ML20134G701

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Summary of 970122 Meeting W/Util Re Program for Replacement of SG at Licensee Facilities.List of Attendees & Matl Used in Presentation Encl
ML20134G701
Person / Time
Site: Byron, Braidwood  Constellation icon.png
Issue date: 02/07/1997
From: Dick G
NRC (Affiliation Not Assigned)
To:
NRC (Affiliation Not Assigned)
References
NUDOCS 9702110008
Download: ML20134G701 (92)
v • d • e


Text

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,f* ~*% y (93 e i UNITED STATES j j 2

NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20eeH001

[O4/9/ 2/O

...../ February 7, 1997 LICENSEE: Commonwealth Edison Company (Comed)

FACILITIES: Byron Station, Unit 1 and Braidwood Station, Unit 1

SUMMARY

SUMARY OF STEAM GENERATOR REPLACEMENT MEETING - JANUARY 22, 1997 I

On January 22, 1997, the staff met with Comed to discuss its program for replacement of the steam generators (SG) at Byron 1 and Braidwood 1. This i meeting was the fourth in the series initiated by Comed to keep the staff informed of the status of its SG replacement program. A list of attendees is

. provided as Enclosure 1. A copy of the licensee's presentation is included as Enclosure 2.

4 The objectives of the meeting were to: (1) update the schedules for the Byron SG replacement; (2) provide the conclusions and results of their licensing evaluation; (3) provide an update on open items related to the containment opening; and (4) discuss the plans for the removal of the old SGs and installation of the new ones.

With regard to the schedule, Comed informed the staff that construction of the SGs is progressing ahead of schedule to the extent that the Byron SG replacement cutage will begin on November 7,1997. The plant will not take a full outage prior to November, but will have a short outage in the summer to remove grease from selected tendons (pending staff approval) and complete a few critical pre-outage activities. The Braid

  • od SG replacement outage is still scheduled to begin in September 1998. The licensee has identified 10 issues that require NRC review. The last one will be submitted for staff review by May 2, 1997. Three have already been submitted and are under review.

Several followup items from the previous SG replacement meeting (August 21, 1996) were addressed. Work is continuing using the 3-D containment model for predicting containment behavior for the various containment configurations to l

be encountered during the project (e.g., detensioning tendons, cutting the hole in the side of containment, etc.). The work is expected to be completed 5 and available for a followup audit by the staff in May 1997. The initial audit and discussions were held on November 18, 1996. The licensee clarified [

its plan for defueling during the outage by stating that all fuel would be {

removed from the reactor vessel and placed into the spent fuel pool before removal of containment concrete is started.

100048 W MEM M 9702110008 970207 DR ADOCK0500g4

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Planning for removal of the old SGs, and receiving, handling and installing of the new SGs appear to have considered the major areas of interest to the staff. The staff informed the licensee that inspectors will be monitoring the SG replacement activities, and auditir.g selected 10 CFR 50.59 evaluations.

Original signed by:

George F. Dick, Jr., Project Manager

  • Project Directorate III-2  :

Division of Reactor Projects - III/IV '

Office of Nuclear Reactor Regulation Docket Nos. STN 50-454, STN 50-456 l

Enclosures:

1. List of Attendees
2. Licensee's Presentation cc w/encls: see next page ,

i DISTRIBUTION w/enci'1 &"2: E-Mail w/ encl 1:

Docket

~

F. Mira~ glia /A. Thadani ,

PUBLIC 'R. Zimmerman  !

l PD3-2 r/f, J.- Roe (JWR)

OGC 015-B18e 'R. Capra (RAC1)

ACRS T2-E26 Bt McCabs (BCM)

G. Dick (GFD) .

C.' Moore (ACM) l R. Lanksbury (RDL) D. Ross (e-mail to SAM)

E. McKenna (EMM)

Lee'Banic (MJB)

Robert Rothman (RLR)

_ John Ma (JSMI)

. Chu-yu Liang (CYL)

- Jai Rajan (JRR)

Melvin Holmberg (MSH)

Mohammed Shuaibi (MAS 4)

Ramin Assa (RRA)

M. David Lynch (MDL) l G:\CMNTJR\ BRAID-BY\0122975C. SUM l l T3 receive a capr of this dactamnt, indicatafin the bos: "C" " Copy without enclosures "E" " Copy with enclosures "N" " No copy l OFC PM:PD3-2 , F LkPE-2 C D:PD3-2 &

NAME GDICK k./d CbORE RCAPRA &

DATE 2 /r,6 /97 / d/6 97 / 1 / 7 /97  !

0FFICIAL RECORD COPY

Byron /Braidwood Power Stations cc:

Ms. I. Johnson Mrs. Phillip B. Johnson Acting Manager, Nuclear Regulatory Services 1907 Stratford Lane Commonwealth Edison Company Rockford, Illinois 61107 Executive Towers West III .

1400 Opus Place, Suite 500 George L. Edgar l l Downers Grove, Illinois 60515 Morgan, Lewis and Bochius l 1800 M Street, N.W.

Mr. William P. Poirier, Director Washington, DC 20036 Westinghouse Electri: Corporation Energy Systems Business Unit Ms. Bridget Little Rorem Post Office Box 355, Bay 236 West Appleseed Coordinator Pittsburgh, Pennsylvania 15230 117 North Linden Street Essex, Illinois 60935 Joseph Gallo Gallo & Ross Attorney General 1250 Eye St., N.W. 500 South Second Street Suite 302 Springfield, Illinois 62701 Washington, DC 20005 EIS Review Coordinator Michael I. Miller, Esquire U.S. Environmental Protection Agency Sidley and Austin 77 W. Jackson Blvd.

One First National Plaza Chicago, Illinois 60604-3590 Chicago, Illinois 60603 Illinois Department of Howard A. Learner Nuclear Safety Environmental law and Policy Office of Nuclear Facility Safety Center of the Midwest 1035 Outer Park Drive i 203 North LaSalle Street Springfield, Illinois 62704 l Suite 1390 Chicago, Illinois 60601 Comonwealth Edison Company Byron Station Manager U.S. Nuclear Regulatory Comission 4450 North German Church Road Byron Resident Inspectors Office Byron, Illinois 61010 4448 North German Church Road Byron, Illinois 61010-9750 Kenneth Graesser, Site Vice President Byron Station Regional Administrator, Region III Comonwealth Edison Station U.S. Nuclear Regulatory Comission 4450 N. German Church Road 801 Warrenville Road Byron, Illinois 61010 Lisle, Illinois 60532-4351 U.S. Nuclear Regulatory Comission Ms. Lorraine Creek Braidwood Resident Inspectors Office Rt. 1, Box 182 Rural Route #1, Box 79 Manteno, Illinois 60950 Braceville, Illinois 60407 Chairman, Ogle County Board Mr. Ron Stephens Post Office Box 357 Illinois Emergency Services Oregon, Illinois 61061 and Disaster Agency 110 East Adams Street Springfield, Illinois 62706

l Chairman Will County Board of Supervisors l Will County Board Courthouse Joliet, Illinois 60434 Commonwealth Edison Company Braidwood Station Manager Rt. 1, Box 84 Braceville, Illinois 60407 Document Control Desk-Licensing Connonwealth Edison Company 1400 Opus Place, Suite 400 Downers Grove, Illinois 60515 Mr. H. G. Stanley Site Vice President Braidwood Station Commonwealth Edison Company RR 1, Box 84 Bracemille, IL 60407 l

l l

4 LIST OF MEETING ATTENDEES JANUARY 22, 1997 NBC Robert Capra <

Eileen McKenna Lee Banic Robert Rothman John Na 1

Chu-yu Liang Jai Rajan 4 Melvin Holmberg Mohammed Shuaibi Ramin Assa

, M. David Lynch  !

George Dick Commonwealth Edison Daniel Shamblin David Rogowski David Lippard Sam Mullins
Jerald Wagner Gerald Groth Mark Leutloff Robert Moravec Marcia Lesniak

, Denise Saccomando Bechtel Charles Weaver Andrew Matyas Frank Wilks

, Brian Reilly Cal Reid Kenneth Clough Eugene Thomas Dave Drulard Farhad Farzam McGraw-Hill David Stellfox STS. Inc.

Deann Raleigh Baltimore Gas & Electric Getachew Tesfaye a

5 Enclosure 1

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Byron /Braidwood Steam Generator Replacement Project ,

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Presentation to the l Nuclear Regulatory Commission i

January 22,1997 r

i Enclosure 2 l l

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Co Ed .

i Byrori/Braidwood Steam Generator Replacement Project Presentation to the Nuclear Regulatory Commission January 22,1997 i vvtsemuu.toeisseimi 1-1

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/nB n/Braidwood t m GeneratorReplacementProject Introduction )

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Dan Shamblin SGR Project Manager

Ob ctives

'a

+ Update NRC on Project Schedule - Byron Outage Acceleration

+ Provide the conclusions and results of our licensing ,

determination process

+ Provide an update on August 21,1996, meeting open items related to the reactor containment opemng

+ Review the steam generator handling and removal engineering and installation work I

v*tstancou EcoteseiPPn 1-3

._-_______ _ __-______- ____ - _ _ __ - _ - - _ _ -_ _ _ ___ _ __ _ -__ _ _ _ - _ ___ _ _l

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Ag da .

1. Introduction / Objectives D. Shamblin
2. Project Schedule - Byron Outage Acceleration D. Shamblin i
3. Licensing Determination Process Conclusions D. Rogowski i and Results
4. Open Items - Containment Opening A. Opening / Closure Schedule Development J. Groth B. Containment Opening Analysis / Restoration F. Farzam I

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Ag da (cont.) .

5. S/G Handling and Removal Activities A. RSG Receipt and Preparation Work B. Moravec B. OSG Removal Preparation D. Drulard C. OSG Removal and Transport On-Site K. Clough D. RSG Installation, Welding and NDE D. Drulard E. Design Considerations M. Leutloff
6. Closing Remarks D. Shamblin

! WRESENTEM EDW14S01PPy 1-5

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" lfCo lusion .

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"SGRP continues to maintain its focus on nuclear safety in their engineering, licensing, and installation planning activities."

I I v=tscwrcou.ttetees ps'TI 1-6

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n/Braidwood -

! t m GeneratorReplacementProject l Proje^ct Schedule Byron Outage Acceleration I

Dan Shamblin SGR Project Manager i

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l BYRON /BRAIDWOOD STEAM GENERATOR REPLACEMENT PROJECT  ;

PROJECT SCHEDULE -LEVEL O 1996 1998 1997 1998 1998 OD TASK NAME Otr 4 Ott 1 l Ott 2 l Otr 3 l Otr 4 ott 1 l Qtt 2 l Ott 3 l Otr 4 ott 1 l Ott 2 l Otr 3 l Ott 4 Qer 1 l Ott 2 l Otr 3 l Qir 4 Otr 1 l Otr 2 l Otr 3 l Otr 4 91 FA8RICATION RELEASE 02 BASELINE STUDY j 03 OPTICAL TEMPLATING B/B l 94 RSO FABRICATION l SS - BYRON DELIVERIES l l 96 - BWD DELIVERIES l l 97 RSG ANALYSIS WORK 98 DETABLED DESIGN WORK l 99 CONSTRUCTION ENGINEERING .

l 10 LICENSING ACTIVITY l 11 SITE PREP ACTIVITY 12 BYRON l 13 -BWD  : .

l 14 N-1 OUTAGE 15 - BWD MOBILIZATION .

16 - BWD N-1 1* MOGIUZE - SOR OUTAGE

.4 -BYRON . l 19 -BWD l l 29 SOR OUTAGE 21 -BYRON l l 22 -BWD l j 23 PLANT DEMOBILIZATION l BYRON l l BWD l DATA DATE: 1115/1997 EAftLY DATE BAR: l l PROGRESS BAR: [dj .

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B n/Braidwood l t m Generator ReplacementProject l

e e e e Licensing Determination Pr_ocess

. Conclusions and Results Dave Rogowski SGR Project Engineer

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+ SG Engineering andLicensing

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+ Current schedule

+ Summarize activities since August 1996 presentation

+ Discuss conclusions reached i

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SG EngineeringSchedule .

f 1996 1997 1998 ,

Task Name Qtr4 Otr1 Otr2 Otr 3 Otr4 Otr 1 Otr2 Otr 3 Otr 4, Otr 1 Otr2 Otr3 Otr4 Otr 1 Detailed Design Work um ,

i j Fabrication Engineer:.73 l 3/2 ,

installation Engineering 1/1 .' '

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Licensing Determination 1/1 m-l 2/2  ; -

Licensing Review Pkg Preps 911 g l 5/2 ,

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NRC Review 11/;1 16 11/3 j Prepare Field Work Packages /7 , .

11/7 ,

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Braidw$od Replacement Outage S/5 m 12/7 I

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_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _______ ________ .___________________________-_________________v

Li sing Determination Effort-

'Co detedRigorousReview '

+ Preliminary Safety Evaluations

+ Licensing issues summary documents

+ Calculations and analysis reviewed for methods / approaches

+ Review of design and licensing basis documents

+ Independent technical experts 4

l WWESEMOW ED91483FPg 3-4

-_---_-___-_____-______--________--__---_________L

41 -

Co lusions

+ No unreviewed safety questions identified

+ Safety Evaluation process remains appropriate for the SGR project 4

+ Licensing packages have been identified

+ Licensing packages prepared to high quality standards I atstwnctw rooseesertl 3-5

, fh its ofLicensingDetermination r ess -

Submittal Request Reauired Licensina Reviews Units Date Date Containment Tendon Grease Removal By 1/Bwd1 11/4/%A 5/1/97 S/G Tube Rupture -Topical Report By 1,2/Bwd 1,2 11/13/%A 4/1/97 Code Case Relief 2142/2143 By 1/Bwd1 12/20/%A 5/15/97 Containment Peak Pressure Change By 1/Bwd 1 1/31/97 11/3/97 Containment Isolation Valves By1/Bwd 1 1/31/97 11/3/97 S/G Water Level Optimization By 1/Bwd1 2/14/97 11/3/97 Revision ofTS due to Degraded S/Gs By1/Bwd 1 2/28/97 11/3/97 Relief Request for Rebar Weld Repair By 1/Bwd 1 3/ 21/ 97 11/3/97 Pressure Temperature Limit Reports By 1,2/Bwd 1,2 3/27/97 11/3/97 Ultimate Heat Sink By 1,2 5/2/97 11/3/97 g utstet:ou touteesprq 3-6 l

/h n/Braidwood t' m Generator ReplacementProject i

Opening / Closure -

Schedule Develop' ment-i i

Jerry Groth Braidwood Site Project Manager I i msenncou.tmoetorn 4A- 1 l

4 O ing/ Closure Schedule elopment

+ Explain challenges faced in schedule development

+ Review first 15 days of the replacement outage schedule l

l v'REKimCOM_EDe14601 PPT l 4A-2

dby ing/ Closure Schedule Opment GOALS  :

1ST PRIORITY

. + Maintain high degree of safety 2ND PRIORITY i

+ Optimi7e production efficiency and overall outage duration '

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Op ing/ Closure Schedule elopment CHALLENGES '

+ Erection of outside lift system

+ Tendon removal

+ Installation of containment opening

+ Closure of containment opening i

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! _.a Ere 'on of Outside Lift System .

CHALLENGE

+ Interaction of outside lift system with adjacent safety ,

related structures ,

APPROACH  ;

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+ Erect runway beam support structure and outside lift system support columns during pre-outage Mode 1 '

power operation  !

+ Complete erection of outside lift system once unit has reached Mode 5 cold shutdown i m_,., , - a-s l

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$[ Tenn Removal .

CHALLENGE

+ Potential tendon damage due to cold weather stiffening tendon grease APPROACH

+ Remove tendon grease during summer power operation i

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Te on Removal .

APPROACH

+ Develop new tendon gripper to improve removal without damaging tendon wires

+ Perform test of new gripper at Midland

+ Procure spare tendon wire as contingency ,

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f ntainment OpeningInstallation . ,

CHALLENGE

+ Maintain required containment integrity prior to completion of core off-load .

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APPROACH ,

+ Detension tendons once unit is in Mode 5 cold shutdown

+ Start concrete chipping after core off-load is complete i

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. Clo re of Containment Opening . i j i CHALLENGE i

+ Restore required containment integrity prior to core reload.

f APPROACH i

+ Reinstall liner to support ventilation requirements

+ Provide tornado missile protection i

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Byron / Braidwood SGR Outage Schedule

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Byron / Braidwood SGR Outage Schedule s.m ,_ ,# . mm , .

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Byron / Braidwood SGR Outage Schedule

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INSTALL RX INTERNALS / RX HEAD INSTALL RX CAVITY D ECKING

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START REMOVAL of SECONDARY PIPING MS/FW k .

SET UP and START CUTTING RCS PIPING START UNBOLTING 1 ST STEAM GENERATOR START REMOVAL of SIG SNUBBERS INSTALL TEMP SG LIFTING ,

SYSTEM ON POLAR CRANE c

REMOVE CONTAINMENT LINER PLATE REMOVE SG ULR

o-o INSTALL INSIDE CONTAINMENT RUNWAY 4 .

START RIGOUT of OLD S/Gs

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/}$ ing/ Closure Schedule l D lopment -

+-

SUMMARY

+ Approach to challenges meets our schedule development goals

+ High degree of safety maintained

+ Outage duration and production efficiency optimized i m--,.., m u_a

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! i n/Braidwood ,

l m Generator ReplacementProject l <

i l Containment Opening Analysis / Restoration Farhad Farzam Civil Structural Senior Engineer IPRESENTE:0M EDW1404 PFQ 48 - 1

4 Top s ofDiscussion .

+ Containment analysis follow-up issues .

+ Containment opening restoration -

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,s D ainment Analysis Follow-Up s es ,

Issues Discussed:

+ BSAP verification

+ Review of 3-D fmite element model

+ Review of analysis results Status:

+ SGRP believes BSAP verification and 3-D model issues are resolved

+ Review of analysis results in May 1997

[ 1rREsEsmCOM.EDW?#ee PFTl E~3

Re ~

ration - New Concrete . i

+ Original Concrete: 5500 psi at 91 days

+ New Concrete: 5500 psi at 7 days

/ Low creep concrete mix

/ Creep testing performed per ASTM C-512

+ Effects of concrete creep are taken into account in the containment analysis by introducing an effective modulus of elasticity for new and old concrete 48 - 4 t vnstmxw roewoe ren I

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>Res ration - Rebar Cadwelding .

+ General Background

/ ASTM A 615 (Grade 60), same material as original construction .

/ Cadweld splice between new and existing rebar

/ Rebar plays secondary role ,

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of' Res ration - Rebar Cadwelding (cont.)

+ Cadweld qualificellon

/ Consistent with original design / construction requirements

/ Participation of manufacturer's representative to train Cadweld operators

/ Cadweld operator qualification -

/ Visual inspection i

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eRes ration - Rebar Cadwelding (cont.)

+ Splice Testing i

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/ Sister splice testing in accordance with ASME Section III, Division 2

/ Previous SGR projects used sister splice testing i

1 48 - 7 I WWESENDCOMMi#OSPPfl

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Res ration - Rebar Repair .

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+ Concrete removal may nick rebar - perform base metal repair by i welding

+ Weld repair of rebar nicks has been used in previous SGR projects

+ iOCF,R50.55a invokes ASME Section XI for containment repair activities

+ Existing rebar has a carbon equivalent in excess of 0.55% - cannot comply with ASME Section III, Division 2

+ SGRP will ask relief per 10 CFR 50.55a(a)(3) to use AWS D 1.4-92

+ SGRP believes use of AWS Dl.4-92 provides an acceptable level of quality and safety

F

.d Res ration - Tendon Retensioning .

+ Measure lift-off prior to detensioning

+ Tendons will be re-tensioned to the required level of prestressing to maintain their design basis 40-year minimum prestressing force t wwstmxu roetasoe rrq 4B- 9

/*B n/Braidwood t m Generator ReplacementProject G Receipt and Preparation Work .

Bob Moravec Byron Site Project Manager SA - 1 I ntstm:cu.tosteesArvai

Top s ofDiscussion .

- ; 1.

+ SG Receipt and Inspection

+ SG Storage and Care While in Storage

+ SG On-Site Preparation Work i

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f. SG" eceipt andInspection .

+ Pre-delivery receipt inspection by Comed at BWI shop prior to transport

< Physicalinspection

< Documentation review and acceptance

+ Post-delivery receipt inspection on site

< Physical inspection - shipping damage

< Eddy current testing of selected tubes end to end Loose pWshipping damage

< ANI review and acceptance l PRESENDCOM.EDW1#05APPy M-3

+

Sto ge and Care While in Storage .

+ SG Delivery

< Transport to site on bolstered rail cars ,

< Hydraulic gantry offload from rail cars

< Move to NSGSF on hydraulic platform trailers ,

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Sto ge and Care While in Storage .

+ Establish F.ME controls ,

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< Cleanliness zones at points of entry

< Tube sheet protection

< Debris dams

+ Release nitrogen purge and remove manway covers i

+ Maintain shipping braces in-place until SG is set in containment i

i I WESONM_EN#UMPPn SA-5 i i

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SG n-Site Preparation Work .

+ Establish RCS nozzle rough cut lines and remove hydro caps

+ Prepare RCS nozzles for welding based upon templating ,

data i

+ Prepare secondary side nozzles for welding

+ Remove miscellaneous instrument and process line nozzle caps or plugs and prepare for field attachments i

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SG n-Site Preparation Work .

+ Weld FW elbows and pipe spools to SG nozzles

+ Perform preinstallation verification

< Upper lateral support restraint ring

< SG support feet bolt hole pattern

+ Install SG rigging attachments

< Two lifting trunions bolted to SG sides

< Pivot trunions bolted to SG support feet

+ Electropolish SG primary bowls l 1PRESOmCOM.EDW1405A PPn SA- 7 i

B n/Braidwood i m Generator ReplacementProject 1

l l

l u OSG Removal Pr~ epa. ration i .

Dave Drulard i

Site Services Manager

--___________...____.___________________________________________________________j

^ OS Preparation .

+ Insulation removal and sealing OSG surface

+ Temporary lateral support of SG support columns

+ Temporary lateral restraint of OSGs

+ Interference removal

/ Main steam whip restraints

/ Platform galleries

/ Steam generator upper lateral restraints / snubbers

+ RCS cutting

+ Secondary piping cutting and nozzle coverplating i msnmem tmme ppy 50 - 2

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Steam Generator Upper Lateral Restraints

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i m GeneratorReplacementProject 4

OSG Removal and Tran ort .

On Site Ken Clough Civil Structural Senior Engineer  !

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O.S Removal . .

+ Outside SG Rigging Features

/ Outside Lift System (OLS)

/ Outside Runway System

/ Hydraulic Platform Trailers

/ Heavy Haul Route i

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4?Y 4 OS Removal .

+ Outside Lift System (OLS)

/ Designed to rig SGs between the runway system and platform trailers

/ Load-tested two leg gantry with a hydraulic chainjack lift system

/ Anchored to a concrete foundation

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/(S O Removal .

+ Outside Runway System

/ Designed to transfer SGs from containment opening to OLS

/ Components Runway beam support structure (RBSS)

Outside runway beams and decking

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+ Heavy Haul Route

/ Established for roadway transport of OSGs to storage facility

/ Also used to transport RSGs

/ Primarily uses original plant construction haul routes g mstaxw toemescrrn SC -5

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-OS Removal .

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+ Inside SG Rigging Equipment

/ Material Handling System (MHS)

/ Auxiliary cranes

/ Inside runway system

/ Temporary lift device (TLD)

/ TLD hydraulic lifter i verstwitou_temmoscer9 $C-7

J L

/

OS Removal -

+ Material Handling System (MHS)

/ Designed to move equipment and materials into  ;

containment through the fuel handling building, auxiliary building, and equipment hatch t mumm.tceiememl SC-8

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OS .

Removal -

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+ MHS Components

/ Existing fuel handling building crane

/ Existing rail system along side spent fuel pool

/ Material handling cart with turntable I

/ Temporary raised track system through equipment hatch

/ Spent fuel pool FME barrier .

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+ Auxiliary Cranes

/ Designed to handle miscellaneous loads

/ Mounted on top of the SG cubicles

/ Load tested I ntstwncm stetenscPPQ SC - 11 l

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i

+ Inside Runway System

/ Designed to support downending and transfer through containment opening

/ Runway beams and decking installed on top of SG cubicles spanning across reactor cavity and through the containment opening l W'RESENTCOM EDWieSe5C PPT] $C ~ 12

p

/OS Removal .

9

+ Temporary Lift Device (TLD)

/ Designed to rig SGs from cubicles to inside runway system

/ Installed on polar crane bridge girders

/ Similar to system used during plant construction

/ Load-tested two-leg gantry with hydraulic chain jack system 1 wwtstNTCOM EDW205cm) 50 - 13

g"

,#r OS Removal .

+ TLD Hydraulic Lifter

/ Designed to lift and set TLD on the polar crane bridge girders

/ Truss tower base anchored to operating floor

/ Hydraulic extend unit mounted in truss tower used to raise and lower TLD i

verstm:cu_toeissescsvg 50 - 14

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  • 4'OS Removal -

+ OSG Rigging Activities Inside Containment i

/ Lift from cubicle

/ Downend onto runway system transfer carts '

/ Install primary nozzle cover plates

/ Transfer through containment opening i

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a i wwsomcm reetnescml 5C - 15 l

/

OS Removal .

+ OSG Rigging Outside Containment

/ Transfer from containment opening to OLS

/ Rig to platform trailer at ground level using OLS

/ Transport on site along approved haul route i

( WESENDCOM_E00t#85C PPf]

SC - 16

i l

B n/Braidwood l t m GeneratorReplacementProject RSG Installation, Welding, and NDE Dave Drulard Site Services Manager l WRESENTTCN EtNH4405DNfl E-I

________.__.____..___._____________.___._.__..______________.________.-_________-_.-__.__._m__ _ _ _ _ _ _ _ - _ . _ . _ - __ . . _

j i _

RS Installation

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+ RCS pipe end preparation

/ RCS pipe end decontamination

/ RCS shielding

/ Final end preparation t

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+ Rig in RSG  :

+ Shim to best fit on RCS

+ Install temporary lateral support  ;

+ Verify vertical alignment i

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RS Installation .

l

+ RCS Welding

/ Weld OD to 1/3  :

/ Grind ID and PT  :

/ Perform info RT -

/ Weld to flush, RT

/ Complete ISI profile, PT ,

/ Perform code RT

/ Perform UT inspections I unsENDCOM_ED9MO50FFq 50 - 5

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/ ' RCS s \: . N0ZZLE

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RCS Weld Joint Configuration

/

L RS Installation .

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+ Remove tube sheet and bowl protection

/ Perform cleanliness inspection

+ Remove shielding and FME barrier

+ " Perform foreign object search and retrieval"  !

+ Install primary manways l

i m-m, m, 30._ 7 r

_ _ _ _ _ _ _ . _---. __ _ _ _i 4

/b n/Braidwood t m Generator ReplacementProject 1

l l Engineering Issues Associated with Steam Generator ,

Mark Leutloff

Byron SGR Project Engineer i

4 4

i i m - - ,. m m *-i

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t Des n ConsiderationsIntroduction -

)

i

+ General discussion of protection measures

+ Manitowoc crane

+ RBSS and OLS

+ Material handling system

+ Auxiliary crane

+ Polar crane /TLD

+ SG removal / reinstallation  !

+ Haul routes .

iv a m m. m m a prq SE -2 i

i ral Approach To Protect Safety

.+ .

ted SSC's i

t

+ Observe accepted industry load handling standards

+ Comply With NUREG 0612 commitments ,

4

+ Comply with Bulletin 96-02 response

+ Perform lift equipment load tests and inspections

+ Use physical separation to preclude interactions

+ Use administrative controls and schedule adjustments to preclude interactions i

,- - ,.. - *-3

ral Approach To Protect Safety

  • ~ '

ted SSC's (cont.) i

+ Design and analyze lift equipment to preclude failure i under seismic loading conditions to preclude interactions

+ Design lift equipment fail safe to preclude interactions

+ Operations contingency measures  :

+ Evaluate potential interactions I

L i

i mx-. . rm se - 4

p' Mn 'towoc Crane .

+ Crane erection will be performed in a remote area

+ Crane use will be controlled administratively

+ Crane will be used during modes 1-6 and while defueled to erect OLS and RBSS

+ Prohibit Manitowoc load ~ handling over safety-related SSC's

+ Load lift heights will be minimized i - ,,-,...st m se-s

0 't0 woc Crane (cont.) .

+ Evaluating loads and lifting sequences including seismic and tornado considerations

+ In the event of high wind or tornado watch suspend crane operations, lower boom and park safely

+ Protection strategies identified for adjacent safety-related SSC'S for each plant mode

+ Position crane to provide physical separation from SSC's

+ Evaluating interactions With SSC's ,

I i msnm mmestprq SE-6

i ide Lift System (OLS) andRunway Support System (RBSS)

+ Erection and use will be controlled administratively

+ Evaluating RBSS and OLS erection sequence including seismic and tornado considerations

+ RBSS and OLS members will be guy wired and anchored during erection as a fail safe mechanism to preclude SSC interactions

+ Completed RBSS will be seismically evaluated and guy wires will remain in place SE -- 7 ,

(.WWESENMCW EDWN05E PP9

_. 7 q

+

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and OLS (cont.) .

+ OLS support columns will be seismically evaluated prior to OLS header beam installation

+ OLS header beams will be installed during Mode 5,6 or defueled to preclude MSV room interaction During Modes 1-4

+ Guy wires will remain in place on completed OLS i

+ OLS will be load-tested per ANSI B30.2

/LMa, rialHandling System (MHS) .

+

+ Erection of MHS complies with NUREG 0612 '

commitments

+ Complies with Tech Spec 3/4.9.7 which prohibits load handling over spent fuel assemblies

+ Fuel At Unit 1 end of SFP adjacent to MHS will be moved prior to placement of FME barrier

+ FME barrier placement will be controlled administratively e

l WWESENDCOM EDW1#05E FT'y SE -9 .

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1

+ FME barrier lift height will be minimized

+ FME barrier and SFP wall structural integrity maintained in the event of drop

+ FME barrier will be seismically evaluated to prevent barrier from entering pool

+ Loads will not be handled on or above FME barrier i

! FRESENDCCN Em#e5E PFil 5E - 10

7_ _-

i / .

Y (C0Nt.) ,

+ Material handling cart will travel on rails and loads will be secured to cart

+ Cart loads will be tethered

+ Raised track designed for disassembly in the event containment closure needs to be established

+ OEM will perform inspection of FHB crane prior to SGRO i

NW EMMM @

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M, X .

iary Cranes .

i

+ Install during Mode 5 with polar crane

+ Auxiliary crane components will be held by polar crane until securely anchored

+ Auxiliary crane erection and use will comply with NUREG 0612 commitments

+ Load test auxiliary cranes in accordance with ANSI B30.2

+ Use of auxiliary cranes will be controlled administratively ,

r

, _ _ - . . , m_u

-.. 0!

~ d[,; iary Cranes (cont.) .

i

+ Auxiliary cranes will be seismically evaluated with load and lift configuration limitations for Modes 5 and 6

+ During defueled conditions, shared safety-related systems in unit 1 containment will be isolated i

i mstwTame_towimprq SE - 13

\

i JPb Crane /TLD .

y .

+ OEM performed polar crane inspections for an engineered lift

+ Polar crane end truck wheel bearing replacements

+ TLD will be assembled and load tested outside containment at Byron

+ TLD installation and use only while defueled i

I vietstutic0M_EDW1460$E PPf]

E- 14

I I

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SG emoval/ Reinstallation .

+ Temporary RCS dead load support and SG column .

restraints will be installed and removed while defueled

+ RCS pipe severence and rewelding will be performed while defueled

+ Secondary piping severence and rewelding on B&C SG's will be performed while defueled l

k i

l l WWESENTuna EDetwow PPq SE - 15

[

7

/h

^RS < RailLoading/OSG HaulRoute

+ Evaluating buried essential service water makeup piping and control cables for impact

+ Test haul route

+ Evaluated postulated release from OSG drop / rupture at OLS

+ Evaluating OSG's remain intact in the event of a drop from the transporter along the haul route l verstunxu tm485E ppg SE - 16

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