examiner Note:

At this point, the candidate will be assessed on the knowledge of the process for changing the CCTAS when a step cannot be performed. This is an LSRO task that will not normally be performed by the RPO. The candidate will describe the process of pen and ink change verbally based on a cue from the qualified FHD, make the change, and the qualified FHD will initial the actual change to the CCTAS. The qualified RPO may take the candidate's place in the cab while the candidate works at the desk. When finished, the candidate will resume examining in the RPO position.

I

13. *Contact Reactor Engineering and Verbal answer:

Perform one of the following per RE

• Contact Reactor Engineering C-40 and CCTAS instructions

"* Return the bundle to the original and location

"* Place the bundle in the approved place the dummy bundle in an approved alternate location on the CCATS alternate location or return to the original cover sheet location FHD Cue: What are the actions to be taken for resolving the current CCTAS execution problem?

I ___________

FHD Cue: The reactor engineer wants us to return the dummy bundle to the original pickup location.

L(

LU#o Jl-MlV i.aoc Jfr'M "IOC Page 9 of 14 Page 9 of 14

EXELON NUCLEAR

.p *

'1 I STEP STANDARD SAT/UNSAT J __________

14. The pen and ink change should follow Pen and ink change made to CCTAS per the following format: RE-C-40 by lining out the "MOVE TO"

i. Single line through item and "ORIENT" information on Move #1 and replacing itwith the location and to be changed orientation from the pickup location:

ii. Date and Initial of both Fuel Handling Director and Reactor Enginering group member FHD Cue: How should the change to the CCTAS be made FHD CUE: "Reactor Engineering has approved the change to the CCTAS and concurs with continuation of CCTAS execution" The Reactor Engineer's initials are "ABC" I ___________

Resumption of Component Transfers in S97.0.M

15. *Position core component over Operate bridge and trolley controls to desired location in accordance with position the mast over the target location the Core Component Transfer on the CCTAS Authlorization Sheet (CCTAS)

16. *Rotate core component as necessary Mast rotated to orient the bundle in the to achieve proper orientation direction called for in the CCTAS.

The bundle channel fastener is oriented per the CCTAS (use mast video image and compass rose painted on refuel bridge deckplates. The mast image is of the corner of the bundle CLOSEST to the operator. (If you cannot see the channel fastener, then the bundle is oriented in the same compass direction as the operator is facing when holding the mast handles)

17. Perform double verification to ensure Double verification performed proper core component location and orientation LUZ*" JI"IV/ 7.OC10 Page 10 of 14

EXELON NUCLEAR...

STEP STANDARD SAT1UNSAT

18. *When directed by the FHD, then lower Bundle lowered until red SLACK CABLE the hoist until core component is seated lamp is lit on hoist control console.

and SLACK CABLE is lit FHD CUE: "Lower the hoist"

19. Verify the following... N/A N/A

a. Component elevation appears Elevation of the handle for the still equivalent to other stored grappled dummy bundle is the same as

,ompon the rack the other bundles Not critcal because next step covers same thing

b. *Hoist position agrees with the Hoist encoder (bottom LED display in value listed in Attachment 2 for front of RPO console) reads:

item seated in Fuel Storage Unit 1:190" to 192" Rack Unit 2 194" to 196"

20. ... then notify the FHD of grapple FHD notified of grapple position position

21. *When directed by the FHD, then Grapple switch taken to RELEASE release grapple FHD CUE: ""Release the grapple"

22. Verify grapple is open Green backlighting out on the grapple control switch

23. *Slowly raise grapple while verifying Grapple control taken to RAISE OIST LOADED remains out and HOIST LOADED yellow lamp on left side grapple remains free of bail handle of hoist control console remains out 1.UOC Page 11 ofl4 LUS JJ-'M L(,5 JI-M "l.dOC Page 11 of 14

EXELON NUCLEAR I STEP I STANDARD SAT/UNSAT

24. Record completion of component CCTAS updated with date, time, and transfer in CCTAS RPO initials NRC CUE: You have reached the termination N/A N/A point for this JPM. You may stop here.

Page 12 of 14 L&S JPM ixioc L S JIM 1. doc Page 12 of 14

I . . ~~EXELONNUCLEAR..J..,

Comments:

Note: Any grade of UNSAT requires a comment.

JPM Overall Rating:

SAT/UNSAT Page 13 of 14 LU.f~i JI-M 7.UOC LbbJI-'M I.dlOC Page 13 of 14

I EXELON NUCLEAR TASK CONDITIONS:

1. Secondary containment integrity is established

2. The Unit refuel platform is ready for operation per S97.0.M and S97.1.A

3. FH-106 prerequisites are complete

4. Reactor Engineering has required a CCTAS for the movement of the dummy fuel bundle.

The CCTAS has been provided to you.

5. Shift supervision permission has been obtained to operate the refueling platform INITIATING CUES:

You are directed by shift supervision to transfer the dummy fuel bundle in the Unit

___spent fuel pool per the attached CCTAS. You are expected to perform the actions of the Platform Operator and to perform actual operation of the equipment, rather than a simulation.

CANDIDATE

RE-C-40, Rev 9.

Exhibit RE-C-40-12 Page 44 of 47 Page I of I CCTAS Instruction/Approval Paqe Page I of 2 Core Component Transfer Authorization Sheet LIMERICK 2 Date 04/03/2002 Unit Title Unit 2: Dummy Bundle Moves (CCTAS # 1) (Rev. #) 0

1. This CCTAS shall be used to move the dummy fuel bundle within the LGS Unit 2 Fuel Pool for training purposes.

in an

2. If any step cannot be completed, contact reactor engineering and place the dummy bundle alternate location or return the bundle to its original location and annotate the CCTAS step appropriately.

An approved alternate locations is JJ-70.

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

4. This CCTAS must be used in conjunction with appropriate fuel handling procedures. SECONDARY CONTAINMENT IS NOT REQUIRED.

5. All changes to this CCTAS must be made in accordance with procedure RE-C-40.

6. This CCTAS DOES NOT involve the transfer of Special Nuclear Material (SNM).

7. Return completed CCTAS (or a copy if original is contaminated) to Reactor Engineering.

8. RE phone #s Home WORK Beepe 1-800-672-2285 Joe Rubinaccio (610)792-3580 3595 0228 Bob Potter (610)369-3612 3565 7540 "GarySnyder (610)406-9148 3566 3015 Dave Hamilton (610)287-3160 3560 7154 Prepared By:

Reviewed By:

Authorized By:

I~ A r'Ct-rAQ R~eview UIolCo* ll3tt P re.v Date SNM Custodian SNM Custodian Date

TRANSFER r'HORIZATION FOR FH-106 TRNDUMM - VERIFIED 6 7 RI DOCTYPE 116 . 8/88 M-2199 Written By: R.C. POTTER Reviewed By: D.B. HAMILTON STATION Date 04/03Z2002 Unit LIMERICK GENERATING (ccTAs Authorized By: D.B.Hamilton Moves Title Unit 2: Dummy bundle ICOMPONENT RPO DATE TIME ORIENT FHD ORIENT MOVE TO I MOVE FROM STEP NO. SERIAL NO. I LSETH -4I*

I IsI HI-44 N S W2SPENT DUMMY IL2SPENT F-1l I

I I I I I I I I IIII I D H s I 2 I I II

S97.1.A, Rev.12 Page 1 of 20 MDF/mrw Exelon Nuclear LIMERICK GENERATING STATION S97.1.A ELECTRICAL, MECHANICAL, AND PNEUMATIC ALIGNMENT/CHECKOUT OF REFUELING PLATFORM BRIDGE, TROLLEY, AND MAIN HOIST FOR OPERATION 1.0 PURPOSE 1.1 To align Refuel Platform Bridge, Trolley, Auxiliary Hoist, and Main Hoist for operation. This procedure does not provide specific instructions for handling of fuel assemblies or other pieces of equipment. Those instructions are covered in other procedures.

1.2 To perform checkout of Refuel Platform prior to operation. It is recommended that this procedure be performed prior to operating the Refuel Platform each day.

2.0 PREREQUISITES 2.1 Jamming buttons are installed on Auxiliary Hoist cables.

2.2 Reactor Select Switch set for desired operation.

2.3 Health Physics (HP) has made necessary surveys.

3.0 PRECAUTIONS 3.1 WHEN not in use, THEN the Main Hoist should be in normal up position.

3.2 WHEN Auxiliary Hoists are in use for handling irradiated core components THEN jam block shall be set to ensure water coverage in accordance with Limerick Technical Specifications OR governing implementing procedure (e.g. jet pump servicing).

3.3 WHEN inspecting Refuel Platform, THEN special care must be taken to avoid dropping any objects into Fuel Pools OR Cavities.

S97.1.A, Rev.12 Page 2 of 20 MDF/mrw 3.4 Refuel Platform should pass all checks, inspections, AND verifications.

IF this is not the case, THEN contact System Manager or Reactor Services Technical Staff for resolution.

3.5 IF removing any items from Reactor Cavity OR Spent Fuel Pool (i.e. aux. hoist grapples),

THEN HP must be contacted.

S97.1.A, Rev. 12 Page 3 of 20 MDF/mrw INITIALS 4.0 PROCEDURE NOTE Conditional IF.. .THEN steps that are not applicable AND steps to be skipped per direction of the IF.. .THEN step shall be marked N/A AND initialed.

4.1 REFUELING PLATFORM ELECTRICAL LINEUP 4.1.1 ENSURE Disconnect Switch *0S380 is on.

4.1.2 OPEN main power AND communication cable service pit cover AND ENSURE service pit is dry AND main power cable is properly connected.

4.1.3 CLOSE service pit cover.

NOTE The Refuel Bridge is equipped with cabinet heaters AND semiconductor coolers which remain energized at all times.

4.2 BRIDGE END STRUCTURE ELECTRICAL PANEL LINEUP 4.2.1 ENSURE the following switches AND circuit breakers on:

1. MAIN DISCONNECT switch

2. MONO DISCONNECT switch

3. AIR DRYER circuit breaker

4. CIRCUIT BREAKERS for GFI outlets

5. AIR DRYER switch

S97.1.A, Rev.12 Page 4 of 20 MDF/mrw INITIALS 4.2.2 ENSURE Compressor switch on.

4.2.3 ENSURE the following valves open:

1. MAIN HOIST Pneumatic Shut-off Valve

2. MONO HOIST Pneumatic Shut-off valve 4.3 MAIN HOIST POWER CENTER CABINET LINEUP 4.3.1 ENSURE Disconnect switch (located outside of cabinet) on.

4.3.2 OPEN hoist power center cabinet door AND ENSURE the following circuit breakers on:

1. MCB

2. LCB2

3. OTCB

4. HTCB

5. GTCB

6. GFI-3

7. CLCB

8. ACCB

9. GRCB 4.3.3 CLOSE cabinet door.

4.4 BRIDGE/TROLLEY CONTROL CABINET LINEUP 4.4.1 OPEN bridge/trolley control cabinet door AND ENSURE circuit breaker BTCB on.

4.4.2 CLOSE cabinet door.

$97.1.A, Rev. 12 Page 5 of 20 MDF/mrw INITIALS 4.5 BOUNDARY ZONE COMPUTER CABINET 4.5.1 ENSURE BOUNDARY ZONE COMPUTER COOLER switches on.

4.6 OPERATOR CAB RIGHT HAND CONTROLLER CONSOLE CHECK 4.6.1 ENSURE PLATFORM variable speed control operator in "NEUTRAL."

4.6.2 ENSURE GRAPPLE variable speed control operator in "NEUTRAL."

4.7 OPERATOR CAB LEFT HAND CONTROLLER CONSOLE CHECK 4.7.1 ENSURE TROLLEY variable speed control operator in "NEUTRAL."

NOTE WHEN control circuits are energized, THEN STOP button will light indicating power on.

4.7.2 PRESS Traverse System "START" button to energize control circuits.

4.7.3 IF necessary to de-energize control circuit, THEN PRESS STOP button.

4.8 ENCODER POWER SUPPLY CHECKS 4.8.1 ENSURE BRIDGE encoder power supply switch on.

4.8.2 ENSURE TROLLEY encoder power supply switch on.

4.8.3 ENSURE HOIST encoder power supply switch on.

S97.1.A, Rev.12 Page 6 of 20 MDF/mrw INITIALS 4.9 MISCELLANEOUS CHECKS 4.9.1 IF Core Alterations per FH-105, Core Component Movement - Core Transfer, are performed, THEN ALIGN direct communications from Refueling Platform to MCR.

4.9.2 PLACE Reactor Select Switch to appropriate position, on selected platform as follows:

1. UNIT 1 PLATFORM ONLY

a. REACTOR #1 for UNIT 1 service.

b. REACTOR #2 for UNIT 2 service.

2. UNIT 2 PLATFORM ONLY

a. REACTOR #1 for UNIT 1 service.

b. REACTOR #2 for UNIT 2 service.

4.10 PRE-OPERATIONAL CHECKS 4.10.1 READ Attachment 1.

4.10.2 COMPLETE Attachment 2.

$97.1.A, Rev.12 Page 7 of 20 MDF/mrw

5.0 REFERENCES

5.1 UFSAR Section 9.1.4 5.2 UFSAR Section 7.7 5.3 Operations and Maintenance Instructions, Refueling Platform GEK-75574 (M1-F21-EO03 VOLS I, II) April 1982 5.4 E-45, Schematic Diagram - MCC Load Tabulation 114C-R-A & 124C-R-A, Reactor Area MCC 440V-1 Unit.

5.5 E-65, Schematic Diagram - MCC Load Tabulation 214C-R-A, Reactor Area MCC 440V-2 Unit.

5.6 MOD 6248, Mast Camera Installation for Refuel Platform 5.7 PIMS A/R Al 250047, Eval. 01.

5.8 PEP Issue 10011758, Main Grapple Air Line entangled with other mast sections.

5.9 MOD P00925, Service Pole Caddy on Refueling Bridge 5.10 MOD P00950, Fuel Floor Auxiliary Platform 6.0 TECHNICAL SPECIFICATIONS 6.1 3.9.1 6.2 3.9.5 6.3 3.9.6 7.0 INTERFACING PROCEDURES 7.1 FH-105, Core Component Movement - Core Transfer 7.2 FH-106, Core Component Movement - Spent Fuel Pool ONLY

S97.1.A, Rev.12 Page 8 of 20 MDF/mrw ATTACHMENT 1 Page 1 of 2 SUPPLEMENTAL NOTES The main disconnect should remain ON following refuel platform operation. This provides power to the cabinet heaters to prevent premature failures of motors and control relays from moisture in the cabinets.

The boundary zone computer enforces the following refueling platform interlocks:

1. The bridge will decelerate into jog mode at approximately 24 inches for Unit 1 and Unit 2 from any spent fuel pool wall AND engage the zone lockout at approximately 12 inches from the wall.

Overriding the zone lockout will provide only jog speed in any direction.

2. Similarly, the trolley will be decelerated into jog mode at approximately 12 inches from a wall AND the zone lockout will be engaged approximately 3 inches from the pipe OR approximately 12 inches from a wall. Override will provide only jog motion.

3. When any boundary is reached, the operator will be permitted to reverse direction without employing the override, unless the grapple has traveled beyond the physical limits of the refueling pool/reactor cavity/cask area.

4. The operator will not be permitted to lower the grapple in the cattle chute or the canal leading to the cask storage area.

5. Unless the grapple is raised to the full up position (< 1 inch down), the logic will not recognize the entrance to the cattle chute or the canal leading to the cask storage area.

6. At any point within the physical limits of the refueling pool, operation of the grapple will depend only on hoist position. If the bridge and trolley are moved close to a wall to remove or store a fuel bundle, the operator needs only to use the zone logic override; the grapple will operate normally.

7. In the core, when using the variable speed controller, the main hoist may stop just prior to the bundle seating. If this occurs, the operator shall use the jog down pushbutton to move the grapple the remaining distance to achieve a SLACK CABLE condition. The BZC enforces a lockout for main hoist lowering approximately 1.5 inches after bundle would be seated to prevent fuel grapple contact with the top guide. Continued lowering of the main hoist is provided by use of the BZC bypass pushbutton and will provide only jog down speed. The main hoist can always be raised with the variable speed controller.

S97.1.A, Rev.12 Page 9 of 20 MDF/mrw ATTACHMENT 1 Page 2 of 2

8. In the spent fuel pool, When using the variable speed controller, the main hoist may stop just prior to the bundle seating in the rack. If this occurs, the operator shall use the jog down pushbutton to move the grapple the remaining distance to achieve a SLACK CABLE condition. This jog zone remains in effect for 6 inches.

The BZC then allows full speed lowering of the main hoist until the fuel grapple is approximately 6 inches from the fuel pool floor. The lowering exclusion zone is set at the fuel pool floor. This corresponds to elevation +370.00. The main hoist can always be raised with the variable speed controller.

9. The fuel grapple is permitted to open in the range of 16 inches above a fuel assembly bail to 2 inches below a fuel assembly bail when the assembly is seated in a fuel storage rack OR in the range of 10 inches above a fuel assembly bail to 2 inches below a fuel assembly bail when the assembly is seated in the core. OPERATION OF FUEL GRAPPLE AT ANY OTHER ELEVATION IS POSSIBLE ONLY THROUGH THE USE OF THE GRAPPLE LOCKOUT BYPASS PUSHBUTTON.

10. The Grapple Lockout Bypass push-button must be pushed to allow opening of the fuel grapple prior to engaging a fuel assembly in either fuel prep machine.

S97.1.A, Rev.12 Page 10 of 20 MDF/mrw ATTACHMENT 2 REFUELING PLATFORM PRE-OPERATIONAL CHECKOFF LIST Date: Time: Unit:

Performed By:

NOTES

1. Mark all steps which do NOT apply "N/A".

2. IF a check cannot be completed, THEN the Fuel Handling Director (FHD) shall make the determination if Attachment 2 may be continued. Comments may be entered at the end of the checkoff list.

3. Subsections AND steps within Attachment 2 may be performed out of sequence OR in parallel to suit field conditions at the discretion of the FHD.

4. Steps concerning the following equipment need NOT be performed if the equipment is NOT functional. This equipment is NOT required for safe operation of the Refueling Platform.

"* Mast camera control unit (CCU)

"* Mast camera monitors

"* Grapple headlights 1.0 PLATFORM CHECKS INITIALS 1.1 ENSURE Auxiliary Platform is located beyond anticipated travel of Refueling Platform during performance of this checkoff list. (Ref. 5.10) 1.2 ENSURE north AND south bridge rails are clear of obstructions AND debris.

1.3 ENSURE NO obstructions to platform travel on adjacent floor areas.

1.4 ENSURE that items hanging from the pool/cavity handrails and platform (i.e, underwater lights, view boxes, underwater cameras, etc.) will NOT interfere with operation of the platform OR hoists.

S97.1.A, Rev. 12 Page 11 of 20 MDF/mrw ATTACHMENT 2 (Cont.)

INITIALS 1.5 ENSURE that channel handling boom, mounted near the fuel prep machines, will NOT interfere with motion of platform.

1.6 ENSURE main power AND communication cable service pit is dry.

1.7 ENSURE lower trolley rail on front of bridge structure is clear of obstructions AND debris.

NOTES

1. Refueling interlock track limit switches RS1 AND RS2 (over the core track switches) are located on north end truck.

2. Do NOT actuate limit switches.

1.8 ENSURE RS1 AND RS2 limit switch actuating arms are intact, pointing down towards floor AND NOT damaged.

IF cover plates are installed (access to switches)

THEN this step may be N/A'd per discretion of FHD.

1.9 ENSURE air compressor switch is "ON" with pressure approximately 80 to 120 psig.

1.10 VERIFY air compressor AND associated piping has NO indication of leakage.

1.11 CHECK bridge gearboxes for excessive leakage.

1.12 PERFORM general bridge inspection for foreign material (cleanliness AND loose hardware).

1.13 IF main hoist jib crane is NOT being used, THEN ENSURE properly stowed with jib hinge pin installed AND cable taut.

S97.1.A, Rev.12 Page 12 of 20 MDF/mrw ATTACHMENT 2 (Cont.)

C- INITIALS 1.14 VERIFY No service poles are sitting in chamfered seat of service pole caddy guide slot OR hanging from pole caddy hoist. (Ref. 5.9) 1.15 ENSURE the following cable reels are operating properly maintaining cable tension without binding OR birdnesting of cable on reel.

1.15.1 Main power cable reel 1.15.2 Communications cable reel 1.16 VERIFY observable portions of the following cables are NOT damaged.

1.16.1 Main power 1.16.2 Communications C* 1.17 ENSURE trolley AND monorail rail clear of obstructions AND debris.

1.18 CHECK trolley gearbox for excessive leakage.

1.19 ENSURE main trolley power track operates properly without binding.

2.0 OPERATOR CAB CHECKS 2.1 ENSURE "TEST IN PROGRESS" light on INTERLOCK STATUS DISPLAY is OFF.

2.2 ENSURE bridge position indicator responds to bridge motion.

2.3 ENSURE trolley position indicator responds to trolley motion.

S97.1.A, Rev.12 Page 1,3 of 20 MDF/mrw ATTACHMENT 2 (Cont.)

INITIALS 2.4 ENSURE that the swing gate on the left front of the trolley cab next to the main hoist AND the main hoist retaining bar are closed AND secured.

2.5 POSITION trolley at approximately encoder position 31.00 AND ENSURE match marks line up between the trolley AND bridge decking.

3.0 MAIN HOIST GRAPPLE CHECKS 3.1 IF main hoist grapple will NOT be used, THEN ENSURE main hoist is in Normal Up position AND MARK remaining steps in Section 3.0 "N/A".

3.2 PLACE grapple light toggle switch to "ON" position.

3.3 PLACE mast camera AND associated monitors to "ON" position.

3.4 VERIFY observable portions of the hoist load cables do NOT have cracks, frayed ends, OR other signs of damage.

3.5 VERIFY observable portions of the hoist air hoses do NOT have cracks, leaks, OR other signs of damage.

3.6 ENSURE mast sections move freely with NO signs of uneven wear.

3.7 ENSURE hoist position indicator responds to hoist motion.

3.8 ENSURE hoist load indicator is operating properly.

3.9 ENSURE hoist motor brake releases when an attempt is made to move the hoist AND engages when hoist movement is stopped.

S97.1.A, Rev.12 Page 14 of 20 MDF/mrw ATTACHMENT 2 (Cont.)

INITIALS 3.10 ENSURE hoist safety brake releases when an attempt is made to move the hoist AND engages with a time delay after hoist movement is stopped.

3.11 ENSURE no component is grappled THEN CYCLE the grapple AND ENSURE "GRAPPLE ENGAGED" light is lit when the grapple is engaged.

3.12 ENSURE the following at the bulkhead on top of the 5 inch mast section: (Ref. 5.8) 3.12.1 Hoist strain relief's are properly connected to cables/hoses AND bulkhead.

3.12.2 Air hose strain relief fasteners are oriented inward AND will not interface with mast section motion.

3.12.3 Cables, hoses and associated strain relief's are centered in the 5 inch section AND are fastened to each other via tie-wraps OR equivalent.

3.13 ENSURE hoist strain relief's at top of 12 inch mast section near trolley upper deck are properly connected to cables AND trolley structure.

S97.1.A, Rev. 12 Page 15 of 20 MDF/mrw ATTACHMENT 2 (Cont.)

INITIALS 3.14 ENSURE the following cable reels are operating properly, maintaining tension without binding OR birdnesting of cable on reels.

3.14.1 Power cable reel 3.14.2 Air hose reel 3.14.3 Camera cable reel 3.15 ENSURE hoist load cables properly wrap on cable drum without birdnesting.

3.16 ENSURE proper reel tension by lowering the hoist until just above fuel seated in core, OR if core is NOT accessible the lowest position available in the fuel pool, AND ENSURE "SLACK CABLE" light remains OFF.

3.17 ENSURE mast automatically stops raising at the Normal Up limit.

3.18 ENSURE satisfactory mast camera operation.

4.0 BOUNDARY ZONE COMPUTER (BZC) CHECKS 4.1 CHECK Boundary Zone Computer for proper operation of bridge, trolley, hoist and grapple motion enforcement in spent fuel pool as follows: (See Attachment 1 for additional information.)

4.2 ENSURE Boundary Zone Computer override keylock switch (located in operator cab) is in "NORMAL" position.

4.3 ENSURE Boundary Zone Computer bypass switch (located in Boundary Zone Computer cabinet) is in "NORMAL" position.

S97.1.A, Rev.12 Page 16 of 20 MDF/mrw ATTACHMENT 2 (Cont.)

INITIALS 4.4 ENSURE that a Boundary Zone Computer (BZC) cooling fan is operational. NOTE: There are two fans for the BZC.

One fan is always operational. The second fan is controlled via a temperature switch.

4.5 ENSURE fuel grapple opens without use of the GRAPPLE LOCKOUT BYPASS pushbutton when grapple is within 16 inches above a fuel assembly bail handle when the fuel assembly is seated in a fuel storage rack.

4.6 DRIVE bridge east AND west to verify automatic boundary enforcement.

4.7 DRIVE main trolley north AND south to verify automatic boundary enforcement.

S97,1.A, Rev.12 Page 17 of 20 MDF/mrw ATTACHMENT 2 (Cont.)

INITIALS 5.0 FRAME MOUNTED HOIST CHECKS 5.1 IF frame mounted hoist will NOT be used, THEN ENSURE frame mounted hoist is full up on hoist override with tools removed OR tools/cables stored in a safe location for platform movement, AND MARK the remaining steps in Section 5.0 "N/A".

5.2 ENSURE frame hoist, trolley AND bridge can be operated using frame hoist control pendant.

5.3 VERIFY observable portions of the hoist load cable do NOT have cracks, frayed ends OR other signs of damage.

5.4 VERIFY observable portions of the hoist air hoses do NOT have cracks, leaks OR other signs of damage.

5.5 ENSURE air hose reel is operating properly, maintaining tension without binding OR birdnesting of hose on reel.

5.6 ENSURE hoist load cable properly wraps on cable drum without birdnesting.

5.7 IF current jam block setting permits, THEN ENSURE normal full up geared limit switch stops hoist raise motion AND pressing HOIST LIMIT OVERRIDE allows raise motion until the over hoist geared limit switch stops raise motion.

5.8 IF jam block is set in accordance with an implementing procedure, THEN ENSURE raise motion is stopped when whisker switch is actuated by the jam block.

S97.1.A, Rev. 12 Page 18 of 20 MDF/mrw ATTACHMENT 2 (Cont.)

INITIALS 5.9 ENSURE hoist motor brake releases when an attempt is made to move the hoist AND engages when hoist movement is stopped.

5.10 ENSURE hoist safety brake releases when an attempt is made to move the hoist AND engages with a time delay after hoist movement is stopped.

5.11 ENSURE hoist load indicator is operating properly.

6.0 MONORAIL HOIST CHECKS 6.1 IF monorail hoist will NOT be used, THEN ENSURE monorail hoist is full up on hoist override with tools removed OR tools/cables stored in a safe location for platform movement, AND MARK the remaining steps in Section 6.0 "N/A".

6.2 ENSURE monorail hoist, monorail trolley AND bridge can be operated using monorail hoist control pendant.

6.3 VERIFY observable portions of the hoist load cable do NOT have cracks, frayed ends OR other signs of damage.

6.4 VERIFY observable portions of the hoist air hoses do NOT have cracks, leaks OR other signs of damage.

6.5 ENSURE air hose reel is operating properly, maintaining tension without binding OR birdnesting of hose on reel.

6.6 ENSURE hoist load cable properly wraps on cable drum without birdnesting.

S97.1.A, Rev.12 Page 19 of 20 MDF/mrw ATTACHMENT 2 (Cont.)

INITIALS 6.7. IF current jam block setting permits, THEN ENSURE normal full up geared limit switch stops hoist raise motion AND pressing HOIST LIMIT OVERRIDE allows raise motion until the over hoist geared limit switch stops raise motion.

6.8 IF jam block is set in accordance with an implementing procedure, THEN ENSURE raise motion is stopped when whisker switch is actuated by the jam block.

6.9 ENSURE hoist motor brake releases when an attempt is made to move the hoist AND engages when hoist movement is stopped.

6.10 ENSURE hoist safety brake releases when an attempt is made to move the hoist AND engages when hoist movement is stopped.

6.11 ENSURE monorail trolley power track operates properly without binding.

6.12 ENSURE hoist load indicator is operating properly.

S97.1.A, Rev.12 Page 20 of 20 MDF/mrw ATTACHMENT 2 (Cont.)

COMMENTS:

S97.0.M, Rev. 12 Page 1 of 26 JAID/jad Exelon Nuclear LIMERICK GENERATING STATION S97.O.M REFUELING PLATFORM OPERATI002UN!;

1.0 PURPOSE 1.1 To provide instruction necessary to operate the Refuel Mplistorr main hoist for core component movements within the Fuel Pool, Cask Pi:tand iiad.iFheactor Core. This procedure shall be used in conjunction with Fuel H.:"41in."'J"Procedure FH-105 "Core Component Movement - Core Transfers", or FH-1106 "Core Component and Irradiated Item Movement - No Core Transfer" a- appropriate.

2.0 PREREQUISITES 2.1 IF performing component transfers in the Reactor, THEN all prerequisites included in Proc.dur.e.:.-.FH- 105, "Core Component Movement

- Core Transfers" have been completed .s appropriate.

2.2 IF performing component transfers nthe.iFuel Pool/Cask Pit only, THEN all prerequisites included in.`::P.oc`dure FH-106, "Core Component and Irradiated Item Movement - No e Tr ansfer", have been completed as appropriate.

2.3 Applicable sections of thp $7.:V... A "Electrical, Mechanical, and Pneumatic Alignment/Checkout of R fueling Platform Bridge, Trolley and Main Hoist for Operation" should be perforetd as necessary. Verification of the mast's ability to fully extend without binding should be performed over the reactor cavity soon after core is accessible.wah the mast.

2.4 IF performing tra.nsf-e.r *: the dummy bundle over the Reactor Cavity, THEN secondary" o 0: .. nment is required during movement over irradiated fuel per Ref. 5.13.

2.5 IF performing:ransfer of the dummy bundle in the spent fuel pool only, THEN seco ,.dry containment is operable as required below:

IF greater than 46 days have elapsed since shutdown of unit just prior to the most recent discharge of fuel which is stored in the appropriate pool, THEN secondary containment is not required per Refs. 5.13 and 5.14.

Previous transfer of fuel between fuel pools must be considered in making this determination, OTHERWISE, secondary containment is required during movement of the dummy bundle over irradiated fuel per Ref. 5.1 3.

S97.0.M, Rev. 12 Page 2 of 26 JAD/jad

( 2.6 IF there is potential for contact with the Auxiliary Platform during performance of any section of this procedure THEN a dedicated Spotter shall be posted on the Refueling Platform to monitor platform separation AND alert the Fuel Handling crew to stop operations IF interference is imminent. (Ref. 5.18) 3.0 PRECAUTIONS 3.1 IF equipment performance is not as expected, THEN the equipment shall be placed in a safe condition AND Shift Management or Fuel Handling Director shall be notified immediately.

3.2 IF a core component is partially inserted into a location, THEN Refuel Platform bridge OR Trolley shall only be moved at JOG speed.

3.3 Fuel bundles shall be seated using a consistent slow hoist speed while gently shaking the mast. Extreme slow speed and the absence of vibration increases the potential for improper bundle seating.

3.4 Double blade guide spacer buttons occasionally tend to hang-up on the top edge of the Unit 2 Spent Fuel Pool racks. Refuel Platform Operator may need to gently shake mast to eliminate interference and fully seat blade guide in rack.

3.5 Bridge and trolley shall be operated at JOG speed when handling double guides with the mast below the reactor vessel flange (per SIL 594).

3.6 Blade guides may be removed from the reactor core provided the associated control rod blade will be diagonally supported by fuel or other blade guide(s).

3.7 To prevent impact or mast/fuel assembly damage:

3.7.1 Trolley and Bridge shall always be accelerated slowly, avoiding sudden starts and stops.

3.7.2 Travel paths shall be clear before moving core components.

3.7.3 NORMAL UP light must be lit before moving through transfer canal.

3.7.4 Double blade guides must be raised beyond NORMAL UP using Hoist Override to -4.0 inches as indicated by hoist encoder before moving through transfer canal.

3.7.5 Main Hoist Grapple must be in full up position when not in use.

S97.0.M, Rev. 12 Page 3 of 26 JAD/jad 3.7.6 Push or pull mast assembly as required when fuel bundle is approaching fully seated position in core, sipping canister, or spent fuel pool rack to protect channel fastener. Observe channel fastener, if possible, as it enters core, rack or sipping canister to ensure channel fastener does not catch.

3.7.7 Operate main hoist slowly when grapple/component approaches fully seated position.

3.8 Mast camera may impact surrounding structures when manipulating core components in the Reactor Core periphery, Fuel Pool periphery or Fuel Preparation Machine. Exercise caution to avoid impact damage.

3.9 LPRM bender stand shall be removed before moving platform to equipment pool.

When installed the LPRM bender stand will prevent refuel platform travel over equipment pool.

NOTE Attachment 1 provides a list of Refuel Platform interlocks, including initiating conditions and effects on the system.

3.10 IF during hoist operation:

3.10.1 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 contacted for instruction.

3.10.2 HOIST LOADED Light goes out prematurely, OR load starts to lean,

1. Hoist Lowering shall be stopped immediately.

2. Grapple switch shall be verified to be in ENGAGED position

3. Grapple engagement shall be verified.

4. GRAPPLE ENGAGED light shall be verified lit.

5. Hoist shall be raised slowly to regain the weight of the load.

6. Fuel Handling Director shall be notified.

S97.O.M, Rev. 12 Page 4 of 26 JAD/jad 3.10.3 GRAPPLE ENGAGED Light goes out unexpectedly during operation, THEN movement shall be stopped immediately, AND FHD notified.

3.10.4 HOIST LOADED Light comes on unexpectedly while raising grapple:

1. Hoist movement shall be stopped.

2. Hoist shall be slowly lowered until HOIST LOADED light goes out.

3. Fuel Handling Director shall be notified.

3.10.5 ROD BLOCK #1 and ROD BLOCK #2 light on interlock status display does not light when platform is over the core AND main hoist is fuel loaded, THEN refuel platform operation shall be stopped, AND FHD notified.

3.11 GRAPPLE LOCKOUT BYPASS and BOUNDARY ZONE COMPUTER BYPASS push button operations may be needed for handling components in the periphery of the Spent Fuel Pool , in a Bundle Sipping Canister, or in a Cask.

- 3.12 Fuel inspection and test equipment when installed in the fuel pools presents an entanglement hazard for the main mast or grappled fuel bundle.

3.13 IF secondary containment becomes inoperable during transfer of the dummy bundle, THEN STOP movement of the dummy bundle over irradiated fuel UNLESS it was determined that secondary containment is not required (Ref. 5.13).

3.14 Prior to component handling concurrent with use of unique equipment in the reactor cavity or fuel pool, a determination should be made regarding the level of monitoring necessary to prevent contact between the equipment and the refuel platform mast, mast camera or core components suspended from the grapple.

Examples of unique equipment include in-vessel inspection or repair equipment, particularly those with umbilical cables. Depending on the risk of interference, consideration shall be given to positioning an individual on the refuel platform assigned the responsibility to monitor the position of the equipment (and umbilical if applicable) and alert Fuel Handling crew to STOP if interference is imminent.

3.15 De-energizing the refuel platform while over the reactor cavity (track switches

( actuated) will generate a Rod Withdrawal Block in the Main Control Room. Notify Reactor Operator prior to de-energizing the refuel platform with the track switches actuated.

S97.0.M, Rev. 12 Page 5 of 26 JAD/jad 3.16 Peripheral fuel assemblies have the potential to miss their fuel support and seat low. Use extreme caution to maintain proper alignment while inserting assembly into the core. (Ref. 5.15).

3.17 Extra caution should be used when handling very old fuel bundles. Monitoring of bundle weight shall be performed during lifting to ensure gross failure of bundle is identified (Ref. 5.16). Also, bent channel fasteners and bent bail handles have been found on old bundles.

3.18 A gentle rotation of the mast in both directions should be used to ensure the fuel grapple is firmly engaged to the bail handle. Rapid or rough rotation during this check has led to fuel failure. (Ref. 5.16) 3.19 Use extreme caution and a slow hoist speed when handling unchanneled fuel bundles. Unchanneled fuel bundles are more susceptible to damage by twisting/rotation of mast. Finger springs on the lower tie plate and fuel rod spacers may catch during fuel bundle removal OR insertion into a spent fuel pool rack OR fuel preparation machine.

3.20 Three dimensional moves of Refueling Platform (e.g. using Bridge, Trolley and Hoist at same time)

AND simultaneous operation of Service Pole Caddy Hoist is not permitted. (Ref. 5.17) 3.21 IF potential for contact exists, THEN slow speed shall be utilized when approaching the Auxiliary Platform. (Ref. 5.18) 3.22 IF Refueling Platform AND Auxiliary Platform need to be brought together THEN PERFORM the following: (Ref. 5.18) 3.22.1 ENSURE Auxiliary Platform is positioned where required.

3.22.2 DEENERGIZE Refueling Platform per NMD Maintenance Supervisor OR FHD direction.

3.22.3 MOVE Refueling Platform up to Auxiliary Platform using hand-crank.

3.23 IF a Control System malfunction occurs, THEN Refueling Platform can be stopped by pressing the STOP push-button on the Left Hand Controller OR by opening the MAIN DISCONNECT switch on the north end truck.

3.24 IF fuel moves must be suspended with an irradiated bundle hanging on the mast, THEN ENSURE bundle is not positioned near invessel remote operated cameras.

This will prevent radiation damage to the cameras.

S97.0.M, Rev. 12 Page 6 of 26 JAD/jad

"-' 4.0 PROCEDURE NOTE

1. The performance steps section of this procedure is separated into the following subsections:

4.1, Pickup Location - Fuel Pool Storage Rack or Cask Pit 4.2, Pickup Location - Reactor Core 4.3, Pickup Location - Fuel Preparation Machine 4.4, Pickup Location - Bundle Sipping Canister 4.5, Release Location - Fuel Pool Storage Rack or Cask Pit 4.6, Release Location - Reactor Core 4.7, Release Location - Fuel Preparation Machine 4.8, Release Location - Bundle Sipping Canister 4.9, Determination of Hoist Position for Bundle Seated in Sipping Canister 4.10. In-Process Adjustment of Bridge/Trolley Encoders.

2. Target Hoist Positions are listed in Attachment 2 which should be posted on the Refuel Platform mast.

3. Sequential steps which perform horizontal positioning of grapple/component (Bridge/Trolley) and vertical positioning of grapple/component (Hoist) may be performed in parallel as conditions permit.

4.1 Pickup Location - Fuel Pool Storage Rack or Cask Pit NOTE A CCTAS is not required for pickup of the dummy bundle.

4.1.1 POSITION Refuel Platform Mast over desired core component in accordance with Core Component Transfer Authorization Sheet (CCTAS).

4.1.2 LOWER grapple until grapple is 6 to 12 inches above bail.

4.1.3 ENSURE grapple is open.

4.1.4 ROTATE grapple as necessary to achieve grapple to bail alignment.

4.1.5 Slowly LOWER grapple until SLACK CABLE Light is lit.

S97.0.M, Rev. 12 Page 7 of 26 JAD/jad NOTE Steps 4.1.6 through 4.1.10 shall be double verified by the Fuel Handling Director (FHD) AND Refuel Platform Operator (RPO)

OR Spotter.

4.1.6 VERIFY proper core component location AND orientation.

4.1.7 VERIFY the following, THEN NOTIFY FHD of grapple position.

Grapple is centered over bail handle.

Hoist Position indication agrees with value listed in Attachment 2 for item seated in Fuel Pool Storage Rack.

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

4.1.8 WHEN directed by FHD, THEN ENGAGE grapple, AND VERIFY GRAPPLE ENGAGED Light is lit.

4.1.9 WHEN directed by FHD, THEN slowly RAISE load while ensuring HOIST LOADED Light is lit (fuel/dummy bundle only),

OR for skeleton fuel bundle VERIFY component movement.

4.1.10 CONTINUE raising until grapple is fully raised, THEN VERIFY NORMAL UP Light is lit.

4.1.11 IF a double blade guide is being transferred through the cattle chute, THEN RAISE the grapple beyond NORMAL UP using the Hoist Override to -4.0 inches as indicated by Hoist Encoder.

4.1.12 GO TO appropriate "Release Location" section of this procedure as directed by FHD.

S97.0.M, Rev. 12 Page 8 of 26 JAD/jad 4.2 Pickup Location - Reactor Core 4.2.1 POSITION Refuel Platform Mast over desired core component in accordance with Core Component Transfer Authorization Sheet (CCTAS).

4.2.2 LOWER grapple until grapple is 6 to 12 inches above bail.

4.2.3 ENSURE grapple is open.

4.2.4 ROTATE grapple as necessary to achieve grapple to bail alignment.

4.2.5 Slowly LOWER grapple until SLACK CABLE Light is lit.

NOTE Steps 4.2.6 through 4.2.10 shall be double verified by the Fuel Handling Director (FHD)

AND Refuel Platform Operator (RPO)

OR Spotter.

4.2.6 VERIFY proper core component location AND orientation.

4.2.7 VERIFY the following, THEN NOTIFY FHD of grapple position.

Grapple is centered over bail handle.

Hoist Position indication agrees with value listed in Attachment 2 for item seated in core.

4.2.8 WHEN directed by FHD, THEN ENGAGE grapple, AND VERIFY GRAPPLE ENGAGED Light is lit.

S97.0.M, Rev. 12 Page 9 of 26 JAD/jad NOTE IF load is a Fuel Bundle, THEN FHD notifies Unit Reactor Operator of pending fuel removal from the core.

4.2.9 WHEN directed by FHD, THEN RAISE load AND VERIFY HOIST LOADED Light is lit (fuel/dummy bundle only).

4.2.10 CONTINUE raising until core component is clear of core.

1. VERIFY HOIST Position indicates less than 355.0 inches.

2. VERIFY item is clear of top guide.

NOTE IF load is a Fuel Bundle, THEN FHD notifies Unit Reactor Operator that fuel bundle has cleared core.

4.2.11 IF load is to be transferred through transfer canal, THEN CONTINUE raising until grapple is fully raised THEN VERIFY NORMAL UP Light is lit.

1. IF load is a double blade guide, THEN RAISE the grapple beyond NORMAL UP using Hoist Override to -4.0 inches as indicated on Hoist Encoder.

4.2.12 GO TO appropriate "Release Location" section of this procedure as directed by FHD.

$97.0.M, Rev. 12 Page 10 of 26 JAD/jad 4.3 Pickup Location - Fuel Preparation Machine 4.3.1 VERIFY Fuel Prep Machine carriage is fully LOWERED.

NOTE A CCTAS is not required for pickup of the dummy bundle.

4.3.2 Carefully POSITION Refuel Platform Mast over fuel prep machine in accordance with Core Component Transfer Authorization Sheet (CCTAS).

4.3.3 LOWER grapple until grapple is 6 to 12 inches above bail.

4.3.4 DEPRESS GRAPPLE LOCKOUT BYPASS push button.

4.3.5 ENSURE grapple is open.

4.3.6 ROTATE grapple as necessary to achieve grapple to bail alignment.

4.3.7 Slowly LOWER grapple until SLACK CABLE Light is lit.

NOTE Steps 4.3.8 through 4.3.13 shall be double verified by the Fuel Handling Director (FHD) and Refuel Platform Operator (RPO) or Spotter.

4.3.8 VERIFY proper core component location AND orientation.

S97.0.M, Rev. 12 Page 11 of 26 JAD/jad 4.3.9 VERIFY the following, THEN NOTIFY FHD of grapple position.

• Grapple is centered over bail handle

• Hoist Position indication agrees with value listed in Attachment 2 for item seated in fuel prep machine.

4.3.10 WHEN directed by FHD, THEN ENGAGE grapple, AND RELEASE GRAPPLE LOCKOUT BYPASS push button.

4.3.11 VERIFY GRAPPLE ENGAGED Light is lit.

4.3.12 WHEN directed by FHD, THEN slowly RAISE load AND VERIFY HOIST LOADED Light is lit (fuel/dummy bundle only),

OR for skeleton fuel bundle visually VERIFY component movement.

4.3.13 CONTINUE raising until grapple is fully raised, THEN VERIFY NORMAL UP Light is lit.

4.3.14 GO TO appropriate "Release Location" section of this procedure as directed by FHD.

$97.0.M, Rev. 12 Page 12 of 26 JAD/jad U**- 4.4 Pickup Location - Bundle SiDpina Canister 4.4.1 VERIFY Bundle Sipping Canister lid is open.

NOTE A CCTAS is not required for pickup of the dummy bundle.

4.4.2 POSITION Refuel Platform Mast over desired Bundle Sipping Canister in accordance with Core Component Transfer Authorization Sheet (CCTAS).

4.4.3 LOWER grapple until grapple is 6 to 12 inches above bail.

4.4.4 ENSURE grapple is open.

4.4.5 ROTATE grapple as necessary to achieve grapple to bail alignment.

4.4.6 Slowly LOWER grapple until SLACK CABLE Light is lit.

NOTE

1. Steps 4.4.7 through 4.4.11 shall be double verified by the Fuel Handling Director and Refuel Platform Operator or Spotter.

2. Expected hoist position indication is determined and posted on Attachment 2 using the dummy bundle in subsection 4.9.

4.4.7 VERIFY proper core component location AND orientation.

4.4.8 VERIFY the following, THEN NOTIFY FHD of grapple position.

6 Grapple is centered over bail handle 0 Hoist Position indication agrees with value posted on Attachment 2 for item seated in Bundle Sipping Canister.

S97.0.M, Rev. 12 Page 13 of 26 JAD/jad 4.4.9 WHEN directed by FHD, THEN ENGAGE grapple AND VERIFY GRAPPLE ENGAGED Light is lit.

4.4.10 WHEN directed by FHD, THEN slowly RAISE load while ensuring HOIST LOADED Light is lit (fuel/dummy bundle only).

4.4.11 CONTINUE raising until grapple is fully raised, THEN VERIFY NORMAL UP Light is lit.

4.4.12 GO TO appropriate "Release Location" section of this procedure as directed by FHD.

IC 4.5 Release Location - Fuel Pool Storaae Rack or Cask Pit NOTE A CCTAS is not required for pickup of the dummy bundle.

4.5.1 POSITION core component over desired location in accordance with Core Component Transfer Authorization Sheet (CCTAS).

4.5.2 ROTATE core component as necessary to achieve proper orientation.

4.5.3 PERFORM Double Verification to ensure proper core component location AND orientation.

4.5.4 WHEN directed by FHD, THEN LOWER hoist until core component is seated AND SLACK CABLE Light is lit.

$97.0.M, Rev. 12 Page 14 of 26 JAD/jad NOTE Steps 4.5.5 through 4.5.8 shall be double verified by the Fuel Handling Director (FHD)

AND Refuel Platform Operator (RPO)

OR Spotter.

4.5.5 VERIFY the following, THEN NOTIFY FHD of grapple position.

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

• Hoist Position indication agrees with value listed in Attachment 2 for item seated in Fuel Storage Rack, OR per M-053-006, subsection 5.4, for a bundle seated in a cask.

4.5.6 WHEN directed by FHD, THEN RELEASE grapple.

1. IF in cask, THEN DEPRESS Grapple Lockout Bypass push button.

4.5.7 VERIFY grapple is open.

4.5.8 Slowly RAISE grapple while verifying HOIST LOADED remains out, AND grapple remains free of bail handle.

4.5.9 RECORD completion of component transfer on CCTAS.

4.6 Release Location - Reactor Core 4.6.1 POSITION core component above desired location in accordance with Core Component Transfer Authorization Sheet (CCTAS).

4.6.2 LOWER load until hoist position indicates approximately 355 inches, THEN STOP lowering.

4.6.3 ROTATE core component as necessary to achieve proper orientation.

4.6.4 PERFORM Double Verification to ensure proper core component location AND orientation.

$97.0.M, Rev. 12 Page 15 of 26 JAD/jad NOTE IF Load is a Fuel Bundle, THEN FHD notifies Unit Reactor Operator of pending fuel insertion in core.

4.6.5 WHEN directed by FHD, THEN LOWER load until SLACK CABLE Light is lit.

NOTE Steps 4.6.6 through 4.6.8 shall be double verified by the Fuel Handling Director (FHD)

AND Refuel Platform Operator (RPO)

OR Spotter.

4.6.6 VERIFY the following, THEN NOTIFY FHD of grapple position.

0 Component elevation appears equivalent to other components in the Reactor Core.

0 Hoist Position indication agrees with value listed in Attachment 2 for item fully seated in Reactor Core.

4.6.7 WHEN directed by FHD, THEN RELEASE grapple, AND VERIFY grapple is open.

4.6.8 Slowly RAISE grapple while verifying HOIST LOADED light remains out.

4.6.9 RECORD completion of component transfer on CCTAS.

S97.0.M, Rev. 12 Page 16 of 26 JAD/jad NOTE IF Load is a Fuel Bundle, THEN FHD notifies Unit Reactor Operator of completion of fuel insertion in core.

4.7 Release Location - Fuel Preparation Machine 4.7.1 ENSURE Fuel Prep Machine carriage is fully lowered.

NOTE A CCTAS is not required for pickup of the dummy bundle.

4.7.2 Carefully POSITION component over desired fuel prep machine in accordance with Core Component Transfer Authorization Sheet (CCTAS).

4.7.3 ROTATE component as necessary to achieve proper alignment.

4.7.4 PERFORM Double Verification to ensure proper core component location AND orientation.

4.7.5 WHEN directed by FHD, THEN LOWER load until SLACK CABLE Light is lit.

$97.0.M, Rev. 12 Page 17of 26 JAD/jad NOTE Steps 4.7.6 through 4.7.9 shall be double verified by the Fuel Handling Director (FHD)

AND Refuel Platform Operator (RPO)

OR Spotter.

4.7.6 VERIFY Hoist Position indication agrees with value listed in Attachment 2 for item fully seated in fuel prep machine, THEN NOTIFY FHD of grapple position.

4.7.7 WHEN directed by FHD, THEN RELEASE grapple, AND DEPRESS GRAPPLE LOCKOUT BYPASS push button.

4.7.8 VERIFY grapple is open.

4.7.9 Slowly RAISE grapple while verifying HOIST LOADED light remains out, AND VERIFY grapple remains free of bail handle.

4.7.10 RELEASE GRAPPLE LOCKOUT BYPASS push button.

4.7.11 RECORD completion of component transfer on CCTAS.

4.8 Release Location - Bundle Sipping Canister 4.8.1 VERIFY Bundle Sipping Canister lid is open.

4.8.2 POSITION fuel bundle over desired Bundle Sipping Canister in accordance with Core Component Transfer Authorization Sheet (OCTAS).

4.8.3 ROTATE fuel bundle as necessary to achieve proper insertion alignment.

$97.0.M, Rev. 12 Page 18 of 26 JAD/jad 4.8.4 PERFORM Double Verification to ensure proper core component location AND orientation.

4.8.5 WHEN directed by FHD, THEN LOWER load until SLACK CABLE light is lit.

NOTE

1. Steps 4.8.6 through 4.8.8 shall be double verified by the Fuel Handling Director (FHD) and Refuel Platform Operator (RPO) or Spotter.

2. Expected hoist position indication is determined and posted on Attachment 2 using the dummy bundle in subsection 4.9.

4.8.6 VERIFY the following, THEN NOTIFY FHD of grapple position.

• Fuel Bundle is fully seated in the Bundle Sipping Canister.

• Hoist Position indication agrees with value posted on Attachment 2 for item seated in Bundle Sipping Canister.

4.8.7 WHEN directed by FHD, THEN RELEASE grapple, AND VERIFY grapple is open.

4.8.8 Slowly RAISE grapple while verifying HOIST LOADED light remains out.

4.8.9 RECORD completion of component transfer on CCTAS.

4.9 Determination of Hoist Position for Bundle Seated in Sipping Canister NOTE A CCTAS is not required for pickup of the DUMMY bundle.

4.9.1 PICKUP DUMMY Bundle in accordance with subsection 4.1.

4.9.2 VERIFY Bundle Sipping Canister lid is open.

$97.0.M, Rev. 12 Page 19 of 26 JAD/jad 4.9.3 POSITION DUMMY Bundle over Bundle Sipping Canister AND ROTATE DUMMY Bundle to achieve alignment.

4.9.4 WHEN directed by FHD, THEN slowly LOWER hoist until DUMMY Bundle is seated r AND SLACK CABLE Light is lit.

4.9.5 VERIFY DUMMY Bundle is seated in Bundle Sipping Canister using r__

underwater camera.

NOTE The DIMENSION (Target Hoist Position) for a fuel bundle seated in a Bundle Sipping Canister (refer to Attachment 2) is calculated by subtracting 1.5 inches from, AND adding 0.5 inches to, the Hoist Position Indication obtained below.

4.9.6 RECORD Hoist Position Indication AND CALCULATE the DIMENSION for each Bundle Sipping Canister below:

CANISTER ID/ HOIST POSITION LOCATION INDICATION DIMENSION 1.

2.

4.9.7 WHEN directed by FHD, THEN slowly RAISE DUMMY Bundle while ensuring HOIST LOADED Light-1 is lit. LEE 4.9.8 CONTINUE raising until grapple is fully raised, ED THEN VERIFY NORMAL UP Light is lit.

4.9.9 REPEAT steps 4.9.2 through 4.9.8 for each additional Bundle Sipping Canister.

4.9.10 WHEN directed by the FHD, THEN GO TO appropriate subsection of this procedure, AND RETURN the DUMMY Bundle to its "As Found" location.

S97.0,.M, Rev. 12 Page 20 of 26 JAD/jad 4.9.11 RECORD ID/ Location, Hoist Position Indication, and DIMENSION for FPCl each Bundle Sipping Canister in the FHD logbook.

4.9.12 RECORD the ID/ Location and DIMENSION for each Bundle Sipping rP~C Canister on the appropriate page of Attachment 2, AND POST a copy of Attachment 2 on the associated Refuel Platform mast.

4.10 "In-Process" Adjustment of Bridge/Trolley Encoders 4.10.1 POSITION Refuel platform Mast over desired core component location.

4.10.2 LOWER grapple until grapple is 6 to 12 inches above bail.

4.10.3 ENSURE grapple is open.

4.10.4 ROTATE grapple as necessary to achieve grapple to bail alignment.

4.10.5 Slowly LOWER grapple until SLACK CABLE Light is lit.

NOTE Steps 4.10.6 through 4.10.12 shall be double verified by the Fuel Handling Director (FHD)

AND Refuel Platform Operator (RPO)

OR Spotter.

4.10.6 VERIFY proper core component location AND orientation.

4.10.7 VERIFY the following, THEN NOTIFY FHD of grapple position.

"* Grapple is centered over bail handle.

"* Hoist position indication agrees with value listed in Attachment 2 for item seated in core.

S97.0.M, Rev. 12 Page 21 of 26 JAD/jad 4.10.8 RECORD "As Found" encoder readout position indication AND Model 1200 Power Supply thumbwheel switch settings for Bridge Position (X)

AND Trolley Position (Y) in the FHD logbook.

4.10.9 IF required, THEN ADJUST thumbwheel switches on Model 1 200 Readout Power Supply for Bridge Position (X)

AND Trolley Position (Y) to obtain desired core location as determined by encoder readout position indication.

4.10.10 RECORD "As Left" encoder readout position indication AND Model 1200 Power Supply thumbwheel switch settings for Bridge Position (X)

AND Trolley Position (Y) in the FHD logbook.

4.10.11 ENSURE grapple is open.

4.10.12 WHEN directed by FHD, THEN slowly RAISE grapple while verifying Hoist Loaded light remains out AND grapple remains free of bail handle.

$97.0.M, Rev. 12 Page 22 of 26 JAD/jad

5.0 REFERENCES

5.1 UFSAR Section 9.1.4.2.10.2 5.2 UFSAR Section 7.7.1.15.3 5.3 UFSAR Section 15.4.1 5.4 F21-EO03-KO06, Operation and Maintenance Instructions, Refueling Platform, Vol. I 5.5 F21-EO03-KO06, Operation and Maintenance Instructions, Refueling Platform, Vol. II 5.6 PBAPS memo J. F. Franz to Plant Superintendents, 02/01/91 5.7 EIR #92-04-19 5.8 MOD 6248, Refuel Platform Mast Mounted Underwater Camera System 5.9 Nuclear Emergency Plan 5.10 NSAC/164L, Guidelines for BWR Reactivity Control During Refueling 5.11 A-C-300, Reactivity Management Program 5.12 GE SIL 594, Refuel Platform Triangular Mast Drag Loading 5.13 UFSAR Section 15.7.4 and 15.7.6 and PECO Calculation LM-033 "Methodology to Determine the Acceptability of Moving Loads over Irradiated Fuel Without Secondary Containment" 5.14 AR A1081310, E01, Evaluation of decay time required for new fuel bundle or dummy bundle movement in Unit 2 SFP without secondary containment 5.15 GE SIL No. 566 Supplement 1, Misaligned GE BWR fuel assemblies 5.16 INPO OE7535, Failed Fuel Bundle at Oyster Creek 5.17 MOD P00925, Service Pole Caddy on Refueling Bridge 5.18 MOD P00950, Fuel Floor Auxiliary Platform

S97.0.M, Rev. 12 Page 23 of 26 JAD/jad 6.0 TECHNICAL SPECIFICATIONS 6.1 3.9.1 6.2 3.9.3 6.3 3.9.5 6.4 3.9.6 6.5 3.9.8 6.6 3.9.9 6.7 3.9.10 7.0 INTERFACING PROCEDURES 7.1 FH-105, Core Component Movement - Core Transfers 7.2 FH-106, Core Component and Irradiated Item Movement - No Core Transfer 7.3 ON-120, Fuel Handling Problems 7.4 S97.1.A, Electrical, Mechanical, and Pneumatic Alignment/Checkout of Refueling Platform Bridge, Trolley and Main Hoist for Operation 7.5 ST-6-097-630-*, Core Alteration Testing for Offloading, Shuffling, and Reloading the Core 7.6 M-097-046, Control of Fuel Inspection Activities 7.7 M-097-035, Vacuum Sipping Irradiated BWR Fuel Assemblies 7.8 S97.1 .B, Fuel Floor Auxiliary Platform Start-up, Checkout, Operation and Shutdown

S97.0.M, Rev. 12 Page 2,4 of 26 JAD/jad ATTACHMENT 1 Page 1 of 1 LIMERICK REFUEL PLATFORM FLOOR INTERLOCKS INTERLOCK STATUS DISPLAY INITIATING CONDITIONS EFFECT ON OPERATIONS ROD BLOCK #1 BRIDGE NEAR OR OVER CORE CONTROL ROD WITHDRAWAL BLOCK AND (RDCS), ROD OUT BLOCK ANY HOIST FUEL LOADED ANNUNCIATOR - MCR ROD BLOCK #2 BRIDGE REVERSE STOP #1 BRIDGE NEAR OR OVER CORE (BRIDGE FORWARD STOP #1, if AND NO BRIDGE MOTION IN INDICATED reactor select switch in non-normal ANY HOIST FUEL LOADED DIRECTION position) AND ANY ROD NOT FULL IN BRIDGE REVERSE STOP #2 BRIDGE NEAR OR OVER CORE (BRIDGE FORWARD STOP #2, if AND NO BRIDGE MOTION IN INDICATED reactor select switch in non-normal RX MODE SWITCH NOT IN REFUEL DIRECTION position) OR CONTROL ROD NOT SELECTED BRIDGE NEAR OR OVER CORE AND MAIN HOIST INOPERATIVE FUEL HOIST INTERLOCK MAIN HOIST FUEL LOADED

(>550 LBS) (HOIST WILL NOT RAISE OR LOWER)

AND ANY ROD NOT FULL IN MONO AUX HOIST INTERLOCK BRIDGE NEAR OR OVER CORE MONO AUX HOIST INOPERATIVE AND AUX HOIST FUEL LOADED (HOIST WILL NOT RAISE OR LOWER)

(> 1500 LBS)

AND ANY ROD NOT FULL IN TROLLEY AUX HOIST INTERLOCK TROLLEY AUX HOIST INOPERATIVE (HOIST WILL NOT RAISE OR LOWER)

THERMAL OVERLOAD BRIDGE WILL NOT OPERATE OPER CHECK TIMER MOTOR FIELD LOSS TROLLEYS WILL NOT OPERATE UNDERVOLTAGE FAULT LOCKOUT MAIN HOIST OVERLOAD HOISTS WILL NOT OPERATE PHASE LOSS (BLOWN FUSE)

INSTANTANEOUS OVERCURRENT AIR OPERATED GRAPPLES GO OR TROLLEY DECK CABINET DOOR OPEN STAY CLOSED VARIABLE SPEED SWITCHES NOT NEUTRAL ON STARTUP CONTROL ROD WITHDRAWAL BLOCK - MCR (OVER CORE ONLY)

VARIABLE TEST IN PROGRESS TEST BOX CONNECTED DEPENDS ON TEST SWITCH POSITIOJ

S97.0.M, Rev. 12 Page 25 of 26 JAD/jad ATTACHMENT 2 Page 1 of 2 U/1 MAIN HOIST POSITION INDICATIONS NOTE: Position indications for single blade guid es are the same as for bundles.

DIMENSION BUNDLE ENTERING RACK 15" - 17" BUNDLE SEATED IN RACK 190"- 192" BUNDLE ENTERING CORE 375" - 377" 549" - 551" BUNDLE SEATED IN CORE DBG ENTERING FUEL RACK 12" - 14" DBG SEATED IN FUEL RACK 184" 189" DGB SEATED IN CRB RACK WITHOUT CRB SPACER 187" - 189" DGB SEATED IN CRB RACK WITH CRB SPACER 175.5" - 177.5" DBG ENTERING CORE 372" 374" DBG SEATED IN CORE 546" 548" DBG TRAVERSING CATTLE CHUTE -411 -4.5" BUNDLE SEATED IN FUEL PREP. MACHINE 164" - 166" BUNDLE SEATED IN FUEL PREP. MACHINE'S ROTATING INSPECTION FIXTURE 158" - 160" BOTTOM OF FUEL POOL approx. 372" BOTTOM OF CASK PIT approx. 422" BUNDLE SEATED IN BUNDLE SIPPING CANISTER ID/ LOCATION BUNDLE SEATED IN BUNDLE SIPPING CANISTER ID/ LOCATION

S97.0.M, Rev. 12 Page 26 of 26 JAD/jad ATTACHMENT 2 Page 2 of 2 U/2 MAIN HOIST POSITION INDICATIONS

=

NOTE: Position indications for single blade guides are the same as foir bundles.

DIMENSION BUNDLE ENTERING RACK 19" -21" BUNDLE SEATED IN RACK 194" - 196" BUNDLE ENTERING CORE 375" - 377" BUNDLE SEATED IN CORE 549" - 551" DBG ENTERING FUEL RACK 16" - 18" DBG SEATED IN FUEL RACK 191" - 193" DGB SEATED IN CRB RACK WITHOUT CRB SPACER 187"- 189" DGB SEATED IN CRB RACK WITH CRB SPACER 175.5" - 177.5" DBG ENTERING CORE 372" - 374" DBG SEATED IN CORE 546" - 548" DBG TRAVERSING CATTLE CHUTE -4" - -4.5" BUNDLE SEATED IN FUEL PREP. MACHINE 164"- 166" BUNDLE SEATED IN FUEL PREP. MACHINE'S ROTATING INSPECTION FIXTURE 158" -160" BOTTOM OF FUEL POOL approx. 372" BOTTOM OF CASK PIT approx. 422" BUNDLE SEATED IN BUNDLE SIPPING CANISTER ID/ LOCATION BUNDLE SEATED IN BUNDLE SIPPING CANISTER ID/ LOCATION

RE-C-40, Rev. 9 Page 1 of 47 JWH cms SQR YES PORC NO NQA NO 50.59 YES RESP MGR YES PECO Energy Company NUCLEAR GENERATION GROUP CORE COMPONENT TRANSFER AUTHORIZATION SHEET GENERATION AND ADMINISTRATION 1.0 PURPOSE This procedure provides instructions for generation and administrative control of Core Component Transfer Authorization Sheets (CCTAS) . (Ref. 3.1.4) 2.0 SCOPE This procedure applies to CCTAS generated for refueling, in-vessel maintenance, and non-refueling movement of core components.

This procedure replaced FH-605 (LGS) and RE-43 (PBAPS).

C 3.0 SOURCES & REFERENCES 3.1 SOURCE DOCUMENTS 3.1.1 LGS Event Investigation Reports, 92-04-27, 92-04-35 "Double Blade Guide Misposition" (A/R A0400493 eval 02) 3.1.2 EPRI NSAC 164L, "Guidelines for BWR Reactivity Control During Refueling", April 1992 3.1.3 PEP Issue 10000293 3.1.4 LGS UFSAR Section 13.5.1.20, (A/R A0411306 Eval 77) 3.1.5 LGS PORC Commitment #91-021 3.1.6 NCRS LG 92-00329, LG 92-000330 3.1.7 Nuclear Regulatory Commission, IE Circular 80-21 3.1.8 PEP Issue 10003697 3.1.9 PEP Issue 10005166 3.1.10 LGS EWR A0004257, Attachment A 3.1.11 LGS Unit 2 Licensing Report For Spent Fuel Storage Capacity Expansion (HOLTEC Calculation HI-931012 Section 9.4)

RE-C-40, Rev. 9 Page 2 of 47 3.1.12 CM-I, Source Document NRC URI 76-46/36; re: annotation of fuel transfer sheets for authenticity, (T01850) 3.1.13 CM-2, PBAPS Event Investigation Report 3-91-201, (T02075) 3.1.14 CM-3, PEP Issue 10000326, (T03250) 3.1.15 CM-4, Letter to NRC 8/19/96; re: Unit 1 Fuel Pool Capacity Limitation to 2500, (T03881) 3.1.16 CM-5, Letter to NRC 8/20/96; re: LGS Procedural Controls for Projected Spent Fuel Pool Heat Loads, (T03941) 3.1.17 PEP Issue 10009435 3.1.18 PEP Issue 10009589 3.1.19 ECR PB 98-02407, MOD P00758 Refueling Platform Controls Upgrade 3.1.20 PEP Issue 10010012 3.1.21 PEP Issue 10010407 3.1.22 PEP Issue 10011047 3.1.23 PEP Issue 10011130 3.2 CROSS REFERENCES 3.2.1 Procedure FM-C-4, "Generation of Core Component Transfer Authorization Sheets using SHUFFLEWORKS".

3.2.2 Procedure RE-C-44, "Accountability and Control of SNM".

3.2.3 ShuffleWorks User's Manual, Combustion Engineering Inc.

3.2.4 Procedure ST-R-002-930-2(3), "Refueling SDM Verification" (PBAPS Only).

3.2.5 Procedure FM-UG-423, "Determination of SRM/WRNM Count Rates" 3.2.6 Procedure SF-300, "TN-68 Cask Spent Fuel Assemblies Storage Selection and Document Requirements" (PBAPS only) 4.0 DEFINITIONS 4.1 CCTAS, CORE COMPONENT TRANSFER AUTHORIZATION SHEET:

An approved sequence specifying the movement of core components which include a paper copy and at PBAPS may include an electronic copy on disk for loading into the Refueling Platform computer.

4.2 ICA, ITEM CONTROL AREA: Area designated in ShuffleWorks

RE-C-40, Rev. 9 Page 3 of 47 allowed to contain SNM, i.e. fuel prep machine, fuel pool, reactor cores and casks.

4.3 CORE COMPONENT: A component which is or was an integral part of the reactor core. This includes fuel pins or assemblies (excluding "Dummy" bundles and individual fuel channels), control blades, local power range monitors, wide range neutron monitors, blade guides, fuel support pieces and startup sources. IRM/SRM/WRNM replacements above vessel are controlled by this procedure. Under vessel replacement of Nuclear Instruments (NIs) are controlled by reference 3.2.2.

4.4 SPECIAL NUCLEAR MATERIAL (SNM): Any material containing plutonium, U-233, or uranium enriched in U-233 or U-235. SNM is controlled by reference 3.2.2.

4.5 REFERENCE LOADING PATTERN: The specific core loading arrangement of the nuclear fuel for the next operating cycle. This arrangement of fuel is used for reload licensing analysis and is obtained from the associated Core Design Report.

4.6 SHUTDOWN MARGIN (SDM): Amount of reactivity by which the reactor is subcritical assuming all control rods are fully inserted except for the single control rod of highest reactivity worth which is assumed to be fully withdrawn and the reactor is in shutdown condition; cold (68 'F) and xenon free. CM-3, (Ref. 3.1.2).

4.7 SHUFFLEWORKS

Computer software which is used to generate fuel/core component sequences.

5.0 RESPONSIBILITY AND AUTHORITY 5.1 REACTOR ENGINEERING BRANCH MANAGER: CM-3 5.1.1 Assign a member(s) of staff to perform this procedure and generate CCTAS.

5.1.2 Authorize CCTAS generation and performance.

5.1.3 Designate individuals qualified to evaluate and authorize changes to CCTAS in accordance with section 8.4.

5.2 STAFF MEMBER(s) assigned to perform this procedure shall:

5.2.1 Maintain current data files for SHUFFLEWORKS.

5.2.2 Generate and review the CCTAS in accordance with section 8.0.

5.3 CCTAS USERS shall:

5.3.1 Ensure CCTAS is appropriate for the task to be performed.

RE-C-40, Rev. 9 Page 4 of 47 5.3.2 Ensure the CCTAS step completion is documented appropriately.

5.3.3 Return completed CCTAS to Reactor Engineering Branch.

5.3.4 Initiate CCTAS changes as required in accordance with section 8.4.

6.0 PREREQUISITES 6.1 Appropriate SDM model AND Once Burnt Bundle constraint have been identified by Nuclear Fuel Management (NFM) (applicable to refueling activities only).

6.2 Reference loading pattern is available (applicable to refueling activities only).

6.3 K-infinities, SDM criteria and radial weighting factors have been loaded into ShuffleWorks. (Fuel moves in reactor vessel only) CM-3.

6.4 IF CCTAS involves steps in the core, THEN determine neutron monitoring instrumentation (SRM or WRNM) applicable to CCTAS being generated. See Exhibit RE-C-40-11.

- 6.5 Information required for other CCTAS applications such as fuel pool reconfiguration, new fuel receipt, CRB exchanges and cask loading.

6.6 ICA files with current and accurate information.

6.7 Any fuel pool locations that are inaccessible or deemed to be unusable have been designated as "UNUSABLE" in the ShuffleWorks computer program. See Exhibits RE-C-40-9 & 10.

6.8 Any core components that are deemed unusable/not moveable (e.g., damaged blade guide, leaking fuel assembly, etc.)

have been designated as "UNUSABLE" in the shuffleWorks program. See Exhibits RE-C-40-9 & 10.

6.9 For a reload sequence, FSD has provided the predicted SRM/WRNM (as appropriate) count rates for the first four bundles surrounding each SRM or WRNM in accordance with Ref. 3.2.5.

6.10 For cask loading, an acceptable cask loading pattern has been developed in accordance with SF-300. (PBAPS only)

RE-C-40, Rev. 9 Page 5 of 47 7.0 PRECAUTIONS AND LIMITATIONS 7.1 When moving fuel in the reactor, sequences must meet the SRM or WRNM connectivity constraint as described in Exhibit RE-C-40-13.

7.2 Do not generate a CCTAS step which places fuel into a cell which has its associated control rod withdrawn.

7.3 Do not generate a CCTAS step which withdraws a fuel assembly or blade guide unless the control rod in the cell is supported diagonally by blade guides or fuel.

7.4 Do not place irradiated fuel with less than 5 year decay time within 3 feet of fuel pool gates (actual or storage locations). Refer to Exhibit RE-C-40-15 for impacted locations. (Ref. 3.1.10) (LGS ONLY) 7.5 Fuel assemblies discharged prior to 1R04 located in the Unit 1 spent fuel pool must be inspected or evaluated for debris prior to use in core. (Ref. 3.1.5) (LGS ONLY) 7.6 The spent fuel pool capacity is limited to 2500 fuel assemblies, and a nominal 6.625 inches center-to-center spacing between fuel assemblies shall apply, until the completion of the high density re-racking of the spent fuel pool. (LGS Unit 1 ONLY) CM-4 7.7 Single blade guides must be oriented such that their channel spacers are adjacent to the control rod. Place a note stating such requirement prior to CCTAS step which uses a single blade guide in the reactor core.

7.8 During complete offload/reload or core shuffle with SRM operable, bundles in the cells on the A/D, A/B, B/C, and C/D quadrant boundaries should be considered to be monitored by the D, B, C and C SRM respectively. Connectivity to these SRMs should be verified. See Exhibit RE-C-40-11.

7.9 CCTAS columns which are not applicable to the specific application should have N/A placed in the column which does not apply.

7.10 SHUFFLEWORKS shall be used to generate CCTAS when it is available and recognizes all the components to be moved.

CM-2

RE-C-40, Rev. 9 Page 6 of 47 C NOTE All open cells of a given fuel rack should be inspected when any of the cells of that rack are planned to be used (Ref. 3.1.22).

7.11 Prior to CCTAS use, NMD is to verify empty cells that will be used do not contain foreign material. Foreign material is not permitted in the component location.CM-2 7.12 CCTAS changes shall be made in accordance with Section 8.4 of this procedure. (Ref. 3.1.2) 7.13 For reload sequence, load four bundles around each SRM/WRNM prior to any other steps. (Ref. 3.1.2) Place a note on the CCTAS stating the predicted count rate for the first four bundles surrounding each SRM or WRNM.

7.14 IF peripheral core locations listed in Exhibit RE-C-40-10 are being used in the sequence, THEN verify a note is added prior to the step which states:

"Caution: Mast camera may interfere with core shroud"(PBAPS Only).

. NOTE (LGS ONLY)

The objective of performing RT-1-053-310-* is to confirm that adequate heat removal capacity is present in the target fuel pool. Performance of a new RT is not required if the results of a previous performance of the RT bounds the anticipated fuel pool configuration.

7.15 Before distributing a CCTAS which moves spent fuel into a Fuel Pool, RT-1-053-310-* must be or have been performed to ensure that adequate heat removal capacity is available in the Fuel Pool (LGS ONLY). CM-5 7.16 Movement of bundles into Fuel Pool rows "A" or "B" is difficult, because the spotter can NOT view the specified rows from the bridge. IF practical, THEN avoid rows "A" and "B" during outage work (LGS Unit 1 ONLY).

7.17 During a refueling outage, the CCTAS should not discharge fuel to locations within two feet of the spent fuel pool walls as this causes the refuel platform to move at slow speeds and causes unnecessary delays.

RE-C-40, Rev. 9 Page 7 of 47 7.18 Ensure that fuel is stored next to the fuel pool coupons.

For Unit 1, the coupons are located next to the cells noted in Exhibit RE-C-40-9. For Unit 2, the coupon tree may be moved such that it is surrounded by freshly discharged fuel assemblies. A refuel outage discharge plan should leave a space available for this requirement. If a bundle surrounding the Unit 2 coupon tree is moved, another freshly discharged bundle shall be moved to replace it. (LGS ONLY) 7.19 In order to avoid obstruction of the RHR and FPC discharge piping flow path to support natural circulation operation, Do Not load rack cells directly under and within two cells of this piping in the LGS 2 spent fuel pool. (LGS ONLY) 7.20 WHEN preparing CCTASs for new CRB receipt or CRE exchange where the combined CRB/FSP grapple may be used, THEN verify that locations for the new CRBs as well as locations planned for the discharge or temporarily stored CRBs have CRB spacers installed prior to using the locations either by documentation or direct observation. (LGS Only) 7.21 Sipping canisters may only be used in CRB rack cells that do not contain CRB spacers. (LGS only) 7.22 Fresh discharged fuel shall not be placed in the eastern most rows to prevent high exposure to personnel.

(Ref. 3.1.11) (LGS Unit 2 ONLY) 7.23 When generating a CCTAS to allow for the removal/reinstallation of a CRB/fuel support piece, it is desirable that at least one of the bundles face adjacent to the north-west quadrant (at LGS) or south-west quadrant (at PBAPS) of the fuel support piece is off-loaded, provided that SRM or WRNM connectivity constraint is met as described in exhibit RE-C-40-13. This is in order to allow camera access for verification of plunger engagement.

7.24 When preparing a CCTAS that includes re-channeling of fuel bundle(s), include a note prior to each step (as appropriate) which provides the expected channel serial number and requires the fuel handlers to check that the correct channel is being used. (Ref. 3.1.17)

RE-C-40, Rev. 9 Page 8 of 47 7.25 For items stored in locations designated in Exhibits RE-C-40-9 & 10, the location may be made usable and the item may be moved provided:

7.25.1 If the item is listed under Bad Fuel, the move is noted in the CCTAS to facilitate resolution of ARM alarms, AND 7.25.2 The item is not used in the core without, after being apprised of the item's status in Shuffleworks, specific FSD and Reactor Engineering Branch Manger approval is obtained, AND 7.25.3 Other constraints on the location (such as bundles next to Coupons) are met or the move is specifically approved by the System Manager or Reactor Engineering Branch Manager, AND 7.25.4 The new storage location is made unusable (unless the location is in-core) and a PPIS issued against the appropriate exhibit following item movement.

7.26 If it is determined that a bundle should not be used in-core (due to debris, failure, future inspections, etc.), then SHUFFLEWORKS shall be updated such that the bundle's storage location is made unusable and a note added to the bundle which describes the issue. If the bundle cannot be used in-core permanently, a PPIS to update Exhibits RE-C-40-9/10 should be created. (Ref. 3.1.18) 7.27 Spent Fuel Assemblies that are being transferred to a cask may be loaded into the cask in any orientation unless a specific orientation is desired, such as cask hold-down ring interference with the channel fasteners.

7.28 IF very old fuel is being moved, THEN ensure the CCTAS includes a note identifying this and that the following precautions should be taken: (Ref. 3.1.20)

1. Carefully monitor hoist load during lifting to promptly identify bundle tie rod failure.

2. Channel fasteners and bail handles have been found bent on old bundles which can make seating or releasing difficult.

3. Older style channel fasteners protrude further making it easier for fastener to catch when seating.

7.29 FOR CCTAS preparation in support of unit outage (Reference 3.1.21):

Ensure no current outage discharge fuel is placed in rack I7.29.1 rows 25-48 between rack columns A-H, inclusive (at LGS Unit 1), in rack rows 32-54 between rack columns TT-AB, inclusive (at LGS Unit 2) OR in rack rows A-G between rack columns 25 48, inclusive (at PBAPS) . (Ref. 3.1.21).

RE-C-40, Rev. 9 Page 9 of 47 7.29.2 Uninspected cells should be made unusable once pre-outage inspections are complete (Ref. 3.1.22).

7.30 For non-outage CCTAS preparation, add requirements to perform the following CCTAS steps, as applicable:

7.30.1 Following placement of spent fuel within 8 rows of spent fuel pool/reactor cavity gates or fuel pool/cask pit gates (LGS Only), contact HP to perform dose measurement at fuel pool gates at reactor cavity or fuel pool side.

7.30.2 Ensure general area dose rate reading at fuel pool gates at reactor cavity/ cask pit (LGS Only) or fuel pool side is acceptable per HP.

7.30.3 IF dose rate is unacceptable, return fuel bundle to original location or other location as designated by Reactor Engineering.

7.31 Ensure all four fuel assemblies off-loaded around each LPRM that will be replaced during the Maintenance window. IF this is not possible due to other constraints, THEN plan a mini-shuffle between the CRB/CRD AND LPRM maintenance windows.

7.32 Do not insert single blade guides to take the place of double blade guides in cells with the control rod withdrawn.

IC The single blade guide may damage the control rod during insertion or "kick out" to adjacent cells.

7.33 When moving core components between Spent Fuel Pools, the CCTAS cover sheet should contain a note reminding the FHD to contact HP to have the Reactor Buildings' 313' elevation properly posted for core component movement (LGS Only).

7.34 When moving LPRMS, ensure LPRM hanger number/rigging tag number is recorded on CCTAS via note associated with respective CCTAS movement step.

8.0 PROCEDURE SECTIONS 8.1 CCTAS GENERATION WITH SHUFFLEWORKS 8.1.1 Complete Exhibit RE-C-40-1, "CCTAS Information/Verification Sheet" with information that is applicable for the particular evolution.

8.1.2 Execute the SHUFFLEWORKS computer program in accordance with Exhibit RE-C-40-8.

8.1.3 IF the CCTAS are being generated automatically, THEN perform the following steps, Otherwise the following steps are N/A.

RE-C-40, Rev. 9 Page 10 of 47

1. Ensure the following constraints are turned on in SHUFFLEWORKS:

a. Shutdown Margin model specified by NFM in step 6.1.

b. SRM or WRNM Connection Path (consistent with neutron.

instrumentation determined in step 6.4)

c. SRM or WRNM Count Rate (consistent with neutron instrumentation determined in step 6.4)

d. Fuel Movement Device Mast Orientation

e. Control Rod Blade Support

f. Fuel Movement Device Unusable locations

g. Once Burnt Bundle constraint specified by NFN in step 6.1.

2. Enter the SHUFFLE menu, select automatic shuffle planning.

a. Supply information as requested by the SHUFFLEWORKS program (maintenance locations, discharge and temporary storage locations, bundles to be sipped/inspected).

b. Generate and save the sequence.

c. PBAPS ONLY: IF sequence is required to be loaded into Refueling Platform Computer "Fuel Machine Sequence" (.fms) format, THEN perform the following:

- Select Reports/Create fuel machine sequence

- Select appropriate sequence source and planning sequence

- Save the sequence to file (converts from .seq to .fms output)

- Select "WRITE SEQUENCE TO A DISK FILE"

- Enter "SHUFFLE" for output file name

- Verify "SHUFFLE.FMS" file was created

RE-C-40, Rev. 9 Page 11 of 47 Copy this file to a disk and label disk with CCTAS title CCTAS preparer shall initial and date the disk label.

3. Ensure SDM log values are above the cycle specific SDM specified by NFM and all applicable constraints are met. CM-3.

a. Confirm SDM limit is correct in appropriate SDM Model.

b. Verify the sequence with SHUFFLEWORKS.

c. Perform ST-R-002-930-2(3) for CCTASs containing steps which insert positive reactivity into the core. (PBAPS Only).

d. IF the SDM log values are below the cycle specific SDM value specified by NFM, THEN send the sequence to NFM for SDM evaluation. See FM-C-4.

4. Print the shuffle sequence and applicable ICA maps (if desired) via the Reports window and proceed to section 8.3 of this procedure.

8.1.4 IF the CCTAS are being generated interactively, THEN perform the following steps, Otherwise the following steps are N/A.

1. Ensure the following constraints are turned on in SHUFFLEWORKS:

a. Shutdown Margin model specified by NFM in step 6.1.

b. SRM or WRNM Connection Path (consistent with neutron instrumentation determined in step 6.4)

c. SRM or WRNM Count Rate (consistent with neutron instrumentation determined in step 6.4)

d. Fuel Movement Device Mast Orientation

e. Control Rod Blade Support

f. Fuel Movement Device Unusable locations

RE-C-40, Rev. 9 Page 12 of 47

g. Once Burnt Bundle constraint specified by NFM in step 6.1.

2. Enter the SHUFFLE menu, select interactive shuffle planning.

a. Move the desired component(s) from the initial ICA location to the desired ICA location.

3. Ensure all applicable constraints are met.

a. Verify and save the sequence with SHUFFLEWORKS.

b. PBAPS ONLY: IF sequence is required to be loaded into Refueling Platform Computer "Fuel Machine Sequence" (.fms) format, THEN perform the following:

Select Reports/Create fuel machine sequence Select appropriate sequence source and planning sequence Save the sequence to file (converts from

.seq to .fms output)

Select "WRITE SEQUENCE TO A DISK FILE" Enter "SHUFFLE" for output file name Verify "SHUFFLE FMS" file was created Copy this file to a disk and label disk with CCTAS title CCTAS preparer shall initial and date the disk label.

c. IF sequence involves moves in the core, THEN ensure SDM log values are above the cycle specific SDM specified by NFM. CM-3

1. Confirm SDM Limit is correct in appropriate SDM Model.

2. Perform ST-R-002-930-2(3) for CCTASs containing step which insert positive reactivity into the core. (PBAPS Only)

3. IF the SDM log values are below the cycle specific SDM value specified by NFM, THEN send the sequence to NFM for SDM evaluation.

See FM-C-4.

4. Print the shuffle sequence and applicable ICA maps (if

RE-C-40, Rev. 9 Page 13 of 47 desired) via the Reports window AND proceed to section 8.3 of this procedure.

8.1.5 IF the CCTAS are being generated for core OR bundle offload/reload, THEN perform the following steps, Otherwise, the following steps are N/A.

1. Ensure the following constraints are turned on in SHUFFLEWORKS:

a. SRM or WRNM Connection Path (consistent with neutron instrumentation determined in step 6.4)

b. SRM or WRNM Count Rate (consistent with neutron instrumentation determined in step 6.4)

c. Fuel Movement Device Mast Orientation

d. Control Rod Blade Support

e. Fuel Movement Device unusable locations

f. Once Burnt Bundle constraint specified by FSD in step 6.1.

2. Enter the SHUFFLE menu, select interactive shuffle planning.

a. Determine the required positioning of blade guides to support planned in-vessel maintenance activities.

b. For each quadrant, move bundles from core to spent fuel pool using the following guidelines:

1. IF SRMs were selected in step 6.4, THEN from core periphery, spiral toward the SRM leaving 4 fuel bundles around the SRM.

IF WRNMs were selected in step 6.4, THEN from core periphery, spiral toward the WRNM detector leaving 4 fuel bundles around each WRNM.

2. Remove fuel bundles from diagonally adjacent fuel cell locations in a cell where a double blade guide is to be located.

3. Install a double blade guide where fuel was removed.

RE-C-40, Rev. 9 Page 14 of 47

4. Remove remaining two bundles from the cell.

5. Perform steps 1 through 4 for all other core cells.

6. WHEN all other fuel has been offloaded, THEN remove last 16 bundles around the SRMs OR remove last 32 bundles around the WRNMs.

c. For each quadrant, move bundles from the spent fuel pool to the final core locations using the following guidelines: (Ref. 3.1.2)

1. Load 4 bundles around each SRM (IF SRMs were selected in step 6.4) OR each WRNM (IF WRNMs were selected in step 6.4). Place a note on the CCTAS prior to each step or group of steps stating the predicted count rates for the first four bundles surrounding each SRM or WRNM.

2. From the SRM OR WRNM, spiral towards core periphery

3. Load 2 fuel bundles in vacant locations

4. WHEN two fuel bundles are installed in a cell THEN remove blade guide.

5. Place fuel in vacant locations created by blade guide removal.

3. Verify AND save the sequences with SHUFFLEWORKS.

4. PBAPS ONLY: IF sequence is required to be loaded into Refueling Platform Computer "Fuel Machine Sequence"

(.fms) format, THEN PERFORM the following:

Select Reports/Create fuel machine sequence Select appropriate sequence source and planning sequence Save the sequence to file (converts from

.seq to .fms output)

Select "WRITE SEQUENCE TO A DISK FILE" Enter "RELOAD" OR "OFFLOAD" for output file name, as appropriate.

Verify the appropriate FMS file was created Copy this file to a disk and label disk

RE-C-40, Rev. 9 Page 15 of 47 with CCTAS title CCTAS preparer shall initial and date the disk label.

5. Print the offload/reload sequence AND applicable ICA maps (if desired) via the Reports window AND proceed to section 8.3 of this procedure.

8.1.6 During CCTAS execution, update CCTAS status log sheet (see Exhibit RE-C-40-2).

8.2 CCTAS GENERATION WITHOUT SHUFFLEWORKS 8.2.1 Generate CCTAS using a word processor.

1. The CCTAS shall contain the following information:

- Title

- Page #/total # of pages

- Written, reviewed, and authorized spaces

- Date

- Step #

- Component Serial #

- Orientation (when applicable)

- From location

- To location

- FHD signoff

- RPO signoff

- CRO signoff (when applicable)

- SRM/WRNM count rate columns consistent with neutron instrumentation determined in step 6.4 (when applicable).

- Date/Time for each step

RE-C-40, Rev. 9 Page 16 of 47 8.2.2 IF generating CCTAS for LPRM replacement THEN perform the following steps, Otherwise, the following steps are N/A.

1. Use Exhibit RE-C-40-3A or RE-C-40-3B as a format/info guide (Separate CCTASs may be generated for batch removal/bending and for installation of LPRMs).

2. Identify LPRM to be replaced

3. Ensure blade guide does not interfere with LPRM

4. Specify LPRM removal and storage locations. Storage locations to avoid due to area radiation monitors are:

a. LGS North Walls

b. PBAPS Unit 2 North Wall

c. PBAPS Unit 3 South Wall

5. Use LPRM serial number as core component ID 8.2.3 IF generating CCTAS for control rod withdrawal, THEN perform the following steps.

Otherwise, the following steps are N/A.

1. Use Exhibit RE-C-40-4A or RE-C-40-4B as a format/info guide.

2. Identify control rods to be withdrawn

3. Verify cell is offloaded

4. Select control rod in offloaded cell

5. Withdraw control rod in offloaded cell

6. Uncouple control rod in offloaded cell NOTE Fuel Support Pieces and Guide Tubes must be returned to the same core cells they were removed from unless specifically noted in the CCTAS and agreed upon by NMD.

8.2.4 IF generating the CCTAS for control rod replacement, THEN perform the following steps.

Otherwise, the following steps are N/A.

1. Use Exhibit RE-C-40-5A or RE-C-40-5B as a format/info guide

2. Identify control rod(s) to be replaced

RE-C-40, Rev. 9 Page 17 of 47

3. Verify control rod is uncoupled

4. Remove blade guide from target cell

5. Remove fuel support piece from target cell

6. Remove spent control rod from cell to storage location

7. IF Guide Tube removal is required, THEN provide steps to:

a. Place Blade Guide and Fuel Support Piece in storage locations.

b. Remove Guide Tube and place in storage location (if required).

c. Return Guide Tube to core cell.

d. Pick up Fuel Support Piece and Blade Guide from storage locations.

8. Move new control rod from storage location to core cell

9. Replace fuel support piece in target cell

10. Replace blade guide in target cell

11. IF the NMD combined Blade/Fuel Support Piece grapple is to be used, THEN add appropriate notes stating that steps 5 and 6, and steps 8 and 9 above may be performed concurrently.

8.2.5 IF generating CCTAS for non-core transfer OR spent fuel assemblies transfer to/from cask, THEN perform the following steps.

Otherwise, the following steps are N/A.

1. Use Exhibit RE-C-40-6A or RE-C-40-6B as a format/info guide

2. Identify core component to be transferred

3. Specify the starting and resting location of the core component.

8.2.6 IF SHUFFLEWORKS is unavailable AND CCTAS for offload/reload fuel moves as described in step 8.1.5 are required, THEN perform the following step.

Otherwise, the following steps are N/A.

1. Use Exhibit RE-C-40-7A or RE-C-40-7B as a format/info guide

2. Perform Steps 8.1.5.2.a through 8.1.5.2.c.

RE-C-40, Rev. 9 Page 18 of 47 8.2.7 Proceed to the section 8.3 of this procedure.

8.2.8 During CCTAS execution, update CCTAS status log sheet (see Exhibit RE-C-40-2).

8.3 CCTAS REVIEW/APPROVAL/DISTRIBUTION 8.3.1 The CCTAS preparer shall perform the following steps:

1. Ensure no unexplained/unexpected constraint violations exist. (Ref. 3.1.2)

2. Ensure component identification numbers, orientations and locations are correct. (Ref. 3.1.2)

3. Ensure moves containing known/suspected fuel failures are noted in CCTAS to facilitate HP monitoring/resolution of ARM alarms.

4. Annotate steps which insert or remove a bundle from next to an SRM/WRNM (if time allows)

5. Ensure accuracy and legibility. (Ref. 3.1.3.)

6. Ensure the prepared by, reviewed by, AND authorized by names are printed on each sheet. CM-i

7. PBAPS ONLY: IF the shuffleworks file is to be loaded into the Refueling Platform computer, THEN ensure the prepared by, reviewed by AND authorized by name's are printed on the electronic disk copy label.

8. For control blade AND LPRM replacements, ensure specific item types are placed in required locations.

(Ref. 3.1.8)

9. Fill out appropriate information on CCTAS status log sheet (see Exhibit RE-C-40-2).

10. Generate AND sign the CCTAS Instruction/Approval sheet.

(Exhibit RE-C-40-12) CM-i.

11. PBAPS ONLY: IF the shuffleworks file is to be loaded into the Refueling Platform Computer, THEN initial and date the electronic disk copy label.

12. Ensure Fuel Pool decay heat removal capacity has been demonstrated in accordance with RT-I-053-310-* for any increased heat load on Fuel Pool (LGS Only). CM-5

RE-C-40, Rev. 9 Page 19 of 47

13. PBAPS ONLY: IF CCTAS moves the fuel to the final configuration, THEN perform the following:

a. Step to the end of the sequence using SHUFFLEWORKS.

b. Print "Current" core map AND spent fuel pool map.

c. Verify "Current" core map matches Core Design Report (reference loading pattern).

d. Complete Exhibit RE-C-40-14 AND attach to spent fuel pool map.

14. Complete Exhibit RE-C-40-1, "CCTAS Information /

Verification Sheet" 8.3.2 The CCTAS reviewer shall perform the following:

1. Ensure no unexpected/unexplained constraint violations exist. (Ref. 3.1.2)

2. Ensure component identification numbers, orientations and locations are correct. (Ref. 3.1.2)

3. Ensure moves containing known/suspected fuel failures are noted in CCTAS to facilitate HP monitoring/resolution of ARM alarms.

4. Ensure steps which insert or remove a bundle from next to an SRM/WRNM are correctly annotated (if performed by preparer).

5. Ensure accuracy and legibility. (Ref. 3.1.3)

6. Ensure the preparer and authorized names are printed on each sheet. CM-i

7. PBAPS ONLY: IF the shuffleworks file is to be loaded into the Refueling Platform computer, THEN ensure the preparer and authorized names are printed on the electronic disk copy label.

8. For control blade AND LPRM replacement CCTAS, ensure specific item types are placed in required locations.

(Ref. 3.1.8)

9. Ensure maximum heat load/temperature of SFP is within limits in accordance with RT-1-053-310-* for any increased heat load on Fuel Pool (LGS Only). CM-5

RE-C-40, Rev. 9 Page 20 of 47

10. Complete Exhibit RE-C-40-1, "CCTAS Information /

Verification Sheet"

11. Sign the CCTAS Instruction/Approval sheet.

(Exhibit RE-C-40-12) CM-i

12. PBAPS ONLY: IF the shuffleworks file is to be loaded into the Refueling Platform Computer, THEN initial and date the electronic disk copy label.

13. PBAPS ONLY: IF CCTAS moves the fuel to the final configuration, THEN perform the following:

a. Step to the end of the sequence using SHUFFLEWORKS.

b. Print "Current" core map AND spent fuel map.

c. Verify "Current" core map matches Core Design Report (reference loading pattern).

d. Complete Exhibit RE-C-40-14.

8.3.3 The CCTAS authorizer shall:

1. Sign the CCTAS info Instruction/Approval sheet (RE-C-40-12) sheet indicating authorization to execute the steps. CM-i.

2. PBAPS ONLY: IF the shuffleworks file is to be loaded into the Refueling Platform Computer, THEN initial and date the electronic disk copy label.

8.3.4 Distribute copies of approved CCTAS to the following locations.

1. Control Room (when performing in-core moves or as requested for information only).

2. Refuel platform (2 copies plus electronic disk copy if required)

3. Other locations as deemed necessary by the evolution. (e.g., Fuel Floor Coordinator info only copy)

4. Cognizant personnel from Nuclear Fuel Management (Control Blade replacement CCTASs only) (Ref. 3.1.8)

5. Dry Cask Storage Campaign Personnel (For cask loading/unloading only)

RE-C-40, Rev. 9 Page 21 of 47 8.4 CCTAS CHANGE PROCESS AFTER REVIEW/APPROVAL NOTE PBAPS ONLY: A pen and ink change made to the paper copy CCTAS does NOT require a change to the electronic copy CCTAS loaded in the Refueling Platform computer. Refueling Platform may be operated in the Manual Mode to execute the affected steps using the paper CCTAS. Full Automatic Mode operation using the electronic copy CCTAS loaded in the Refueling Platform computer may resume after completion of the pen and ink changed steps.

8.4.1 IF it is deemed necessary to change the CCTAS to support unanticipated conditions on the fuel floor, THEN perform the following steps. (Ref. 3.1.2)

1. Suspend CCTAS execution prior to execution of CCTAS step requiring change.

2. Contact a member of Reactor Engineering who is authorized to make changes as listed on the CCTAS instruction sheet, Exhibit RE-C-40-12.

3. Describe the reason for the change and a proposed revision 8.4.2 The Reactor Engineering group member contacted shall perform the following steps based on the information provided.

(Ref. 3.1.3)

1. Evaluate the effect of the change on the remainder of the CCTAS sequence AND all other previously approved CCTAS's (including completed and partially completed sequences) AND make appropriate changes to maintain congruency of sequence.

RE-C-40, Rev. 9 Page 22 of 47

2. IF all the changes involve one of the situations listed below, THEN the changes do not affect SDM AND can be processed as a pen & ink change.

a. Blade guides

b. LPRMs

c. WRNMs

d. Fuel in or being moved to the spent fuel pool

e. Control rod blade changes in defueled cells or in the spent fuel pool

f. Fuel in or being moved to or from a storage cask

g. All of the bundles currently in the core are in their final configuration AND the fuel bundle(s) of interest are being moved to their final core configuration (final core reload pattern remains the same)

3. IF any of the changes involve a fuel assembly with a change in core configuration, THEN use SHUFFLEWORKS to ensure SDM is met in accordance with Section 8.1 and follow approval process in Section 8.3. CM-3

4. IF the changes do not adversely affect SDM, THEN perform the following:

a. The Fuel Handling Director (or Designated Alternate) or Reactor Engineer shall perform pen & ink change on Refuel Floor copies.

b. The Reactor Engineering group member shall perform pen & ink change on the original CCTAS AND troubleshooting guides when applicable. Updates pen & ink change log if used.

c. The Reactor Engineering group member, Fuel Handling Director (or Designated Alternate)

OR CRO shall perform the Pen & Ink change on the control room copy of the CCTAS (if applicable).

d. The Reactor Engineering group member OR CCTAS Lead shall make the change to the sequence Saved in SHUFFLEWORKS.

RE-C-40, Rev. 9 Page 23 of 47

e. The pen & ink change should follow the following format.

- Single line through item to be changed Date AND initials of both Fuel Handling Director (or Designated Alternate) AND Reactor Engineering group member

5. IF the change is believed to have a significant effect on decay heat calculations, THEN consider reperforming RT-I-053-310-* AND follow approval process in Section 8.3 (LGS Only). CM-5 8.5 CCTAS TROUBLESHOOTING GUIDE DEVELOPMENT 8.5.1 IF desired, THEN develop CCTAS troubleshooting guide so any changes can be evaluated appropriately.

1. The guide should contain the following information:

a. Appropriate CCTAS sequences

b. Maps at key milestones/configurations such as:

(Ref. 3.1.2)

- LPRM's/WRNM's to be replaced

- CRD's requiring maintenance

- Control blades requiring replacement

- Core maintenance configuration

c. List of bundle K-infinity for fuel moved during refueling

d. Copy of RE-C-40

e. CCTAS Info sheet

f. Pen & Ink Change/CCTAS Revision Status Log.

g. Lists/maps of maintenance control blades and drives and LPRMS.

h. Lists/maps of previously inspected fuel pool locations suitable for item storage.

i. Copies of/support information for RE sign offs in any applicable FH procedures.

2. Provide troubleshooting guide to Reactor Engineering group members authorized to approve changes.

RE-C-40, Rev. 9 Page 24 of 47 9.0 DOCUMENTATION 9.1 Completed CCTAS sheets AND electronic disk copy OR copies of contaminated sheets shall be returned to Reactor Engineering by the CCTAS users.

9.1.1 IF copies of contaminated CCTASs are received, THEN cover sheet should be annotated "Copy - Original Contaminated", initialed, and dated.

9.2 IF the CCTAS become contaminated, AND copies cannot be made, THEN the CCTAS originals can be used to document the completion of the CCTAS steps.

9.2.1 Note on the original CCTAS that field copies were contaminated and were executed between days X and Y.

9.3 Reactor Engineering shall periodically send completed CCTAS OR copies of appropriate CCTAS if contaminated, to NRMS and NFM (if required).

9.4 Update SHUFFLEWORKS files upon completion of the CCTAS.

Every implemented CCTAS shall be incorporated in SHUFFLEWORKS regardless of whether or not the CCTAS appears to change the location/orientation of any fuel bundle.

(Ref. 3.1.9) 9.5 Update SNM records in accordance with RE-C-044, Accountability and Control of SNM. If re-channeling has been performed, ensure channel serial number's are appropriately updated on the Fuel History Sheets.

9.6 Backup SHUFFLEWORKS files appropriately.

9.7 Provide copies of completed blade replacement CCTASs to FSD.

9.8 Provide copies of SHUFFLEWORKS sequence files (or copy of controlled CCTAS if not created with SHUFFLEWORKS) for all completed fuel moves to NFM for updating of SNM records/isotopic reports.

10.0 EXHIBITS 10.1 RE-C-40-1 CCTAS Info Sheet 10.2 RE-C-40-2 CCTAS Status Log 10.3 RE-C-40-3A Example CCTAS for LPRM Replacement (SRM only) 10.4 RE-C-40-3B Example CCTAS for LPRM Replacement (WRNM only) 10.5 RE-C-40-4A Example CCTAS for Blade Withdrawal (SRM Only) 10.6 RE-C-40-4B Example CCTAS for Blade Withdrawal (WRNM Only) 10.7 RE-C-40-5A Example CCTAS for Blade Replacement (SRM Only)

RE-C-40, Rev. 9 Page 25 of 47 10 8 RE-C-40-5B Example CCTAS for Blade Replacement (WRNM Only) 10.9 RE-C-40-6A Example CCTAS for Non Core Transfers 10 .10 RE-C-40-6B Example CCTAS for Spent Fuel Assemblies Transfers 10.11 RE-C-40-7A Example CCTAS for Core Transfers (SRM Only) 10.12 RE-C-40-7B Example CCTAS for Core Transfers (WRNM Only) 10.13 RE-C-40-8 Executing SHUFFLEWORKS 10 .14 RE-C-40-9 LGS Unusable/Inaccessible Spent Fuel Pool Locations 10.15 RE-C-40-10 PBAPS Unusable/Inaccessible/Restricted Locations 10.16 RE-C-40-11 Core Map 10.17 RE-C-40-12 CCTAS Instruction/Approval Sheet 10.18 RE-C-40-13 SRM/WRNM Connectivity Constraint 10.19 RE-C-40-14 Final Configuration Map Checklist 10.20 RE-C-40-15 LGS Fuel Pool Cells Within Three (3) Feet Of Gate Seals

Exhibit RE-C-40-1 RE-C-40, Rev. 9 Page 26 of 47 Page 1 of 1 CCTAS INFORMATION/VERIFICATION SHEET CCTAS

Title:

Rev. Date:

File Name: Directory:

Description of CCTAS:

Location/file name of Discharge Locations:

Location/file name of Temporary Storage:

NI's to be replaced:

Control Blades to be replaced/swapped:

Control Rod Drives to be worked:

Bundles to be Inspected/Sipped/Rechanneled/Reseated:

Constraints: (Circle/provide value or N/A if not applicable)

SDM Limit:  %) N/A STFROD2 STROD3 N/A SDM Model:

Neighborhood Size: 1 5 9 25 Full Core N/A 1 2 3 N/A Exposed Assemblies around each SRM 2 3 4 N/A Once Burned Assemblies around a Control Blade 1 2 3 4 N/A Once Burned Face Adjacent Allowed 1 N/A Minimum k-infinity Value for Once Burned Assemblies:

WRNM N/A Connectivity Path: SRM U Core None N/A Control Rod Blade Support U Core U Core None N/A Unusable Locations: U SFP U SFP U Core U Core None N/A Item Type Locations: U SFP U SFP U Core Fuel Movement Device N/A Mast Orientation: U SFP U SFP U Core U Core None Date/WO of RT-I-053-310-* (LGS Only):

Spent Fuel Cask (PBAPS ONLY): S/N Other Precautions and Limitations of RE-C-40 No (Exceptions Listed)

Section 7.0 met: Yes Signature confirms that constraints/data provided above are correct and applied as specified AND that all verifications specified in Section 8.3.1/8.3.2(as appropriate) have been done:

Prepared By: Date:

Reviewed By: Date:

RE-C-40 w. 9 Exic t RE-C-40-2 Page 2r. f 47 Page 1 of 1 CCTAS STATUS LOG:

CCTAS Steps DATE/TIME PERFORMED ORIGINALS RETRIEVED** Updated In TAB STATUS* Performed START END FHD RPO I CRO S/Works SNM

1. CCTAS TITLE REV #

I I I I I I I 4 1 1 1 L I I I I I t I t T I_ _ _ _ _ _ I I__ I i - i 0 t 1 t I I I I I I I I I 1 t T

__ I I I. I I I I I t I I

_ _ I _ _ _ _ _ _ _ _ I I- I i + II t- I I I1 I i i i i it I i 11

__ I I I I I I I I 1 1 1 I I I I I I I

- - - ------ ~--,------ - ~ Q.L

~ "J-L"ý

-~77~ 'T~~r, 11 l F was cont ami nate

• nded or Canceiea orlr,

RE-C-40, Rev. 9 Exhibit RE-C-40-3A SRM ONLY Page 28 of 47 Page 1 of 1 Written By:

Reviewed By:

Unit Authorized By:

Title EXAMPLE CCTAS FOR LPRM REPLACEMENT STEP COMPONENT MOVE FROM ORIENT MOVE TO ORIENT FHD RPO CRO SRM COUNTRATE DATE TIME NO. SERIAL NO.

A B C D XX-YY NONE BENDER NONE NA NA NA NA I LPRM X,YYY, ZZZ 2 LPRM BENDER NONE UNIT 1 SPENT FUEL POOL NONE NA NA NA NA X,YYY,ZZZ WALL Above LPRM hung on Tag #

NONE XX-YY NONE NA NA NA NA 3 LPRM FUEL FLOOR X,YYY,zzz

______ I___________ I I I I *F-t-I--t-I I

______ J___________ I _____________________ I ________ I ____________________ .1.

r, RE-C-40, Rev. 9 Exhibit RE-C-40-3B WRNM ONLY Page 29 of 47 Page 1 of 1 Written By:

Unit Reviewed By:

Authorized By:

Title EXAMPLE CCTAS FOR LPRMIWRNM REPLACEMENT STEP COMPONENT MOVE FROM ORIENT MOVE TO ORIENT FHD RPO CRO WRNM COUNTRATE DATE TIME NO. SERIAL NO, A B C D E F G H LPRM/WRNM XX-YY NONE BENDER NONE NA NA NA NA NA NA NA NA 1

X,YYY,ZZZ 2 LPRMIWRNM BENDER NONE UNIT 2 SPENT FUEL POOL NONE NA NA NA NA NA NA NA NA X,YYYZZZ WALL Above LPRM/WRNM hung on Tag #

FUEL FLOOR NONE XX-YY NONE NA NA NA NA NA NA NA NA 3 LPRM/WRNM X,YYYzzz

RE-C-40, Rev. 9 Exhibit RE-C-40-4A SRM ONLY Page 30 of 47 Page 1 of 1 Written By:

Unit Reviewed By:

Title EXAMPLE CCTAS FOR BLADE WITHDRAWAL Authorized By:

COMPONENT MOVE FROM ORIENT MOVE TO ORIENT FHD RPO CRO SRM COUNTRATE DATE TIME STEP NO. SERIAL NO.

A B C D Step 1 for each rod may be performed anytime after fuel movement has ceased for maintenance 1 VERIFY CONTROL CELL 02-43 ISOFFLOADED NA NA NA NA NA The CRD/CRB Coordinator may sign as FHD for steps 2, 3, and 4 2 SELECT CONTROL ROD 02-43 NA WARNING: IFANY SRM COUNTRATE DOUBLES INSERT CONTROL ROD TO POSITION 00 3 WITHDRAW CONTROL ROD 02-43 TO POSITION 48 NA NA NA NA NA NA 4 UNCOUPLE CONTROL ROD 02-43 PER M-C-747-011 OR M-C-741-301

Exhibit RE-C-40-4B WRNM ONLY RE-C-40, Rev. 9 Page 1 of 1 Page 31 of 47 Written By:

Unit Reviewed By:

Title EXAMPLE CCTAS FOR BLADE WITHDRAWAL Authorized By:

STEP COMPONENT MOVE FROM ORIENT MOVE TO ORIENT FHD RPO CRO WRNM COUNTRATE DATE TIME NO. SERIAL NO.

A C D E F G H Step 1 for each rod may be performed anytime after fuel movement has ceased for maintenance I VERIFY CONTROL CELL 02-43 ISOFFLOADED NA NA NA NA NA NA NA NA NA The CRD/CRB Coordinator may sign as FHD for steps 2,3, and 4 2 SELECT CONTROL ROD 02-43 NA WARNING: IF ANY WRNM COUNTRATE DOUBLES INSERT CONTROL ROD TO POSITION 00 3 WITHDRAW CONTROL ROD 02-43 TO POSITION 48 NA NA NA NA NA NA NA NA NA NA 4 UNCOUPLE CONTROL ROD 02-43 PER M-C-747-011 OR M-C-741-301

Exhibit RE-C-40-5A SRM ONLY RE-C-40, Rev. 9 Page 1 of 2 Page 32 of 47 Written By:

Reviewed By:

Unit Authorized By:

Title EXAMPLE CCTAS FOR BLADE REPLACEMENT MOVE FROM ORIENT MOVE TO ORIENT FHD RPO CRO SRM COUNTRATE DATE TIME STEP COMPONENT NO. SERIAL NO.

A B C D NA NA NA NA NA 1 VERIFY CONTROL ROD 30-47 ISUNCOUPLED 31-48129-46 NONE HANG MN HOIST NONE NA NA NA NA 2 DBL BIG NW HANG HOIST NONE NA NA NA NA 3 SUP PC 30-47 NA NA NA NA NA NA NA 4 IF CRD EXCHANGE INPROGRESS, THEN PERFORM STEPS 4A, 48, & 4C, OTHERWISE, N/A STEPS 4A,41, & 4C NA NA NA NA NA NA 4A INFORM UNDERVESSEL TEAM OF INTENT TO REMOVE CRB NA NA NA NA NA 4B RAISE CRB 30-47 APPROXIMATELY 12 INCHES NA NA NA NA NA NA 4C RECEIVE CONFIRMATION FROM UNDERVESSEL TO CONTINUE NONE CBRCK 5N-1 NONE NA NA NA NA 5 CRB 30-47 NONE 30-47 NONE NA NA NA NA 6 CRB H605 CBRCK 6N-4 NONE 30-47 NW NA NA NA NA 7 SUP PB HANG HOIST

SRM ONLY RE-C-40, Rev. 9 Exhibit RE-C-40-5A Page 33 of 47 Page 2 of 2 Written By:

Reviewed By:

Unit Authorized By:

Title EXAMPLE CCTAS FOR BLADE REPLACEMENT MOVE TO ORIENT FHD RPO CRO SRM COUNTRATE DATE TIME STEP COMPONENT MOVE FROM ORIENT NO. SERIAL NO.

NA NA NA NA NA 8 NOTIFY HCU/CRD COORDINATOR CRB 30-47 FULLY SEATED NONE 31-48/29-46 NONE NA NA NA NA 9 DBL B/G HANG MN HOIST NA NA NA NA NA 10 CHECK SEATING OF DBL B/G WITH CAMERA

RE-C-40, Rev. 9 Exhibit RE-C-40-5B WRNM ONLY Page 34 of 47 Page 1 of 2 Written By:

Reviewed By:

Unit Authorized By:

Title EXAMPLE CCTAS FOR BLADE REPLACEMENT MOVE TO ORIENT FHD RPO CRO WRNM COUNTRATE DATE TIME STEP COMPONENT MOVE FROM ORIENT NO. SERIAL NO. - G-NA -A-- NA NA - - NA

- - -NA - - NA

- - - NA NA NA 1 VERIFY CONTROL ROD 30-47 IS UNCOUPLED NONE HANG MN HOIST NONE NA NA NA NA NA NA NA NA 2 DBL B/G 31-48/29-46 30-47 NW HANG HOIST NONE NA NA NA NA NA NA NA NA 3 SUP PC NA NA NA NA NA NA NA NA NA NA NA IF CRD EXCHANGE INPROGRESS, THEN PERFORM STEPS 4A, 46, &4C, OTHERWISE, N/A STEPS 4A,41, &4C NA NA NA NA NA NA NA NA NA NA 4A INFORM UNDERVESSEL TEAM OF INTENT TO REMOVE CRB NA NA NA NA NA NA NA NA NA 46 RAISE CRB 30-47 APPROXIMATELY 12 INCHES 4C RECEIVE CONFIRMATION FROM UNDERVESSEL TO CONTINUE NA NA NA NA NA NA NA NA NA NA SFP NONE NA NA NA NA NA NA NA NA CRB 30-47 NONE NONE 30-47 NONE NA NA NA NA NA NA NA NA 6 CRB H605 CBRCK 6N-4 NONE 30-47 NW NA NA NA NA NA NA NA NA 7 SUP PB HANG HOIST

r" WRNM ONLY RE-C-40, Rev. 9 Exhibit RE-C-40-5B Page 35 of 47 Page 2 of 2 Written By:

Reviewed By:

Unit Authorized By:

Title EXAMPLE CCTAS FOR BLADE REPLACEMENT I I. DATE TIME MOVE TO ORIENT FHD RPO CRO WRNM COUNTRATE STEP COMPONENT MOVE FROM ORIENT NO. SERIAL NO.

AIB C D ElF G H R

1.NOTIFY HCU/CRD I COORDINATOR CRB 30-47 FULLY SEATED I

I tF t NA r ITiTITITTIT7I i-f-i NA NA NA NA T NANA NA NA 8 NOTIFY HCU/CRD COORDINATOR CR13 30-47 FULLY SEATED r

DBL BIG HANG MN HOIST NONE 31-48/29-46 NONE ____ F-NI NA NA NA I NA NA NA L

____________ I I I 1 1 1 NA NA NA NA NA NA NA NA NA 10 CHECK SEATING OF DBL B/G WITH CAMERA 10CHC SETN OF WIT CAER 1 1 I I I I r T I I + I r T z

______ 1 4- 4- + T T I

___ .1 1 I t T I I I I I T 1 I I T I I V I 1 1 1 1 -

I I I I t ttt11 1

______ I ___________ J 4 1 t TTT RE-C- * , Rev.

I______ J____________ .1____ J ___________ - __

xhibit RE-C- O-6A

Page 36 of 47 Page 1 of 1 Written By:

Unit Reviewed By:

Title EXAMPLE CCTAS FOR NON CORE TRANSFERS Authorized By:

STEP COMPONENT MOVE FROM ORIENT MOVE TO ORIENT FHD RPO DATE TIME NO. SERIAL NO.

I LY8487 L2SPENT KK-158 SW L1SPENT T-58 SW 2 LY8488 L2SPENT KK156 SW L1SPENT U-57 SW 3 LY8811 L2SPENT KK-154 SW LISPENT U-56 SW 4 LYNO91 L2SPENT KK-152 SW L1SPENTV-58 SW 5 LY8812 L2SPENT KK-150 SW LiSPENT V-56 SW 6 LY8813 L2SPENT KK148 SW LISPENT W-58 SW 7 LYN104 L2SPENT KK146 SW L1SPENT W-57 SW

RE-C-40, Rev. 9 Exhibit RE-C-40-6B Page 37 of 47 Page 1 of 1 Written By:

Reviewed By:

Unit Authorized By:

Title EXAMPLE CCTAS FOR SPENT FUEL ASSEMBLIES TRANSFERS 1 T T I F*O MOVE TO ORIENT FHD FHD RPO DATE TIME STEP COMPONENT MOVE FROM ORIENT NO. SERIAL NO.

I I 1 PYN521 P2SPENT C-22 N/A CASK S/N_ A-1 N/A I

2 PYG651 P2SPENT N-8 N/A CSK SIN___ G-1 J NA-I N- I N C N/A P2SPENT C-21 N/A CASK S/N_ C-6 N/A 3 PYN463 J 4. 1 t I N/A PYG764 P2SPENT P-46 N/A CASK SIN------ F-1 I. 1 I N/A CASK SIN____ A-7 N/A 5 PJ1407 P2SPENT C-20 I. I I

____ I T 1 I - i -

______ 4 -t

___________ a r r I 4- 1 t 1 I - t T I I- t I 4- ---- - I[ -

____ I _______ .L ____________

NOTE: See RE-C-44 Figure 10 for cask alphanumeric layout

Exhibit RE-C-40-7A SRM ONLY RE-C-40, Rev. 9 Page 1 of 1 Page 38 of 47 Written By:

0D,,Anu.d

.40#.

Unit Frvlr.vwvu Wye Title EXAMPLE CCTAS FOR CORE TRANSFERS Authorized By:

STEP COMPONENT MOVE FROM ORIENT MOVE TO ORIENT FHD RPO CRO SRM COUNTRATE DATE TIME NO. SERIAL NO.

A B C D I LYN521 LlCORE 01-44 SE L1SPENTC-22 NW 2 LYG651 LICORE 03-42 NW L1SPENT N-46 SW 3 DBL B/G LUSPENT B-31/C-32 NONE LICORE 01-44/03-42 NONE 4 LYN463 L1CORE 01-42 NE LISPENT C-21 SW 5 LYG764 LiCORE 03-44 SW L1SPENT P-46 SW 6 YJ1407 LICORE 19-52 SW L1SPENT C-20 SW 7 YJ1447 LICORE 17-50 NE L1SPENT C-18 SW

C C WRNM ONLY RE-C-40, Rev. 9 Exhibit RE-C-40-7B Page 39 of 47 Page 1 of 1 Written By:

Reviewed By:

Unit Authorized By:

Title EXAMPLE CCTAS FOR CORE TRANSFERS MOVE FROM ORIENT MOVE TO ORIENT FHD RPO CRO WRNM COUNTRATE DATE TIME STEP COMPONENT NO. SERIAL NO.

A B C D E F G H 1 PYN521 P2CORE 01-44 SE P2SPENT C-22 NW 2 PYG651 P2CORE 03-42 NW P2SPENT N-46 SW 3 D8L B/G P2SPENT B-311C-32 NONE P2CORE 01-44/03-42 NONE 4 PYN463 P2CORE 01-42 NE P2SPENT C-21 SW 5 PYG764 P2CORE 03-44 SW P2SPENT P-46 SW 6 PJ1407 P2CORE 19-52 SW P2SPENT C-20 SW 7 PJ1447 P2CORE 17-50 NE P2SPENT C-18 SW

Exhibit RE-C-40-8 RE-C-40, Rev. 9 Page 1 of 1 Page 40 of 47 EXECUTING SHUFFLEWORKS

1. Log on to LAN on SHUFFLEWORKS-loaded Computer. If SHUFFLEWORKS is running directly off of the PC desktop, then verify with NFM that the correct version of shuffleworks is being run.

2. Double-click on SHUFFLEWORKS icon.

3. Change data directory using the "set-up" menu option.

4. Load appropriate plant information using the "set-up" window option.

5. Follow program prompts/pull-down menu options in order to execute the desired SHUFFLEWORKS functions.

Exhibit RE-C-40-9 RE-C-40, Rev. 9 Page 1 of 1 Page 41 of 47 LGS UNUSABLE/INACCESSIBLE SPENT FUEL POOL LOCATIONS UNIT 1 UNIT 2 BINDING: COVERED BY LABELS A-1I R-14 Z-18 JJ-23 B-2 thru B-18, A-19 thru A-66,B-73 thru B-84 A-35 T-18 AA-69 KK-16 R-2 thru R-84 G-21 U-19 EE-47 SS-23 LL-72 thru LL-85, U-79 thru KK-79 P-20 X-22 FF-70 SS-35 AB-19 thru AB-70 Q-19 X-34 GG-23 VV-22 A-i thru T-i, U-5 thru ZZ-5 Q-21 Y-15 JJ-li X-42 A-85 thru T-85 CC-43 HH-38 S-52 T-51 U-56 thru ZZ-56 T-52 T-53 U-52 U-21 thru ZZ-21 OBSTRUCTED E-44 thru 49 A-77 E-67 thru 71 KK-77 through TT-77 OBSTRUCTED BY GATE BRACKETS LL-88 through SS-88 AB-53 thru AB-59, AB-49 thru AB-51 BAD FUEL AB-26 thru AB-33, AB-36 B-14 JJ-18 through JJ-22 D-12 KK-18 J-31 KK-20 OBSTRUCTED OBSTRUCTED BY CLIPS K-32 KK-22 A-i thru A-3, A-50 S-3 V-20 L-23 KK-23 A-82 thru A-85 S-17 KK-20 M-24 LL-15 B-i thru B-3 S-20 NN-20 CC-21 LL-17 B43, B50, and B73 S-35 YY-20 IDD-16 through DD-22 LL-19 B-82 thru B-85 S-38 EE-16 LL-43 C-I thru C-4 S-53 V-55 EE-18 through EE-22 RR-20 C50 and C73 S-56 KK-55

-16 through FF-23 RR-22 C-82 thru C-85 S-70 NN-55

-- 16 RR-51 D-1 thru D-4 S-73 YY-55 GG-18 through GG-22 UU-18 D-82 thru D-85 S-83 HH-16 through HH-22 UU-22 E-1 thru E-5 A-3 JJ-16 E-82 thru E-85 A-17 F-i thru F-6 A-74 TEST COUPONS ADJACENT TO THE FOLLOWING CELLS F-82 thru F-85 A-83 P-58 BB-70 Z-70 Q-58 G-I thru G-6 V-4 T-58 DD-70 EE-70 R-58 H-1i thru H-3 KK-4 CC-70 Y-70 J-I thru J-3 NN-4 K-i thru K-3 YY-4 OTHER ZZ-1 thru ZZ-3 V-80 FF-63 AB-1 thru AB-4 JJ-80 NN-36 BAD FUEL K-23 K-15 X-1 OTHER V-I L-83 I T-9 I T-11 I U-52 I FF-69 FF-70 ZZ-22 HH-47 QQ-36 INACCESSIBLE DUE TO LEVEL SWITCH SS-36 N-84 P-84 Q-84 SS-39 N-85 P-85 Q-85 INACCESSIBLE DUE TO REFUEL BRIDGE ACCESS All of Rows 1, 2, and 85 TO PREVENT UNPLANNED MOVEMENT 8 Bundles around coupon tree

Exhibit RE-C-40-10 RE-C-40, Rev. 9 Page 1 of 1 Page 42 of 47 Exhibit RE-C-40-10 PBAPS UNUSABLE/INACCESSIBLE SPENT FUEL POOL LOCATIONS POTENTIAL MAST CAMERA INTERFERENCE PERIPHERAL CORE LOCATIONS (Both Units) 43-02 55-12 01-18 11-06 01-44 11-56 43-60 55-50 49-06 59-18 05-12 05-50 17-02 17-60 49-56 b9-44 UNIT 2 UNIT 3 Covered by rack markers: Covered by rack markers:

A-25 thru WW-25, A-17 THRU LL-17, YY-18 thru HHH-18, XX-21 thru XX-55 LL-1 thru LL-20, MM-20 thru XX-20, Fuel Pool Gate Heavy Load Path: NN-21 thru NN-55 A-21 thru A-55 Fuel Pool Gate Heavy Load Path:

Boraflex Liner Damage: A-21 thru A-55 JJ-30, MM-30 FPM Mounting Concerns:.

Boraflex Coupon: HHH-2 thru HHH-5, HHH-19 thru HHH-22 Q-1, S-i Damaged DBG: Boraflex Coupon:

T-71/S-72 CCC-71 Failed Fuel Pin: Dechanneled Bundle:

CCC-71 Z-51 Debris: Bowed Bundles:

TLL-30, LLL-33 X-54, EE-57 Other: Other:

GGG-2, GGG-3 S-72 thru XX-72 EEE-66 thru KKK-66 11-45, JJ-46, GGG-2, HHH-2 EEE-67 thru EEE-71 GGG-66 ("skeleton" bundle)

S-72 thru XX-72 JJ-22 Unusable Fuel Locations: Unusable Fuel Locations:

BB-18, BB-19, BBB-25, BBB-3, AA-39, AAA-14, AAA-7, BB-36, BBB-4, CC-13, CC-15, CC-16, BBB-13, BBB-15, BBB-19, BBB-20, CCC-6, DD-13, DD-16, DD-17, DD-18, BBB-21, BBB-3, BBB-61, BBB-63, DD-19, DD-20, DD-21, DD-22, DD-23, BBB-64, CCC-2, D-22, DD-26, DD-58, E-1, DD-24, EEE-5, F-18, F-21, FFF-3 EE-37, EE-5, EE-6, F-17, GG-21, HHH-17, JJ-12, KK-12, LL-12, HH-12, HH-18, HH-4, HH-56, HH-62, NN-7, P-19, PP-51, PP-55, PP-7, HH-64, HH-7, HHH-I1, HHH-14, PP-8, QQ-8, RR-10, T-55, U-18, U-19, HHH-17, 11-10, 11-19, 11-61, JJ-8, V-18, WW-67, YY-65, YY-7, ZZ-2, K-41, KK-55, L-31, L-41, LL-15, LL-20, ZZ-3, ZZ-4, ZZ-5 LL-54, LLL-32, M-6, MM-9, N-40, NN-16, 0-40, 00-54, PP-17, PP-5, PP-53, PP-7, QQ-53, QQ-54, QQ-62, QQ-68, QQ-8, SS-53, SS-54, SS-55, SS-6, T-13, TT-13, TT-54, U-38, U-9, VV-16, VV-17, W-13, W-38, W-39,

.W-7, X-37, X-54, Y-36, YY-67, YY-8, JZ-39, Z-51, Z-68, ZZ-67, ZZ-68

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Exhibit RE-C-40-12 RE-C-40, Rev. 9 Page 1 of 1 Page 44 of 47 CCTAS Instruction/Approval Page (Sample Sheet Only)

Core Component Transfer Authorization Sheet Page of Unit Date Title (Rev. #)

1. This CCTAS provides the moves necessary to ...

2. This CCTAS assumes that SRM A, B, C, D (or WRNM A through H) are in service.

3. (Guidance on placement of a fuel bundle which cannot be placed in original target location, e.g. SRMs/WRNM inoperable or in an emergency)

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

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

6. This CCTAS must be used in conjunction with appropriate spent fuel procedures.

7. All changes to this CCTAS must be made in accordance with procedure RE-C-40.

8. This CCTAS involves the transfer of Special Nuclear Material (SNM).

SNM transfers shall be controlled in accordance with procedure RE-C-44.

9. Return completed CCTAS (or a copy if original is contaminated) to Reactor Engineering.

10. (RE contacts and phone numbers)

(etc.)

Prepared By:

Reviewed By:

Authorized By:

Exhibit RE-C-40-13 RE-C-40, Rev. 9 Page 1 of 1 Page 45 of 47

( SRM/WRNM CONNECTIVITY CONSTRAINT The SRM or WRNM connectivity constraint consistent with the neutron instrumentation determined in step 6.4 is to be used for in-core shuffles and will also be applied to offload/reload.

Face Adjacent Rules:

1. A continuous face adjacent path must exist between each bundle and an operable SRM OR between each bundle and at least one operable WRNM.

2. The only exceptions to rule #1 are bundles that fulfill the diagonal coupling rules.

Diagonal Coupling Rules:

1. It is permissible for single fuel bundles ONLY to be diagonally connected to an array of face adjacent fuel-.undles. No other fuel bundles can be connected to the single diagonally adjacent fuel bundle except per rule #2.

2. In addition to the diagonally adjacent connection path allowed by rule

1. 1, two fuel bundles diagonally adjacent within the same control cell are considered connected.

Exhibit RE-C-40-14 RE-C-40, Rev. 9 Page 1 of 1 Page 46 of 47 FINAL CONFIGURATION MAP CHECKLIST Preparer Reviewer

1. "Current" Final Configuration core map matches Core Design Report.

2. Discharge fuel bundles identified on spent fuel pool map.

3. New fuel/reinsert bundle empty locations identified on spent fuel pool map.

4. Reload bundle (temporary) empty locations identified on spent fuel pool map.

5. Discharge bundles and empty locations on preparer's map matched reviewer's map.

6. Previously completed Exhibit RE-C-40-14 AND spent fuel pool map discarded.

Exhibit RE-C-40-15 RE-C-40, Rev. 9 Page 47 of 47 Page 1 of 1 LGS FUEL POOL CELLS WITHIN THREE (3) FEET OF GATE SEALS Per AT EWR A0004257, irradiated fuel which has decayed for less than 5 years cannot be stored within three (3) feet of the fuel pool gate seals. This is to support justification for extending the seal lifetime from 5 to 10 years. This constraint is conservatively assumed to include gate storage locations as well as gate locations in place.

UNIT 1 SPENT FUEL POOL UNIT 2 SPENT FUEL POOL Cattle Chute Gate Storage: Cattle Chute Gate Storage:

(North Side) (North Side)

E-77 through BB-77 VV-44 through VV-64 E-88 through BB-88 WW-43 through WW-65 E-I through BB-I XX-43 through XX-65 E-2 through BB-2 YY-43 through YY-65 E-3 through BB-3 ZZ-43 through ZZ-65 F-4 through AA-4 AB-43 through AB-65 (South Side) (South Side)

V-64 through V-70 VV-22 through VV-42 W-64 through W-70 WW-21 through WW-43 X-64 through X-70 XX-21 through XX-43 Y-64 through Y-70 YY-21 through YY-43 Z-64 through Z-70 ZZ-21 through ZZ-43 AA-65 through AA-70 AB-21 through AB-43 BB-66 through BB-70 Cattle Chute Gate In Place: Cattle Chute Gate In Place:

A-25 through A-46 VV-33 through VV-53 B-25 through B-46 WW-32 through WW-54 C-25 through C-46 XX-32 through XX-54 D-25 through D-46 YY-32 through YY-54 E-25 through E-46 ZZ-32 through ZZ-54 F-26 through F-45 AB-32 through AB-54 Cask Pit Gat e In Place: Cask Pit Gate In Place:

RR-77, RR-88, RR-l through RR-16 A-I through A-20 SS-77, SS-88, SS-i through SS-16 B-i through B-20 TT-77, TT-88, TT-i through TT-16 C-i through C-20 UU-77, UU-88, UU-I through UU-16 D-1 through D-20 VV-77, VV-88, VV-I through VV-16 E-1 through E-20 F-I through F-19

I . EXELON NUCLEAR::

TITLE: LPRM Removal TASK PERFORMED BY: EVALUATOR:

EVALUATOR SIGNATURE: DATE:

DIRECTIONS TO EVALUATOR:

There is a mockup of a small portion of top guide and core plate on the refuel floor; usually near the East end of the Unit 2 fuel pool. It contains a LPRM mockup. Examiners may wish to allow the candidate to demonstrate the pr6cess of LPRM removal using the mockup and included pictures of the tool.

EVALUATION METHOD:

SIMULATE EVALUATION LOCATION:

REFUEL PLATFORM APPROXIMATE COMPLETION TIME:

Comp)letion Time: 30 min IMPORTANCE RATING(S): SYSTEM NUMBER(S):

3.5 2.2.27

REFERENCES:

M-C-774-010, LPRM/SRM, IRM, WRNM DRY TUBE REPLACEMENT TASK STANDARD(S):

LPRM removed and transported per the CCTAS and M-C-774-01 0 Lbi, JiM 2.dOC Page 3 of 13

F7 EXELON NUCLEAR TASK CONDITIONS:

1. LPRM Replacement per M-C-774-01 0 is in progress

2. A copy of M-C-774-010 with section 5.4 ready to execute has been provided

3. A CCTAS has been provided

4. The 4 bundles around the LPRM are removed

5. The instrument handling tool is installed on the monorail aux hoist

6. Undervessel personnel have installed and tested the seal tube and flush fixture to LPRM 24-25 INITIATING CUES:

Shift supervision has directed you to execute the CCTAS for removal of LPRM 24-25 per M-C-774-01 0 Section 5.4 LUg,, JVM 2.dCOC Page 4 of 13

EXELON NUCLEAR Critical Element(s) indicated by in Performance Checklist.

PERFORMANCE CHECKLIST:

STEP STANDARD SAT/UNSAT

1. Verify the four core locations Bundles verified removed surrounding each instrument to be replaced are vacant

2. Ensure the proper operation of the Recognize tool is cycling correctly. Both instrument handling tool by actuating the lower slide and the upper roller are tool and observing that both the upper extending and retracting roller stop and lower slide move feely CUE: While actuating the tool, it responds per the figures provided (Provide attached photos of the tool for JPM Step 2)

3. *Press ENGAGE on hoist pendant to ENGAGE depressed place tool roller stop in the extended position CUE: ENGAGE has been depressed and the roller stop has extended

4. Ensure refuel platform hoist Jam block setting verified mechanical stop (jam block) is set such that the tool lower slide is at least 5 feet 6 inches below the surface of the water. Record on Attachment 6 CUE: "You set the jam blocks earlier to 5 feet six and one half inches"

5. *Per CCTAS, verify proper core Tool lowered onto top guide and pointing location, then lower tool onto top toward 24-25 guide with tool oriented such that the roller stop and slide point toward instrument to be removed CUE: The tool is lowered and is resting on the top guide.

Page 5 of 13 L& JPM 2.doc LGS JI-'M 2doe Page 5 of 13

EXELON NUCLEAR STEP STANDARD SAT/UNSAT

6. Request undervessel personnel Undervessel personnel requested to perform Step 5.4.6 perform Step 5.4.6 to install and test the CUE: Step 5.4.6 has been performed flush fixture

7. Using camera, ensure the tool is Recognize correct seating and continue seated on the top guide and the slide in oriented toward instrument CUE: The tool appears as per the picture provided. (Provide camera view photo for JPM Step 7)

8. *Ensure hoist cable is taut by bumping Bump hoist up OR use safety bend on hoist up to remove all slack or by cable performing safety bend CUE: Cable is taut using (hoist / safety bend)

9. *Press RELEASE on hoist pendant Depress RELEASE on hoist pendant CUE: RELEASE is depressed

10. Using camera, verify tool slide has Ensure tool slide straddles instrument extended and straddles instrument plunger plunger CUE: The tool slide has extended and straddles t6e instrument plunger

11. *Lower tool using hoist or by releasing Lower tool by lowering hoist or releasing safety bend safety bend CUE: Tool has been lowered

12. Using camera, verify tool has Plunger verified to be free of the top depressed plunger out from top guide guide socket socket CUE: The plunger has come down with the tool and is free of the top guide socket

13. *Press ENGAGE on hoist pendant ENGAGE depressed.

and verify tool slide retracts Tool slide verified to retract plunger into instrument plunger into tool tool CUE: Engage is depressed and the tool slide has retracted the plunger into the tool LUZ),, Ji-M a.COC Page 6 of 13

EXELON NUCLEAR >

STEP STANDARD SAT/UNSAT

• Ensure access to upper elevations of Contact drywell control point and notify 14.

drywell have been restricted as that irradiated component movement is required by Health Physics prior to about to commence.

removing irradiated instruments CUE: Health Physics drywell control point reports that access to the upper elevations of the drywell is restricted

15. Request undervessel personnel to Request undervessel crew commence backflush instrument housing per Step backflush Step 5.4.16 5.4.16 CUE: Backflush of LPRM 24-25 has commenced

16. WARNING: Health Physics shall Ensure Health Physics Technician is monitor dose rates during raising, monitoring dose rates bending, and transport of the instrument. Raising of the instrument shall stop if radiation levels exceed 30 mr/hr at water surface with instrument 1 foot below water CUE: Health Physics is monitoring dose rates (if recjuested for updates later, simulate monitoring by providing slowly rising dose rates corresponding to raising the LPRM. Do not exceed 15 mr/hr)

17. *When notified that flush has RAISE depressed on pendant controller commenced, Raise instrument from core until it clears the core top guide

18. CUE: The LPRM is clear of the core Stop raising the LPRM top guide

19. CUE: You have reached the termination point of the JPM. You may stop here.

I *r ra L4.0 .11JVI Z.U0U Page 7 of 13

EXELON NUCLEAR .

Comments:

Note: Any grade of UNSAT requires a comment.

I JPM Overall Rating:

I SAT/UNSAT Z.UOC JI-'M 2.dOC L(, J-M LU.fi Page 8 of 13 Page 8 of 13

EXELON NUCLEAR.

TASK CONDITIONS:

1. LPRM Replacement per M-C-774-010 is in progress

2. A copy of M-C-774-01 0 with section 5.4 ready to execute has been provided

3. A CCTAS has been provided

4. The 4 bundles around the LPRM are removed

5. The instrument handling tool is installed on the monorail aux hoist

6. Undervessel personnel have installed and tested the seal tube and flush fixture to LPRM 24-25 INITIATING CUES:

Shift supervision has directed you to execute the CCTAS for removal of LPRM 24-25 per M-C 774-010 Section 5.4 CANDIDATE

EXELON NUCLEAR' Instrument Handling Tool While Actuating Tool JPM Step 2 a

IL! w co

-j 0.

w.

Lu w L

a WW CANDIDATE J

I EXELON NUCLEAR I

Camera View for Step 5.4.7 JPM Step 7 CANDIDATE

TRANSFEI. ,JTHORIZATION FOR FH-106 Page I of ,

M-219966 Rev. 1/89 DOCTYPE 113 SRM ONLY Written By: TRAINING USE ONLY Unit LIMERICK GENERATING STATION Date 6/3/02 Reviewed By: TRAINING USE ONLY Title TRAINING CCTAS Authorized By: TRAINING USE ONLY STEP NO. COMPONENT MOVE FROM ORIENT MOVE TO ORIENT FHD RPO CRO SRM COUNTRATE DATE TIME SERIAL NO.

A B C D 118~~ LPRM- 42 OEBNE 118 L,123,XYZ 24-25 NONE BENDER NONE NA NA NA NA 119 L,123,XYZ BENDER NONE UNIT I SPENT FUEL POOL WALL NONE NA NA NA NA Above LPRM hung on Tag#_....

120 LOU812 LPRM FUEL FOE FLOOR NONE 24-25 NONE NA NA NA NA  ;

JPM 2 CCTAS for Unit I CANDIDATE

TRANSFEK. ,JTHORIZATION FOR FH-106 Page 1 of ,

M-219966 Rev. 1/89 DOCTYPE 113 SRM ONLY Written By: TRAINING USE ONLY Unit LIMERICK GENERATING STATION Date 6/3/02 Reviewed By: TRAINING USE ONLY Title TRAINING CCTAS Authorized By: TRAINING USE ONLY STEP NO. COMPONENT MOVE FROM ORIENT MOVE TO ORIENT FHD RPO CRO SRM COUNTRATE DATE TIME SERIAL NO.

A B C D LPRM 118 L,123,XYZ 24-25 NONE BENDER NONE NA NA NA NA 119 L,123,XYZ BENDER NONE UNIT 2 SPENT FUEL POOL WALL NONE NA NA NA NA Above LPRM hung on Tag#

LPRM-120 LOU812 FUEL FLOOR NONE 24-25 NONE NA NA NA NA JPM 2 CCTAS for Unit 2 CANDIDATE

Effective Date:

M-C-774-010 Rev 16 LGS PB Page 1 of 61 S/R YES YES -A :jad EQ NO NO 150.59 YES YES Exelon Nuclear LPRM / SRM, IRM, WRNM DRY TUBE REPLACEMENT 1.0 PURPOSE 1.1 This procedure provides instructions for replacement of LPRMs AND replacement of SRM/IRM/WRNM dry tubes following disconnection AND preparation of the dry tube undervessel.

This procedure also provides instruction for the replacement of the metal O-ring between an LPRM flange AND the mating incore housing flange (undervessel), IF required at Peach Bottom.

1.2 Section 5.0 of this procedure has been divided into the following subsections:

5.1 Preparation 5.2 Disconnection and Preparation of Instrument Undervessel 5.3 Transport of Bender to Reactor Cavity 5.4 Removal, Bending and Storage of Instrument 5.5 Removal of Bender from Reactor Cavity 5.6 Replacement of Metal O-Ring in LPRM Flange at Peach Bottom 5.7 Staging of New Instruments in Reactor Cavity 5.8 Installation of New Instruments 5.9 Assembly of Hardware Undervessel 5.10 Reseating of Leaking Instrument 5.11 Contingency Instrument Removal with Crow's Foot Tool 5 .12 Contingency Instrument Removal with Bowing Tool 5 .13 LPRM/Dry Tube Removal Tool Operating Instructions (PBAPS) 2.0 APPARATUS AND SPECIAL EQUIPMENT NOTE: The following list of tools AND equipment are recommended for use in the performance of this procedure AND may be substituted with equivalent items, except as noted.

2.1 Tools and Equipment NOTE: The following are above vessel tools.

2.1.1 Instrument handling tool

M-C-774-010 Rev. 16 Page 2 of 61 2.1.2 Multiple LPRM strongback 2.1.3 Single LPRM strongback for LPRM Gamma Thermometer assemblies.

2.1.4 LPRM bending tool with dedicated, approximately 20 ft long, wire rope sling 2.1.5 Underwater camera system 2.1.6 Light weight handling pole(s), as required 2.1.7 Certified storage hooks AND cable, for each Instrument removed, overall length hook saddle to hook saddle 14.5 feet to 16 feet, with tags for vibra-etching (or equivalent) instrument SIN and Core Location (ref. 7.2.2).

2.1.8 Certified slings AND rigging, as required (ref. 3.2.4).

2.1.9 1 Ton hand chain hoist with approximate 20ft hand chain; only required IF up-ending of Bender is required.

2.1.10 Fuel support covers, as required.

2.1.11 Crow's foot for LPRM plunger, as required.

2.1.12 Bowing Tool, as required.

2 2.1.13 Hydraulic grippers, as required.

2.1.14 Air ratchet/drill with variable speed AND in-line air shut off valve (ball valve OR similar) for elevator operation (optional) 2.1.15 LPRM/Dry Tube Removal Tool (PBAPS only, as required) 2.1.16 Hardware to lock stored instruments, as required.

2.1.17 Load binder to retain instruments in strongback.

2.1.18 In-Core Guide Tube Seal (required IF replacement of metal o ring in LPRM flange is planned).

2.1.19 Air line controller with positive feature to prevent inadvertent operation. (Aux. platform only) 2.1.20 Small buoyancy device(s) to maintain bender hose bundle nearly vertical (i.e. prevent it from interfering with vessel studs or entangling with other tools) (optional).

NOTE: The following are below vessel tools.

C 2.1.21 LPRM teflon seal wrenches, 6 inch AND 36 inch 2.1.22 LPRM nut runner

M-C-774-010 Rev. 16 Page 3 of 61 2.1.23 LPRM torque tube 2.1.24 Calibrated torque wrenches; range to torque 30 ft-lb; range to torque 95 ft-lb.

Schedule 80 LPRM seal tubes OR other seal tubes approved 2.1.25 through engineering analysis.

2.1.26 Gamma Thermometer Seal Tube GE P/N 131C9362 (LGS only) 2.1.27 Drain hose/filter unit 2.1.28 Flush fixture 2.1.29 LPRM nose pieces 2.1.30 Socket wrenches, with 2-1/8 inch sockets, 2 inch sockets AND 36 inch extension 2.1.31 Mini-cask AND liner, for hot filter removal NOTE: Except as noted, materials may be substituted with approved equivalent items as approved by Reactor Services Technical Staff (RSTS).

2.2 Materials 2.2.1 Blank Information Tag (for hoist pendent) 2.2.2 Lubricant, Nickel Never-Seeze, Nuclear Grade 2.2.3 Solvent, Acetone 2.2.4 Clean lint-free nylon gloves 2.2.5 Clean lint-free cloths 2.2.6 Tygon tubing (for drain hose) 2.2.7 Drain filters 2.2.8 Safety can for solvent-soaked wiping cloths 2.2.9 Black AND White plastic Capture devices, one per Dry tube to be removed, WHEN using the LPRM/Dry tube removal tool (PBAPS) .

2 .2 .10 Nylon braided rope, approximately 160 ft.

2.2.11 Source of Regulated Helium NOTE: Replacement parts that are NOT "Identical Items" shall be approved AND documented by Engineering prior to installation.

M-C-774-010 Rev. 16 Pag'e 4 of 61 2.3 Replacement Parts 2.3.1 KEL-F Seal (tip tubing adapter to calibration tube), as required 2.3.2 LPRM Drip Skirts, as required 2.3.3 TIP Tubing Adapters, as required 2.3.4 Metallic O-ring for LPRM flange (required IF replacement of metal o-ring in LPRM flange is planned).

2.3.5 For specific replacement parts associated with LPRM Gamma Thermometer assemblies, refer to ECR LG-94-10498.

3.0 PRECAUTIONS AND LIMITATIONS 3.1 Precautions 3.1.1 Instruments removed from reactor core are highly radioactive.

3.1.2 A radiological survey shall be performed WHEN removing any item from the Fuel Pool OR Reactor Cavity.

3.1.3 Tooling OR equipment must be rinsed with demineralized water as it is removed from Fuel Pool OR Reactor Cavity.

3.1.4 WHEN removing Instruments, the jamming block on the' appropriate refueling platform hoist shall be set such that the Instrument handling tool slide will remain at least 5 foot 6 inches below water surface.

3.1.5 Never use more than one swivel adapter on the hoist cables.

The upper female thread is NOT the same size as the lower male thread AND therefore NOT compatible.

3.1.6 Use extreme caution WHEN working undervessel so as to NOT bump OR damage instruments OR tip tubes. Bumping instrument while seal tube and instrument nut is removed could cause a burst of highly contaminated water to discharge from housing flange (ref. 7.4.14).

3.1.7 Debris OR foreign material introduced into reactor cavity has the potential to become a future radiological hazard OR cause equipment OR fuel damage. Extreme care shall be exercised in maintaining cleanliness AND foreign material exclusion.

3.1.8 WHEN NOT in use, main fuel grapple must be FULL UP AND auxiliary hoists positioned to prevent damaging hoist cables OR attached tools.

M-C-774-010 Rev. 16 Page 5 of 61 3.1.9 Whenever moving a tool into OR out of top guide, monitor air hose so that it does NOT slacken AND jam between top guide AND tool.

3.1.10 New Instruments must be handled with clean gloves at all times to safeguard against hand print smears.

3.1.11 Limerick assemblies 20-S400-32-49 AND 20-S400-40-41 are LPRM Gamma Thermometers which are different than other LPRM assemblies. Voltage is provided to the thermometer via panel 20L106, breaker #22 which should be blocked prior to working on these assemblies. Refer to ECR LG 94-10498.

3.1.12 Ball shut-off valve OR similar air shut-off valve must be installed near air ratchet, IF used, for emergency stop of elevator.

3.1.13 WHEN using air drive tool to raise elevator, raise elevator at very slow speed only. Remain alert AND cease raising should elevator bind on guide pole.

3.1.14 IF in-vessel inspection/repair equipment is used in the reactor vessel concurrent with performance of this procedure, THEN use extreme caution to avoid interference between components being handled.

-3.1.15 LIMERC Step 3.1.15 does NOT apply.

PEACH BOTTOM WHEN using the LPRM/Dry tube removal tool, THEN the capture devices must be installed with the smaller diameter opening facing up. IF installed incorrectly, THEN fragmentation of the capture device is possible.

M-C-774-010 Rev. 16 Page 6 of 61 3.2 Limitations 3.2.1 Load handling over irradiated fuel shall be suspended upon the loss of fuel floor secondary containment. In lieu of operable secondary containment, the acceptability of load handing operations (without secondary containment) may be evaluated AND documented in accordance with PECO Calculation LM-033 OR other engineering approved evaluation.

3.2.2 IF systems OR equipment required to be operable per FH-105 (LGS) OR FH-6C (PBAPS) for core component transfers OR load handling over irradiated fuel becomes inoperable, THEN as required by FH-105 OR FH-6C discontinue instrument handling AND handling of loads over irradiated fuel.

3.2.3 Handling of the LPRM Strongback AND Bender shall be conducted at the lowest height practicable. At no time shall strongback be moved over the reactor cavity with the strongback pivot point higher than 55"' above the Fuel Floor. Note that this correlates to approximately 6

between top of cavity handrails and strongback (ref. 7.4.9).

3.2.4 Rigging hardware, except for dedicated 20 ft long wire rope sling, used for handling bender OR multiple strongback over fuel shall be rated for 1 Ton minimum.

3.2.5 Spent instruments shall be stored in accordance with requirements of A-C-132 '-Spent Fuel Pool Material Storage/Inventory AND Housekeeping.

3.2.6 Movement of Instruments shall be documented on the CCTAS provided by the Reactor Engineer.

3.2.7 All hardware AND fasteners must be positively secured with lockwire, tack welds, cotter pins OR other approved method to prevent any part from dropping into Fuel Pool, Reactor Cavity, OR Equipment Pool.

3.2.8 During movement of Overhead Crane, designated rigger AND crane operator shall be in voice contact using wireless communication whenever line of sight communication is NOT possible.

3.2.9 Verification Points have been established AND shall be implemented in accordance with A-C-33.

3.2.10 Maintenance Supervision AND Reactor Engineering, as appropriate, shall be notified immediately of abnormal conditions. Abnormal conditions AND corrective actions taken shall be documented in the Remarks Section of this procedure.

3.2.11 In-Vessel work activities shall be supervised by qualified Fuel Handling Directors (ref. 7.2.7).

M-C-774-010 Rev. 16 Page 7 of 61 3 .2.12 Steps of this procedure performed per CCTAS shall be double verified by the Refuel Platform Operator AND Fuel Handling Director AND documented on the CCTAS.

3.2.13 WHEN using a torque wrench where the exact target torque value is NOT achievable AND NO range is given, the final torque value shall be the next setting OR the closest increment marking above the target value.

3.2.14 LPRM/Dry Tube Removal Tool may be used as primary tool, i.e.

it is NOT a requirement of this procedure to first attempt instrument removal with Instrument Handling Tool.

3 .2.15 Sections 5.2 through 5.13 may be performed out of sequence OR in parallel to suit field conditions per the discretion of the Lead Maintenance Technician (LMT).

3.2.16 The Auxiliary Platform may be used to install non-irradiated nuclear instrumentation (LPRM's, Wide Range Nuclear Monitors OR SRM/IRM Dry Tubes) (Reference 7.4.11 and 7.4.13).

3 .2.17 All verifications require initials AND date.

4.0 PREREQUISITES 4.1 RECORD Work Order number. WO#:

NOTE: Prerequisites do NOT apply to Sections 5.1 AND 5.2.

4.2 LIIMERICK VERIFY Prereqiiisites of FH-105 are complete WV L PEACH BOPTTeM VERIFY Prereqi iisites are complete for FH-6C WV 4.3 IF Dry tube to be replaced is an SRM/IRM, THEN VERIFY via documentation review that detector is disconnected AND secured in fully inserted position OR has been removed from dry tube.

M-C-774-010 Rev. 16 Page 8 of 61 4.4 NOTIFY Shift Supervision that this procedure is to be performed.

Person Contacted 'WV 4.5 ENSURE communications are established between Control Room, Refueling Platform or Auxiliary Platform, AND Undervessel.

4.6 ENSURE ALARA briefing has been performed prior to performing work undervessel.

4.7 IF LPRM housing flange metallic 0-ring replacement is planned at Peach Bottom, THEN CONSIDER performing Mock-up training with qualified FHD AND craft personnel for planned activities.

4.8 Prerequisites complete, precautions AND limitations understood.

WV

M-C-774-010 Rev. 16 Page 9 of 61 5.0 PROCEDURE 5.1 Preparation Subsection Required: YESL NO___

NOTE: The term "Instrument" refers to either the LPRM OR the IRM/SRM/WRNM dry tube assembly.

5.1.1 NOTIFY Reactor Engineering that procedure is to be performed AND request the preparation of Special Nuclear Material (SNM) accounting sheets AND a Core Component Transfer Authorization Sheet (CCTAS).

Person Contacted WV 5.1.2 LIMERICK IF work is to be performed on LGS LPRM Gamma Thermometer assemblies, 20-S400-32-49 OR 20-S400-40-41, ENSURE breaker OPEN.

L #22 in 20L106 is blocked PECHBOTTOM Step 5.1.2 does NOT apply.

5.1.3 IF replacing LPRMs, ENSURE LPRM signal cables are disconnected in main control room (PB) OR LPRM detector power supply is disconnected in Aux Equipment Room (LGS) for LPRMs being replaced. IF assembly to be removed is a gamma thermometer, THEN inform I&C AND refer them to ECR LG-94-10498 for details. IF replacing WRNMs, THEN ENSURE WRNM high voltage cable is disconnected in main control room OR in pre-amp panel.

WV 5.1.4 ENSURE that new LPRMs/WRNMs are examined in accordance with procedure M-C-774-008.

Person Contacted?

M-C-774-010 Rev. 16 PagelI0 of 61 5.1.5 ENSURE new LPRMs/WRNMs have been tested by I&C as required by station I&C procedures.

WV NOTE: Seal tubes for LPRM Gamma Thermometer assemblies are longer than standard LPRM seal tubes. GE P/N 131C9362 should be used for Gamma Thermometer LPRMs.

5.1.6 ENSURE seal tubes have been visually inspected, especially the threaded area, AND leak tested by holding station demineralized water pressure for ten minutes with no leaks.

WV 5.1.7 ENSURE bending tool has been assembled, inspected AND functionally tested per M-C-797-110 OR an approved work order activity.

5.1.8 IF air drive tool will be used for elevator operation THEN ENSURE air shut-off valve (ball valve OR similar) is installed in air line near drive tool. Al I. WV 5.1.9 ENSURE bending tool has been set-up as follows:

1. ENSURE hydraulic hoses are bundled together.

2. POSITION pump station at cavity curb to minimize interference with other equipment and activities. "7 O'Clock" position WHEN looking down on cavity with Fuel Pool at "12 O'Clock" is recommended.

3. ENSURE pump reservoir water level is 1-3 inches below top of reservoir.

4. CONNECT station service air to pump AND ensure regulator is set at approximately 45 psi air pressure.

5. CONNECT hydraulic lines using color coded indicators.

6. IF desired, THEN ATTACH small buoyancy device to hose bundle approximately 25 - 30 ft from bender mechanism (this will maintain hose nearly vertical to avoid snagging on studs or other service tools).

C

M-C-774-010 Rev. 16 Page 11 of 61 C s.5.1.10 INSTALL Instrument handling tool as follows:

1. Using a single swivel adapter, THREAD adapter into grapple stud past view port in grapple stud.

2. TORQUE swivel adapter jam nut to 25-30 ft.lbs.

wv

3. PLACE roller stop pin in storage position.

• vT 5.1.11 ENSURE demineralized water hose has been routed to undervessel area.

5.1.12 NOTIFY Health Physics that this procedure is to be performed AND REQUEST preparations be made to restrict access to upper elevations of the drywell.

Person Contacted WV 5.1.13 ENSURE Health Physics has performed a smear survey of each LPRM in accordance with ST-0-107-494-0 (LGS) within 30 days prior to LPRM installation. 4ý HP 5.1.14 ENSURE required number of storage hooks/cables are available with tags indicating instrument S/N AND Core Location per the CCTAS.

WV 5.1.15 VERIFY instrument storage area in pool AND travel path for storage of instruments is clear of obstructions.

WV 5.1.16 VERIFY Health Physics has locks AND keys as required to lock stored instruments.

5.1.17 INITIAL AND DATE indicating subsection complete.4 .*A wv

M-C-774-010 Rev. 16 Page 12 of 61 Disconnection and Preparation of Instrument Undervessel C- 5.2 Subsection Required: YES NO WV CAUTION Use extreme care while moving AND working undervessel to avoid bumping AND damaging instrumentation OR TIP tubing.

DOUBLE VERIFICATION 5.2.1 VERIFY correct core location using tagging on Instrument (IF present) AND labeling on adjacent support steel AND components. RECORD on Attachment 6.

NOTES: Steps 5.2.2 through 5.2.6 apply to LPRM only.

LPRM Gamma Thermometer TIP Tube adapters do NOT have wrench flats on LPRM end.

5.2.2 ENSURE TIP tube adapter is removed AND stored.

M*C-774-010 Rev. 16 Page 13 of 61 Figure 1 CAUTION Cutting of any cables EXCEPT those protruding directly from LPRM to be replaced will lead to extensive rework AND dose exposure. Ensure cut is performed on reactor vessel side of connector.

D OUBL.E- VER-I1FICATION 5.2.3 CUT cables protruding from LPRM flush with bottom of LPRM per Figure 1 AND leave "stub piece" connected to signal cable to protect connector. RECORD on Attachment 6.

(Ref. 7.4.15) 5.2.4 REMOVE sleeve AND drip skirt AND store.

M-C-774-010 Rev. 16 Page'14 of 61 NOTE: A 2-1/8 inch socket wrench may be required instead of a 2-inch socket wrench for removal of the nut.

5.2.5 REMOVE AND STORE the following:

1. Teflon seal

2. Nut

3. Washer NOTE: GE P/N 131C9362 should be used for Gamma Thermometer assemblies.

5.2.6 IF LPRM Gamma Thermometer is being installed OR removed, THEN ENSURE longer seal tube is installed.

5.2.7 INSPECT threads on seal tube AND Instrument housing flange.

REWORK threads OR REPLACE seal tube as required.

5.2.8 APPLY thread sealant on seal tube threads AND INSTALL tube onto housing flange.

5.2.9 Securely TIGHTEN seal tube to housing flange.

5.2.10 CLOSE seal tube valve.

5.2.11 Step 5.2.11 does NOT apply.

PECHBOTTOM ENSURE filter is installed for drywell sump AND water level is sufficient in sump. IF water level is NOT sufficient, THEN NOTIFY Reactor Operator AND ADD demineralized water.

5.2.12 INITIAL AND DATE indicating subsection complete. .__*

WV

M-C-774-010 Rev. 16 Page 15 of 61 Transport of Bender to Reactor Cavity C5.3 Subsection Required: YES \ NO -/ WV NOTES: All rigging hardware, except for the dedicated 20 ft wire rope sling, called for in this section shall be certified AND rated for a minimum of 1 Ton. The dedicated 20 ft wire rope sling has a safe working load of 1250 lbs.

Only one of the following three steps is required for transport of bender to cavity.

5.3.1 IF LPRM Bender is assembled AND staged in bender stand, THEN PERFORM the following:

1. ENSURE Bender elevator is lowered at least 3 feet from its full up position.

2. ENSURE dedicated wire rope sling is attached to Bender lifting bail.

3. ATTACH dedicated sling to overhead crane hook.

NOTE: Depending on storage location, the dedicated LPRM bender sling may NOT permit raising the Bender to a height C. sufficient for transport to the reactor vessel.

sling may be used with the other crane hook for transport to the reactor vessel.

A shorter

4. IF necessary, ATTACH a certified 12 foot (OR shorter) sling AND shackles (IF required) to Bender lifting bail AND to other overhead crane hook.

CAUTION IF bender is raised excessively while in stand, elevator will come in contact with bottom surface of stand. At PBAPS, clearance between bender winch square drive AND handrail is small; use extreme caution to avoid contact with handrail.

5. Using crane hook with shorter sling (IF used), RAISE Bender approximately 1 foot, THEN TRAVERSE Bender away from stand.

6. RAISE bender approximately 10 feet, THEN MOVE bender to position over reactor vessel.

7. IF necessary, RAISE crane hook with dedicated sling AND/OR LOWER crane hook with shorter sling as required to transfer bender to longer dedicated sling.

M-C-774-010 Rev. 16 Page'16 of 61

( 5.3.1 (cor 8t)

8. IF necessary, DISCONNECT AND REMOVE shorter sling from Bender.

5.3.2 IF LPRM Bender is to be moved to cavity with lower guide pole NOT attached to upper guide pole, THEN PERFORM the following:

1. ENSURE bender elevator is at full up position.

2. Using certified rigging, MOVE upper portion of bender into vertical position over reactor cavity.

3. ATTACH rope lanyard to lower pole section AND carefully manually POSITION pole section in cavity below bender.

4. ATTACH lower half of guide pole AND ENSURE grooves in pole sections align with each other.

5. ENSURE lock mechanism AND/OR alignment pin are secure to lock pole sections.

6. ENSURE dedicated sling is used to support bender AND crane hook is raised near upper limit.

g 5.3.3 IF LPRM Bender is to be moved to cavity from Fuel Floor while fully assembled, THEN PERFORM the following:

CAUTION Extreme care must be used WHEN handling Bender.

Bending of Guide pole will render tool inoperable.

1. ENSURE bending tool elevator is at full up position.

2. ENSURE dedicated wire rope sling is attached to Bender lifting bail.

3. ATTACH dedicated sling to overhead crane hook using a sling AND shackle (IF required).

CAUTION Do NOT attach sling directly to bail since this may induce excessive side pull on bail during lift.

4. ATTACH a certified sling 6-10 foot long, with shackles (IF required), between top of Bender AND the same overhead crane hook as dedicated sling was attached to.

M-C-774-010 Rev. 16 Page 17 of 61 5.3.3 (cont)

C-NOTE: Positioning of up-ending sling in the following step minimizes stresses induced on the guide pole splice connection.

5. ATTACH "up-ending nylon sling, approximately 10-15 feet long in a choker hitch, to bender guide pole approximately 2 feet below pole splice connection.

6. ATTACH up-ending sling to other overhead crane hook using hand chain hoist, slings AND shackles. PAY OUT approximately 10-20 feet of load chain to keep crane hook up high.

7. RAISE Bender in horizontal configuration, THEN MOVE lower end of bender over reactor cavity handrail.

8. Using chain hoist, LOWER bottom of Bender into reactor cavity UNTIL Bender is in vertical position.

9. RAISE bender as required AND REMOVE up-ending sling from bender.

10. ATTACH Bender bail to free crane hook using slings AND shackles as required, THEN TRANSFER weight to this

_C crane hook.

11. DISCONNECT 6-10 foot sling from crane hook with dedicated sling.

12. RAISE crane hook with dedicated sling AND/OR LOWER Bender to transfer Bender weight to dedicated sling.

13. REMOVE rigging NOT in use OR SECURE rigging as required for Bender removal.

5.3.4 INITIAL AND DATE indicating subsection complete. 6-oq WV 5.4 Removal, Bending and Storage of Instrument Subsection Required: YES_)__ NO_

WV NOTES: This subsection AND all following subsections of this procedure apply to SRM/IRM/WRNM dry tubes AND LPRMs EXCEPT as indicated.

Performance of this section requires undervessel workers to backflush Instrument housing WHEN Instrument is removed.

C 5.4.1 VERIFY the four core locations surrounding each instrument to be replaced are vacant.

M-C-774-010 Rev. 16 Pagei18 of 61 5.4.2 ENSURE proper operation of Instrument handling tool by actuating tool AND observing that both the upper roller stop AND the lower slide move freely.

5.4.3 PRESS ENGAGE on hoist pendent to place tool roller stop in the extended position.

DOUBLE VERIFICATION 5.4.4 ENSURE refuel platform hoist mechanical stop (Jam Block) is set such that tool lower slide is at least 5 feet 6 inches below surface of water. RECORD on Attachment 6.

5.4.5 Per CCTAS, VERIFY proper core location, THEN LOWER tool onto top guide with tool oriented such that roller stop AND slide point toward Instrument to be removed.

NOTE: Step 5.4.6 may proceed in parallel with subsequent fuel floor steps.

5.4.6 REQUEST Undervessel personnel to INSTALL AND TEST flush fixture as follows:

1. CONNECT flush fixture to seal tube AND ENSURE demineralized water supply hose is attached.

2. CLOSE flush fixture drain valve.

3. OPEN seal tube valve.

4. OPEN demineralized water supply valve to check for leaks. IF excessive leakage is noted THEN CLOSE seal tube valve AND demin water supply valve AND REWORK as required prior to continuing.

5. CLOSE demin water supply valve.

6. CLOSE seal tube valve.

7. MOVE to low dose area until fuel floor is ready to flush instrument housing AND NOTIFY Fuel Floor crew step is complete.

5.4.7 Using camera, ENSURE tool is seated on top guide AND tool slide is oriented toward Instrument.

5.4.8 ENSURE hoist cable is taut by bumping hoist up to remove all slack OR by performing safety bend.

5.4.9 PRESS RELEASE on hoist pendent.

5.4.10 Using camera, VERIFY tool slide has extended AND straddles instrument plunger.

M-C-774-010 Rev. 16 Page 19 of 61 NOTE: During the following step, the tool should lower approximately 1-1/2 inches as tool depresses Instrument plunger.

5.4.11 LOWER tool using hoist OR by releasing safety bend.

5.4.12 Using camera, VERIFY tool has depressed plunger out from top guide socket.

5.4.13 IF plunger is stuck THEN PROCEED to Sections 5.11, 5.12 OR 5.13.

5.4.14 PRESS ENGAGE on hoist pendant AND VERIFY tool slide retracts Instrument plunger into tool.

5.4.15 ENSURE access to upper elevations of drywell have been restricted as required by Health Physics prior to removing irradiated Instruments.

NOTE: As soon as backflush is started, Fuel Floor crew should proceed with performance of Step 5.4.17. IF housing flange O-Ring replacement is planned flush time should be increased from 3 minutes to 5 minutes.

5.4.16 REQUEST Undervessel personnel to BACKFLUSH instrument housing as follows:

1. VERIFY flush fixture drain valve closed.

2. OPEN seal tube valve.

3. OPEN Demin water supply valve.

4. NOTIFY Fuel Floor personnel flush is started.

5. FLUSH for minimum of 3 minutes, THEN CLOSE demin water supply valve.

6. CLOSE seal tube valve.

7. OPEN flush fixture drain valve, THEN REMOVE flush fixture from seal tube, IF required.

M-C-774-010 Rev. 16 Page'20 of 61 CAUTION While raising Instrument, care must be taken to prevent boss rings OR bottom portion of Instrument from catching on core Top Guide.

WARNING Health Physics shall monitor dose rates during raising, bending, AND transport of the Instrument. Raising of the Instrument shall stop IF radiation levels exceed 30 mr/hr at water surface with Instrument 1 foot below water.

5.4.17 WHEN notified that flush has commenced, RAISE Instrument from core UNTIL it clears core top guide.

5.4.18 MOVE Instrument AND bending tool adjacent to vessel wall closest to the transfer canal OR other vessel wall area clear of obstructions.

WARNING Elevator of bending tool must be lowered to the full down position in order to bend the Instrument approximately in the middle. Failure to bend the Instrument in the middle will result in reduced water coverage over hot end of Instrument AND possible high radiation levels during raising AND transport of Instrument to fuel pool.

Air shut-off valve must be installed in-line to air drive tool, IF used, for emergency stop of elevator in case of air drive tool malfunction.

DOUBLE VERIFICATION 5.4.19 LOWER bending tool elevator to full down position AND visually VERIFY elevator is full DOWN as follows.

RECORD completion on Attachment 6.

1. VERIFY winch cable is slack.

2. Using camera, VERIFY scribe mark on inner tube is visible above elevator.

3. IF present, THEN VERIFY existing tape mark on winch cable is next to cable guide roller.

M-:C-774-010 Rev. 16 Page 21 of 61 5.4.20 IF this is the first of several bending operations, THEN MARK hoist cable with a piece of tape next to cable guide roller.

5.4.21 MOVE Instrument into clamp on bending tool, between mandrel AND roller.

5.4.22 MOVE Instrument vertically as required to align top of Instrument with red bands on bender guide tube.

5.4.23 CLAMP Instrument in bender by moving clamp cylinder control valve to ON position UNTIL pump stalls, THEN RETURN valve to STOP position.

5.4.24 VERIFY engagement of instrument relative to clamp AND mandrel (i.e. in the "-saddle"I) using underwater camera at multiple angles AND views as required (ref. 7.4.12).

CAUTION IF instrument is bent an excessive amount, plunger of Instrument may break off OR damage to Instrument handling tool may occur.

5.4.25 BEND Instrument a slight amount by moving bending cylinder control valve to BEND position UNTIL bend starts, THEN STOP bending by moving valve to STOP position.

5.4.26 PRESS RELEASE on hoist pendant control to release Instrument handling tool from Instrument.

CAUTION IF instrument is bent excessively during the initial bend, it will hit the vessel flange AND possibly cause damage OR Instrument plunger to break off.

Do NOT exceed 1150 psig hydraulic pressure (pressure relief valve is set for 1200 psi).

5.4.27 BEND Instrument approximately 90 degrees by moving bending cylinder control valve to '-BEND position, THEN RETURN valve to STOP position; IF tool stalls OR bends instrument very sluggishly, THEN INCREASE air pressure regulator, as required, to a maximum hydraulic pressure of 1150 psi.

M-C-774-010 Rev. 16 Page,22 of 61 CAUTION WHEN using air drive tool to raise elevator, raise elevator at very slow speed only. Remain alert AND cease raising should elevator bind during operation.

5.4.28 WHILE monitoring motion of elevator, slowly RAISE elevator while concurrently completing bend of Instrument to approximately 180 degrees.

5.4.29 RAISE elevator UNTIL bent portion of instrument is just below water surface.

NOTE: During -- RETRACT operation in the following step it is NOT necessary to run pump UNTIL it stops (stalls). Doing so unnecessarily applies high forces AND pressure on tool components.

5.4.30 RETRACT bending roller by moving the bending cylinder control valve to the RETRACT position UNTIL roller is fully retracted, THEN MOVE valve to "'STOP position.

5.4.31 IF using air drive ratchet to operate bender, THEN ENSURE air hose is positioned to allow refuel platform travel to the spent fuel pool.

5.4.32 ENGAGE Instrument with J-hook as approved by the Fuel Handling Director.

NOTE: During unclamping operation in the following step it is NOT necessary to run pump UNTIL it stops running (stalls).

CAUTION The following step will release the Instrument from the bender. Securely hold onto rigging assembly. Instrument weight is approximately 75 lbs.

5.4.33 WHILE maintaining an upward pull on Instrument, RELEASE clamp by moving clamp cylinder control valve to "OFF

position UNTIL pump begins to stall, THEN MOVE valve to

"'STOP position.

5.4.34 Slowly MOVE Instrument away from bender.

5.4.35 ENGAGE Instrument with safety latched fuel pool storage hook assembly.

M-C-774-010 Rev. 16 Page 23 of 61 CAUTION Plunger at top of Instrument may be brittle AND susceptible to breaking. Use care WHEN traversing cattle chute AND transfer canal to keep the Instrument plunger from dragging.

5.4.36 MOVE Instrument to fuel pool AND STORE in accordance with CCTAS AND A-C-132, ý Spent Fuel Pool Material Storage/Inventory AND Housekeeping.

5.4.37 INITIAL AND DATE indicating subsection complete.

WV 5.5 Removal of Bender from Reactor Cavity Subsection Required: YES___NO WV NOTES: All rigging hardware called for in this section shall be certified AND rated for a minimum of 1 Ton.

Only one of the following three steps is required for transport of bender from the reactor cavity.

5.5.1 IF LPRM Bender will be transferred to bender stand, THEN PERFORM the following:

NOTE: Depending on storage location, the dedicated LPRM bender sling may NOT permit raising the Bender to a height sufficient for transport to the bender stand. A shorter sling may be used with the other crane hook for transport to the bender stand.

1. ENSURE bending tool elevator is lowered at least 3 feet from its full up position.

2. *IF necessary, ATTACH a certified 12 foot OR shorter sling, with shackles (IF required), to Bender lifting bail AND to other overhead crane hook.

M-C-774-010 Rev. 16 Page 24 of 61 5.5.1 (cont)

CAUTION Bender must be raised approximately 6 ft. above vessel flange to clear ledge to equipment pool (LGS). Bender must also be at proper height to enter stand otherwise it will come in contact with bottom surface of stand. At PBAPS, clearance between bender winch square drive AND handrail is small. Use extreme caution to avoid contact with handrail.

3. RAISE bender such that bottom end of guide pole will clear obstructions THEN MOVE bender adjacent to stand.

4. LOWER Bender to enter stand, THEN MOVE bender into stand AND LOWER load.

5. DISCONNECT rigging from Bender.

5.5.2 IF LPRM bender is to be moved to Fuel Floor by disassembling lower guide pole, THEN PERFORM the following:

1. ENSURE bender is at full up position.

2. ATTACH a short certified rigging sling between bender AND other overhead crane hook.

3. With Health Physics support, RINSE bender with water AND RAISE bender as required to access pole splice connection.

4. ATTACH rope lanyard to lower guide pole section.

5. DISASSEMBLE AND/OR UNLOCK mechanism securing pole sections.

6. Carefully DISCONNECT lower guide pole AND STORE.

7. REMOVE bender from cavity AND carefully STORE.

M-C-774-010 Rev. 16 Page 25 of 61 5.5.3 IF LPRM Bender is to be moved to Fuel Floor fully assembled, THEN PERFORM the following:

1. ENSURE bending tool elevator is at full up position.

NOTE: The next step will permit raising the bender high enough to traverse away from reactor vessel AND permit attachment of a sling to up-end the bender.

CAUTION Do NOT attach sling directly to bail since this may induce excessive side pull on bail during lift.

2. LOWER other crane hook, THEN ATTACH 6-10 foot sling, with shackles (IF required), between top of Bender AND the crane hook.

3. RAISE bender above vessel, THEN MOVE bender away from vessel.

4. REMOVE dedicated 20 ft wire rope sling from crane hook AND SECURE to Bender.

NOTE: Positioning the up-ending sling in the following step minimizes stresses induced on the guide pole splice connection.

CAUTION Extreme care must be used WHEN handling Bender.

Bending of Guide pole will render tool inoperable.

5. ATTACH "'up-endingA nylon sling, approximately 10-15 feet long, in a choker hitch to bender guide pole approximately 2 feet below pole splice connection.

6. ATTACH up-ending sling AND hand chain hoist to other overhead crane hook using, slings AND shackles as required.

7. RAISE Bender into horizontal configuration, THEN MOVE bender over cavity handrail to fuel floor storage location.

8. DISCONNECT rigging from Bender.

5.5.4 INITIAL AND DATE indicatinq subsection complete.

WV

M-C-774-010 Rev. 16 Page' 26 of 61 5.6 Replacement of Metal O-Ring in LPRM Flange at Peach Bottom Subsection Required: YES NO WV NOTES: This section is approved for PBAPS only. This work is NOT considered OPDRV work as defined in GP-6 (less than 1.5 inch opening), since the minimum diameter of the incore housing (6280-M-1-B-58-4) is 1.384 .

Reference Attachments 9 AND 10 for information about the In core guide tube seal. The top of the seal engages the Top Guide but does NOT rest on the top guide. WHEN fully installed, the round bar protruding from the sides of the seal rests on the core plate. The round bar is attached to the bottom end of the rubber seal AND the body of the tool is effectively attached to the top of the rubber seal. WHEN the weight of the tool is transferred to the round bar, the seal is compressed AND expands.

Sign-offs are to be performed on Attachment 7.

5.6.1 VERIFY seal is free of foreign material AND that seal parts move freely (round bar should be able to move up slot without binding as seal is compressed).

5.6.2 Using a Jet Pump grapple OR rope, LOWER the seal into target location in core plate UNTIL tool engages Top Guide AND round bar rests on core plate AND hoist cable begins to go slack.

5.6.3 While camera views round bar at core plate elevation, PERFORM gentle safety bends AND VERIFY round bar moves freely up slot as bar contacts core plate.

5.6.4 RELEASE Jet Pump grapple from seal OR SECURE rope to cavity handrail.

5.6.5 INFORM Maintenance Supervisor that guide tube seal is installed AND RECORD completion of seal installation on Attachment 7.

NOTE: The following steps are performed undervessel.

5.6.6 ATTACH a drain line to the LPRM seal tube.

M-C-774-010 Rev. 16 Page 27 of 61 Drainage of housing may take a considerable amount of time C NOTE: since volume being drained is a closed volume.

need to back fill Air will through drain line to permit complete drainage.

CAUTION As water drains from in-core housing, a potential exists for increased radiation from the flange area.

Radiation levels must be monitored continuously AND draining shall be suspended IF dose rates exceed predetermined level.

5.6.7 Slowly DRAIN all water from housing.

HP HOLD 5.6.8 REMOVE drain line AND Seal Tube AND immediately PERFORM a radiation survey of opening in housing flange. RECORD completion on Attachment 7.

5.6.9 REMOVE flange. BAG AND TAG bolts.

5.6.10 REMOVE old o-ring carefully so that as-found condition of o ring is preserved.

5.6.11 INSPECT 0-ring AND sealing surfaces of both flanges for defects AND abnormalities. Also INSPECT LPRM seating surface inside removed flange AND RECORD results in Remarks Section of this procedure.

NOTE: The following step is intended to verify that potential sources of foreign material are eliminated.

5.6.12 CLEAN bolt holes in LPRM housing flange AND WIPE top surface of LPRM housing flange AND adjacent CRD housing flanges with a clean, lint free rag.

CAUTION Repairs of sealing surface shall only be performed as authorized via separate Engineering approved documentation.

5.6.13 CLEAN 0-ring sealing surface on both flanges AND seating surface for LPRM (inside removed flange).

M-C-774-010 Rev. 16 Page'28 of 61 NOTE: Repair OR replacement of bolts OR flange requires a Repair/Replacement plan per A-C-80. Step 5.6.14 can be performed at any time prior to use of the parts.

5.6.14 ENSURE inspection of any replacement parts has been performed by a Certified NDE Examiner.

ENSURE bolts are inspected, cleaned AND lubricated. ENSURE 5.6.15 four washers are clean AND free of defects.

5.6.16 VERIFY new replacement 0-ring is clean AND free of defects.

5.6.17 INSTALL new 0-ring in recess in flange.

5.6.18 While carefully aligning flanges, RAISE flange into position against housing flange AND INSTALL bolts (with washers) hand tight.

5.6.19 Using a star pattern AND multiple passes, SNUG UP bolts with wrench.

DOUBLE VERIFICATION 5.6.20 TORQUE bolts using standard torquing pattern for all four passes. RECORD completion on Attachment 7.

C 1st pass:

2nd pass:

25 ft-lbs 50 ft-lbs 3rd pass: 75 ft-lbs 4th pass: 75 ft-lbs 5.6.21 APPLY thread sealant on seal tube threads AND INSTALL tube onto housing flange.

5.6.22 Securely TIGHTEN seal tube to housing flange.

5.6.23 CLOSE seal tube valve.

5. 6 .24 IF Leak Test will be performed, THEN PERFORM the following:

1. IF more than approximately 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> has elapsed since seal tube was installed, THEN CONNECT a drain hose to seal tube AND VERIFY seal tube is drained of water, OTHERWISE CONTINUE.

2. ENSURE regulator on air supply is "backed-offý so that no pressure is delivered to supply hose.

3. CONNECT regulated source of air to seal tube

M-C-774-010 Rev. 16 Page 29 of 61 5.6.24 (cont)

4. ESTABLISH direct communication with Refuel Platform or Auxiliary Platform personnel AND REQUEST personnel on fuel floor to monitor seal with underwater camera at core plate elevation.

CAUTION Over-pressurization of housing will cause the incore guide tube seal to be ejected.

5. OPEN seal tube valve AND air supply valve as required to align air supply with LPRM housing.

6. Slowly INCREASE air pressure delivered to LPRM housing to a maximum pressure of 15 psig.

7. VERIFY no leakage through O-ring by use of Snoop leak detector. RECORD results on Attachment 7.

WARNING Air inside Instrument housing may contain high levels of air borne contamination. Do NOT vent air to sub-pile room.

8. CLOSE seal tube valve AND ISOLATE air supply.

9. REDUCE air supply pressure to 0 psig AND DISCONNECT air hose.

NOTE: The following steps will backfill the LPRM guide tube which will decrease differential pressure across the guide tube seal AND aid in removal of the In-Core guide tube seal from above vessel.

5.6.25 Backfill the LPRM guide tube as follows:

1. CONNECT a Demin water supply hose to the seal tube.

2. OPEN Demin water supply valve to backfill the LPRM guide tube.

3. CLOSE Demin water supply valve.

4. OPEN seal tube drain valve to partially drain LPRM guide tube, THEN quickly CLOSE seal tube drain valve to isolate the seal tube.

M-C-774-010 Rev. 16 Page' 30 of 61 NOTES: The following steps are performed above vessel. Air will bubble up out of housing as seal is removed. Air should stop within about 1 minute.

INDEPENDENT VERIFICATION 5.6.26 VERIFY LPRM flange is installed with all bolts torqued AND seal tube is installed with valves in the closed position.

RECORD completion on Attachment 7.

5.6.27 ENGAGE In-core Guide Tube seal with a Jet Pump grapple OR rope.

5.6.28 PERFORM Safety Bend to free seal.

5.6.29 VERIFY no gross leakage undervessel. RECORD completion on Attachment 7.

5.6.30 RAISE seal out of vessel. RECORD completion of guide tube seal removal on Attachment 7.

5.6.31 INITIAL AND DATE indicating subsection complete.

WV 5.7 Staging of New Instruments in Reactor Cavity Subsection

• ,. Required: YES NO WV NOTES: Use clean lint-free nylon gloves WHEN handling Instruments.

Single LPRM Strongback should be used to install LPRM gamma thermometer assemblies.

Steps to load instruments in strongback may be performed pre-outage.

CAUTION Instrument can be bent IF NOT properly handled. A minimum of 6 persons should be used WHEN handling an in core Instrument.

5.7.1 IF required, WIPE down Instrument with clean lint free cloths dampened with solvent, THEN ALLOW solvent to dry.

5.7.2 IF instruments were cleaned with solvent, THEN WIPE down Instrument with demineralized water.

M-C-774-010 Rev. 16 Page 31 of 61 5C7.3 IF multiple strongback is used:

• 1 . LOAD Instruments into strongback.

2. CLOSE AND LOCK access doors at top of strongback.

5.7.4 IF single strongback is used:

1. LOAD Instrument into strongback.

2. CLOSE AND PIN handle at top of strongback.

3. ENSURE LPRM bosses are captured by strongback clamps to prevent LPRM from sliding WHEN strongback is lifted vertically.

5.7.5 IF multiple strongback is used, ENSURE bosses on each instrument are captured by fingers of strongback.

5.7.6 ATTACH tag lines (approximately 80 ft long) at both ends of strongback.

5.7.7 ROUTE tag line attached to lower end of strongback over crane hook.

NOTE: Weight of fully loaded multiple LPRM strongback is approximately 1000 pounds.

5.7.8 IF required, REMOVE swivel hook/sling AND use the sister hook WHEN transitioning from bender to LPRM strongback.

5.7.9 ATTACH strongback to overhead crane using 1/2 inch nominal shackle AND sling rated for 1 ton minimum.

5.7.10 INSTALL a load binder approximately 10 foot from the upper end of the instrument strongback.

CAUTION Drop of a fully loaded strongback onto the reactor core from a height above the specified limit (below) has a potential to cause more severe consequences than analyzed in the UFSAR (ref. 7.4.9).

5.7.11 WHILE ensuring strongback pivot point is maintained less than 55"' above the fuel floor, TRANSFER the loaded strongback over the reactor cavity so that the lower end of the strongback is approximately over the center of the reactor vessel.

5.7.12 WHILE wetting the strongback with demineralized water, UP-END, AND LOWER strongback into reactor vessel into a vertical position.

M-C-774-010 Rev. 16 Page' 32 of 61 5.7.13 REMOVE the load binder previously installed.

5.7.14 POSITION lifting arm (multiple strongback) 9R rigging cable (single strongback) inside retaining lugs at top of strongback AND LOCK with retaining pin.

5.7.15 SECURE guide ropes to crane hook.

5.7.16 INITIAL AND DATE indicating subsection complete.

WV 5.8 Installation of New Instruments Subsection Required: YES__ NO WV NOTE: IF the metal O-Ring (159A2816P004) between any LPRM flanges AND Incore Housing Flange (undervessel) are being replaced, Section 5.6 is completed prior to performing this section for those locations.

Performance of this section requires workers undervessel to backflush in-core guide tube housing while Instrument is lowered in housing.

WARNING Instrument handling tool may be highly contaminated.

Exercise caution WHEN handling tool AND minimize time handling tool.

5.8.1 IF using Refuel Platform hoist, ADJUST jam block to allow Instrument handling tool to be raised out of water.

5.8.2 PRESS hoist pendent RELEASE for refuel platform OR RELEASE via air line controller (Aux. Platform only), THEN INSTALL Instrument handling tool slide lock pin to lock roller in retracted position.

5.8.3 RECORD instrument serial number on CCTAS.

M-C-774-010 Rev. 16 Page 33 of 61 CAUTION Use extreme caution to prevent contact between overhead crane AND monorail hoist structure.

5.8.4 IF multiple strongback is used, GRAPPLE LPRM as follows:

1. MOVE top of selected Instrument outside strongback cover by carefully opening cover OR by depressing instrument plunger. CLOSE AND LOCK strongback cover IF required.

2. CAPTURE Instrument in tool by placing tool slide over middle boss on Instrument plunger, THEN PRESS ENGAGE on hoist pendent for refuel platform OR ENGAGE via air line controller (Aux. platform only).

3. Carefully REMOVE Instrument from strongback, lifting by hand OR by slowly lowering strongback approximately six inches.

5.8.5 IF single strongback is used, GRAPPLE LPRM as follows:

1. CAPTURE Instrument in tool by placing tool slide over middle boss on Instrument plunger, THEN PRESS ENGAGE on hoist pendent for refuel platform OR ENGAGE via air line controller (Aux. platform only).

2. RAISE hoist on refueling platform OR Aux. platform (IF used) to pick up weight of Instrument handling tool on LPRM assembly.

3. RELEASE strongback latches by pulling latch operating handle release pin AND rotating handle.

5.8.6 MOVE strongback clear of Instrument several feet.

CAUTION Use extreme care WHEN lowering Instrument so that it does NOT get caught on the top guide nor move rapidly into contact with the core plate. Instruments are quite fragile AND can be bent AND damaged beyond repair.

5.8.7 Per CCTAS, POSITION Instrument over desired core location.

M-C-774-010 Rev. 16 Page' 34 of 61 5.8.8 Using underwater camera, slowly LOWER Instrument UNTIL it is just above the core plate (approximately even with the top of adjacent fuel support castings).

5.8.9 IF this is the first Instrument installation, THEN MARK hoist cable with a piece of tape level with the refuel platform hand rail OR Aux. platform hand rail (IF used) to serve as an aid for remaining Instrument installations.

5.8.10 MANEUVER Instrument to enter Instrument housing opening in core plate, THEN STOP.

5.8.11 REQUEST Undervessel personnel to backflush Instrument housing as follows:

1. CONNECT flush fixture to seal tube AND ENSURE demineralized water supply hose is attached.

2. VERIFY flush fixture drain valve CLOSED.

3. OPEN seal tube valve.

4. OPEN demineralized water supply valve.

5. NOTIFY Fuel Floor personnel flush is started.

I r- 5.8.12 WHEN notified that flush has commenced, LOWER Instrument handling tool UNTIL it seats on top guide.

5.8.13 REQUEST Undervessel personnel to test for proper seating as follows:

1. CLOSE demin water supply valve fully.

2. OPEN flush fixture drain valve to check for seat leakage.

3. VERIFY Instrument is properly seated by observing little OR no leakage from drain line.

4. NOTIFY Fuel Floor personnel of results.

5.8.14 IF excessive flow is noted, THEN manually LIFT Instrument handling tool a couple inches AND RESEAT Instrument, REPEAT I as necessary.

5.8.15 VERIFY Instrument is properly seated by observing little OR no leakage from drain line, AND NOTIFY Fuel Floor personnel of results.

M-C-774-010 Rev. 16 Page 35 of 61 5.8.16 IF excessive flow is noted, THEN REQUEST Undervessel personnel to backflush Instrument housing as follows, OTHERWISE proceed to step 5.8.22:

1. CLOSE flush fixture drain valve.

2. OPEN demineralized water supply valve.

3. NOTIFY Fuel Floor personnel flush is started.

5.8.17 WHEN notified that flush has commenced, manually LIFT instrument handling tool a couple inches AND RESEAT Instrument.

5.8.18 REQUEST Undervessel personnel to test for proper seating as follows:

1. CLOSE demin water supply valve fully.

2. OPEN flush fixture drain valve to check for seat leakage.

3. VERIFY Instrument is properly seated by observing little OR no leakage from drain line.

4. NOTIFY Fuel Floor personnel of results.

5.8.19 IF excessive flow is noted, THEN manually LIFT Instrument handling tool a couple inches AND RESEAT Instrument, REPEAT as necessary.

5.8.20 VERIFY Instrument is properly seated by observing little OR no leakage from drain line, AND NOTIFY Fuel Floor personnel of results.

5.8.21 REPEAT steps 5.8.16 through 5.8.20 as necessary.

NOTE; Any remaining leakage will be addressed in subsection 5.9.

5.8.22 PRESS RELEASE on hoist pendent for refuel platform OR RELEASE via air line controller (Aux. platform only) AND using a safety bend, RAISE tool by hand UNTIL slide contacts underside of top guide, THEN HOLD tool in raised position.

5.8.23 PRESS ENGAGE on hoist pendent OR ENGAGE via air line controller (Aux. platform only) AND RAISE tool clear of top guide.

DOUBLE VERIFICATION 5.8.24 VERIFY engagement of Instrument with top guide by checking that the wide portion of plunger is contained within the notch AND does NOT extend below the top guide.

RECORD on Attachment 6.

M-C-774-010 Rev. 16 Page 36 of 61 C

5.8.25 REQUEST Undervessel personnel to CLOSE seal tube valve, REMOVE flush fixture from seal tube.

THEN CAUTION Handle the LPRM strongback at the lowest height practicable during movement over the reactor vessel.

At no time shall strongback pivot point be moved over vessel with pivot point raised higher than 5 ft. above fuel floor.

5.8.26 REMOVE strongback from cavity as follows:

1. REMOVE tag lines from overhead crane hook.

2. WHILE maintaining tension on tag line running over crane hook, REMOVE lock pin from top end of strongback.

3. WHILE raising strongback, ROTATE strongback to horizontal position.

4. MOVE strongback to storage location on Fuel Floor.

INITIAL AND DATE indicating subsection complete.

5.8.27 WV 5.9 Assembly of Hardware Undervessel Subsection Required: YES_ NO WV CAUTION Highly contaminated water can be expected to drain from seal tube during removal.

5.9.1 CONNECT flush fixture OR any other suitable drain line to bottom of seal tube AND DIRECT hose to floor sump.

5.9.2 IF required, THEN OPEN seal tube valve AND flush fixture drain valve to verify seal tube is drained AND that Instrument seat is effectively sealing.

5.9.3 IF excessive flow is noted, THEN RESEAT Instrument per subsection 5.10 beginning with step 5.10.3.

5.9.4 REMOVE seal tube AND any excess pipe thread sealant from housing flange.

5.9.5 LUBRICATE threads of Instrument, nut, AND washer.

M-C-774-010 Rev. 16 Page 37 of 61 5.9.6 IF installing an LPRM gamma thermometer assembly, THEN REMOVE bullet nose piece.

CAUTION Washer is larger than Instrument AND care must be taken to center washer over raised face of nut.

5.9.7 INSTALL washer next to flange, THEN INSTALL nut with raised face toward washer ensuring washer is centered over raised face of nut.

DOUBLE VERIFICATION 5.9.8 For LPRMs AND SRM/IRM dry tubes, TORQUE nut to 95 ft-lbs AND VERIFY that there is no leakage. RECORD on Attachment 6.

DOUBLE VERIFICATION 5.9.9 For WRNM dry tubes, torque nut to 50 ft-lbs AND verify that there is no leakage. RECORD on Attachment 6. (IF during hydro, WRNM dry tube leaks, nut can be torqued up to but NOT greater than 100 ft-lbs).

5.9.10 IF leakage continues, THEN RESEAT Instrument per Subsection 5.10.

5.9.11 THREAD seal into bottom of nut, THEN snug TIGHTEN.

NOTES: Steps 5.9.12 through 5.9.14 apply only to LPRMs.

Steps 5.9.12 AND 5.9.13 may be skipped IF scheduled under vessel decontamination work may introduce moisture into instrument. IF NOT performed, these steps will be performed during I&C connection of signal cables AND during tip tube installation.

5.9.12 IF required, THEN REMOVE nose piece.

NOTE: LPRM gamma thermometer assembly TIP tube adapters do NOT have wrench flats on LPRM end.

5.9.13 IF required, THEN INSTALL TIP tube adapter.

NOTE: Stainless Steel tie wraps AND/OR hose clamps may be used as necessary to secure clamshell (sleeve) on LPRMS per ECR 98-01124.

5.9.14 INSTALL drip skirt AND sleeve.

5.9.15 INITIAL AND DATE indicatinq subsection complete.

WV

M.-C-774-010 Rev. 16 Page' 38 of 61 5.10 Reseating of Leaking Instrument Subsection Required: YES__ NO WV 5.10.1 PREPARE Instrument as follows:

1. REMOVE nut AND washer.

2. IF work is being performed on LPRM gamma thermometer, INSTALL nose piece.

3. INSPECT threads on seal tube AND Instrument housing flange. REWORK threads OR REPLACE seal tube as required.

4. APPLY thread sealant to seal tube threads, THEN INSTALL seal tube onto housing flange.

5.

Step 5.10.1.5 does NOT apply.

7PEACH BTO ENSURE filter is installed for drywell sump AND water level is sufficient in sump as determined by radiological engineering.

5.10.2 INSTALL flush fixture to seal tube.

5.10.3 ENSURE demineralized water supply valve AND flush fixture drain valve are closed.

5.10.4 OPEN seal tube valve.

5.10.5 OPEN demineralized water supply valve to flush Instrument seating surface for approximately 1 minute.

5.10.6 CLOSE demineralized water supply valve fully.

5.10.7 OPEN flush fixture drain valve to check for seat leakage.

5.10.8 ENSURE Instrument is properly seated by observing little OR no leakage from drain line.

5.10.9 REPEAT steps 5.10.3 through 5.10.8 as necessary.

M-C-774-010 Rev. 16 Page 39 of 61 5.10.10 REMOVE flush fixture from seal tube.

! 5.10.11 REMOVE seal tube, THEN REMOVE any excess pipe thread sealant from housing flange.

5.10.12 IF work is being on LPRM gamma thermometer, REMOVE nose piece.

5.10.13 LUBRICATE threads of Instrument, washer, AND threads of nut.

CAUTION Washer is larger than Instrument AND care must be taken to center washer over raised face of nut.

5.10.14 INSTALL washer next to flange, THEN INSTALL nut with raised face toward washer ensuring washer is centered over raised face of nut.

DOUBLE VERIFICATION 5.10.15 For LPRMs AND SRM/IRM dry tubes, TORQUE nut to 95 ft-lbs AND RECORD new leakage rate on Attachment 6.

4 DOUBLE VERIFICATION 5.10.16 For WRNM dry tubes, TORQUE nut to 50 ft-lbs. IF during hydro, WRNM dry tube leaks, nut can be torqued up to but NOT greater than 100 ft-lbs. RECORD new leakage rate on Attachment 6.

5.10.17 IF leakage exists, THEN CONTACT Maintenance Supervision AND RSTS prior to continuing.

5.10.18 THREAD seal into bottom of nut, THEN snug TIGHTEN.

NOTES: Steps 5.10.19 through 5.10.21 apply only to LPRMs.

Steps 5.10.19 AND 5.10.20 may be skipped IF scheduled under vessel decontamination work may introduce moisture into instrument. IF NOT performed, these steps will be performed during I&C connection of signal cables AND during tip tube installation.

5.10.19 IF required, THEN REMOVE nose piece.

5.10.20 IF required, THEN INSTALL TIP tube adapter.

5.10.21 INSTALL drip skirt AND sleeve.

5.10.22 INITIAL AND DATE indicating subsection complete.

WV

M-C-774-010 Rev. 16 Page 40.of 61 5.11 Contingency Instrument Removal with Crow's Foot Tool Subsection Required: YES__ NO WV 5.11.1 IF required, REPOSITION double blade guides per CCTAS.

5.11.2 INSTALL fuel support piece covers in adjacent cells.

5.11.3 INSTALL Crow's Foot tool onto handling poles.

5.11.4 LOWER Crow's Foot onto top side of boss of LPRM plunger.

5.11.5 RAISE AND LOWER Crow's foot as necessary to free stuck plunger.

5.11.6 IF plunger will NOT free, THEN PROCEED to Section 5.12.

5.11.7 IF plunger becomes free, THEN, IF possible, PLACE plunger in top guide socket AND RESTART Instrument removal per Subsection 5.4 CAUTION WHEN using cable mounted crows foot the jamming block on appropriate refueling platform hoist shall be set such that the cable mounted crows foot will remain at least 5 foot 6 inches below water surface.

DO NOT RAISE Grappled Instrument until flush is commenced per step 5.4.16. Otherwise, sudden change in radiological condition under vessel may result.

5.11.8 IF plunger does become free AND cannot be returned to position in top guide, THEN GRAPPLE the free instrument with the Instrument Handling tool, hydraulic grippers, air operated pliers OR cable mounted crow's foot.

5.11.9 BACKFLUSH instrument per Step 5.4.16.

5.11.10 REMOVE, BEND AND STORE Instrument following guidance provided in Subsection 5.4 5.11.11 REMOVE fuel support covers, IF required.

5.11.12 INITIAL AND DATE indicating subsection complete.

WV

M-C-774-010 Rev. 16 Page 41 of 61 5.12 Contingency Instrument Removal with Bowing Tool Subsection Required: YES NO WV 5.12.1 IF required, REPOSITION double blade guides per CCTAS 5.12.2 INSTALL fuel support piece covers in adjacent cells.

5.12.3 INSTALL Bowing tool onto ITI handling poles.

CAUTION IF using the over head crane to support ITI poles all raising AND lowering of the pole must be performed using a chain fall to prevent damage to reactor internals.

5.12.4 IF using overhead crane THEN INSTALL a chain fall inline with the rigging to the ITI poles 5.12.5 LOWER bowing tool AND ENGAGE to mid section of stuck LPRM.

5.12.6 Slowly TWIST LPRM UNTIL the plunger is free of the top guide.

5.12.7 INSPECT LPRM plunger AND VERIFY plunger is intact.

5.12.8 IF required, RETRIEVE loose plunger using air OR electric operated pliers AND store per approved procedures.

CAUTION WHEN using cable mounted crows foot the jamming block on appropriate refueling platform hoist shall be set such that the cable mounted crows foot will remain at least 5 foot 6 inches below water surface.

DO NOT RAISE Grappled Instrument until flush is commenced per step 5.4.16. OTHERWISE sudden change in radiological condition under vessel may result.

5.12.9 GRAPPLE the free LPRM with the Instrument Handling tool, hydraulic grippers, air operated pliers, cable mounted crow's foot OR safety clamp.

5.12.10 BACKFLUSH instrument per Step 5.4.16.

5.12.11 REMOVE, BEND AND STORE Instrument following guidance provided in Subsection 5.4.

5.12.12 REMOVE fuel support covers, IF required.

M-C-774-010 Rev. 16 Page'42 of 61 5.12.13 INITIAL AND DATE indicating subsection complete.

WV 5.13 LPRM/Dry Tube Removal Tool Operating Instructions (PBAPS)

Subsection Required: YES NO WV 5.13.1 ENSURE applicable steps of sections 5.1 AND 5.2 of this procedure are performed for the preparation for removal of a LPRM/Dry tube.

5.13.2 ENSURE the following steps are accomplished prior to using the Stuck LPRM/Dry tube removal tool.

1. SET Stuck LPRM/Dry tube removal tool lead-in to position 1. REFER to Attachment8.

2. INSTALL Hydraulic station on Refueling platform handrail AND CONNECT to station service air supply.

NOTE: The 1/2 inch OD hose attaches to the clamp (the lower cylinder)

3. ENSURE all air has been bled from the system AND hydraulic hoses connected to the Hydraulic station AND the tool.

4. TEST operation of the tool by actuating (pressurizing) both cylinders AND ensuring no interference exist.

5. For stuck LPRM removal only, Jaws are used instead of capture device clamp AND capture devices. Be sure to INSTALL LPRM Jaws instead of capture device clamp AND lock wire bolts.

NOTES: Steps 5.10.3 through 5.13.4 apply only to Dry tube removal.

The LPRM/Dry tube removal tool is sensitive to which side the capture device halves (black AND white) are located on the Clamp.

5.13.3 INSTALL one each black (on left) AND white (on right) capture device onto the Clamp halves AND maneuver the safety clip to capture devices.

5.13.4 VERIFY the capture devices are secured prior to submerging the tool into the Reactor cavity.

5.13.5 VERIFY the four core locations surrounding each instrument to be replaced are vacant.

M-C-774-010 Rev. 16 Page 43 of 61 5.13.6 INSTALL the Stuck LPRM/Dry tube removal tool as follows:

• 1. Using a single swivel adapter, THREAD adapter into jet pump grapple stud past view port in grapple stud.

2. TORQUE swivel adapter jam nut to 25-30 ft.lbs.

WV

3. INSTALL shackle into eyebolt on top of tool AND CONNECT jet pump grapple to shackle.

NOTES: Cell covers can be installed using ropes attached directly to cell covers OR a rope AND hook OR hook AND poles.

Cell cover installation can occur any time access is available to the instrument to be removed.

5.13.7 INSTALL 4 cell covers into exposed cells surrounding the instrument to be removed.

DOUBLE VERIFICATION 5.13.8 ENSURE refuel platform hoist mechanical stop (Jam Block) is set such that the middle of the upper hydraulic cylinder while in the retracted position is at least 5 feet 6 inches below surface of water. RECORD on Attachment 6.

NOTE: The following step may proceed in parallel with subsequent fuel floor steps.

5.13.9 REQUEST Undervessel personnel to INSTALL AND TEST flush fixture as follows:

1. CONNECT flush fixture to seal tube AND ENSURE demineralized water supply hose is attached.

2. CLOSE flush fixture drain valve.

3. OPEN seal tube valve.

4. OPEN demineralized water supply valve to check for leaks. IF excessive leakage is noted THEN CLOSE seal tube valve AND demin water supply valve AND REWORK as required prior to continuing.

5. CLOSE demin water supply valve.

6. CLOSE seal tube valve.

7. MOVE to low dose area until fuel floor is ready to C_ flush instrument housing AND NOTIFY Fuel Floor crew step is complete.

M-C-774-010 Rev. 16 Page'44 of 61 5.13.10 Per CCTAS, VERIFY proper core location, THEN LOWER the tool into the Reactor cavity until just above the top guide AND POSITION the tool over the LPRM/Dry tube to be removed.

NOTE: The final resting position for the tool is where the sides of the tool are touching the side of the top guide AND the clamping jaws are on opposite sides of the Dry tube.

5.13.11 CONTINUE to lower the tool through the top guide, making sure to align the tool so the top lead-in rests on the top guide's "cross section AND the capture devices are surrounding the Dry tube.

5.13.12 IF required, THEN MOVE the hoist cable AND/OR the bridge to adjust the tool into final position.

5.13.13 VERIFY using the underwater camera, the tools final position. ENSURE that the smaller I.D. at the top of the capture device will NOT clamp around the larger diameter section of the dry tube. IF necessary, REMOVE tool AND ADJUST capture devices.

5.13.14 EXTEND the Clamp at the hydraulic station to a minimum of 2000 psig, NOT to exceed 3000 psig AND VERIFY the capture device has closed completely around the Dry tube AND the inserts are clamped together at least one notch.

S5.13.15 EXTEND the Press at the hydraulic station to a maximum of 400 psig. Continue to observe the Press as it moves through full stroke (approx. 4 inches) AND compressed the plunger.

5.13.16 IF the Press did NOT over come the plungers resistance, THEN INCREASE the Press pressure NOT to exceed 550 psig.

5.13.17 Once the Press has traveled full stroke OR the plunger is retracted from the top guide, THEN RETRACT the Press at the hydraulic station.

5.13.18 VERIFY the plunger is released from the top guide. The plunger may release after the Press is retracted.

5.13.19 VERIFY a minimum of 2000 psig pressure exists on the Clamp at the hydraulic station.

5.13.20 ENSURE access to upper elevations of drywell have been restricted as required by Health Physics prior to removing irradiated Instruments.

M-C-774-010 Rev. 16 Page 45 of 61 C-NOTE:

5.13.21 As soon as backflush is started, Fuel Floor crew should proceed with performance of Step 5.13.22.

REQUEST Undervessel personnel to BACKFLUSH instrument housing as follows:

1. VERIFY flush Fixture drain valve CLOSED.

2. OPEN seal tube valve.

3. OPEN Demin water supply valve.

4. NOTIFY Fuel Floor personnel flush is started.

5. WAIT 3 minutes, THEN CLOSE demin water supply valve.

6. CLOSE seal tube valve.

7. OPEN flush fixture drain valve, THEN REMOVE flush fixture from seal tube, IF required.

CAUTION While raising Instrument, care must be taken to prevent boss rings OR bottom portion of Instrument from catching on core Top Guide.

WARNING Health Physics shall monitor dose rates during raising, bending, AND transport of the Instrument. Raising of the Instrument shall stop IF radiation levels exceed 30 mr/hr at water surface with Instrument 1 foot below water.

5.13.22 USE a "Safety Kink to verify the tool is free to move, THEN BEGIN removal of the tool AND dry tube by moving the tool as far away from the cross section as possible.

5.13.23 Slowly RAISE the tool AND dry tube up through the top guide while watching with the under water camera to prevent any item from -'hanging up on the top guide.

5.13.24 PERFORM steps 5.4.18 through 5.4.25 of this procedure, THEN RETURN to step 5.13.25.

5.13.25 RELEASE the dry tube from the Clamp by placing the Clamp lever in the "RETRACT position at the hydraulic station.

One side of the capture device should come out of the Clamp.

M-C-774-010 Rev. 16 Page.46 of 61 5.13.26 RELEASE the other half of the capture device AND the Dry tube Assembly from the tool using a "J OR "L hook on an underwater handling pole IF required.

5.13.27 IF NOT already done, THEN RELEASE the hydraulic pressure from the Clamp AND Press.

5.13.28 PERFORM steps 5.4.27 through 5.4.36 of this procedure AND RETURN to step 5.13.29.

5.13.29 IF the Stuck LPRM/Dry tube removal tool is to be used again, THEN RAISE the tool out of the water AND REPEAT steps as necessary for the remaining LPRM/Dry tube assemblies.

Otherwise, RETURN the Stuck LPRM/Dry tube removal tool AND associated support equipment to the designated storage location.

5.13.30 Prior to cell cover removal, VACUUM/RETRIEVE debris as required.

5.13.31 REMOVE cell covers as required.

6.0 RETURN TO NORMAL 6.1 ENSURE the following:

- Tools AND equipment are returned to designated storage location AND work area is clean.

M&TE numbers, date used, AND out of cal dates are recorded in WO.

Name AND initials of each person who initialed procedure steps is entered on last page of this procedure.

Attachment 6 has been completed with all appropriate signature blocks accounted for.

Procedure is complete AND attached to WO.

WV 6.2 IF it is anticipated that LPRM bender(s) will be exposed to very low temperatures, e.g. will be shipped to another site or stored outdoors during winter months, THEN CONSIDER taking one of the following actions to preclude damage to tool due to freezing:

1. DRAIN reservoir, hoses, hydraulic cylinders and control station.

2. REQUEST Planner to revise or create a work order activity to perform draining and layup of bender tool.

M-C-774-010 Rev. 16 Page 47 of 61 WV

7.0 REFERENCES

7.1 Vendor/Technical Manuals 7.1.1 M-1-JJ-170 (PBAPS), Bll-D193-K-001 (LGS), General Electric GEK 97055, Local Power Range Monitor 7.1.2 F20-E007-K-001 (LGS), General Electric GEK 33143, Instrument Handling Tool 7.1.3 NE-203-200 (PBAPS), Operation and Maintenance Instructions for WRNM Detector F14-00084-01, Operation and Maintenance Instructions for Dry 7.1.4 Tube Removal Tool 177D2032 7.2 Plant Procedures/Drawings 7.2.1 A-C-33, Nuclear Generation Group Process for Verification of Quality 7.2.2 A-C-132, Spent Fuel Pool Material Storage/Inventory and Housekeeping 7.2.3 M-C-774-008, Preparation of New Local Power Range Monitors (LPRMs) 7.2.4 ST-O-107-494-0 (LGS), Non-Routine By-Product Material Leakage Test 7.2.5 ST-H-099-820-2, Sealed Source Accountability & Leak Test 7.2.6 IC-11-00482, Checkout and Troubleshooting of LPRM Detectors 7.2.7 OP-AA-101-111, Roles and Responsibilities of On-Shift Personnel 7.2.8 RE-C-040, Core Component Transfer Authorization Sheet Generation and Administration 7.2.9 Drawing 6280-Ml-JJ-106-3 7.2.10 MAG-CG-301, Control of Bolting/Torquing/Tensioning 7.3 UFSAR/Technical Specifications 7.3.1 LGS UFSAR Sections 15.7.4 and 15.7.6 and PECO Calculation LM-033, Methodology to Determine the Acceptability of Moving Loads Over Irradiated Fuel Without Secondary Containment.

M-C-774-010 Rev. 16 Page'48 of 61

( 7.4 Miscellaneous 7.4.1 SSES Significant Operating Occurrence Report 93-326 7.4.2 RSAI A0675443-05 7.4.3 CAR Q0002436 7.4.4 10001540, Swivel Adapter 7.4.5 LGS REIF/EIR 92-04-29; AR# A0403672, CA-2 7.4.6 SIL 082, Rev. 1, Supplement 1 7.4.7 Limerick ECR LG 94-10498 for LPRM gamma thermometer assemblies.

7.4.8 MOD P00271, (PBAPS) Startup Range Neutron Monitoring System Improvements 7.4.9 A1143608 E02, E03, A0849919 E21, Evaluation of Loaded LPRM Strongback and LPRM Bender Handling.

7.4.10 ECR 98-01124 Rev. 0, Missing Ears on LPRM Clamshells.

C 7.4.11 ECR 98-02056 Rev. 0, Revision to UFSAR "Plant Refueling Outage'" and "'In Vessel Servicing Equipment to eliminate the strict use of instrument handling tool.

7.4.12 PEP 10011081, LPRM Came Out of Clamp During Bending.

7.4.13 ECR 01-00038, LGS Fuel Floor Auxiliary Platform 7.4.14 OE 12238, Multiple Personnel Contaminations during LPRM Work 7.4.15 CR 77040, LPRM Signal Cables Cut in Wrong Location During Maintenance 8.0 ATTACHMENTS 8.1 Attachment 1, Core Map 8.2 Attachment 2, LPRM Assembly 8.3 Attachment 3, Instrument Plunger Detail 8.4 Attachment 4, Instrument Handling Tool 8.5 Attachment 5, Top Guide Detail

( 8.6 Attachment 6, Multiple Sign-Off Sheet

M-C-774-010 Rev. 16 Page 49 of 61 8.7 Attachment 7, Multiple Sign-Off Sheet for Subsection 5.6 C8.8 Attachment 8, Stuck LPRM/Dry Tube Removal Tool Lead-In Setup 8.9 Attachment 9, In-Core Housing Guide Tube Seal 8.10 Attachment 10, In-Core Housing Guide Tube Seal Installation Position

M-C-774-010 Rev. 16 Page' 50 of 61 01 03 05 07 09 11 13 15 17 19 21 23252729 31 33 35 37 39 41 43 45 47 49 51 53 55 57 59 60 60 alQ M 58 58 D E0m 56 56 m E 54 54 ED m10 52 52 50 BUDN

-B* 48 46 46 aus 44 11IN 42 40 32 MID ISO@ lmn[i@ ISiE a]@]% [ 38 38 Mr/

36 34 32 IMIN I

G IN1 30 30 lfIs MINIS 28 ]as DO .*fM M-F- 'M_* 7 'Mf7 Mr7/ MVMf,*28 26 ýLo 0 m, UpF/

m M4r7/ M r/7 ODEMS H [ 1*

Im BID Di 0 B1ID DID[11 i I"Do"O[]D D11 26 Doom0mi offluso Dimon 24 24 22 n! MOW MS MOMB-FMOO 22 20 20 18 - JUDDI BUDf r/7M r/7 ODOMMEDI F pr/7 M r7/ M r7/ 18 16 16 so @0 Fa Q Zo WS 0 zip Nism BD 14 14 n BOOM IDSWOUBS 12 12 MOUSMA BUSES 3100 373ED4 4 740 ]3575E33 10 10 08 08 BEMom ýlsu 06 06 04 D I'mMMU-N-0 04 02 01 DUMB 03 05 07 09 11 13 15 17 19 21 23 25 27 29 02 0 LPRM N Note I

[] Note 2 Note 1: IRM at LGS; WRNM at PBAPS.

Note 2: SRM at LGS; spare WRNM Dry Tube at PBAPS.

CORE MAP Attachment 1 Page 1 of 1

M-C-774-010 Rev. 16 Page 51 of 61 VIEW SHOR"INO SHEILD REMOVED

-f WASHER 4-r Nu.r

• _-- DRIP SKIRT

-- SEAL SEAL TUBE, rn

< SLEEVE SEAL TUBhE VALVE C

CHECK "VALVE FflflRE1 LPRM ASSEMBLY Attachment 2 Page 1 of 1

M-C-774-010 Rev. 16 Page'52 of 61 MIDDLE "BOSS" 0

IV.A LPRM DETECTOR ASSEMBLY SPRING-LOADED PLUNGER NOTE:

ALL DIMENSIONS ARE IN INCHES.

INSTRUMENT PLUNGER DETAIL Attachment 3 Page 1 of 1

M-C-774-010 Rev. 16 Page 53 of 61 AIR LINE CONNECTIONS SLIDE LOCK PIN ROLLER STOP CYLINDER INSTRUMENT HANDLING TOOL Attachment 4 Page 1 of 1

M-C-774-010 Rev. 16 Page 54 of 61 1/4" - 450 CHAMFER TYP.

Note: All dimensions are in inches.

TOP GUIDE DETAIL Attachment 5 Page 1 of 1

M-i*4-010

-,ev. 16 Page 55 of 61 5.2.1 5.2.3 5.4.4 R 5.4.19 5.8.24 5.9.8OR 5.10.15 ORR CORE LOCATION PROPER 5.13.8 ELEVATOR ENGAGEMENT 5.9.9 5.10.16 LOCATION CUT JAN BLOCK FULL IN TOP NUT NUT TORQUED; U.V.

LOCATION SET DOWN GUIDE TORQUED LEAK RATE (DPM)

DV DV DV DV DV DV DPM DV DV DV DV DV DV DPM DV DV DV -D DV DV DV DV DV DPM S-DV DV DV DV DV DV DV DPM MULTIPLE SIGN-OFF SHEET Attachment Page 1 of 2 6

M-C("' -010

-,*V. 16 Page 56 of 61 5.4.4 OK 5 8 .24 5.9.8 (JR 5.10.15 OR

5. 4. 4 9R 5.4 5.4.19

.19 .

5.8.24 S. 9. 8 OR 5.10.16 CORE 5.2.1 5.2.3 5.13.8 5.9.9 LOCATION LOCATION PROPER ELEVATOR IENGAGEMENT NUT NUT TORQUED; JAM BLOCK U.V. CUT SET FULL IN TOP TORQUED LEAK RATE LOCATION DOWN GUIDE (DPM)

I 4 + t I DV DV DV DV DV DV DV DPM i I T DV DV DV DV DV DV DV DPM

_ _I_ _ 4-i DV DV DV DV DV DV DPM DV DV DV DV DV DV DV DPM DV

____ I ____ j _____ I_____ L_____ I _____ ______ .1________

Attachment Page 2 of 2 6 MULTIPLE SIGN-OFF SHEET

M-(ý4-010 rev. 16 Page 57 of 61 5.6.20 5.6.24.7 5.6.26 5.6.29 5.6.30 CORE 5.6.5 5.6.8 HP Flange No Flange/ No Gross Guide Comments LOCATION Guide Survey Bolts Leakage Seal Tube Leakage Tube Tube Seal Installed Torqued Installed Undervessel Seal Removed WV HP DV wV IV WV WV WV HP ____ _ _

DV WV IV WV WV WV HP DV WV IV WV WV WV HP DV IV WV WV WV 5.6 Attachment 7 MULTIPLE SIGN-OFF SHEET FOR SUBSECTION Page 1 of 1

M-C-774-010 Rev. 16 Page 58'of 61 View A-A STUCK LPRM/DRY TUBE REMOVAL TOOL LEAD-IN SETUP Attachment 8 Page 1 of 1

M-C-774-010 Rev. 16 Page 59 of 61 BAIL (6) BODY PIN (4) TIP In-Core Housing Guide Tube Seal Attachment 9 Page 1 of 1

M-C-774-010 Rev. 16 Page 60 of 61 Tool ýdie S* ..::-" -* X ........................ .........

S* Tool "'Hair

• Pin (typ 2)

NOTE: Similar to Instrument Handling Tool, rotational orientation with respect to target instrument is NOT critical.

In-Core Housincr Guide Tube Seal Installation Position Attachment 10 Page 1 of 1

M-C-774-010 Rev. 16 Page 61 of 61 PRINTED NAME SIGNATURE INITIALS REMARKS C¢

zzzmmzzzz I

I EXELON NUCLEAR TITLE: Movement of fuel from the fuel prep machine (Alternate Path)

TASK PERFORMED BY:

EVALUATOR:

EVALUATOR SIGNATURE:

DATE:

DIRECTIONS TO EVALUATOR:

EVALUATION METHOD:

SIMULATE EVALUATION LOCATION:

REFUELING PLATFORM APPROXIMATE COMPLETION TIME:

Completion Time: 30 min IMPORTANCE RATING(S): SYSTEM NUMBER(S):

3 3.5 2.2.28

REFERENCES:

FH-106, CORE COMPONENT AND IRRADIATED ITEM MOVEMENT

- NO CORE TRANSFER

$97.0.M, REFUELING PLATFORM OPERATION TASK STANDARD(S):

Fuel moved to target location per CCTAS, with response to unexpected slack cable warning per

$97.0.M

-.-. *.I5 aVt "-.tLJIJr, Page 3 of 13

I EXELON NUCLEAR TASK CONDITIONS:

1. A fuel bundle is ready for pickup in the Unit North fuel prep machine and release in the spent fuel pool

2. All prerequisites are complete, with FH-106 and S97.0.M in progress

3. The refueling platform is in operation and positioned over the spent fuel pool INITIATING CUES:

You are directed to perform the fuel transfer listed in the attached CCTAS Iv 2 r LG Page 4 of 13

EXELON NUCLEAR Critical Element(s) indicated by '" in Performance Checklist.

PERFORMANCE CHECKLIST:

STEP STANDARD SAT/UNSAT Section 4 of S97.0.M, Pickup Location- Fuel Prep Machine

1. Verify fuel prep machine is fully Verify fuel prep machine is fully lowered lowered (Note: Normally performedby NMD, not CUE: The fuel prep machine is fully lowered the LSRO)

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

2. *Carefully position the refuel platform Bridge and trolley controls operated to mast over the fuel prep machine in position the bridge over the fuel prep accordance with the CCTAS machine CUE:The bridge is positioned over the fuel prep machine.

3. *Lower grapple until the grapple is 6 Hoist lowered until the grapple is 6 to 12 to 12 inches above the bail inches above the bail handle CUE: The grapple encoder reads 157 inches

4. *Depress the GRAPPLE LOCKOUT GRAPPLE LOCKOUT BYPASS BYPASS pushbutton pushbutton depresse CUE: GRAPPLE LOCKOUT BYPASS pushbutton is depressed and held

5. Ensure the grapple is open Ensure the grapple is open CUE: The grapple switch is in RELEASE with no backlight

6. *Rotate grapple as necessary to Rotate grapple until the grapple end is achieve grapple to bail alignment oriented the same as the bail handle CUE: The grapple head is aligned the same as the bail handle r- 0*_ IDAI, A* ,4,1-U Page 5 of 13

EXELON NUCLEAR I STEP STANDARD SAT/UNSAT

7. *Slowly lower grapple until SLACK Grapple controls taken to LOWER until CABLE light is lit SLACK CABLE is lit CUE: The red SLACK CABLE lamp is lit stp. .. 3.5hog . 3.3salb.obevrfe yteFe adigDrco n h eulPafr Steps 4.3.8 through 4.3.13 shall be double verified by the Fuel Handling Director and the Refuel Platform Operator or Spotter CUE: The Fuel Handling Director is performing double verification

8. Verify proper core component location Bundle location and orientation verified and orientation CUE: Bundle is in the fuel prep machine and the channel fastener is northeast

9. Verify the following then notify FHD of 4 N/A N/A grapple position i I ___-

a. Grapple is centered over bail Grapple verified to be centered over the handle bail handle CUE: Grapple is centered over the bail handle 4 1 ___

b. Hoist position indication Hoist position verified agrees with value listed in Attachment 2 for item seated in the fuel prep machine CUE: Hoist position indicates 165 inches I

10. *When directed by FHD, then engage i Grapple control switch taken to the grapple and release the grapple ENGAGE lockout pushbutton GRAPPLE LOCKOUT BYPASS CUE: Grapple control switch is in ENGAGE pushbutton released position. GRAPPLE LOCKOUT BYPASS is released

11. Verify GRAPPLE ENGAGED light is lit Grapple control switch verified to have CUE: The grapple control switch is now green backlight lit backlit green II f-'C IDAA 0 4-lvi . UL, -.

DA Page 6 of 13

EXELON NUCLEAR STEP STANDARD SAT/UNSAT

12. *When directed by FHD, then raise Hoist controls taken to RAISE load and verify HOIST LOADED light HOIST LOADED lamp verified to be lit is lit (fuel/dummy bundle only) or for skeleton fuel bundle visually verify component movement CUE: HOIST LOADED light is lit and bundle is coming up

13. *Continue raeising until grapple is fully Raise bundle until NORMAL UP lamp is raised then verify NORMAL UP lamp lit, then release controls is lit CUE: (Wait about 10 seconds, then "The NORMAL UP" lamp is lit"

14. Go to appropriate RELEASE N/A N/A LOCATION section of this procedure as directed by FHD Section 4.5 of S97.0.M Release Location in Spent Fuel Pool

15. *Position core component over Operate bridge and trolley controls to desired location in accordance with position the mast over the target location the Core Component Transfer on the CCTAS Authorization Sheet (CCTAS)

CUE: The mast is over the fuel rack location in the CCTAS

16. *Rotate core component as necessary Verify CCTAS orientation and rotate to achieve proper orientation mast to properly orient the bundle CUE: The channel fastener is southwest

17. Perform double verification to ensure Verify bundle location and orientation proper core component location and orientation CUE: "The Fuel Handling Director and Spotter have double verified location and orientation" ^C' L.*7 r-l'V1 J3.C00C Page 7 of 13

EXELON NUCLEAR

-I I ('.1-I-', - -

01 -1 STANDARD I*ATII IklO ^I-STANDARD 2121TI

. . .t 1 - 0Af

,/ t 14 U

• O '

18. *When directed by the FHD, then lower I.

Bundle lowered until red SLACK CABLE the hoist until core component is seated lamp is lit on hoist control console.

and SLACK CABLE is lit Recognize SLACK CABLE is being CUE: The Fuel Handling Director has received early and the bundle is not directed you to lower the bundle into the seated (seated is 195n) rack

...wait 10 seconds CUE: "The slack cable lamp is lit with the hoist position 20 inches. The bundle is pivoting on the nosepiece and leaning over Response to Unexpected Slack Cable Warning (Precaution 3.10)

19. If HOIST LOADED light goes out N/A prematurely or load starts to lean

a. *Hoist lowering shall be Stop lowering stopped immediately CUE: Hoist motion has stopped

b. Grapple switch shall be Grapple verified engaged verified to be in ENGAGED position I CUE: Grapp'le switch shows ENGAGED

c. Grapple engagement shall be Grapple engagement verified verified CUE: Mast camera still shows the bundle to be grappled Green backlighting verified on grapple

d. GRAPPLE ENGAGED light shall be verified lit control switch CUE: The grapple control switch is backlit green

e. *Hoist shall be raised slowly to Hoist raised to regain the weight regain the weight CUE:

CUE: The hoist indicates 30 inches and HOIST HOIST LOADED lamp is lit LGS JPM ! dnr rfn -

Page 8 of 13 LG

"EXELONNUCLEAR

]

STEP STANDARD SAT/UNSAT

f. Fuel Handling Director shall be FHD notified notified CUE: Fuel Handling Director has been notified.

20. CUE: You have reached the N/A termination point for this JPM. You may stop here..

LG-q -IPJ doc Page 9 of 13

I N . , . ..,- .

I EXELON NUCLEAR Comments:

Note: Any grade of UNSAT requires a comment.

JPM Overall Rating:

SAT/U NSAT i ,n ,dae , A LL70 JIW -5J.00C Page 10 of 13

• -.-,-.6**.

-t ..

S..

I NUCLEAR m'&XELON NUC EAR TASK CONDITIONS:

1. A fuel bundle is ready for pickup in the Unit North fuel prep machine and release in the spent fuel pool

2. All prerequisites are complete, with FH-106 and S97.0.M in progress

3. The refueling platform is in operation and positioned over the spent fuel pool INITIATING CUES:

You are directed to perform the fuel transfer listed in the attached CCTAS CANDIDATE

\NSFER AUTHORIZATION FOR FH-1 06 ivi-219966 Rev. 1/89 P3 I of I DOCTYPE 113 Written By: TRAINING USE ONLY Unit LIMERICK GENERATING STATION Date 6/3/02 Reviewed By: TRAINING US EONLY Title TRAINING CCTAS Authorized By: TRAINING W E ONLY

l. * ,ME**

TIME JPM 3 CCTAS for Unit I CANDIDATE

.NSFER AUTHORIZATION FOR FH-106 M-219966 Rev. 1/89 PC, of DOCTYPE 113 Written By: TRAINING USE ONLY Unit LIMERICK GENERATING STATION Date 6/3/02 Reviewed By: TRAINING USE ONLY Title TRAINING CCTAS Authorized By: TRAINING USE ONLY STEP NO. COMPONENT MOVE FROM ORIENT MOVE TO ORIENT FHD RPO CRO DATE TIME SERIAL NO.

7 LYN521 NFPM NE L2SPENT 0-21 SW JPM 3 CCTAS for Unit 2 CANDIDATE

• 1

'A -

Page 1f21 Exelon Nuclear FOR TRAINING PURPOSES ONLY ja Limerick Generating Statio move- (\FiYV - 6r ..... '

FH-106 CORE COMPONENT AND IRRADIATED ITEM MOVEMENT - NO CORE TRANSFER 1.0 PURPOSE This procedure provides instructions and requirements for the performance of core component and irradiated item movement when the core is not accessible from the fuel floor.

This procedure establishes:

a. the necessary initial conditions for core component and Irradiated Item Movement - No Core Transfer.

b. accounting guidelines for Special Nuclear Material (SNM) as per RE-C-44.

2.0 REFERENCES

2.1 RE-C-44, Procedure for Accountability and Control of SNM

( 2.2 TQ-AA-210, Procedure for Management of Training 2.3 RE-C-40, Core Component Transfer Authorization Sheet Generation and Administration 2.4 S97.0.M, Refueling Platform Operation 2.5 LGS UFSAR Section 13.5.1.20.

2.6 EIR #92-04-19 2.7 NSAC/164L, Guidelines for BWR Reactivity Control During Refueling 2.8 A-C-300, Reactivity Management Program 2.9 NOM-L-8.4, Unavailable Equipment/Equipment Release 2.10 OP-AA-108-106, Equipment Return to Service 2.11 NRC Information Notice 95-56, Shielding Deficiency in Spent Fuel Transfer Canal at BWR's 2.12 ON-120, Fuel Handling Problems

FH-106, Rev. 24 Page 2 of 21 JAD/j ad 2.13 UFSAR Section 15.7.4 AND 15.7.6 AND PECO Calculation LM-033 "Methodology to Determine the Acceptability of Moving Loads over Irradiated Fuel without Secondary Containment Integrity."

2.14 LGS Tech Specs 3.6.5.1.2, 3.6.5.2.2 AND 3.6.5.3.

2.15 AR A1158987, A1159331, Response to INPO IE8834 - "Problems associated with irradiated fuel inspection activities" 2.16 AR A1081310e01, Evaluation of decay time required for new fuel bundle or dummy bundle movement in Unit 2 SFP without secondary containment.

2.17 LGS UFSAR Section 9.1.1.3 New Fuel Storage - Safety Evaluation.

2.18 S97.0.L, Manual Operation of Refuel Platform Hoist 2.19 PEP Issue 10009814, Fuel Bundle contacted fuel in core during hoist lowering.

2.20 PEP Issue 10010407, High Rad levels detected by HP during cavity drain down.

2.21 ECR LG 01-00282, Calculation for movement of light loads over irradiated fuel without Secondary Containment 2.22 AR A1308847 eval 04, Clarification on use of light weight handling poles over irradiated fuel per ECR LG 01-00282 3.0 RESPONSIBILITIES 3.1 The Reactor Engineer shall be responsible to:

3.1.1 Determine the proper prerequisites.

3.1.2 Ensure fuel handling procedures and Special Nuclear Material Accounting documents required to perform the core component and irradiated item movements are available.

3.1.3 Inspect core component transfer and fuel accountability documents during the handling operation and initiate any appropriate additions or changes.

3.1.4 Prepare the Core Component Transfer Authorization Sheet (CCTAS) as per RE-C-40 prior to implementation of the procedure.

3.1.5 Collect, distribute and file documentation associated with this procedure.

3.1.6 Review all future revisions to this procedure.

FH-106, Rev. 24 Page 3 of 21 JAD/jad 3.2 The Maintenance Supervisor shall be responsible to:

3.2.1 Perform required maintenance and tests of equipment following the release of refueling bridge equipment by Shift Management/LSRO.

3.2.2 Inform shift supervision of core component and irradiated item transfer progress.

3.2.3 Notify Fuel Handling Director and supervision of abnormalities or malfunctions of equipment.

(Ref. 2.8) 3.3 The Fuel Handling Director shall be responsible to:

3.3.1 Ensure completion of applicable procedures, data sheets and forms, and when necessary, obtain any required document changes.

3.3.2 Ensure compliance with the appropriate prerequisites as determined by the Reactor Engineer.

3.3.3 Ensure all core components and irradiated items are moved in accordance with the CCTAS. This includes DOUBLE VERIFICATION with the refuel platform operator of correct mast positiQn prior to grappling, prior to placing the bundle in the designated location, AND documentation of the move on the CCTAS to ensure safe and accurate placement in the fuel pool and cask handling pit. (Ref. 2.8) 3.3.4 Initiate necessary changes to the CCTAS as per RE-C-40. (Ref. 2.7) 3.3.5 Direct and supervise the actions of refueling platform operators and other NMD personnel involved in core component transfers.

3.3.6 Ensure that the refueling bridge operator and spotter (if used) are qualified as refueling bridge operators.

3.3.7 Be positioned on the refueling bridge during transfer of core components.

3.3.8 Consider consequences of, and if appropriate, authorize release and return of refueling bridge equipment to/from an operable status in accordance with Operations Manual. (LSRO ONLY)

(Ref. 2.9 and 2.10)

FH-106, Rev. 24 Page 4 of 21 JAD/j ad 3.3.9 IF REFUELING FLOOR SECONDARY CONTAINMENT INTEGRITY is not maintained THEN Cease movement of irradiated fuel AND of objects over irradiated fuel in accordance with Ref. 2.14 Tech Specs UNLESS objects are analyzed per References 2.13 and 2.21 (See Tables 1 and 2).

3.3.10 Overlap during a turnover for at least one (1) move OR until comfortable with the situation prior to the relieved individual leaving. Turnover shall not take place in the middle of a move involving transfer of a fuel bundle or blade guide, unless warranted by extraordinary circumstances (Ref. 2.19).

3.4 The Refueling Platform Operators shall be responsible to:

3.4.1 Perform core component and irradiated item movement in accordance with the applicable system procedures and the CCTAS.

3.4.2 Participate in the DOUBLE VERIFICATION of all core component AND irradiated item transfers.

3.4.3 Be qualified to operate the Refueling Platform.

3.4.4 Overlap during a turnover for at least one (1) move OR until comfortable with the situation prior to the relieved individual leaving. Turnover shall not take place in the middle of a move involving transfer of a fuel bundle or blade guide, unless warranted by extraordinary circumstances (Ref. 2.19).

3.5 Health Physics personnel shall be responsible to:

3.5.1 Designate controlled access areas.

3.5.2 Provide personnel monitoring.

3.5.3 Provide and maintain safe and orderly decontamination areas.

3.5.4 Follow the guidelines specified in the applicable HP procedure.

3.5.5 Be present on the Refuel floor during fuel movements.

FH-10.6, Rev. 24 Page 5 of 21 JAD/jad 3.5.6 Determine the radiological effects of moving/storing irradiated components in the Spent Fuel Pool, Cask Pit and Transfer Canal and recommend ALARA controls as necessary.

3.6 The Training Department, Limerick Generating Station, shall be responsible to:

3.6.1 Ensure that personnel involved with core component movement are familiar with fuel handling and radiological safety requirements.

3.6.2 Maintain and update certification records of Fuel Handling Directors per TQ-AA-210.

3.7 The Training Department, Peach Bottom Atomic Power Station, shall be responsible to:

3.7.1 Ensure that personnel involved with core component movement are familiar with fuel handling and radiological safety requirements.

3.7.2 Maintain and update certification records of Refueling Platform Operators per TQ-AA-210.

3.8 The Control Room Operator (RO/SRO) shall:

3.8.1 Contact the Fuel Handling Director to suspend movement of irradiated fuel OR movement of objects over irradiated fuel IF REFUELING FLOOR SECONDARY CONTAINMENT INTEGRITY is not maintained, in accordance with Ref. 2.14 Tech Specs. unless items are confirmed to have been analyzed per Refs. 2.i3 and 2.21.

FH-106, Rev. 24 Page 6 of 21 JAD/j ad PREREQUISITES

( 4.0

- It NOTE

1. The following prerequisites may be considered unique to Core Component and Irradiated Item Movement with no core transfer.

2. The prerequisites may be signed-off in any order.

3. Step 9.1.4 provides guidance if it is desired to expand the scope of work to be performed under this procedure after all prerequisite signoffs are completed (e.g., addition of fuel inspections in the fuel prep machines).

CAUTION Secondary Containment Integrity is required:

1. During all movement of irradiated fuel (Ref.2.14) AND

2. During the movement of objects over irradiated fuel unless analyzed per References 2.13 and 2.21.

4.1 Complete these prerequisites regardless of the type of irradiated item to be moved.

4.1.1 Check Unit(s) which Core Component AND Irradiated Item Movement with no core transfer is to be performed.

Unit 1 Unit 2 Initials Date 4.1.2 Label top of cover page with scope of work to be performed under this procedure.

Initials Date 4.1.3 Permission is granted by Shift Supervision to perform this procedure.

SSVN Date

FH-106, Rev. 24 Page 7 of 21 JAD/jad 4.1.4 Health Physics has been informed of the activity AND all necessary surveys AND ALARA Planning are complete.

IF an RWP is required, THEN verify it is active.

HP Supv Date Rad Eng.

4.1.5 The following Fuel Handling procedure for refueling platform operational checkout over the fuel pool is complete:

M-C-797-005 Initials Dastate 4.1.6 IF fuel preparation machines are to be used THEN they are to be checked out per M-C-797-008 Otherwise mark signoff N/A.

Unit 1 NFPM:

Inltials Date Unit 1 SFPM:

I/fA 1 Initials Date Unit 2 NFPM:

Initials Date Unit 2 SFPM:

Initials Date 4.1.7 The CCTAS required to begin the scope of work labeled on the cover page is prepared, reviewed, approved and distributed as per RE-C-40. Initials Date 4.1.8 All Fuel Handling procedures, Special Nuclear Material accountability forms, AND data sheets required to perform the task of core component and irradiated item movement are available. Initials Date

FH-106, Rev. 24 Page 8 of 21 JAD/j ad 4.1.9 Refuel floor fire hose stations and extinguishers are unobstructed. ioZ z*2 /&L IL Initials Date 4.1.10 Adequate lighting AND Water clarity exists in the Fuel Pool(s)

OR Cask Pit Area, as applicable, to perform Core Component AND Irradiated Item Movement.

(Ref. 2.6)

FHD Date 4.1.11 IF portable demin system is installed in the Fuel Pool OR Cask Pit Area THEN ensure pump AND hose locations do not interfere with component/refuel platform movements.

IF NOT, N/A this step.

Initials Date 4.1.12 Ensure no current outage discharge fuel is placed within 8 rack rows of spent fuel pool/reactor cavity gates as defined per RE-C-40.

(Ref.2.20)

Rx Eng Date 4.1.13 Reactor Cavity flooded to > 481.5 inches (Shutdown or Upset Range)

OR STOP LOG 15 installed prior to movement of any irradiated fuel OR irradiated core components in the spent fuel pool.

(Ref. 2.20)

FHD Date

FH-106, Rev. 24 Page 9 of 21 JAD/jad NOTE ST's must be verified in surveillance.

4.2 Complete the following prerequisites if fuel assemblies are stored in the fuel pool.

4.2.1 All requisite fuel floor Radiation Monitors are operable (TS 3.3.7.1):

Stm. Separator Area: ST-2-026-413-*

ST-2-026-613-*

Fuel Pool Criticality: ST-2-026-428-*

ST-2-026-614-*

Plug Laydown: ST-2-026-444-*

ST-2-0.26-628-*

Temporary ARM ST-0-027-640-*

(if required) 4 Initlias Dat-e 4.2.2 The fuel floor reactor enclosure crane boundary zone control is operable:

(N/A if crane will not be used during this evolution)

ST-4-098-320-0 Initials Da-t-e 4.3 IF irradiated fuel assemblies are stored in the fuel pool THEN verify at least 22 feet of water is maintained above the top of fuel seated in the spent fuel pool storage racks by reviewing the current ST-6-I07-594-*.

Otherwise, mark N/A for this step.

Initials Da e

FH-106, Rev. 24 Page 10 of 21 JAD/jad NOTE Tables 1 and 2 list some of the items currently analyzed per Refs.

2.13 and 2.21.

Contact Reactor Engineering to determine if items not listed have been analyzed.

IF item meets design limits AND fuel decay times as listed in Table 1 OR limitations listed in Table 2, THEN secondary containment is not required.

4.4 IF secondary containment is required (if 1-Tradiated fuel assemblies are to be handled in the reactor enclosure, fuel floor OR objects will be moved over irradiated fuel that are not analyzed per Refs. 2.13 and 2.21)

THEN Complete the following prerequisites.

Otherwise, mark these steps N/A:

4.4.1 IF either unit is in OPCON 1, 2, 3, 4 uO 5 T-HEN the applicable Daily Log

(- 6-i07-590-* or ST-6-I07-591-*) is being performed to reflect irradiated fuel handling.

Initials Date 4.4.2 The Control Room normal fresh air radiation monitors are operable:

ST-2-026-421-0 ST-2-026-422-0 ST-2-026-423-0 ST-2-026-424-0 ST-2-026-607-0 ST-2-026-608-0 S(V/ /_

Initials Date

FH-106, Rev. 24 Page 11 of 21 JAD/jad NOTE Refuel Floor Ventilation Exhaust Rad Monitor surveillance for both units may be necessary. Check both units operability as required by current OR expected plant HVAC conditions and lineups.

4.4.3 The Refuel Floor high radiation isolation monitors are operable:

ST-2-026-430-* ST-2-026-622-*

ST-2-026-431-* ST-2-026-623-*

ST-2-026-432-* ST-2-026-624-*

ST-2-026-433-* ST-2-026-625-*

-,VL /

Initials Date 4.4.4 The outside atmosphere to refueling area low Delta P isolation instrumentation is operable:

RT-2-076-402-0 RT-2-076-403-0 //_14 Initials Date 4.4.5 The Refuel floor isolation logic and standby gas treatment system initiation.

logic is operable:

ST-2-072-106-0 ST-2-072-I06-*

ST-2-072-107-0 ST-2-072-107-*

Initials Date 4.4.6 The Refuel floor isolation valves are operable:

ST-6-076-200-*.

Initials Date 4.4.7 Refuel floor secondary containment integrity is demonstrated:

ST-6-076-310-0 ST-6-076-360-0 Initials Date

FH-106, Rev. 24 Page 12 of 21 JAD/j ad 4.4.8 The Standby Gas Treatment System Filter trains are operable:

ST-4-076-321-0 ST-4-076-801-0 ST-4-076-322-0 ST-4-076-802-0 ST-6-076-250-* ST-6-076-380-0

('V A /

Initials Date 4.4.9 Verify SGD-076-206-3 is locked open. ,1v /__

Initials Date NOTE The Reactor Enclosure Slide Gate damper may be reopened to facilitate testing with Reactor Enclosure Secondary Containment not being established. The Flow Balance Damper in the duct from Reactor Enclosure Secondary Containment to Standby Gas Treatment System (SGTS) is balanced AND tested to ensure adequate Fan capacity to the other zones.

4.4.10 IF Reactor Enclosure secondary containment is not established, THEN verify SGD-076-206-1 for Unit 1 only, SGD-076-506-2 for Unit 2 only, is locked closed.

Otherwise mark N/A. Int/A /a Initials Date 4.4.11 Verify the following systems meet the requirements of their Technical Specification, as required for the planned evolution.

ESW TS 3.7.1.2 Ultimate Heat Sink TS 3.7.1.3 CREFAS TS 3.7.2 AC Sources TS 3.8.1.2 DC Sources TS 3.8.2.2 Electrical Distribution TS 3.8.3.2 Initials Date

FH-106, Rev. 24 Page 13 of 21 JAD/jad 4.5 The Control Room Shift Supervisor shall review this procedure's prerequisites AND determine if all equipment required by Tech Specs to be operable for the planned evolution is operable by reviewing the following:

TPA log Clearances Regulatory Actions log Outstanding A/R's __/____

Initials Date 4.6 The Surveillance Test Coordinator is aware of this activity AND appropriate Surveillance Tests are being performed. Intil D zA InitialsD /

4.7 IF Pool to Pool moves are anticipated THEN ensure personnel barrier AND safety postings are in place along north and south refuel platform rails on the peninsulas between the fuel pools to limit personnel entry into the area inside the bridge rails, Otherwise, N/A this step. IA /_

Initials Date 4.8 Ensure signed off original up to this step of the procedure is returned to the Reactor Engineer AND a signed off copy is issued to the Fuel 1&[ b/.

Handling Director. /

Initials Date 5.0 SPECIAL EQUIPMENT NONE.

6.0 FUEL/SNM ACCOUNTABILITY 6.1 CCTAS - NO CORE TRANSFER Upon completion of a step in the CCTAS, the verifying person must fill in the date AND time of transfer and initial the indicated space.

6.2 FUEL LOCATION HISTORY SHEETS Each fuel assembly has an associated Fuel Location History Sheet, This sheet must be updated within three months of the completion of any activity in which the assembly changes residence locations OR is physically altered.

FH-106, Rev. 24 Page 14 of 21 JAD/j ad 6.3 FUEL INVENTORY

SUMMARY

SHEET At the end of the core component and irradiated item movement operation OR at any point the Reactor Engineer determines necessary, t-his sheet shall be updated by entering a new row of information concerning the location of all fuel. (if changes are required) 6.4 FUEL POOL INVENTORY LOG This log is updated within three months of the end of the core component and irradiated item movement operations per RE-C-44.

NON-FUEL SPECIAL NUCLEAR MATERIAL (SNM) 6.5 FISSION CHAMBER INVENTORY

SUMMARY

SHEET At the end of operations involving fission chamber movement OR at any point the Reactor Engineer determines necessary, this sheet shall be updated by entering a new row of information concerning the location of all fission chambers.

6.6 FISSION CHAMBER TRANSFER AUTHORIZATION SHEET (FCTAS)

Upon completion of a step in the FCTAS, the verifying person must fill in the date of transfer AND initial the indicated space.

6.7 FISSION CHAMBER LOCATION HISTORY SHEETS Each fission chamber has an associated Fission Chamber Location History Sheet. This sheet shall be updated whenever the fission chamber changes residence locations.

7.0 PRECAUTIONS 7.1 Fuel shall only be moved to locations specified in the CCTAS.

7.2 Observe precautions AND instructions in $97.0.M when moving fuel.

7.3 Observe precautions AND instructions specified in the RWP.

FH-106, Rev. 24 Page 15 of 21 JAD/jad 7.4 IF any of the following symptoms occur, THEN perform actions required by ON-120:

- Fuel Floor Area radiation monitor alarms

- Fuel Bundle dropped or damaged Unanticipated reduction of Reactor Cavity OR Spent Fuel Pool Water Level 7.5 Ensure that no loads greater than 1200 lbs are carried over fuel in the spent fuel pool.

7.6 New fuel shall not be stored in the new fuel storage vault (Ref. 2.17).

7.7 When using auxiliary hoists to handle irradiated components, ensure jam blocks are set to provide required water coverage per the implementing procedure.

8.0 LIMITATIONS AND ACTIONS 8.1 Difficulties in handling fuel shall be treated as described in S97.0.M (Ref. 2.4). Manual operation of refuel platform hoist, when necessary to maintain refuel platform in a safe condition, shall be performed in accordance with Operating Procedure S97.0.L (Ref. 2.18).

8.2 IF any core component or irradiated item is dropped OR damaged during a transfer operation, THEN work under this procedure AND associated Fuel Handling procedures shall be suspended until the exact nature and cause of the incident is determined. Permission to continue fuel handling operations shall be obtained from the Operations Senior Manager.

8.3 IF REFUELING FLOOR SECONDARY CONTAINMENT INTEGRITY is not maintained, THEN suspend handling of irradiated fuel in accordance with Reference 2.14 AND suspend movement of items over irradiated fuel UNLESS items are analyzed per References 2.13 and 2.21.

(See Tables 1 and 2) 8.4 Table 2 provides requirements and limitations for handling light loads over irradiated fuel without secondary containment or other systems/equipment required to mitigate the fuel handling design basis accident (i.e., prerequisites 4.3 and 4.4). These requirements and limitations are based on an engineering analysis documented in References 2.21 and 2.22.

FH-106, Rev. 24 Page 16 of 21 JAD/j ad 8.5 "The Emergency Plan" should be implemented (Ref. ERP-101) if the following conditions exist:

8.5.1 Unexpected Increase in Plant Radiation or Airborne Concentration. (UNUSUAL EVENT) 8.5.2 Major Damage to Irradiated Fuel, or Loss of Water Level that Has or Will Result in the Uncovering of Irradiated Fuel Outside the Reactor Vessel. (ALERT) 8.6 IF it becomes necessary to deviate from the CCTAS, THEN Fuel Handling Director shall halt core component moves prior to performing the step requiring deviation AND initiate a revision to the CCTAS as per RE-C-40. (Ref. 2.7) 8.7 Regarding use of the Fuel Preparation Machine(s):

a) IF work is temporarily suspended, e.g. stop for a lunch break, with a fuel bundle containing irradiated components in a fuel prep machine, THEN prep machine shall be lowered to its lower stop AND the air supply shall be disconnected.

b) Fuel Preparation Machines are NOT for storage of irradiated fuel assemblies. Therefore, prior to C completing work activities for the day, OR whenever an extended delay in work is anticipated, fuel bundle(s) containing irradiated fuel rods shall be placed back into the fuel storage racks (Ref. 2.15).

8.8 Revisions to this procedure shall require the review of Reactor Engineering.

8.9 IF failure of a Double Verification is discovered, THEN Core Component movement shall be terminated AND Shift Management, NMD Management, and Reactor Engineering shall be notified immediately. (Ref. 2.7 )

8.9.1 A CR shall be initiated per LS-AA-125 for failure of a DV. Challenges of the DV process (e.g., one of the verifiers accepts a discrepant condition which is caught by the other verifier) should be monitored. CR initiation should be considered for cases of multiple DV challenges.

FH-106, Rev. 24 Page 17 of 21 JAD/jad 9.0 PROCEDURE NOTE The procedure section describes the methods by which other procedures are used to accomplish the "physical work" of core component and irradiated item movement. This section also describes how work may change from being under the purview of FH-106 to that of FH-105 and back again. Finally, tasks that are to be done after completion of core component and irradiated item movement operations are delineated.

9.1 PRIOR TO CORE COMPONENT AND IRRADIATED ITEM MOVEMENT 9.1.1 The Reactor Engineer or Fuel Handling Director may require that the prerequisites for this procedure be re-established prior to movement operations.

a. The Reactor Engineer will inform the Fuel Handling Director of this requirement if needed.

9.1.2 Maintenance Supervisor OR Fuel Handling Director shall notify the Fuel Floor Health Physics Supervisor, Radiological Engineer OR Designee prior to starting evolutions involving moving/storing irradiated components in the Spent Fuel Pool, Cask Pit OR Transfer Canal.

NOTE WHEN performing the following evaluation, THEN the potential radiological effects in Reactor Enclosure elevation 313' shall be considered, IF the irradiated component is dropped.

9.1.3 The Fuel Floor Radiological Engineer OR Health Physics Supervisor shall d-etermine the radiological effects of moving/storing irradiated components in the Spent Fuel Pool, Cask Pit OR Transfer Canal AND recommend ALARA controls as necessary.

FH-106, Rev. 24 Page 18 of 21 JAD/jad 9.1.4 If it is desired to expand the scope of work to be performed under this procedure after all prerequisite signoffs are complete (e.g., addition of fuel inspections in the fuel prep machines), then the following may be performed with concurrence from the Control Room Shift Supervisor:

a. Verify that the prerequisites applicable to the new scope are satisfied.

b. For prerequisites previously marked N/A that are now applicable to the new scope - line out, initial and date "N/As" signifying prerequisite is satisfied.

c. Have the Control Room Shift Supervisor re-perform prerequisite 4.5 for the expanded scope, and document the review by re initialing prerequisite 4.5.

9.2 CORE COMPONENT AND IRRADIATED ITEM MOVEMENT 9.2.1 The handling of fuel or other core components C shall be governed by this procedure, $97.0.M, other applicable maintenance procedures (as required)

AND the CCTAS. (Ref. 2.3) 9.2.2 At the end of a shift that core component or irradiated item movement will not carry over into the next shift, the following should be done:

a. Place all refuel platform hoist and grapple loads in a safe storage location.

b. De-energize the Refueling Platform control circuitry by pressing the STOP button on the left hand controller.

c. Turn off the air compressor by taking the COMPRESSOR switch to the OFF position on the north bridge end structure.

d. Ensure cabinet heaters remain on by leaving MAIN and MONO switches in the ON position on the north bridge end structure.

FH-106, Rev. 24 Page 19 of 21 SJAD/jad 9.3 CHANGING GOVERNING PROCEDURES 9.3.1 The Reactor Engineer may decide (or circumstances may dictate) that core components and irradiated items shall be moved under FH-105.

a. When changing from FH-106 to FH-105 a new CCTAS may be required. The Reactor Engineer shall determine if a new CCTAS issue is required or if the current CCTAS may be revised.

b. When entering this procedure from FH-105, the Reactor Engineer should issue an explanation establishing the necessary criteria of this procedure prior to core component or irradiated item moves using this procedure.

9.4 COMPLETION OF CORE COMPONENT AND IRRADIATED ITEM MOVEMENT 9.4.1 Upon completion of activities governed by this procedure, the Reactor Engineer shall assemble all documentation concerned AND ensure all forms, data sheets and check-out sheets have been completed. Intil/Dt Initials Date 9.4.2 The SNM Coordinator or approved alternate shall initiate the update of all SNM accounting documents affected by the completion of this procedure.

Initials Date 9.4.3 The Reactor Engineer or Fuel Handling Director has informed the Surveillance Test Coordinator of the completion of this activity.

Initials Date

(le FH-1 Rev . 24 Pag'g 20 of 21 JAD/j ad TABLE 1 Required Decay Times For Transport Of Certain Items In The Spent Fuel Pool Over Irradiated Fuel Without Secondary Containment (Refs. 2.13 and 2.16)

DESIGN LIMITS DECAY TIME (2) REQUIRED TO ASSUMED ASSUMED ASSUMED LIFTING TRANSPORT ITEM WITHOUT ITEM TO BE MOVED WEIGHT (1) LENGTH (1) DEVICE (1) SECONDARY CONTAINMENT UNIT 1 UNIT 2 LPRM (12'Section) 14 lbs 12' Inst. Handling Tool 32 days __

Fuel Support Piece 62 lbs 0.85' Fuel Support Piece 41 days **

Grapple Double Blade Guide 180 lbs 14.91' Main Grapple 46 days -k Single Blade Guide 90 lbs 14.91' Main Grapple 42 days **

Control Rod Blade 200 lbs 11.92' CRB Grapple 32 days **

New Fuel Assembly 700 lbs 14.68' Main Grapple 46 days 54 days OR Dummy Bundles _

• • = items not analyzed for current racks, secondary containment required (1) IF actual weight is greater O-R length is less than assumed values O--R lifting device is different than assumed T-HEN secondary containment is required unless decay time is verified using Ref. 2.13.

(2) Decay time is time since shutdown of unit just prior to most recent discharge of fuel which is stored in appropriate fuel pool. Previous transfer of fuel between fuel pools must be considered in making this determination.

FH-lI Rev. 24 Pag- 21 of 21 JAD/jad TABLE 2 ALLOWABLE LIGHT LOADS OVER IRRADIATED FUEL WITHOUT SECONDARY CONTAINMENT This table provides a listing of light loads allowed to be handled over irradiated fuel without secondary containment or other systems/equipment required to mitigate the fuel handling design basis accident. These requirements and limitations are based on an engineering analysis documented in References 2.21 and 2.22.

Object Limitations

• Any object 5 lbs. or less None Any object 10 lbs. or less Object has drag and buoyancy properties less severe than either a 10 lb 1 inch dia. steel rod OR a 10 lb solid steel cube TriNuc cartridge filter 10 lbs. or less (approx. 6" O.D. x 30" long)

Teletector survey instrument 10 lbs. or less Black & White Camera/Light Assembly 10 lbs. or less (approx. 1.25" dia. with 3" x 4.5" light assembly)

Color Camera/Light Assembly 15 lbs. or less (approx. 5" x 5" x 10")

Guide Tube Vacuum Head 15 lbs. or less (approx. 10" dia.)

Color Camera/Light Assembly attached to 15 lbs. or less (approx. 5"1 x 5" x 10")

lightweight handling poles (LWHP) LWHPs - any length, but no more than 10' above pole handler Guide Tube Vacuum Head attached to LWHP 15 lbs. or less (approx. 10" dia.)

LWHPs - any length, but no more than 10' above pole handler LWHPs w/ no attachments Maximum length = 20' OR Maximum length = 70' if bottom of assembly is withirf 4' of fuel

• For all objects, reactor cavity/spent fuel pool water level must be at least 350' 4" (2' below curb)

1. Poles must be assembled in an area clear of fuel (e.g., over cask pit)

S97.0.M, Rev. 12 Page 1 of 26 JAD/jad Exelon Nuclear C LIMERICK GENERATING STATION S97.O.M REFUELING PLATFORM OPERATION.

1.0 PURPOSE 1.1 To provide instruction necessary to operate the Refuel platform main hoist for core component movements within the Fuel Pool, Cask Pits. and leactor Core. This procedure shall be used in conjunction with Fuel I-Jsndli.g Procedure FH-105 "Core Component Movement - Core Transfers", or FH-106 "Gore Component and Irradiated Item Movement - No Core Transfer" as apriopriate.

2.0 PREREQUISITES 2.1 IF performing component transfers in the Reactor, THEN all prerequisites included in Proc.e r..FH-105,

.. "Core Component Movement

- Core Transfers" have been completed...... . a p'propriate.

I 2.2 IF performing component transfers :if.pnth.e ýFuel Pool/Cask Pit only, THEN all prerequisites included in Proced,6'ure FH-106, "Core Component and Irradiated Item Movement - NoCi Tr...ansfer", have been completed as appropriate.

2.3 Applicable sections of the .*ig

.4A "Electrical, Mechanical, and Pneumatic Alignment/Checkout of Refue'i'g Platform Bridge, Trolley and Main Hoist for Operation" should be perfor-ed as necessary. Verification of the mast's ability to fully extend without b*nding should be performed over the reactor cavity soon after core is accessibl Wi--t-,h the mast.

2.4 IF performing tran.fer of the dummy bundle over the Reactor Cavity, THEN secondar-y Ooinment is required during movement over irradiated fuel per Ref. 5.13.

2.5 IF performkg..iV!!1ransfer of the dummy bundle in the spent fuel pool only, THEN secnidary containment is operable as required below:

IF greater than 46 days have elapsed since shutdown of unit just prior to the most recent discharge of fuel which is stored in the appropriate pool, THEN secondary containment is not required per Refs. 5.13 and 5.14.

Previous transfer of fuel between fuel pools must be considered in making this determination, OTHERWISE, secondary containment is required during movement of the dummy bundle over irradiated fuel per Ref. 5.13.

$97.0.M, Rev. 12 Page 2 of 26 J AD/jad

_ 2.6 IF there is potential for contact with the Auxiliary Platform during performance of any section of this procedure THEN a dedicated Spotter shall be posted on the Refueling Platform to monitor platform separation AND alert the Fuel Handling crew to stop operations IF interference is imminent. (Ref. 5.18) 3.0 PRECAUTIONS 3.1 IF equipment performance is not as expected, THEN the equipment shall be placed in a safe condition AND Shift Management or Fuel Handling Director shall be notified immediately.

3.2 IF a core component is partially inserted into a location, THEN Refuel Platform bridge OR Trolley shall only be moved at JOG speed.

3.3 Fuel bundles shall be seated using a consistent slow hoist speed while gently shaking the mast. Extreme slow speed and the absence of vibration increases the potential for improper bundle seating.

3.4 Double blade guide spacer buttons occasionally tend to hang-up on the'top edge of the Unit 2 Spent Fuel Pool racks. Refuel Platform Operator may need to gently shake mast to eliminate interference and fully seat blade guide in rack.

3.5 Bridge and trolley shall be operated at JOG speed when handling double guides with the mast below the reactor vessel flange (per SIL 594).

3.6 Blade guides may be removed from the reactor core provided the associated control rod blade will be diagonally supported by fuel or other blade guide(s).

3.7 To prevent impact or mast/fuel assembly damage:

3.7.1 Trolley and Bridge shall always be accelerated slowly, avoiding sudden starts and stops.

3.7.2 Travel paths shall be clear before moving core components.

3.7.3 NORMAL UP light must be lit before moving through transfer canal.

3.7.4 Double blade guides must be raised beyond NORMAL UP using Hoist Override to -4.0 inches as indicated by hoist encoder before moving through transfer canal.

3.7.5 Main Hoist Grapple must be in full up position when not in use.

S97.0.M, Rev. 12 Page 3 of 26 JAD/jad 3.7.6 Push or pull mast assembly as required when fuel bundle is approaching fully seated position in core, sipping canister, or spent fuel pool rack to protect channel fastener. Observe channel fastener, if possible, as it enters core, rack or sipping canister to ensure channel fastener does not catch.

3.7.7 Operate main hoist slowly when grapple/component approaches fully seated position.

3.8 Mast camera may impact surrounding structures when manipulating core components in the Reactor Core periphery, Fuel Pool periphery or Fuel Preparation Machine. Exercise caution to avoid impact damage.

3.9 LPRM bender stand shall be removed before moving platform to equipment pool.

When installed the LPRM bender stand will prevent refuel platform travel over equipment pool.

NOTE Attachment 1 provides a list of Refuel Platform interlocks, including initiating conditions and effects on the system.

3.10 IF during hoist operation:

3.10.1 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 contacted for instruction.

3.10.2 HOIST LOADED Light goes out prematurely, OR load starts to lean,

1. Hoist Lowering shall be stopped immediately.

2. Grapple switch shall be verified to be in ENGAGED position

3. Grapple engagement shall be verified.

4. GRAPPLE ENGAGED light shall be verified lit.

5. Hoist shall be raised slowly to regain the weight of the load.

6. Fuel Handling Director shall be notified.

S97.0.M, Rev. 12 Page 4 of 26 JAD/jad r 3.10.3 GRAPPLE ENGAGED Light goes out unexpectedly during operation, THEN movement shall be stopped immediately, AND FHD notified.

3.10.4 HOIST LOADED Light comes on unexpectedly while raising grapple:

1. Hoist movement shall be stopped.

2. Hoist shall be slowly lowered until HOIST LOADED light goes out.

3. Fuel Handling Director shall be notified.

3.10.5 ROD BLOCK #1 and ROD BLOCK #2 light on interlock status display does not light when platform is over the core AND main hoist is fuel loaded, THEN refuel platform operation shall be stopped, AND FHD notified.

3.11 GRAPPLE LOCKOUT BYPASS and BOUNDARY ZONE COMPUTER BYPASS push button operations may be needed for handling components in the periphery of the Spent Fuel Pool , in a Bundle Sipping Canister, or in a Cask.

1 3.12 Fuel inspection and test equipment when installed in the fuel pools presents an entanglement hazard for the main mast or grappled fuel bundle.

3.13 IF secondary containment becomes inoperable during transfer of the dummy bundle, THEN STOP movement of the dummy bundle over irradiated fuel UNLESS it was determined that secondary containment is not required (Ref. 5.13).

3.14 Prior to component handling concurrent with use of unique equipment in the reactor cavity or fuel pool, a determination should be made regarding the level of monitoring necessary to prevent contact between the equipment and the refuel platform mast, mast camera or core components suspended from the grapple.

Examples of unique equipment include in-vessel inspection or repair equipment, particularly those with umbilical cables. Depending on the risk of interference, consideration shall be given to positioning an individual on the refuel platform assigned the responsibility to monitor the position of the equipment (and umbilical if applicable) and alert Fuel Handling crew to STOP if interference is imminent.

3.15 De-energizing the refuel platform while over the reactor cavity (track switches actuated) will generate a Rod Withdrawal Block in the Main Control Room. Notify r ,

Reactor Operator prior to de-energizing the refuel platform with the track switches actuated.

$97.0.M, Rev. 12 Page 5 of 26 JAD/jad e 3.16 Peripheral fuel assemblies have the potential to miss their fuel support and seat low. Use extreme caution to maintain proper alignment while inserting assembly into the core. (Ref. 5.15).

3.17 Extra caution should be used when handling very old fuel bundles. Monitoring of bundle weight shall be performed during lifting to ensure gross failure of bundle is identified (Ref. 5.16). Also, bent channel fasteners and bent bail handles have been found on old bundles.

3.18 A gentle rotation of the mast in both directions should be used to ensure the fuel grapple is firmly engaged to the bail handle. Rapid or rough rotation during this check has led to fuel failure. (Ref. 5.16) 3.19 Use extreme caution and a slow hoist speed when handling unchanneled fuel bundles. Unchanneled fuel bundles are more susceptible to damage by twisting/rotation of mast. Finger springs on the lower tie plate and fuel rod spacers may catch during fuel bundle removal OR insertion into a spent fuel pool rack OR fuel preparation machine.

3.20 Three dimensional moves of Refueling Platform (e.g. using Bridge, Trolley and Hoist at same time)

AND simultaneous operation of Service Pole Caddy Hoist is not permitted. (Ref. 5.17) 3.21 IF potential for contact exists, THEN slow speed shall be utilized when approaching the Auxiliary Platform. (Ref. 5.18) 3.22 IF Refueling Platform AND Auxiliary Platform need to be brought together THEN PERFORM the following: (Ref. 5.18) 3.22.1 ENSURE Auxiliary Platform is positioned where required.

3.22.2 DEENERGIZE Refueling Platform per NMD Maintenance Supervisor OR FHD direction.

3.22.3 MOVE Refueling Platform up to Auxiliary Platform using hand-crank.

3.23 IF a Control System malfunction occurs, THEN Refueling Platform can be stopped by pressing the STOP push-button on the Left Hand Controller OR by opening the MAIN DISCONNECT switch on the north end truck.

3.24 IF fuel moves must be suspended with an irradiated bundle hanging on the mast, THEN ENSURE bundle is not positioned near invessel remote operated cameras.

This will prevent radiation damage to the cameras.

$97.0.M, Rev. 12 Page. 6 of 26 JAD/jad 4.0 PROCEDURE NOTE

1. The performance steps section of this procedure is separated into the following subsections:

4.1, Pickup Location - Fuel Pool Storage Rack or Cask Pit 4.2, Pickup Location - Reactor Core 4.3, Pickup Location - Fuel Preparation Machine 4.4, Pickup Location - Bundle Sipping Canister 4.5, Release Location - Fuel Pool Storage Rack or Cask Pit 4.6, Release Location - Reactor Core 4.7, Release Location - Fuel Preparation Machine 4.8, Release Location - Bundle Sipping Canister 4.9, Determination of Hoist Position for Bundle Seated in Sipping Canister 4.10. In-Process Adjustment of Bridge/Trolley Encoders.

2. Target Hoist Positions are listed in Attachment 2 which should be posted on the Refuel Platform mast.

3. Sequential steps which perform horizontal positioning of grapple/component (Bridge/Trolley) and vertical positioning of grapple/component (Hoist) may be performed in parallel as conditions permit.

4.1 Pickup Location - Fuel Pool Storage Rack or Cask Pit NOTE A CCTAS is not required for pickup of the dummy bundle.

4.1.1 POSITION Refuel Platform Mast over desired core component in accordance with Core Component Transfer Authorization Sheet (CCTAS).

4.1.2 LOWER grapple until grapple is 6 to 12 inches above bail.

4.1.3 ENSURE grapple is open.

4.1.4 ROTATE grapple as necessary to achieve grapple to bail alignment.

4.1.5 Slowly LOWER grapple until SLACK CABLE Light is lit.

S97.0.M, Rev. 12 Page 7 of 26 JAD/jad NOTE Steps 4.1.6 through 4.1.10 shall be double verified by the Fuel Handling Director (FHD) AND Refuel Platform Operator (RPO)

OR Spotter.

4.1.6 VERIFY proper core component location AND orientation.

4.1.7 VERIFY the following, THEN NOTIFY FHD of grapple position.

Grapple is centered over bail handle.

• Hoist Position indication agrees with value listed in Attachment 2 for item seated in Fuel Pool Storage Rack.

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

4.1.8 WHEN directed by FHD, THEN ENGAGE grapple, AND VERIFY GRAPPLE ENGAGED Light is lit.

4.1.9 WHEN directed by FHD, THEN slowly RAISE load while ensuring HOIST LOADED Light is lit (fuel/dummy bundle only),

OR for skeleton fuel bundle VERIFY component movement.

4.1.10 CONTINUE raising until grapple is fully raised, THEN VERIFY NORMAL UP Light is lit.

4.1.11 IF a double blade guide is being transferred through the cattle chute, THEN RAISE the grapple beyond NORMAL UP using the Hoist Override to -4.0 inches as indicated by Hoist Encoder.

4.1.12 GO TO appropriate "Release Location" section of this procedure as directed by FHD.

S97.0.M, Rev. 12 Page 8 of 26 JAD/jad 4.2 Pickup Location - Reactor Core 4.2.1 POSITION Refuel Platform Mast over desired core component in accordance with Core Component Transfer Authorization Sheet (CCTAS).

4.2.2 LOWER grapple until grapple is 6 to 12 inches above bail.

4.2.3 ENSURE grapple is open.

4.2.4 ROTATE grapple as necessary to achieve grapple to bail alignment.

4.2.5 Slowly LOWER grapple until SLACK CABLE Light is lit.

NOTE Steps 4.2.6 through 4.2.10 shall be double-verified by the Fuel Handling Director (FHD)

AND Refuel Platform Operator (RPO)

OR Spotter.

4.2.6 VERIFY proper core component location AND orientation.

4.2.7 VERIFY the following, THEN NOTIFY FHD of grapple position.

Grapple is centered over bail handle.

Hoist Position indication agrees with value listed in Attachment 2 for item seated in core.

4.2.8 WHEN directed by FHD, THEN ENGAGE grapple, AND VERIFY GRAPPLE ENGAGED Light is lit.

S97.0.M, Rev. 12 Page 9 of 26 JAD/jad NOTE IF load is a Fuel Bundle, THEN FHD notifies Unit Reactor Operator of pending fuel removal from the core.

4.2.9 WHEN directed by FHD, THEN RAISE load AND VERIFY HOIST LOADED Light is lit (fuel/dummy bundle only).

4.2.10 CONTINUE raising until core component is clear of core.

1. VERIFY HOIST Position indicates less than 355.0 inches.

2. VERIFY item is clear of top guide.

NOTE IF load is a Fuel Bundle, THEN FHD notifies Unit Reactor Operator that fuel bundle has cleared core.

4.2.11 IF load is to be transferred through transfer canal, THEN CONTINUE raising until grapple is fully raised THEN VERIFY NORMAL UP Light is lit.

1. IF load is a double blade guide, THEN RAISE the grapple beyond NORMAL UP using Hoist Override to -4.0 inches as indicated on Hoist Encoder.

4.2.12 GO TO appropriate "Release Location" section of this procedure as directed by FHD.

$97.0.M, Rev. 12 Page lOof 26 JAD/jad 4.3 Pickup Location - Fuel Preparation Machine 4.3.1 VERIFY Fuel Prep Machine carriage is fully LOWERED.

NOTE A CCTAS is not required for pickup of the dummy bundle.

4.3.2 Carefully POSITION Refuel Platform Mast over fuel prep machine in accordance with Core Component Transfer Authorization Sheet (CCTAS).

4.3.3 LOWER grapple until grapple is 6 to 12 inches above bail.

4.3.4 DEPRESS GRAPPLE LOCKOUT BYPASS push button.

4.3.5 ENSURE grapple is open.

4.3.6 ROTATE grapple as necessary to achieve grapple to bail alignment.

4.3.7 Slowly LOWER grapple until SLACK CABLE Light is lit.

NOTE Steps 4.3.8 through 4.3.13 shall be double verified by the Fuel Handling Director (FHD) and Refuel Platform Operator (RPO) or Spotter.

4.3.8 VERIFY proper core component location AND orientation.

S97.0.M, Rev. 12 Page 11 of 26 JAD/jad 4.3.9 VERIFY the following, THEN NOTIFY FHD of grapple position.

Grapple is centered over bail handle Hoist Position indication agrees with value listed in Attachment 2 for item seated in fuel prep machine.

4.3.10 WHEN directed by FHD, THEN ENGAGE grapple, AND RELEASE GRAPPLE LOCKOUT BYPASS push button.

4.3.11 VERIFY GRAPPLE ENGAGED Light is lit.

4.3.12 WHEN directed by FHD, THEN slowly RAISE load AND VERIFY HOIST LOADED Light is lit (fuel/dummy bundle only),

OR for skeleton fuel bundle visually VERIFY component movement.

4.3.13 CONTINUE raising until grapple is fully raised, THEN VERIFY NORMAL UP Light is lit.

4.3.14 GO TO appropriate "Release Location" section of this procedure as directed by FHD.

S97.0.M, Rev. 12 Page 12 of 26 JAD/jad

-.. 4.4 Pickup Location - Bundle SioDina Canister 4.4.1 VERIFY Bundle Sipping Canister lid is open.

NOTE A CCTAS is not required for pickup of the dummy bundle.

4.4.2 POSITION Refuel Platform Mast over desired Bundle Sipping Canister in accordance with Core Component Transfer Authorization Sheet (CCTAS).

4.4.3 LOWER grapple until grapple is 6 to 12 inches above bail.

4.4.4 ENSURE grapple is open.

4.4.5 ROTATE grapple as necessary to achieve grapple to bail alignment.

4.4.6 Slowly LOWER grapple until SLACK CABLE Light is lit.

NOTE

1. Steps 4.4.7 through 4.4.11 shall be double verified by the Fuel Handling Director and Refuel Platform Operator or Spotter.

2. Expected hoist position indication is determined and posted on Attachment 2 using the dummy bundle in subsection 4.9.

4.4.7 VERIFY proper core component location AND orientation.

4.4.8 VERIFY the following, THEN NOTIFY FHD of grapple position.

0 Grapple is centered over bail handle S Hoist Position indication agrees with value posted on Attachment 2 for item seated in Bundle Sipping Canister.

S97.0.M, Rev. 12 Page 13of 26 JAD/jad 4.4.9 WHEN directed by FHD, THEN ENGAGE grapple AND VERIFY GRAPPLE ENGAGED Light is lit.

4.4.10 WHEN directed by FHD, THEN slowly RAISE load while ensuring HOIST LOADED Light is lit (fuel/dummy bundle only).

4.4.11 CONTINUE raising until grapple is fully raised, THEN VERIFY NORMAL UP Light is lit.

4.4.12 GO TO appropriate "Release Location" section of this procedure as directed by FHD.

C 4.5 Release Location - Fuel Pool Storage Rack or Cask Pit NOTE A CCTAS is not required for pickup of the dummy bundle.

4.5.1 POSITION core component over desired location in accordance with Core Component Transfer Authorization Sheet (CCTAS).

4.5.2 ROTATE core component as necessary to achieve proper orientation.

4.5.3 PERFORM Double Verification to ensure proper core component location AND orientation.

4.5.4 WHEN directed by FHD, THEN LOWER hoist until core component is seated AND SLACK CABLE Light is lit.

S97.0.M, Rev. 12 Page 14of 26 JAD/jad NOTE Steps 4.5.5 through 4.5.8 shall be double verified by the Fuel Handling Director (FHD)

AND Refuel Platform Operator (RPO)

OR Spotter.

4.5.5 VERIFY the following, THEN NOTIFY FHD of grapple position.

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

• Hoist Position indication agrees with value listed in Attachment 2 for item seated in Fuel Storage Rack, OR per M-053-006, subsection 5.4, for a bundle seated in a cask.

4.5.6 WHEN directed by FHD, THEN RELEASE grapple.

1. IF in cask, THEN DEPRESS Grapple Lockout Bypass push button.

4.5.7 VERIFY grapple is open.

4.5.8 Slowly RAISE grapple while verifying HOIST LOADED remains out, AND grapple remains free of bail handle.

4.5.9 RECORD completion of component transfer on CCTAS.

4.6 Release Location - Reactor Core 4.6.1 POSITION core component above desired location in accordance with Core Component Transfer Authorization Sheet (CCTAS).

4.6.2 LOWER load until hoist position indicates approximately 355 inches, THEN STOP lowering.

4.6.3 ROTATE core component as necessary to achieve proper orientation.

4.6.4 PERFORM Double Verification to ensure proper core component location AND orientation.

S97.0.M, Rev. 12 Page 15of 26 JAD/jad NOTE IF Load is a Fuel Bundle, THEN FHD notifies Unit Reactor Operator of pending fuel insertion in core.

4.6.5 WHEN directed by FHD, THEN LOWER load until SLACK CABLE Light is lit. FP-C NOTE Steps 4.6.6 through 4.6.8 shall be double verified by the Fuel Handling Director (FHD)

AND Refuel Platform Operator (RPO)

OR Spotter.

4.6.6 VERIFY the following, THEN NOTIFY FHD of grapple position.

Component elevation appears equivalent to other components in the Reactor Core.

Hoist Position indication agrees with value listed in Attachment 2 for item fully seated in Reactor Core.

4.6.7 WHEN directed by FHD, THEN RELEASE grapple, AND VERIFY grapple is open.

4.6.8 Slowly RAISE grapple while verifying HOIST LOADED light remains out.

4.6.9 RECORD completion of component transfer on CCTAS.

S97.0.M, Rev. 12 Page 1.6 of 26 JAD/jad NOTE IF Load is a Fuel Bundle, THEN FHD notifies Unit Reactor Operator of completion of fuel insertion in core.

4.7 Release Location - Fuel Preparation Machine 4.7.1 ENSURE Fuel Prep Machine carriage is fully lowered.

NOTE A CCTAS is not required for pickup of the dummy bundle.

4.7.2 Carefully POSITION component over desired fuel prep machine in accordance with Core Component Transfer Authorization Sheet (CCTAS).

4.7.3 ROTATE component as necessary to achieve proper alignment 4.7.4 PERFORM Double Verification to ensure proper core component location AND orientation.

4.7.5 WHEN directed by FHD, THEN LOWER load until SLACK CABLE Light is lit.

S97.0.M, Rev. 12 Page 17 of 26 JAD/jad NOTE Steps 4.7.6 through 4.7.9 shall be double verified by the Fuel Handling Director (FHD)

AND Refuel Platform Operator (RPO)

OR Spotter.

4.7.6 VERIFY Hoist Position indication agrees with value listed in Attachment 2 for item fully seated in fuel prep machine, THEN NOTIFY FHD of grapple position.

4.7.7 WHEN directed by FHD, THEN RELEASE grapple, AND DEPRESS GRAPPLE LOCKOUT BYPASS push button.

4.7.8 VERIFY grapple is open.

4.7.9 Slowly RAISE grapple while verifying HOIST LOADED light remains out, AND VERIFY grapple remains free of bail handle.

4.7.10 RELEASE GRAPPLE LOCKOUT BYPASS push button.

4.7.11 RECORD completion of component transfer on CCTAS.

4 .8 Release Location - Bundle Sipping Canister 4.8.1 VERIFY Bundle Sipping Canister lid is open.

4.8.2 POSITION fuel bundle over desired Bundle Sipping Canister in accordance with Core Component Transfer Authorization Sheet (CCTAS).

4.8.3 ROTATE fuel bundle as necessary to achieve proper insertion alignment.

S97.0.M, Rev. 12 Page 18 of 26 JAD/jad 4.8.4 PERFORM Double Verification to ensure proper core component location AND orientation.

4.8.5 WHEN directed by FHD, THEN LOWER load until SLACK CABLE light is lit. Pc NOTE

1. Steps 4.8.6 through 4.8.8 shall be double verified by the Fuel Handling Director (FHD) and Refuel Platform Operator (RPO) or Spotter.

2. Expected hoist position indication is determined and posted on Attachment 2 using thedummy bundle in subsection 4.9.

4.8.6 VERIFY the following, THEN NOTIFY FHD of grapple position.

• Fuel Bundle is fully seated in the Bundle Sipping Canister.

• Hoist Position indication agrees with value posted on Attachment 2 for item seated in Bundle Sipping Canister.

4.8.7 WHEN directed by FHD, THEN RELEASE grapple, AND VERIFY grapple is open.

4.8.8 Slowly RAISE grapple while verifying HOIST LOADED light remains out.

4.8.9 RECORD completion of component transfer on CCTAS.

4.9 Determination of Hoist Position for Bundle Seated in Sipping Canister NOTE A CCTAS is not required for pickup of the DUMMY bundle.

4.9.1 PICKUP DUMMY Bundle in accordance with subsection 4.1.

4.9.2 VERIFY Bundle Sipping Canister lid is open.

S97.0.M, Rev. 12 Page 19 of 26 JAD/jad 4.9.3 POSITION DUMMY Bundle over Bundle Sipping Canister AND ROTATE DUMMY Bundle to achieve alignment.

4.9.4 WHEN directed by FHD, THEN slowly LOWER hoist until DUMMY Bundle is seated AND SLACK CABLE Light is lit.

4.9.5 VERIFY DUMMY Bundle is seated in Bundle Sipping Canister using underwater camera. I' NOTE The DIMENSION (Target Hoist Position) for a fuel bundle seated in a Bundle Sipping Canister (refer to Attachment 2) is calculated by subtracting 1.5 inches from, AND adding 0.5 inches to, the Hoist Position Indication obtained below.

4.9.6 RECORD Hoist Position Indication AND CALCULATE the DIMENSION for each Bundle Sipping Canister [

below:

CANISTER ID/ HOIST POSITION LOCATION INDICATION DIMENSION 1.

2.

4.9.7 WHEN directed by FHD, THEN slowly RAISE DUMMY Bundle while ensuring HOIST LOADED Ligh.-,

is lit. LEE 4.9.8 CONTINUE raising until grapple is fully raised, ED THEN VERIFY NORMAL UP Light is lit.

4.9.9 REPEAT steps 4.9.2 through 4.9.8 for each additional Bundle Sipping Canister.

4.9.10 WHEN directed by the FHD, THEN GO TO appropriate subsection of this procedure, AND RETURN the DUMMY Bundle to its "As Found" location.

$97.0.M, Rev. 12 Page 20 of 26 JAD/jad 4.9.11 RECORD ID/ Location, Hoist Position Indication, and DIMENSION for each Bundle Sipping Canister in the FHD logbook.

4.9.12 RECORD the ID/ Location and DIMENSION for each Bundle Sipping FP C Canister on the appropriate page of Attachment 2, AND POST a copy of Attachment 2 on the associated Refuel Platform mast.

4.10 "In-Process" Adjustment of Bridge/Trolley Encoders 4.10.1 POSITION Refuel platform Mast over desired core component location.

4.10.2 LOWER grapple until grapple is 6 to 12 inches above bail.

4.10.3 ENSURE grapple is open.

4.10.4 ROTATE grapple as necessary to achieve grapple to bail alignment.

4.10.5 Slowly LOWER grapple until SLACK CABLE Light is lit.

NOTE Steps 4.10.6 through 4.10.12 shall be double verified by the Fuel Handling Director (FHD)

AND Refuel Platform Operator (RPO)

OR Spotter.

4.10.6 VERIFY proper core component location AND orientation.

4.10.7 VERIFY the following, THEN NOTIFY FHD of grapple position.

"* Grapple is centered over bail handle.

"* Hoist position indication agrees with value listed in Attachment 2 for item seated in core.

S97.0.M, Rev. 12 Page 21 of 26 JAD/jad 4.10.8 RECORD "As Found" encoder readout position indication AND Model 1200 Power Supply thumbwheel switch settings for Bridge Position (X)

AND Trolley Position (Y) in the FHD logbook.

4.10.9 IF required, THEN ADJUST thumbwheel switches on Model 1200 Readout Power Supply for Bridge Position (X)

AND Trolley Position (Y) to obtain desired core location as determined by encoder readout position indication.

4.10.10 RECORD "As Left" encoder readout position indication AND Model 1200 Power Supply thumbwheel switch settings for Bridge Position (X)

AND Trolley Position (Y) in the FHD logbook.

4.10.11 ENSURE grapple is open.

4.10.12 WHEN directed by FHD, THEN slowly RAISE grapple while verifying Hoist Loaded light remains out AND grapple remains free of bail handle.

S97.0,.M, Rev. 12 Page 22 of 26 JAD/jad

5.0 REFERENCES

5.1 UFSAR Section 9.1.4.2.10.2 5.2 UFSAR Section 7.7.1.15.3 5.3 UFSAR Section 15.4.1 5.4 F21-EO03-KO06, Operation and Maintenance Instructions, Refueling Platform, Vol. I 5.5 F21-E003-KO06, Operation and Maintenance Instructions, Refueling Platform, Vol. II 5.6 PBAPS memo J. F. Franz to Plant Superintendents, 02/01/91 5.7 EIR #92-04-19 5.8 MOD 6248, Refuel Platform Mast Mounted Underwater Camera System 5.9 Nuclear Emergency Plan 5.10 NSAC/164L, Guidelines for BWR Reactivity Control During Refueling 5.11 A-C-300, Reactivity Management Program 5.12 GE SIL 594, Refuel Platform Triangular Mast Drag Loading 5.13 UFSAR Section 15.7.4 and 15.7.6 and PECO Calculation LM-033 "Methodology to Determine the Acceptability of Moving Loads over Irradiated Fuel Without Secondary Containment" 5.14 AR A1081310, E01, Evaluation of decay time required for new fuel bundle or dummy bundle movement in Unit 2 SFP without secondary containment 5.15 GE SIL No. 566 Supplement 1, Misaligned GE BWR fuel assemblies 5.16 INPO OE7535, Failed Fuel Bundle at Oyster Creek 5.17 MOD P00925, Service Pole Caddy on Refueling Bridge 5.18 MOD P00950, Fuel Floor Auxiliary Platform

S97.0.M, Rev. 12 Page 23 of 26 JAD/jad 6.0 TECHNICAL SPECIFICATIONS 6.1 3.9.1 6.2 3.9.3 6.3 3.9.5 6.4 3.9.6 6.5 3.9.8 6.6 3.9.9 6.7 3.9.10 7.0 INTERFACING PROCEDURES 7.1 FH-105, Core Component Movement - Core Transfers 7.2 FH-106, Core Component and Irradiated Item Movement - No Core Transfer 7.3 ON-120, Fuel Handling Problems 7.4 S97.1 .A, Electrical, Mechanical, and Pneumatic Alignment/Checkout of Refueling Platform Bridge, Trolley and Main Hoist for Operation 7.5 ST-6-097-630-*, Core Alteration Testing for Offloading, Shuffling, and Reloading the Core 7.6 M-097-046, Control of Fuel Inspection Activities 7.7 M-097-035, Vacuum Sipping Irradiated BWR Fuel Assemblies 7.8 S97.1..B, Fuel Floor Auxiliary Platform Start-up, Checkout, Operation and Shutdown

S97.0.M, Rev. 12 Page 24 of 26 JAD/jad ATTACHMENT 1 Page 1 of 1 LIMERICK REFUEL PLATFORM FLOOR INTERLOCKS INTERLOCK STATUS DISPLAY INITIATING CONDITIONS EFFECT ON OPERATIONS ROD BLOCK #1 BRIDGE NEAR OR OVER CORE CONTROL ROD WITHDRAWAL BLOCK AND (RDCS), ROD OUT BLOCK ANY HOIST FUEL LOADED ANNUNCIATOR - MCR ROD BLOCK #2 BRIDGE REVERSE STOP #1 BRIDGE NEAR OR OVER CORE (BRIDGE FORWARD STOP #1, if AND NO BRIDGE MOTION IN INDICATED reactor select switch in non-normal ANY HOIST FUEL LOADED DIRECTION position) AND ANY ROD NOT FULL IN BRIDGE REVERSE STOP #2 BRIDGE NEAR OR OVER CORE (BRIDGEFORWARD STOP #2, if AND NO BRIDGE MOTION IN INDICATED reactor select switch in non-normal RX MODE SWITCH NOT IN REFUEL DIRECTION position) OR CONTROL ROD NOT SELECTED BRIDGE NEAR OR OVER CORE AND MAIN HOIST INOPERATIVE FUEL HOIST INTERLOCK MAIN HOIST FUEL LOADED

(> 550 LBS) (HOIST WILL NOT RAISE OR LOWER)

AND ANY ROD NOT FULL IN MONO AUX HOIST INTERLOCK BRIDGE NEAR OR OVER CORE MONO AUX HOIST INOPERATIVE AND AUX HOIST FUEL LOADED (HOIST WILL NOT RAISE OR LOWER)

(> 1500 LBS)

AND ANY ROD NOT FULL IN TROLLEY AUX HOIST INTERLOCK TROLLEY AUX HOIST INOPERATIVE (HOIST WILL NOT RAISE OR LOWER)

THERMAL OVERLOAD BRIDGE WILL NOT OPERATE OPER CHECK TIMER MOTOR FIELD LOSS TROLLEYS WILL NOT OPERATE UNDERVOLTAGE FAULT LOCKOUT MAIN HOIST OVERLOAD HOISTS WILL NOT OPERATE PHASE LOSS (BLOWN FUSE)

INSTANTANEOUS OVERCURRENT AIR OPERATED GRAPPLES GO OR TROLLEY DECK CABINET DOOR OPEN STAY CLOSED VARIABLE SPEED SWITCHES NOT NEUTRAL ON STARTUP CONTROL ROD WITHDRAWAL BLOCK - MCR (OVER CORE ONLY)

VARIABLE TEST IN PROGRESS TEST BOX CONNECTED DEPENDS ON TEST SWITCH POSITION

S97.0.M, Rev. 12 Page 25 of 26 JAD/jad ATTACHMENT 2 Page 1 of 2 U/1 MAIN HOIST POSITIONI INDICATIONS NOTE: Position indications for single blade gui ies are the same as for bundles.

DIMENSION BUNDLE ENTERING RACK 15" - 17" BUNDLE SEATED IN RACK 190"- 192" BUNDLE ENTERING CORE 375" - 377" BUNDLE SEATED IN CORE 549"- 551" DBG ENTERING FUEL RACK 12" 14" DBG SEATED IN FUEL RACK 184"- 189" DGB SEATED IN CRB RACK WITHOUT CRB SPACER 187" - 189" DGB SEATED IN CRB RACK WITH CRB SPACER 175.5" 177.5" DBG ENTERING CORE 372" 374" DBG SEATED IN CORE 546" 548" DBG TRAVERSING CATTLE CHUTE -4"1 -4.5" BUNDLE SEATED IN FUEL PREP. MACHINE 164" - 166" BUNDLE SEATED IN FUEL PREP. MACHINE'S ROTATING INSPECTION FIXTURE 158" - 160" BOTTOM OF FUEL POOL approx. 372" BOTTOM OF CASK PIT approx. 422" BUNDLE SEATED IN BUNDLE SIPPING CANISTER ID/ LOCATION BUNDLE SEATED IN BUNDLE SIPPING CANISTER ID/ LOCATION

S97.0.M, Rev. 12 Page 26 of 26 JAD/jad ATTACHMENT 2 Page 2 of 2 U/2 MAIN HOIST POSITION INDICATIONS NOTE: Position indications for single blade guides are the same as foir bundles.

DIMENSION BUNDLE ENTERING RACK 19"- 21" BUNDLE SEATED IN RACK 194"- 196" BUNDLE ENTERING CORE 375" - 377" BUNDLE SEATED IN CORE 549" - 551" DBG ENTERING FUEL RACK 16"1- 18" DBG SEATED IN FUEL RACK 191"1- 193" DGB SEATED IN CRB RACK WITHOUT CRB SPACER 187"- 189" DGB SEATED IN CRB RACK WITH CRB SPACER 175.5" - 177.5" DBG ENTERING CORE 372" - 374" DBG SEATED IN CORE 546" - 548" DBG TRAVERSING CATTLE CHUTE -4" - -4.5" BUNDLE SEATED IN FUEL PREP. MACHINE 164"- 166" BUNDLE SEATED IN FUEL PREP. MACHINE'S ROTATING INSPECTION FIXTURE 158"- 160" BOTTOM OF FUEL POOL approx. 372" BOTTOM OF CASK PIT approx. 422" BUNDLE SEATED IN BUNDLE SIPPING CANISTER .

ID/ LOCATION BUNDLE SEATED IN BUNDLE SIPPING CANISTER ID/ LOCATION

EXELON NUCLEAR TITLE: Response to Loss of Air to Cavity Seals TASK PERFORMED BY: EVALUATOR:

EVALUATOR SIGNATURE:

DATE:

DIRECTIONS TO EVALUATOR:

EVALUATION METHOD:

Simulate EVALUATION LOCATION:

Refuel Floor APPROXIMATE COMPLETION TIME:

20 min.

IMPORTANCE RATING(S):

SYSTEM NUMBER(S):

3.2 233000A2.11

REFERENCES:

ON-120, FUEL HANDLING PROBLEMS

$53.0.A, NORMAL MAKEUP/RESPONSE TO LOW LEVEL IN FUEL STORAGE POOL OR REACTOR WELL ARC-BOP-*OC222, BALANCE OF PLANT PANEL *0C222 ANNUNCIATOR RESPONSE CARDS

$15.3.C, RESPONSE TO LOSS OF SERVICE AIR TO REFUEL FLOOR INFLATABLE SEALS TASK STANDARD(S):

Backup bottle aligned to spent fuel pool seals per $15.3.C L GS JPM4. doc Page 3 of 10

EXELON NUCLEAR TASK CONDITIONS:

1. Fuel movement in the spent fuel pool is in progress

2. The reactor cavity gates are installed and the reactor well is drained

3. A loss of service air on Unit has occurred

4. Alarm D-1, SEAL NO. 7 REACTOR WELL / SPENT FUEL POOL STOP LOG (SOUTH SEAL) has been received on __0C222 INITIATING CUES:

You have been directed by the CRS to respond to __0C222 alarms and backup refuel floor inflatable seals using backup bottles. Additional operators are being dispatched to the refuel floor.

LGSJPM4dnr 4 d LG JP)....

Page 4 of 10

EXELON NUCLEAR Critical Element(s) indicated by =*" in Performance Checklist.

PERFORMANCE CHECKLIST:

STEP STANDARD TSAT/UNSAT ARC Response D-1 *0C222

1. Reference ARC for *0C222 D-1 ARC D-1 referenced

2. Verify integrity of Seal No. 10 (the Verify Seal 10 pressure redundant seal)

CUE: Seal 10 pressure is 46 psig and slowly dropping (Examiner Note: Pressureon all seals will eventually drop because service air was lost.

The JPM only examines backing up one seal.All seals would eventually need the same steps performed)

3. Refer to S15.3.C S15.3.C obtained and referenced

4. If Seal 7 is functioning as secondary N/A containment then refer to Technical SpeCifications section 3.6.5 With the shield plugs removed, the seals are not part of secondary containment

5. Investigate and contain any leakage N/A per $53.0.A CUE: No leakage is detected yet SI 5.3.C Assessment Actions

6. Check *0C222 for any annunciators N/A - Task condition indicating low seal air pressure CUE: D-1 is still in alarm (I rQ IRAVI"".~

I-.Vt.J~

A Ae4 fk, Page 5 of 10

I --.EXELON NUCLEAR ,j-r jL I QTr-D I II .QTAKInrADn ['* A "r' ii ILldS. l*

___________________________________________________ - I "auPIAI

'A-rn I&.. -

7. Ifservice air is still available as N/A - Regulator adjustment will not work 'I evidenced by observing pressure with the air supply failing gauge P1-015-*44(A-K) then adjust service air pressure to the seal per

$15.3.E CUE: PI-015-*44A through K indicate 45 psig and dropping slowly. The control room reports that the service air compressor and backup service air compressor are both tripped

8. If service air pressure is dropping Proceed to Section 4.2 for backup bottle noticeably or gone evidenced by attachment observing pressure gauge PI-015

• 44(A-K), then proceed to step 4.2 and attach secondary backup bottles CUE: PI-01 5-*44A through K indicate 43 psig and dropping slowly Backup Air Bottle Installation to Seal 7 per S15.3.C Rev 12

9. Obtain cart containing two backup Locate backup bottle equipment.

bottles with regulators, hose, and appropriate quick disconnect fittings Examiner Note: (The hoses and, CUE (after,locating boxes and bottles): You Iregulmaors are stored in toolbox along the North wall of Refuel Floorequipped with have the backup bottle and equipment breakablelocks. The bottles are in variouslocations. The last location was at the East wall) The candidate should show the bottles and the location of the box. He or she need not open the box.

10. *Position cart near seal station and Indicate location of Seal Station "G" connect one bottle to quick disconnect where bottle would be placed attached to calibration port of PI-015

"*49A (B-K), Seal Supply Press Indicate location of quick disconnect indicator and..."Ln CUE: Bottle cart is positioned and quick disconnect fitting is attached to calibration port of P1-0 15-__49G LGS JPM 4.doc 4.doc Page 6 of 10 LGS JPM

44 EXELON NUCLEAR I -

Q I C=-

STANDARn r _SATIUNSAT STANDARD

11. *Close 15-"41 1A(B-K) "Supply Valve" Close supply valve and root valve fi and "Root Valve" for PI-01 5-*49A(B ~rPl-1 01&5*49G K).(Both valves located in pit next to manifold)

CUE: The supply valve and the root valve are closed

12. UNIT 2 ONLY Unit 2: Plug valve dosed Ensure "Plug Valve" for P!-01 5 Unit 1: N/A 249A(B-K) closed. Plug valve located on manifold CUE if performing on Unit 2 only: "Plug valve is closed" The plug valve is a bar stock valve on the vertical section of tubing just under the disconnect fitting

13. *Open bottle valve and adjust Open bottle valve and adjust regulator to regulator for pressure setting on between 42 and 48 psig applicable seal as follows:

SEAL PREFERRED ACCEPTABLE REGULATOR REGULATOR SETTING P (psig) PRESSURE RANGE (psig)

A,B,G,K 47 42 to 48 C,D 56.5 52.5 to 57.5 E,F,HJ 41.5 37 to 42.5 CUE: Bottle valve is open and regulator is adjusted to the pressure you specified

14. *UNIT 2 ONLY Unit 2: Plug valve is open Open "Plug Valve" for PI-015-249A(B-K)

Unit 1: N/A CUE if performing on Unit 2 only: "Plug valve is open" LOS JPM 4 div rfn, "LGSJPM 4. Page 7 of 10

I ~EXELON NUCLEAR

- - - j ____________

Q 1 C=

STAN*AR* OATII Ilklt't Aq-S....... ..... lII L~l tl%-A

15. *Open root valve for PI-015-*49A(B-K) Root valve for PI-015-*49G opened and ensure it indicates accordingly CUE: Root valve is open. Seal pressure indicates 47 psig

16. CUE: You have reached the termination point for the JPM. You may stop here LGS JPM 4 dev-S........ *VV Page 8 of 10

-EXELON NUCLEAR Comments.

Note: Any grade of UNSAT requires a comment.

JPM Overall Rating: _

/ SAT/UNSAT LGS JPM 4doe

.... v S......

Page'9 of 10

S. EXELON NUCLEAR,..

TASK CONDITIONS:

1. Fuel movement in the spent fuel pool is in progress

2. The reactor cavity gates are installed and the reactor well is drained

3. A loss of service air on Unit has occurred

4. Alarm D-1, SEAL NO. 7 REACTOR WELL / SPENT FUEL POOL STOP LOG (SOUTH SEAL) has been received on 0C222 INITIATING CUES:

You have been directed by the CRS to respond to 0C222 alarms and backup refuel floor inflatable seals using backup bottles. Additional operators are being dispatched to the refuel floor.

CANDIDATE

I ARC-BOP-20C222, Rev. 3 (32 Pages)

WEF/JFP/JMO/DJS:eer

• • UNIT 2 ONLY **

PECO ENERGY COMPANY LIMERICK GENERATING STATION ARC-BOP-20C222 BALANCE OF PLANT PANEL 20C222 ANNUNCIATOR RESPONSE CARDS (ARC)

PURPOSE To provide the automatic actuations of and the operational responses for the annunciators on Balance of Plant (BOP) Panel 20C222. Any alarm on this panel alarms a common FUEL POOL COOLING & CLEAN-UP SYSTEM TROUBLE alarm in the Main Control Room on Panel 212, Window J-5.

ARC-BOP-20C222, REV. 3 C6 February 9, 2000 Windows that have been changed:

TABLE OF CONTENTS ADDED WITH THIS REVISION I B-3

TABLE OF CONTENTS Page 1 of 1 ARC-BOP-20C222, REV. 3 WINDOW TITLE Rev.

NUMBER COVERSHEET ...................... .. .................... 3 TITLE PAGE ...................... t O O I O O O ° 3 A-I SEAL NO. 1 DRYER & SEPARATOR STOP LOG (SOUTH SEAL) ....................... 3 A-2 SEAL NO. 2 DRYER & SEPARATOR STOP LOG (NORTH SEAL) 3 A-3 SPARE ........................................ ............. 3 A-4 SPARE ................... ..................... 3 B-I SEAL NO. 3 REACTOR WELL (TOP SEAL) ........... 3 B-2 SEAL NO. 4 REACTOR WELL (BOTTOM SEAL) ........ 3 B-3 2BT208 SKIMMER SURGE TANK HI-LEVEL ........... 3 B-4 2BT208 SKIMMER SURGE TANK LO-LEVEL ........... 3 C-I SEAL NO. 5 SPENT FUEL POOL/CASK WASHDOWN GATE (EAST) 3 C-2 SEAL NO. 6 SPENT FUEL POOL/CASK WASHDOWN GATE (WEST) 3 C-3 SPARE 3...........................

C-4 FUEL POOL GATE DRAIN HI FLOW .............................. 3 D-1 SEAL NO. 7 REACTOR WELL/SPENT FUEL STOP LOG (SOUTH SEAL) .............................................. 3 D-2 SEAL NO. 8 REACTOR WELL/SPENT FUEL GATE (EAST) ............ 3 D-3 REACTOR WELL SEAL RUPTURE DRAIN HI FLOW ................... 3 D-4 REFUELING BELLOWS LEAK DETECT HI FLOW ..................... 3 E-1 SEAL NO. 9 REACTOR WELL/SPENT FUEL POOL GATE (WEST) ........ 3 E-2 SEAL NO. 10 REACTOR WELL/SPENT FUEL POOL STOP LOG (NORTH SEAL) .............................................. 3 E-3 SPARE 3...........................

E-4 HORN RELAY 3...........................

20C222 A-I 20C222 01 ALARM WORDING:

2 SEAL NO. 1 DRYER &

3 SEPARATOR STOP LOG (SOUTH SEAL) 4 A B C D E AUTOMATIC ACTIONS:

1. FUEL POOL'COOLING & CLEAN-UP SYSTEM TROUBLE alarms at 212 CLEANUP.

OPERATOR ACTIONS:

1. Refer to S15.3.C.

2. Verify integrity of Seal No. 2.

3. IF Seal'No. 1 is functioning as secondary containment, THEN refer to Tech Spec 3.6.5.

4, IF dryer/separator storage pool is flooded, THEN investigate AND contain any leakage per $53.0.A.

CAUSES:

1. Low pressure in Seal No. 1 with Service Air Supply 15-2413A NOT in full vent position.

ANNUNCIATOR#:

• PAL-15-245A SETPOINT:

0 43 psig DEVICE(S):

° PSL-15-249A

"* ZS-15-245A ARC-BOP-20C222, REV. 3 PAGE 1 OF 32

20C222 20C222 A-I 01

REFERENCES:

1. E-643

2. M-15

3. M-600

4. M-53 ARC-BOP-20C222, REV. 3 PAGE 2 OF 32

20C222 A-2 20C222 02 1 ALARM WORDING:

2

• SEAL NO. 2 DRYER &

3 SEPARATOR STOP LOG (NORTH SEAL) 4 A B C D E AUTOMATIC ACTIONS:

1. FUEL POOL COOLING & CLEAN-UP SYSTEM TROUBLE alarms at 212 CLEANUP.

OPERATOR ACTIONS:

1. Refer to S15.3.C.

2. Verify integrity of Seal No. 1.

3. IF Seal No. 2 is functioning as secondary containment, THEN refer to Tech Spec 3.6.5.

4. IF dryer/separator storage pool is flooded, THEN investigate AND contain any leakage per S53.O.A.

CAUSES:

1. Low pressure in Seal No. 2 with Service Air Supply 15-2413B NOT in full vent position.

ANNUNCIATOR#:

PAL-15-245B SETPOINT:

• 43 psig DEVICE(S):

• PSL-15-249B

• ZS-15-245B I ARC-BOP-20C222, PAGE 3 OF 32 REV. 3

20C222 A-2 20C222 02

REFERENCES:

1. E-643

2. M-15

3. M-53

4. M-600 ARC-BOP-20C222, REV. 3 PAGE 4 OF 32

20C222 20C222 A- 3 1

ALARM WORDING:

2 SPARE 3

• 4 A B C D E F AUTOMATIC ACTIONS:

1. None OPERATOR ACTIONS:

1. N/A CAUSES:

1. N/A ANNUNCIATOR#:

• None SETPOINT:

• N/A DEVICE(S):

"* None

REFERENCES:

1. E-643 I ARC-BOP-20C222, PAGE 5 OF 32 REV. 3

20C222 20C222 A-4 04 ALARM WORDING:

2 SPARE 3

4

• A B C D E F AUTOMATIC ACTIONS:

1. None OPERATOR ACTIONS:

1. N/A CAUSES:

1. N/A ANNUNCIATOR#:

• None SETPOINT:

• N/A DEVICE (S):

• None

REFERENCES:

1. E-643 I ARC-BOP-20C222, PAGE 6 OF REV. 3 32

20C222 B-1 20C222 05 1

• ALARM WORDING:

2 SEAL NO. 3 REACTOR 3 WELL (TOP SEAL) 4 A B C D E AUTOMATIC ACTIONS:

1. FUEL POOL COOLING & CLEAN-UP SYSTEM TROUBLE alarms at 212 CLEANUP.

OPERATOR ACTIONS:

1. . Refer to S15.3.C.

2. IF reactor cavity is flooded, THEN investigate AND contain any leakage from the Reactor well per S53.0.A.

3. Verify integrity of Seal No. 4.

4. Refill well as necessary per S53.0.A.

CAUSES:

1. Low pressure in Seal No. 3 with Service Air Supply 15-2413C NOT in full vent position.

ANNUNCIATOR#:

• PAL-15-245C SETPOINT:

• 53.5 PSIG DEVICE(S):

• PSL-15-249C

• ZS-15-245D ARC-BOP-20C222, REV. 3 PAGE 7 OF 32

20C222 B-i 20C222 05

REFERENCES:

1. E-643

2. M-15

3. M-600

4. M-53 1 4, ARC-BOP-20C222, REV. 3 PAGE 8 OF 32

20C222 B-2 20C222 06 ALARM WORDING:

2

• SEAL NO. 4 REACTOR WELL (BOTTOM SEAL) 4 A B C D E AUTOMATIC ACTIONS:

1. FUEL POOL COOLING & CLEAN-UP SYSTEM TROUBLE alarms at 212 CLEANUP.

OPERATOR ACTIONS:

1. Refer to S15.3.C.

2. IF reactor cavity is flooded THEN, investigate AND contain leakage from Reactor Well per S53.0.A.

3. Verify integrity of Seal No. 3.

4. Refill well as necessary per $53.0.A.

CAUSES:

1. Low pressure in Seal No. 4 with Service Air Supply 15-2413D NOT in full vent position.

ANNUNCIATOR#:

• PAL-15-245D SETPOINT:

• 53.5 psig DEVICE(S):

• PSL-15-249D

• ZS-15-245D ARC-BOP-20C222, REV. 3 PAGE 9 OF 32

20C222 B-2 20C222 06

REFERENCES:

1. E-643

2. M-15

3. M-600

4. M-53 I ARC-BOP-20C222, REV. 3 PAGE 10 OF 32

20C222 B-3 20C222 07 1 ALARM WORDING:

2 2BT208 SKIMMER SURGE TANK HI-LEVEL 4

A B C D E AUTOMATIC ACTIONS:

1. FUEL POOL COOLING & CLEAN-UP SYSTEM TROUBLE alarms at 212 CLEANUP.

OPERATOR ACTIONS:

1. Identify source of water in fuel pool OR reactor well.

2. Verify HV-53-207 closed at 20C222.

3 Perform one of the following based on Fuel Pool line-up:

a) For fuel pool(s) connected to the cavity VERIFY SST level is offscale high.

b) For Unit 2 fuel pool connected to the Unit 1 fuel pool AND neither fuel pool connected to Unit 1 or Unit 2 Reactor Cavity:

1) IF Fuel Pool Cooling system is out of service VERIFY SST level is greater than 8 feet.

2) IF Fuel Pool Cooling system is in service VERIFY SST level is being maintained 8-12 feet.

c) For fuel pool not connected to the reactor cavity AND separated from the other unit's fuel pool VERIFY SST level is being maintained 8-12 feet.

4. RESTORE skimmer surge tank to appropriate level per S53.3.G.

CAUSES:

1. High level in 2BT208 Skimmer Surge Tank due to failure of makeup control valve OR increase in fuel pool/reactor well inventory from ESW, RHR, CRD OR any system capable of adding water to reactor well during refueling OR leakage past weir plates WHEN the FPC system is shutdown.

ANNUNCIATOR#:

• LAH-53-202B SETPOINT:

0 14' 6" DEVICE(S):

• LSH-53-202 A RC-BOP-20C222, REV. 3 PAGE 11 OF 32

20C222 B-3 20C222 07 l

REFERENCES:

I. E-53

2. M-643

3. M-600 I ARC-BOP-20C222, PAGE 12 OF 32 REV. 3

20C222 20C222 B-4 08 1 ALARM WORDING:

2 2BT208 SKIMMER SURGE TANK LO-LEVEL 4*

A B C D E AUTOMATIC ACTIONS:

1. FUEL POOL COOLING & CLEAN-UP SYSTEM TROUBLE alarms at 212 CLEANUP.

OPERATOR ACTIONS:

1. Restore Skimmer Surge Tank level per $53.3.A.

2. Investigate AND contain any system leakage per $53.0.A CAUSES:

1. Low level in Skimmer Surge Tank 2BT208 due to system leakage OR failure of makeup valve HV-53-207.

ANNUNCIATOR#:

° LAL-15-202B SETPOINT:

• 6P' 0" DEVICE(S):

• LSL-53-203

REFERENCES:

1. E-643

2. E-577

3. M-53

4. M-600 ARC-BOP-20C222, REV. 3 PAGE 13 OF 32

20C222 20C222 C-I 1 ALARM WORDING:

2 SEAL NO. 5 SPENT.FUEL POOL/CASK WASHDOWN GATE 4 (EAST)

A B C D E AUTOMATIC ACTIONS:

1. FUEL POOL COOLING & CLEAN-UP SYSTEM TROUBLE alarms at 212 CLEANUP.

OPERATOR ACTIONS:

1. Refer to S15.3.C.

2. Verify integrity of Seal No. 6.

3. Investigate AND contain any leakage from Spent Fuel Cask Storage Pit per $53.0.A.

4. Refill pit as necessary per S53.0.A.

CAUSES:

1. Low pressure in Seal No. 5 with Service Air Supply 15-2413E NOT in full vent position.

ANNUNCIATOR#:

• PAL-15-245E SETPOINT:

• 38.5 psig DEVICE(S):

• PSL-15-249E

• ZS-15-245E I ARC-BOP-20C222, PAGE 14 OF 32 REV. 3

20C222 20C222 C-I 09

REFERENCES:

1. E-643

2. M-15

3. M-600

4. M-53 I F ARC-BOP-20C222, REV. 3 PAGE 15 OF 32

20C222 C-2 20C222 10 1 ALARM WORDING:

2

• SEAL NO. 6 SPENT FUEL POOL/CASK 3 WASH DOWN GATE 4 (WEST)

A B C D E AUTOMATIC ACTIONS:

1. FUEL POOL COOLING & CLEAN-UP SYSTEM TROUBLE alarms at 212 CLEANUP.

OPERATOR ACTIONS:

1. Refer to S15.3.C.

2. Verify integrity of Seal No. 5.

3. Investigate AND contain any leakage from Spent Fuel Cask Storage Pit per $53.0.A.

4. Refill pit as necessary per $53.0.A.

CAUSES:

1. Low pressure in Seal No. 6 with Service Air Supply 15-2413F NOT in full vent position.

ANNUNCIATOR#:

• PAL-15-245F SETPOINT:

• 38.5 Psig DEVICE(S):

PSL-15-249F

• ZS-15-245F ARC-BOP-20C222, REV. 3 PAGE 16 OF 32

20C222 C-2 20C222 10

REFERENCES:

1. E-643

2. M-15

3. M-600

4. M-53 I ARC-BOP-20C222, REV. 3 PAGE 17 OF 32

20C222 C-3 20C222 II ALARM WORDING:

2 SPARE 3

• 4 A B C D E F AUTOMATIC ACTIONS:

1. None OPERATOR ACTIONS:

1. N/A CAUSES:

1. N/A ANNUNCIATOR#:

• None SETPOINT:

• N/A DEVICE(S):

• None

REFERENCES:

1. E-643 ARC-BOP-20C222, REV. 3 PAGE 18 OF 32

20C222 C-4 20C222 12 1 ALARM WORDING:

2 FUEL POOL GATE DRAIN 3 HI FLOW 4

• A B C D E AUTOMATIC ACTIONS:

1. FUEL POOL COOLING & CLEAN-UP SYSTEM TROUBLE alarms at 212 CLEANUP.

OPERATOR ACTIONS:

1. IF scheduled draining is NOT in progress, THEN identify source of leakage by sequentially shutting valves 53-2051 AND 53-2052.

2. Verify valves 53-2033, 53-2043 AND 53-2045 closed.

3. Repair/repressurize leaking seals as required.

4. Refill pool as required per S53.0.A.

CAUSES:

1. Flow in drain line from reactor well, dryer/separator storage pool AND gate area between seals 8, 9 AND between 5, 6.

ANNUNCIATOR#:

° FAH-53-203 SETPOINT:

1.5 GPM DEVICE(S):

• FSH-53-203 I ARC-BOP-20C222, PAGE 19 OF 32 REV. 3

20C222 C-4 20C222 12 12

REFERENCES:

M-53

2. E-643

3. M-600 I ARC-BOP-20C222, REV. 3 PAGE 20 OF 32

20C222 D-1 20C222 13 1 ALARM WORDING:

2 SEAL NO. 7 REACTOR WELL/SPENT FUEL POOL STOP LOG 4 (SOUTH SEAL)

A B C D E AUTOMATIC ACTIONS:

1. FUEL POOL COOLING & CLEAN-UP SYSTEM TROUBLE alarms at 212 CLEANUP.

OPERATOR ACTIONS:

1. Refer to S15.3.C.

2. Verify integrity of Seal No. 10.

3. IF Seal No. 7 is functioning as secondary containment, THEN refer to Tech Spec 3.6.5.

4. Investigate AND contain any leakage per $53.0.A.

CAUSES:

1. Low pressure in Seal No. 7 with Service Air Supply HV-15-2413G NOT in full vent position.

ANNUNCIATOR#:

• PAL-15-245G SETPOINT:

• 43 psig DEVICE(S):

• PSL-15-249G

• ZS-15-245G ARC-BOP-20C222, REV. 3 PAGE 21 OF 32

I 20C222 D-1 20C222 13 w

REFERENCES:

a. E-643

2. M-15

3. M-600

4. M-53 ARC-BOP-20C222, REV. 3 PAGE 22 OF 32

20C222 D-2 20C222 14 1 ALARM WORDING:

2

• SEAL NO. 8 REACTOR WELL/SPENT 3

FUEL POOL GATE 4 (EAST)

A B C D E AUTOMATIC ACTIONS:

1. FUEL POOL COOLING & CLEAN-UP SYSTEM TROUBLE alarms at 212 CLEANUP.

OPERATOR ACTIONS:

1. Refer to S15.3.C.

2. Verify integrity of Seal No. 9.

3. Investigate AND contain any leakage from Spent Fuel Pool per S53.0.A.

4. Refill pool as required per $53.0.A.

CAUSES:

1. Low pressure in Seal No. 8 with Service Air Supply 15-2413H NOT in full vent position.

ANNUNCIATOR#:

• PAL-15-245H SETPOINT:

• 38.5 psig DEVICE(S):

• PSL-15-249H

• ZS-15-245H I ARC-BOP-20C222, PAGE 23 OF 32 REV. 3

20C222 20C222 D-2

_20C222ES14

REFERENCES:

1. E-643

2. M-15

3. M-600

4. M-53 I ARC-BOP-20C222, REV. 3 PAGE 24 OF 32

I 20C222 20C222 D-4 ALARM WORDING:

2 REFUELING BELLOWS LEAK DETECT HI FLOW 4

A B C D E AUTOMATIC ACTIONS:

1 FUEL POOL COOLING & CLEAN-UP SYSTEM TROUBLE alarms at 212 CLEANUP.

OPERATOR ACTIONS:.

1. Refer to S53.0.A.

2. Verify proper operation of refueling bellows per S53.0.A.

3. Refill Reactor Well as required per S53.0.A.

CAUSES:

1. Failure of refueling bellows.

ANNUNCIATOR#:

• FAH-53-202 SETPOINT:

"* 1.5 GPM DEVICE(S):

FSH-53-202

REFERENCES:

1. M-53

2. E-643 I ARC-BOP-20C222, REV. 3 PAGE 26 OF 32

20C222 20C222 E-1 17 1

ALARM WORDING:

2 SEAL NO. 9 REACTOR 3 WELL/SPENT FUEL POOL 4 GATE (WEST)

A B C D E A B AUTOMATIC ACTIONS:

1. FUEL POOL COOLING & CLEAN-Up SYSTEM TROUBLE alarms at 212 CLEANUP.

OPERATOR ACTIONS:

1. Refer to S15.3.C.

2. Verify integrity of Seal No. 8.

3. Investigate AND contain any leakage from Reactor Well per $53.0.A.

4. Refill well as necessary per $53.0.A.

CAUSES:

1. Low pressure in Seal No. 9 with Service Air Supply 15-2413J NOT in full vent position.

ANNUNCIATOR#:

° PAL-15-245J SETPOINT:

• 38.5 psig DEVICE(S):

• PSL-15-249J

• ZS-15-245J ARC-BOP-20C222, REV. 3 PAGE 27 OF 32

2220C222

• 20C222 E-1 17

REFERENCES:

1. E-643

2. M-15

3. M-600

4. M-53 I ARC-BOP-20C222, PAGE 28 OF 32 REV. 3

202220C222 E-2 11 ALARM WORDING:

2

• SEAL NO. 10 REACTOR 3 WELL/SPENT FUEL POOL STOP LOG 4

(NORTH SEAL)

A B C D E AUTOMATIC ACTIONS:

1. FUEL POOL COOLING & CLEAN-UP SYSTEM TROUBLE alarms at 212 CLEANUP.

OPERATOR ACTIONS:

1. Refer to S15.3.C.

2. Verify integrity of Seal No. 7.

3. IF Seal No. 10 is functioning as secondary containment, THEN refer to Tech Spec 3.6.5.

4. Investigate AND contain any leakage per $53.0.A.

CAUSES:

1. Low pressure in Seal No. 10 with Service Air Supply 15-2413K NOT in full vent position.

ANNUNCIATOR#:

PAL-15-245K SETPOINT:

• 43 psig DEVICE(S):

• PSL-15-249K

• ZS-15-245K I ARC-BOP-20C222, REV. 3 PAGE 29 OF 32

20C222 E-2 18

REFERENCES:

1. E-643

2. M-15

3. M-600

4. M-53 ARC-BOP-20C222, REV. 3 PAGE 30 OF 32

20C222 E-3 20C222 19 1 WORDING ALARM ALARM WORDING:

2 SPARE SPARE 3

4 A B C D E AUTOMATIC ACTIONS:

1. None OPERATOR ACTIONS:

1. N/A CAUSES:

1. N/A ANNUNCIATOR#:

• None SETPOINT:

• N/A DEVICE(S):

• None

REFERENCES:

1. E-643 ARC-BOP-20C222, REV. 3 PAGE 31 OF 32

20C222 E-4 420C222 20 1 ALARM WORDING:

2 HORN RELAY 3

4

• A B C D E AUTOMATIC ACTIONS:

1. None OPERATOR ACTIONS:

1. N/A CAUSES:

1. N/A ANNUNCIATOR#:

• None SETPOINT:

• N/A DEVICE(S):

• None

REFERENCES:

1. E-643 ARC-BOP-20C222, REV. 3 PAGE 32 OF 32

S15.3.C, Rev. 12 Page 1 of 10 ALC/LBM:eer/jml EXELON NUCLEAR LIMERICK GENERATING STATION S15.3.C RESPONSE TO LOSS OF SERVICE AIR FOR REFUEL FLOOR INFLATABLE SEALS 1.0 PURPOSE To maintain integrity of inflatable seals during a loss of Service Air or during planned maintenance activities.

2.0 PREREQUISITES 2.1 One of the following is established:

Secondary Containment Integrity per Tech Spec 3.6.5.1.2 OR Spent Fuel Pool flooded OR Reactor Well flooded 2.2 Emergency Backup Air Bottle Carts are available.

2.3 Air bottles for planned maintenance have been obtained.

3.0 PRECAUTIONS 3.1 Loss of Service Air has potential to vent inflatable seals installed on Refuel Floor.

3.2 WHEN an alarm annunciates from seal station indicating potential loss of Secondary Containment Integrity OR potential loss of water inventory in Spent Fuel Pool/Reactor Cavity THEN all fuel handling activities AND any activity with potential of draining Reactor Vessel while there is still fuel in vessel must be suspended.

S15.3.C, Rev. 12 Page 2 of 10 ALC/LBM:eer/jml 3.3 The latest performance of ST-6-076-360-*, RX ENCL SEC CNTMT INTEGRITY VERIFICATION, should be referred to when determining which seals are required to maintain secondary containment.

S 15.3.C, Rev. 12 Page 3 of 10 ALC/LBM:eer/jml 4.0 PROCEDURE NOTE

1. Attachment 1 shows the relationship between the letter and number designators for an inflatable seal.

2. Attachment 2 shows locations of Seal Air Supply Stations.

These seals are in place to provide Secondary Containment during handling of spent fuel AND also to maintain water inventory of Reactor Well/Spent Fuel Pool during flooded conditions.

Procedure should be performed on seals alarming on *0C222 first.

3. IF procedure is being performed for planned work, THEN Section 4.1 is not required.

4.1 SEAL AND SERVICE AIR ASSESSMENT 4.1.1 CHECK *0C222 for any annunciators indicating low seal air pressure.

NOTE

1. Seal alarms may come in periodically due to the need for a small adjustment in the pressure regulator setting. This is particularly true for seals which have a narrow operating pressure range.

2. The MCR should be kept informed about actions taken on the seals due to their affect on Secondary Containment or Pool water levels.

4.1.2 IF Service Air is still available as evidenced by observing pressure gauge PI-01 5-*44(A-K).

THEN ADJUST service air pressure to the seal per S15.3.E AND EXIT this procedure.

4.1.3 IF Service Air pressure is dropping noticeably or gone evidenced by observing pressure gauge PI-015-*44(A-K),

THEN PROCEED to step 4.2 and attach Secondary Back up Bottles.

S1 5.3.C, Rev. 12 Page 4 of 10 ALC/LBM:eer/jml 4.2 INSTALLATION OF SECONDARY BACKUP BOTTLES TO INFLATABLE SEALS NOTE

1. Backup air bottles are maintained on the Refuel Floor AND are readily accessible for use as secondary backup air for inflatable seals.

I Bottles are labeled denoting their function.

2. Primary location for backup air bottles is along the North Side of the Refuel Floor. Bottles may be located in other refuel floor locations due to refuel floor activities.

3. Hoses AND regulators are stored in toolbox along north wall of Refuel Floor.

4.2.1 IF backup air is being used for a planned maintenance activity, THEN USE air bottles obtained for maintenance activity AND GO TO step 4.2.3.

4.2.2 OBTAIN cart containing two backup air bottles with regulators, hose AND appropriate quick disconnect fittings.

4.2.3 POSITION cart/air bottle near seal station AND CONNECT one bottle to quick disconnect attached to calibration port of PI-015-*49A(B,C,D,E,F,G,H,J,K), "Seal Supply Press Indicator."

S15.3.C, Rev. 12 Page 5 of 10 ALC/LBM:eer/jml 4.2.4 CLOSE 15-*41 1A(B,C,D,E,F,G,H,J,K), "Supply Valve,"

AND "Root Valve" for PI-015-*49A(B,C,D,E,F,G,H,J,K).

(Both valves located in PIT next to manifolds.)

4.2.5 UNIT 2 ONLY ENSURE "Plug Valve" for PI-015-249A(B,C,D,E,F,G,H,J,K) closed.

(Plug valve located on manifold.)

4.2.6 OPEN bottle valve AND ADJUST regulator for pressure setting on applicable seal as follows:

PREFERRED ACCEPTABLE SEAL REGULATOR REGULATOR SETTING PRESSURE RANGE (psig) (psig)

A, B,G, K 47 42 to 48 C,D 56.5 52.5 to 57.5 E,F,H,J 41.5 37 to 42.5 4.2.7 UNIT 2 ONLY OPEN "Plug Valve" for PI-01 5-249A(B,C,D,E,F,G,H,J,K).

4.2.8 OPEN "Root Valve" for PI-015-*49A(B,C,D,E,F,G,H,JK)

AND ENSURE it indicates accordingly.

S15.3.C, Rev. 12 Page 6 of 10 ALC/LBM:eer/jml 1 4.3 RETURN TO NORMAL NOTE WHEN determined by SSV that system can be returned to normal OR all maintenance activities are complete, THEN section 4.3 can be performed.

4.3.1 OPEN 15-*411 (A-K).

UNIT 2 ONLY 4.3.2 CLOSE "Plug Valve" for PI-01 5-249(A-K).

4.3.3 ENSURE PI-015-*44 (A-K) is indicating air pressure to seals.

4.3.4 REDUCE pressure regulator setting AND CLOSE bottle valve.

4.3.5 OBSERVE air pressure at PI-015-*44(A-K) within range of table below AND ADJUST per S15.3.E if necessary.

PREFERRED ACCEPTABLE SEAL REGULATOR REGULATOR L (psig)

SETTING PRESSURE RANGE (psig) 47 42 to 4488 A,B,G,K 56.5 52.5 to 557.55 C,D 41.5 37 to 442.55 E,F,H,J 4.3.6 IF backup nitrogen bottle is < 500#

THEN REPLACE per S15.6.F.

S15.3.C, Page Rev.

7 of 12 10 ALC/LBM:eer/jml 4.3.7 IF "Emergency Air" bottle was used THEN REPLACE bottle if < 1000#.

4.3.8 RETURN all equipment to storage locations AND ENSURE bottles are secured.

S15.3.C, Rev. 12 Page 8 of 10 ALC/LBM:eer/jml

5.0 REFERENCES

NONE 6.0 TECHNICAL SPECIFICATIONS 6.1 3.6.5.1.2 7.0 INTERFACING PROCEDURES 7.1 E-1, Loss Of All AC Power (Station Blackout) 7.2 E-10/20, Loss Of Offsite Power 7.3 ST-6-076-360-*, RX ENCL SEC CNTMT Integrity Verification 7.4 S15.3.E, Adjustment to operating pressure for Reactor Well, Fuel Pool Gate, Fuel Pool Stop Log, Cask Handling Pit Gate, and Equipment Pool Stop Log Seals.

I 7.5 S15.3.A, Inflation of Reactor Well, Fuel Pool Gate, Fuel Pool Stop Log #15, Cask Handling Pit Gate and Steam Dryer and Separator Stop Log Seals I 7.6 S15.6.F, Swapping Backup Nitrogen Bottle For Refuel Floor Inflatable Seals

S15.3.C, Rev. 12 Page 9 of 10 ALC/LBM:eer/jml Page 1 of 1 SEAL TO VALVE ASSIGNMENTS Seal # Description Valve Suffix Letter 1 Steam Dryer & Separator Stop Log (South)

A 2 Steam Dryer & Separator Stop Log (North)

B 3 Reactor Well (Top)

C 4 Reactor Well (Bottom)

D 5 Cask Washdown Gate (U/i: East, U/2: West)

E 6 Cask Washdown Gate (U/i: West, U/2: East)

F 7 Spent Fuel Pool/Reactor Well Stop Log (South)

G 8 Spent Fuel Pool Gate (U/i: East, U/2: West)

H 9 Spent Fuel Pool Gate (U/i: West, U/2: East)

J 10 Spent Fuel Pool/Reactor Well Stop Log (North)

K These suffix apply to the following for each seal:

1. 15-'411 - Service Air Supply Valve

2.

• F285 - Service Air Supply Air Filter

3. PCV-15-*44 - Service Air Supply Pressure Control Valve

4. PI *44 - Service Air Supply Pressure Indicator

5. 15-*412 - Service Air Supply Check Valve

6. PCV-15-*46 - Backup N2 Bottle Supply Pressure Control Valve

7. 15-*706 - Backup N2 Bottle Supply Valve

8. PSV *49 - Seal Supply Pressure Relief Valve

9. 15-*413 - Seal Supply 3-Way Valve

10. ZS-15-*45 - Seal Supply 3-Way Valve Position Switch

11. PSL- 15-*49 - Seal Supply Pressure Switch Low

12. PI-15-*49 - Seal Supply Pressure Indicator

S15.3.C, Rev. 12 Page 10 of 10 ALC/LBM:eer/jml ATTACHMENT 2 Page 1 of 1 LOCATIONS OF SEAL AIR SUPPLY STATIONS Unit 1/2, Elev. 352' a

0 cu x S,

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"EXELONNUCLEAR.

TITLE: Defeat Unit I and Unit 2 Refuel Floor HVAC High Rad Isolation Signals TASK PERFORMED BY: EVALUATOR:

EVALUATOR SIGNATURE: DATE:

DIRECTIONS TO EVALUATOR:

N/A EVALUATION METHOD:

Simulate EVALUATION LOCATION:

Plant APPROXIMATE COMPLETION TIME:

20 min.

IMPORTANCE RATING(S): 3.7 SYSTEM NUMBER(S): 234000A3.02

REFERENCES:

1. M-041-200 Rev. 14; Reactor Pressure Vessel Disassembly TASK STANDARD(S):

1. Jumpers installed per M-041-200 Attachment 2 LGS JPM 5.doc Page 3 of 10

EXELON NUCLEAR *. ....

TASK CONDITIONS:

I

"* Defeat of the Hi Rad Isolations from Refuel Floor HVAC is required to support Steam Dryer/Separator movement on Unit I

"* The CRS and Unit 1 RO have given permission to perform the procedure

"* Core alterations and OPDRVs are suspended INITIATING CUES:

You have been directed to defeat the Unit 1 and Unit 2 Refuel Floor HVAC Hi Rad isolation signals, and Unit 1 P'rimary Containment Isolation signals per M-041-200, Attachment 2.

LGS JPM 5.doc Page 4 of 10

k. .....

EXELON NUCLEAR Critical Element(s) indicated by in Performance Checklist.

PERFORMANCE CHECKLIST:

STEP STANDARD JSATIUNSAT Equipment Status Tags I

1. CUE: You have been provided with an Equipment Status tag filled in. Use the equipment status tag. Please fill out the attachment as an evaluation guide.

tag as if it is to be installed with the first MINIMUM information to pass this step jumper. The second tag on the sheet is a includes:

spare blank copy . . . . ... ..

i. Proceaure and Step# M-041-200 Provide the candidate with the EST sheet Attachment 2 Step 2.1 After the candidate has completed filling out one tag: "You are in possession of tags filled out in the same manner for the remaining steps" Jumper Installation

2. PERFQRM installation of the following N/A jumpers, with Blue Equipment Status I Tag(s), referencing this procedure AND applicable steps

3.

• INSTALL a jumper from EEE6-2 to Jumper and EST installed from EEE6-2 EEE6-3 AND Blue Equipment Status to EEE6-3 in panel 10C606 Bay A Tag(s) at panel 10C606 (Bay A)

CUE: Jumper and tag are installed

4.

• INSTALL a jumper from FFF8-3 to Jumper and EST installed from FFF8-3 FFF8-4 AND Blue Equipment Status to FFF8-4 in panel 10C606 Bay Tag(s) at panel 1 0C606 (Bay A)

CUE: Jumper and tag are installed

5.

• INSTALL a jumper from EEE6-2 to Jumper and EST installed from EEE6-2 EEE6-3 AND Blue Equipment Status to EEE6-3 in panel 20C606 Bay A.

Tag(s) at panel 20C606 (Bay A)

I CUE: Jumper and tag are installed LGS JPM 5.doc Page 5 of 10

-. .t e.3/4

--.-EXELON NUCLER,..

STEP J STANDARD SATIUNSAT

6.

• INSTALL a jumper from FFF8-3 to Jumper and EST installed from FFF8-3 FFF8-4 AND Blue Equipment Status to FFF8-4 in panel 20C606 Bay A.

Tag(s) at panel 20C606 (Bay A)

CUE: Jumper and tag are installed

+

7. PERFORM installation of the following N/A jumpers, with Blue Equipment Status N/A Tag(s) referencing this procedure AND applicable steps.

8.

• At panel *0C606 (Bay A) INSTALL a Jumper and EST installed from C51A jumper from C51A-Z2A TB7-10 to C5tA- Z2A TB7-10 to C51A-Z2A TB7-11 in Z2A TB7-11 AND Blue Equipment Status panel 10C606 Bay A.

Tag CUE: Jumper and tag are installed

9.

• At panel *0C606 (Bay B) INSTALL a Jumper and EST installed from C51A jumper from C51A-Z2C TB7-10 to C51A- Z2C TB7-10 to C51A-Z2C TB7-11 in Z2C TB7-11 AND Blue Equipment Status panel 10C606 Bay B Tag CUE: Jumper and tag are installed

10.

• At panel *0C633 (Bay A) INSTALL a Jumper and EST installed from C51A jumper from C51A-Z2B TB7-10 to C51A- Z2B TB7-10 to C51A-Z2B TB7-11 in Z2B TB7-11 AND Blue Equipment Status panel 10C633 Bay A Tag CUE: Jumper and tag are installed

11.

• At panel 10C633 (Bay B) INSTALL a Jumper and EST installed from C51A jumper from C51A-Z2D TB7-10 to C51A- Z2D TB7-10 to C51A-Z2D TB7-11 in Z2D TB7-11 AND Blue Equipment Status panel 10C633 Bay B Tag CUE: Jumper and tag are installed CUE: You have reached the termination N/A point for the JPM. You may stop here LGS JPM 5.doc Page 6 of 10

Comments:

Note: Any grade of UNSAT requires a comment.

JPM Overall Rating:

SAT/UNSAT LGS JPM 5.doc Page 7 of 10

~:..;EXELON NUCLEAR -s;;': ."7iI '

TASK CONDITIONS:

• Defeat of the Hi Rad Isolations from Refuel Floor HVAC is required to support Steam Dryer/Separator movement on Unit I

• The CRS and Unit 1 RO have given permission to perform the procedure

• Core alterations and OPDRVs are suspended INITIATING CUES:

You have been directed to defeat the Unit I and Unit 2 Refuel Floor HVAC Hi Rad isolation signals, and Unit I Primary Containment Isolation signals per M-041-200, Attachment 2.

CANDIDATE

EXELON NUCLEAR,~

Attachment Equipment Status Tag Grading Guide A tt c h e n e _ ..

Minimum Entries are circled ANSWER KEY

I ... **,.EXELON NUCLEAR, Equipment Status Tag OM ~IDE () 1 _ _ _ _ _ __ _ _ _ _ _ _ _ _

Spare Sample Tag

[ CANDIDATE!

M-041-200 Rev. 14 Page 110 of 121 REFUEL FLOOR HVAC HI-RAD JUMPER INSTALLATION/ARM REMOVAL FROM SERVICE NOTE: Refueling Area Secondary Containment will be made inoperable during the time the jumpers are installed. Handling of irradiated fuel, core alterations, operations with a potential for draining the reactor vessel and load handling over fuel (unless previously approved by Engineering) must be suspended while the jumpers are installed.

This activity defeats Unit 1 and Unit 2 Refuel Floor HVAC High Radiation Isolation Signals, Refuel Floor High Radiation Primary Containment Isolations, Barrier Block and Vent Actuation to permit removal and transport of Steam Dryer and Steam Separator. Activity also removes three (3) fuel floor ARMs from service (2 of which are Criticality Monitors).

Depending on conditions verified by GP-6.1, this Attachment may be used only to remove the ARMs from service (Steps 4.0 through 9.0). Enter N/A for other steps.

FOR TRAINING PURPOSES ONLY Attachment 2 Page 1 of 5

M-041-200 Rev. 14 Page 111 of 121 REFUEL FLOOR HVAC HI-RAD JUMPER INSTALLATION/ARM REMOVAL FROM SERVICE 1.0 DIRECT Fuel Floor Coordinator to SUSPEND any Fuel Handling, Core Alterations, Operations with a potential for draining the reactor vessel and any load handling over fuel.

Person Contacted NOTE: The following steps bypass the Unit 1 AND Unit 2 High Rad Isolation Signals to the Refuel Floor HVAC and Standby Gas Treatment System.

2.0 PERFORM installation of the following Equipment Status Tag(s) referencing thisjumpers, with Blue procedure AND applicable steps.

DOUBLE VERIFICATION 2.1 At panel 1OC606 (Bay A) INSTALL a jumper from EEE6-2 to EEE6-3 AND Blue Equipment Status Tag.

WV DV DOUBLE VERIFICATION 2.2 At Panel IOC606 (Bay A) INSTALL a jumper from FFF8-3 to FFF8-4 AND Blue Equipment Status Tag.

WV DV DOUBLE VERIFICATION 2.3 At Panel 20C606 (Bay A) INSTALL a jumper from EEE6-2 to EEE6-3 AND Blue Equipment Status Tag.

WV DV DOUBLE VERIFICATION 2.4 At Panel 20C606(Bay A) INSTALL a jumper from FFF8-3 to FFF8-4 AND Blue Equipment Status Tag.

WV DV Attachment 2 Page 2 of 5

M-041-200 Rev. 14 Page 112 of 121 I REFUEL FLOOR HVAC HI-RAD JUMPER INSTALLATION/ARM REMOVAL FROM SERVICE NOTE: The following step defeats Refuel Outage Unit

• Refuel Floor High Radiation Primary Containment isolation (H 2 /0 2 Analyzers, Hydrogen Recombiners, AND Containment Leak Detector)

AND the Barrier Block AND Vent actuation to permit Steam Dryer/Separator removal.

These isolations are NOT required in OPCON 5 (TS 3.3.2).

3.0 PERFORM installation of the following jumpers, with Blue Equipment Status Tag(s) referencing this procedure AND applicable steps.

DOUBLE VERIFICATION 3.1 At panel *0C606 (Bay A) INSTALL a jumper from C51A-Z2A TB7-10 to C51A-Z2A TB7-11 AND Blue Equipment Status Tag.

WV DV DOUBLE VERIFICATION

( 3.2 At panel *0C606 (Bay B) INSTALL a jumper from C51A-Z2C TB7-10 to C51A-Z2C TB7-11 AND Blue Equipment Status Tag.

WV DV DOUBLE VERIFICATION 3.3 At panel *0C633 (Bay A) INSTALL a jumper from C51A-Z2B TB7-10 to C51A-Z2B TB7-11 AND Blue Equipment Status Tag.

WV DV DOUBLE VERIFICATION 3.4 At panel *0C633 (Bay B) INSTALL a jumper from C51A-Z2D TB7-10 to C51A-Z2D TB7-11 AND Blue Equipment Status Tag.

WV DV Attachment Page 3 of 25

M-041-200 Rev. 14 Page 113 of 121 REFUEL FLOOR HVAC HI-RAD JUMPER INSTALLATION/ARM REMOVAL FROM SERVICE NOTE: The following step ensures the requirements of Tech Spec (T.S.) 3.3.7.1 are met.

4.0 ENSURE Radiation Protection is performing ST-0-027-640-*,

INOP Fuel Floor criticality Area Radiation Monitors.

Person Contacted WV NOTE: The following steps removes Refuel Outage Unit ARM RIS30-MI

• K600, Steam Separator Area El 352, ARM RIS33-Ml-*K600, Pool Plug Laydown.Area El 352, AND ARM RIS29-M1-*K600, D/W Head Laydown Area El 352 from service AND requires entry into TS LCO 3.3.7.1.

DOUBLE VERIFICATION 5.0 At Auxiliary Equipment Room Panel *0C605 PLACE mode switch for ARM RIS30-MI-*K600, Steam Separator Area El 352, to "ZERO" position AND INSTALL Blue Equipment Status Tag referencing this procedure AND applicable step.

WV DV DOUBLE VERIFICATION 6.0 At Auxiliary Equipment Room Panel *0C605 PLACE mode switch for ARM RIS33-MI-*K600, Pool Plug Laydown Area El 352, to "ZERO" position AND INSTALL Blue Equipment Status Tag referencing this procedure and applicable steps.

WV DV DOUBLE VERIFICATION 7.0 At Auxiliary Equipment Room Panel *OC605 PLACE mode switch for ARM RIS29-MI-*K600, D/W Head Laydown Area El 352, to "ZERO" position AND Blue Equipment Status Tag referencing this procedure and applicable steps.

WV DV Attachment 2 Page 4 of 5

M-041-200 Rev. 14 Page 114 of 121 REFUEL FLOOR HVAC HI-RAD JUMPER INSTALLATION/ARM REMOVAL FROM SERVICE As applicable, INFORM Shift Management that the following 1 8.0 actions are complete:

1. Refuel Floor HVAC High Radiation Isolation AND Refuel Floor High Radiation Primary Containment Isolation AND the Barrier Block AND Vent Actuation has been defeated.

2. ARM RIS30-MI-*K600, Steam Separator Area El 352, AND ARM RIS33-MI-*K600, Pool Plug Laydown Area El 352, AND ARM RIS29-MI-*K600, D/W Head Laydown Area El 352 are removed from service.

3. Radiation Protection is performing ST-0-027-640-* INOP Fuel Floor Criticality Area Radiation Monitors.

Person Contacted WV 9.0 INFORM Refuel Floor Coordinator High-Rad Jumpers are installed AND/OR ARMs are removed from service.

Person Contacted WV Attachment 2 Page 5 of 5

AtacmepEXELON NUCLEAR a Gi Attachment Equipment Status Tag Grading Guide Minimum Entries are circled ANSWER KEY

I *EXELON NUCLEAR Equipment Status Tag I .. -.

"SYSTEý" -M

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• UB w-t (3)~~

i P.O" Su .* .:O  : ::!::::!*:'*::.E-* !,*:

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Spare Sample Tag CANDIDATE!-