ML13309A398

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Temporary Change Notice 1-2 to Rev 1 to Maint Procedure S01-I-3.2, Crane - Spent Fuel Bridge Crane Checkout & Operation
ML13309A398
Person / Time
Site: San Onofre Southern California Edison icon.png
Issue date: 02/28/1989
From: Sheeks K
SOUTHERN CALIFORNIA EDISON CO.
To:
Shared Package
ML13309A397 List:
References
S01-I-3.2, S1-I-3.2, NUDOCS 9312030249
Download: ML13309A398 (18)


Text

SDMS No.:

(1 Appicabie)

REFERENCE:

SO123-VI-1.0.1 TEMPORARY CHANGE NOTICE Page 1 of FOR CDHf USE ONL Y:

) aFEB 2D8 St Single Use TCN Cancels On:

DaleNo Copy forwarded to the Nuclear Safety Group. PERFORMED BY:

Dat e:

TECHNICAL SPECIFICATION VIOLATION IF NOT COMPLETED WITHIN 14 DAYS Site Document No.-

Revision No.

Single Use TON: YES El NO Site Document Title 1

PREPARED BY:_

i L

-51_7360____414

_M ORGINATOR ODF "ME ORGANIZATION 2

If required, TCN Deviation Approval. APPROVED BY:

on___

co__so_____DAT__

TIME CFDM (or designee)

SIGNATUH.

F Of TELECON PRINT NAME -0 SO STATE DATETIME

3. Checd appropriate box: D Entire Document Attached i

Afected Page(s) Attached

(

ECEVEP r UEC Superseded/Incorporated TCN(s).

kilt 1

(No applcable GLE USE TCNs)

INO hr1 NON.

so GTE.V

4. This change cannot wait until the next revision of the Site Document and is required.

FEB 2 8 689 A

=

To implement facility design change (PFC, NCR. TFM. etc.)

§ITE FILE COPY Facility design change identifier tNitCA1 E PFC. NCR TrM ETC IDENTIFIER if NO, a TCN cannot be approved uti the Implementation of the tacility design change has been determined YESO NO ility design change has been implenteted.)

B.

Other (e.g., CAR, NRC Commitments)

Specific Reason:

5DC1k FSV

,2L6 i

L Descipin of Chnge~s Reeso~do R

Peu0e)APed o.3 A

)

r.F7; an.

5 Is the document being TCN d OA Affecting?

YESK NO D (If YES, complete the boxes below.)

(if NO. see' below.)

(This is indicated on the Table of Contents page of the Site Document. If not indicated, treat as OA Affecting.)

A Does this change affect FSAR or Tech Spec. commitments?

swy bnispplied, h is prein usd t coTc tion Oia B, Does this change affect the nontadiological environment of any off site area previousl unitreYuigst rprtinadpatcntuto'ES O rmay C Is the intent of the original document altered" YESO Ns E.~ ~

Dosti hn e

oos anurvee a qetio e 10 CI 059. 1e.,does it increase ithe procability of accurrence or the con sequences of an

<cs O se5 accident: create the possibility of a difieent accident: or reduce th Aeh Sc rgi Ef,sanofathoizd.

6Aecanges beiing made to numercaldata, or is neEG da8 hen aple.tas aen ueud

t.

promTcnia Specification Surveillance testing?

YES E]

NO 9 i"YES. Form EG(1 23) 16 attached.

A TICN Is NOT authorized until a Technical Divison review is obtained.

7. The entire document was reviewed in conjunction with this TCN and found to be acceptable as written. This constitutes an annual/biennial review disposition of Acceptable As Written-Extend (SO123-VI-1.0.2).

REVIEWED and APPROVED BY:___

CFDM OR OESiO4EE 8 For SPG Use Only.

Is OA/OC Review/Approval Required?

YES O NO*

. Note: Utilize current QAO Procedure Review/Approval Waiver List to respond.

  • If to, eter WA on the Ouany Assurance Review/Approva Ie below.

PERFORMED BY:

SPG DATE 9 Signatures Required:

INITIAL APPROVAL r

REVIEW-,p(t PED.BY:

ilaseioneU SRO zqthe I

-r

1) i
2) lLNT MANAGEMENT STA57F UNIT DA TE T.C PLANT kIANGElvENI &T.-'

U-TS 2533 nD.tF t

Could this TCN affect or does it represent a change to a plant Could this TCN affect or does it represent a change to a plant oper iont ro ess?

YES-NO operation in progress?

YES..

NO 4)

.o UNITI b

1 E

11M SRC JNITS2&3 REVIEWED and APPROVED BY:

FINAL APPROVAL

5)
6) 5)CGNIZAN7 FUNCTIONAL DIVISION MANAGER DA 6)QUALITY ASSURANCE UNITS I 2 AND 3 DATE Iad, tIroertis No CA Afecting obtain iitial approval irom the Cognizant SuoervsortsI on the aiected unrts (signs Plant Manageet staff itrets!) and final approval from the CF0M pror to submittal to S

CoIJ. NT other sinaftures are required F CA A te tirg. asignate s be b i member of he Plant manae ei staff and ore SPO Lcensed on the u rnt or units aftected tFor TCN approval nemoers of the Plant Management Stalf are aelineo Aq he sucarvisor inchargedt tie stuff or as designated In wting by fie CF

c.

exercrs ng reSpoS ni4 io the Swecific area and unitts adcessed by the charge I C

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m. hsirIRwinterdeni shall roode the IeQuIre SRO approva(

9312030249 931123

'i PDR ADOCK 05000206 P

PDR

NUCLEAR GENERATION SITE MAINTENANCE PROCEDURE SOl-I-3.2 UNIT I REVISION 1 PAGE 1 OF 17 EFFECTIVE DATE TCN CRAE SEN FELBRIDGE CRANE CHECKOUT-ANDOP ERATION T-ABLE OF CONT-ENTS SECTION PAGE 1.0 OBJECTIVE 2

2.0 REFERENCES

2 1 2.1 Procedures I

3.0 PREREQUISITES 3

4 4.0 PRECAUTIONS 5

5.0 CHECKLISTS 5

6.0 PROCEDURE 5

6.1 Visual Preoperational Inspection 6

6.2 Functional Preoperational Testing 7

6.3 Spent Fuel Crane Operation 9

6.4 Removing Crane From Service 12 6.5 Restoration 12 7.0 RECORDS 13 ATTACHMENTS I

Special Tools 16 2

Spent Fuel Bridge Crane Service Area 17 1700a.aut QA PROGRAM AFFECTING

NUCLEAR GENERATION SITE MAINTENANCE PROCEDURE 2OF-1-3.2 UNIT 1 REVISION 1 PAGE 2 OF 17 CRANE

-SPENT FUEL BRIDGE CRN CHCOTAD OPERATION 1.0 0BJECTIVE 1.1 This procedure provides preoperational checkout operating instructions and prior to use visual inspection requirements.

2.0 REERE N CE S 2.1 Procedures1 2.1.1 S0123-1-1. 3, Maintenance Documentation 2.1.2 S0123-1-1.18, Foreign Material Exclusion/Inventory Controls During Maintenance, Testing and Inspection Acti vities 2.1.3 50123-1-7.14, Maintenance and Inspection of Cranes 2.1.4 S0123-1-1.1 3, Cranes, Rigging and Lifting Controls 2.1.5 SOI-1-3.35, Foreign Material Control During Refueling

NUCLEAR GENERATION SITE MAINTENANCE PROCEDURE S01-1-3.2 UNIT 1 REVISION 1 PAGE 3 OF 17 TCN

/

3.0 PREREQUISITES 3.1 Prior to use of a user-controlled copy of thi s procedure, it is the user's responsibility to verify C.

that the revision and any TCN's are current by utilizing one of the following methods:

3.1.1 Check it against a COM controlled copy and any TCN's.

3.1.2 Access the SCE Document Configuration System (SDCS).

3.1.3 Contact CDM by telephone or through counter inquiry.

3.1.4 Obtain a user-controlled copy of this procedure from CDM.

3.1.5 Reference a current (within one week)

Configuration Control Log and associated daily update.

3.2 A calibrated load cell (minimum 2000 lbs) is required which has a valid calibration which exceeds the expected duration of these activities.

3.3 Foreign Material Exclusion/Inventory Controls have been established in accordance with S0123-I-1.1S, Foreign Material Exclusion/Inventory Controls During Maintenance, Testing and Inspection Activities or SOI-1-3.35, Foreign Material Control During Refueling or as directed by the applicable Maintenance Order.

3.4 Conduct Tailboard meeting to discuss prerequisites, precautions and procedure.

3.5 The Prerequisites in this procedure have been satisfied, or if this procedure is not performed in a continuous manner and a shift change has occurred, the prerequisites shall be verified.

--VERIFIED BY Date~

VERIFIED BY Date Y-gIFlDBY ateVER ED BY Date VERIED BY

/Date VERTFIED BY

NUCLEAR GENERATION SITE M4AINTENANCE PROCEDURE SOl-I-3. 2 UNIT 1 REVISION 1 PAGE 4 OF 17 TCN 4.0 PRECUIN 4.1 Extreme care must be exercised to minimize exposure (ALARA) of all personnel per S0l23-VII-3.0, Alara Job ITCN Review. Radiological hazards and requirements identified on the Radiation Exposure Permit shall be observed.

4.2 The Spent Fuel Bridge Crane shall not be loaded beyond its rated capacity except for test purposes or special lifts as described in S0123-I-7.14, Maintenance and ITCN Inspection of Cranes.

4.3 Before moving the Spent Fuel Bridge Crane, check for any obstruction that would interfere with the safe operation or cause damage to the crane, fuel assemblies or storage racks.

4.4 When not in use, the Spent Fuel Bridge Crane shall be parked over the Upender Cavity.

4.5 Heavy loads greater than 1500 lbs shall not be lifted or transported over Spent Fuel in the Spent Fuel Pool.

4.6 Do not bypass, override or exceed any crane limits or interlocks unless directed to do so by a written procedure or on orders of the Refueling Engineer!

TC Refueling Shift Supervisor and Operating Deck SRO in anTC Emergency situation.

Upon completion of this activity restore all limits and/or interlocks.

4.7 Limit switches are to serve solely as a backup rather than as the primary means for stopping travel.

It is

,the crane operators responsibility to stop the travel prior to reaching its limit.

4.8 Prior to lowe ring a fuel assembly intoth opent Fuel Racks or upender, visually verify that the storage location or upender is free from obstructions (i.e.

other fuel assemblies, fuel-cell-like containers, debris, etc.).

NUCLEAR GENERATION SITE MAINTENANCE PROCEDURE S01-1-3.2 UNIT 1 REVISION 1 PAGE 5 OF 17 5.0 HECL2IST 5.1 Data taken during this maintenance action shall be recorded in the body of this procedure.

5.2 Record the following information in the procedure:

5.2.1 Discrepancies discovered during the performance of this maintenance procedure.

5.2.2 Identification and documented approval for any equivalent consumable material used during the performance of this procedure.

5.3 Documentation of pre-operational checks is not required unless specifically called for in a procedure applicable to the lifting activity such as during refueling.

6.0 PROCEURE NOTES: 1. Discrepancies discovered shall be reported to these responsible Maintenance Supervisor.

This supervisor shall ensure that these discrepancies C

are properly documented in accordance with 50123-1-1.3.

2. All lifting and rigging activities shall be performed in accordance with S0123-1-.1 3.
3. During refueling outages this and the procedures referenced here may be incorporated into the Refueling Manual.

These procedures may be implemented in part or whole depending on the sequence of events.

The refueling may necessitate resequencing sections/steps (including those containing QHP's) or the performance of only specific sections/steps which apply to the intended evolution/refueling activity.

The Refueling Supervisor is responsible for verifying that the resequencing of steps including QHP's will not prevent the QHP from being completed in the revised sequence.

4. A heavy load is defined as any load suspended from the hook whose weight is greater than 1500 pounds, excluding the weight of the lifting device and/or rigging.

NUCLEAR GENERATION SITE MAINTENANCE PROCEDURE S01-1-3.2 NuT 1 REVISION PAGE 6 OF 17 UNIT 1 TCN

/I 6.0 PROCEDURE (Continued)

NOTES: 5. Ensure that Riggers are qualified in accordance with S0123-I-7.23, Qualification and Certification of Rigger.

6. Loads in excess of 1500 lbs shall be prohibited C

from travel over fuel assemblies in the Spent Fuel Pool.

6.1 perai 1 InsDectiSA NOTE:

Visual Inspection shall be performed prior to the lifting activity.

Visual inspection is not required prior to each lift performed during the same maintenance activity, but is recommendedsduring successive lifts of heavy loads.

6.1.1 Inspect the crane hooks.

ACCEPTANCE CRITERIA:

No deformation, visible cracks or latch mechanism damage (if latch is provided).

SAT UNSAT

-- ygygg -I

-- -- t

~ORM!DIY flate 6.1.2 Inspect readily accessible portions of wire rope and drum reeving.

ACCEPTANCE CRITERIA:

No excessive wear, broken wires, heat

damage, kinking, twisting, corrosion, and ropes properly reeved.

SAT

_UNSAT

-- ERFORM Ei BY Date

NUCLEAR GENERATION SITE MAINTENANCE PROCEDURE SoI-1-3-2 e UNIT-1 REVISION 1 PAGE 7 OF 17 UNIT 1 TCN

/

6.0 PROCEDURE (Continued) 6.1.3 Visually inspect control cables.

ACCEPTANCE CRITERIA:

No excessive wear or damage.

SAT __

_ UNSAT -

RFOW RMlED BY Date 6.2 Functoa Proeaifal Testing NOTES: 1. Functional testing shall be performed prior to any activity involving lifts of New Fuel, Spent Fuel, heavy loads greater then 1500 pounds or as determined by the Refueling Supervisor.

2. All discrepancies found during performance of Section 6.1 must be dispositioned before functionally testing the affected component in Section 6.2.

6.2.1 Have Operations.shut the 480V circuit breaker for the Spent Fuel Bridge Crane.

Control Operator N ame VERtI TIS5BY Date 6.2.2 Energize Crane by depressing "START" pushbutton on Crane Control pendant.

NUCLEAR GENERATION SITE MAINTENANCE PROCEDURE SOF1-3.2 UNI 1REVISION 1

PAGE 8 OF 17 UNIT 1 TCN 6.0 PROCE-DURE (Continued) 6.2.3 Verify the Hoist Control and High Hoist Limit.

.1 Depress the "DOWN" pushbuttton on the control p endant.

Lower the hook to several inches above the water level and then raise it to an elevation above the fuel storage racks.

.2 Depress the "UP" pushbutton on the control pendant.

Raise the hook until the "UP LIMIT" stops movement.

6.2.4 Check trolley control as follows:

.1 Move trolley through full travel using manual drive chain.

Ensure freedom of mo-vement and that trolley can reach North and South stops.

gT L2 There are no limit.switches to limit EAST or WEST bridge travel.

Spent Fuel Bridge should be operated in the "JO" mode only, when within 2' of bridge rail stop.

6.2.5 Check the bridge controls as follows:

NOTES: 1. Refer to Attachment 2.

2. For jogging operation use "JOG" pushbutton instead of "RUN" pushbutton.

.1 Move bridge East by depressing and holding the "FORWARD" pushbutton.

For slow speed operation of the bridge, depress the pushbutton until the drive motor starts in slow speed.

For fast speed operation depress the pushbutton further until the drive motor shifts to fast.

Releas.e the pushbutton to stop bridge movement.

NUCLAR GNERAION ITEMAINTENANCE PROCEDURE oi-I-3.2 NUCLEAK ENTIOl ST REVISION 1 PAGE 9 OF 17 UNIT 1 TCH N

6.0 PROCEDURE (Continued) 6.2.5.2 Move bridge West by depressing and holding the "REVERSE"' pushbutton.

For slow speed operation of the bridge depress the pushbutton until the drive motor starts in.

slow speed.

For fast speed operation depress the pushbutton further until the drive motor shifts to fast.

Release the pushbutton to stop bridge movement.

6.2.6 Functional Preoperational Testing completed and crane is ready for service.

P ERFORHE

~ Y Date 6.3 Soent Fue Crn Orton Do not operate the bridge while raising or lowering the hoist.

Ensure that sufficient clearance exists between a suspended tool or assembly and structural components in the Spent Fuel Pool before movingthe bridge or trolley.

There are no limit switches to limit EAST or WEST bridge movement. Therefore, bridge should be operated in OJ06" mode only, when within 2' of rail stop.

6.3.1 Lift any load and ch eck for proper operation of the hoist brake by suspending the load 1/4" and holding for 5 minutes.

NUCLEAR GENERATION SITE MAINTENANCE PROCEDURE SOl-1-3.2 UNT 1 REVISION 1 PAGE 10 OF 17 UNIT 1 TCN

/

6.0

(

(Continued) 6.3.2 Bridge Movement NOTE:

The bridge drive has no manual operation features.

If the bridge drive should become inoperative while moving a Fuel/Dummy Assembly the supervisor of Nuclear Fuel Services and the Supervisor of Plant Maintenance must make an evaluation to ensure that this operation will not further endanger the Fuel/Dummfly Assembly or personnel.

.1 Move bridge East by depressing and holding the "FORWARD" pushbutton.

For slow speed operation of the bridge, depress the pushbutton until the drive motor starts in slow speed.

For fast speed operation depress the pushbutton further until the drive motor shifts to fast.

Release the pushbutton to stop bridge movement.

.2 Move bridge West by depressing and holding the "REVERSE" pushbutton.

For slow speed operation of the bridge depress the pushbutton.until the drive motor starts in slow speed.

For fast speed operation depress the pushbutton further until the drive motor shifts to fast.

Release the pushbutton to stop bridge movement.

NUCLEAR GENERATION SITE MAINTENANCE PROCEDURE SOI-1-3.2 UNIT 1 REVISION 1 PAGE 11 OF 17 TCN 6.0 PROCEDURE (Continued) 6.3.3 Trolley Movement CUTION n

If the trolley drive should become inoperative while moving a Fuel/Dummy Assembly the Supervisor of Nuclear Fuel Services and the Supervisor of Plant Maintenance must make an evaluation to ensure that this operation will not further damage the Fuel/Dummy Assembly or personnel.

Do not operate the trolley while raising or lowering the hoist..

CAUTION Visually ensure that clearance exists between a suspended load and structural components in the Spent Fuel Pool before moving the Trolley.

.1 Move the trolley North or South by pulling the manual drive chain.

6.3.4 Hoist Operation NOTE:

The "UP" limit switch on the Spent Fuel Bridge Crane hoist provides at least 6" of clearance between the bottom of a fully raised fuel assembly and top of the upender carriage (or fuel racks).

CAUION Do not operate the hoist while moving the bridge or trolley.

.1 Raise the hoist by depressing and holding the "UP" pushbutton.

For slow operation of the hoist depress the pushbutton until the hoist motor starts in slow.

For fast speed operation depress the pushbuttonfurther until the hoist motor shifts to fast.

Release the pushbutton to stop the hoist.

NUCLEAR GENERATION SITE MAINTENANCE PROCEDURE S0l-I-3.2 UNIT 1 REVISION 1 PAGE 12 OF 17 TCN 6.0 PROCEDURE (Continued) 6.3.4.2 Prior to lowering a fuel assembly into the TON spent fuel racks or upender, visually verify the rack location or upender is unoccupied and free from obstructions.

6.3.4.3 Lower the hoist by depressing and holding the "DOWN" pushbutton. For slow operation of the hoist depress the pushbutton until the hoist motor starts in slow. For fast speed operation depress the pushbutton further until the hoist motor shifts to fast.

Release the pushbutton to stop the hoist.

6.4 Removing The Crane From Service 6.4.1 When operations with the Spent Fuel Bridge Crane are completed, secure as follows:

.1 Raise the hoist to the full up position.

.2 Position the bridge above the upender walkway.

.3 Open the local controller by depressing the "STOP" button.

PERFORMED BY Date 6.5 Restoration 6.5.1 The Shift Refueling Supervisor shall sign the associated Maintenance Order, if applicable, and Section 7.3 of this procedure to verify that the Maintenance Activity has been completed.

6.5.2 Notify Operations that the maintenance evolution has been completed.

NUCLEAR GENERATION SITE MAINTENANCE PROCEDURE S01-1-3.2 UNIT 1 REVISION 1 PAGE 13 OF 17 TCN 7.0 REORDS 7.1 Measurif n d TetEqimnt Used in this procedure Description

.5 Description

.1 ID Number ID Number Range--

Range Cue Cal Due Date Cal Due Date

.2 Description

.6 Description -----------

ID Number Range Range

-al Due Date Cal Due Date

.3 Description ---.

7 Description ID Number ID Number Range Cal Due Date-----------

Cal Due Date

.4 Description -------------

.8 Description-----------

D Number IDanumer Range Rangee Cal Due Date Cal Due Date 7.2 Consumable-Material Eivlet Use i h tis cdr Supervisor Approval Material Specified Equivalent Used Signature


7------- -------------------- ---------

NUCLEAR GENERATION SITE MAINTENANCE PROCEDURE S01-1-3.2 UNIT 1 REVISION 1 PAGE 14 OF 17 TCN iI 7.0 RECORDS (Continued) 7.3 The Remark(s) Form of this section shall be used to record the following:

7.3.1 Discrepancies discovered during the performance of this Maintenance Procedure, and corrective actions init iated 7.3.2 Remark(s) Form REMARKS, DISCREPANCIES AND CORRECTIVE ACTIONS:

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

N UCLEAR GENERATION SITE.

MAINTENANCE PROCEDURE S01-1-3.2 UIT 1

-REVISION 1

PAGE 15 OF 17 UNIT 1

TCN 7.0 RECORDS (Continued) 7.4 Package eview/Data Documentation 7.4.1 This procedure shall be signed by the of immediate supervisor indicating completion of C

the maintenance activity and completeness of the documentation.

7.4.2 The Shift Refueling Supervisor shall review data, signoffs and remarks in the procedure.

He shall ensure that discrepancies have corrective actions initiated and documented.

7.4.3 The Refueling Supervisor shall approve the completed procedure and forward the entire work package, including the procedure, attachments and "Maintenance Order(s)", if applicable, to CDM per 50123-1-1.3, Maintenance Documentation.

DATE:--------

Ic PERFORMED BY:

IMEIATE SERTE-DATE:------

REVIEWED BY:

DATE:PpyVyp DATE:------

APPROVED BY:

_ _U IG 1700a.aut

NUCLEAR GENERATION SITE MAINTENANCE PROCEDURE r01-1-3.2 UNIT 1 REVISION 1 PAGE 16 OF 17 TCN SEILTOOLS 1.Load Cell (Minimum 2,000 pounds)

ATTACHMENT I PAGE 1 OF 1 1700a.aut

GENEATIO REVISION 1 PAGE 17 OF 17 ATTACHMENT 2 TCN SPEN

,ULBRIDGE CRANE SERVICE AREUA East Cask Washdown Area Walkw YsUp der Cavity

-Gat s

West 1700a~~~aut ATTACHMENT 2.

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