ML20059L065

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Summary of 931201 Meeting W/Util in Rockville,Md Re Presentation by Licensee on SG Replacement Project. Attendees Listed in Encl 1
ML20059L065
Person / Time
Site: Mcguire, Catawba, McGuire  Duke Energy icon.png
Issue date: 01/26/1994
From: Nerses V
Office of Nuclear Reactor Regulation
To:
Office of Nuclear Reactor Regulation
References
NUDOCS 9402030119
Download: ML20059L065 (43)
v • d • e


Text

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a UNITED STATES 5-o :l NUCLEAR REGULATORY COMMISSION g

j WASHINGTON, O C. 20555-0001 January 26, 1994 Docket Nos. 50-369, 50-370 and 50-413 LICENSEE: Duke Power Company FACILITY: McGuire Nuclear Station Units 1 and 2 Catawba Nuclear Station Unit 1

SUBJECT:

STEAM GENERATOR REPLACEMENT PROJECT On December 1, 1993, the NRC staff met with representatives of Duke Power Company (DPC) at NRC headquarters in Rockville, Maryland. The purpose of the meeting was to hear a presentation by DPC on the McGuire, Units 1 and 2, and Catawba, Unit 1, steam generator (SG) replacement project.

Meeting attendees are listed in Enclosure 1. A copy of the DPC handout is provided in Enclosure 2.

DPC noted that significant SG tube degradation on the three units led DPC to decide to replace the SGs as soon as possible. McGuire, Unit 1, is scheduled for replacement first between November 1995 and February 1996; Catawba, Unit 1, is second and scheduled for replacement between July 1996 and November 1996; and McGuire, Unit 2, is third and scheduled for replacement between September 1997 and January 1998. The replacement outage for McGuire Unit 1 is currently estimated for 117 days. Of this, 17 days are projected for core unload, 69 days are projected for the actual SG replacement activities, and 33 days are projected for core reload and testing.

The SG replacement will be done under 10 CFR 50.59.- Operating parameters are expected to change and for these changes it will require Technical Specification changes. DPC noted that there will be a number of Topical Reports related to the SG replacement that will need revision. DPC agreed to identify to the NRC which of these will be submitted (as well as the submittal schedule)~for NRC review.

DPC noted that a SG Replacement Project site organization has been recently formulated at the McGuire and Catawba sites. Up to now, most of the SG replacement activities were being. handled at DPC corporate headquarters.

f 9402030119 940126 8 PDR ADOCK 05000369 P PDR 4( g

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DPC agreed to future meetings to allow the NRC to maintain cognizance of the SG replacement activities at DPC and to discuss Technical Specification changes.

Original signed by:

Victor Nerses, Project Manager Project Directorate 11-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Enclosures:

F 1. List of Attendees

2. DPC Handouts cc w/ enclosures:

See next page DISTRIBUTION: ,

DockettfilesW/ Handouts NRC & Local PDRs w/ Handouts PDII-3 Reading w/ Handouts T. Murley/F. Miraglia,12G18 J. Roe, Acting, 12G18 S. Varga G. Lainas L.-Plisco V. Nerses w/ Handouts L. Berry OGC, 15B18

- E.-Jordan, MNBB3701 W. Russell, 12G18 ACRS (10), P-315 Ril Plants, EDO, 17G21 EMerschoff, Ril, w/ Handouts K. Desai, 8E23 J. Ma, 7H15 C. Gratton, 10D22 C..Hinson, 1004 R. Guel, 8H7 J. Blake, RIl G. Hornseith, 704 J. Rajan, 7E23 R. Martin OFF

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. Document Name: G:\MCGUIRE\DPCl2-1. SUM L 3100n5- [

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DPC agreed to future meetings to allow the NRC to maintain cognizance of the SG replacement activities at DPC and to discuss Technical Specification-changes.

Original signed by:

Victor Nerses, Project Manager Project Directorate II-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Enclosures:

1. List of Attendees
2. DPC Handouts cc w/ enclosures:

See next page RISTRIBUTION:

Docket File w/ Handouts NRC & Local PDRs w/ Handouts PDil-3 Reading w/ Handouts T. Murley/F, Miraglia,12G18 J. Roe, Acting, 12G18 S. Varga G. Lainas L. Plisco V. Nerses w/ Handouts L. Berry OGC, 15B18 E. Jordan, MNBB3701 W. Russell, 12G18 ACRS (10), P-315 Rll Plants, EDO,17G21 EMerschoff, RII, w/ Handouts K. Desai, 8E23 J. Ma, 7H15 C. Gratton, 10022 C. Hinson, 1004 R. Guel, 8H7 J. Blake, Rll G. Hornseith, 704 J. Rajan, 7E23 R. Martin 0FF LA:PD23pMP_E PM;/l)R:DRPE (A)D:PD23:pRPE NAME LBerry e es:cw LPlisc DATE f/ (/g4 [ Mh/g4 / / 26 /94 _

Document Name: G:\MCGUIRE\DPCl2-1. SUM

a DPC agreed to future meetings to allow the NRC to maintain cognizance of the SG replacement activities at DPC and to discuss Technical Specification changes.

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Victor Nerses, Project Manager Project Directorate 11-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Enclosures:

1. List of Attendees
2. DPC Handouts cc w/ enclosures:

See next page E

a McGuire Nuclear Station Duke Power Company Catawba Nuclear Station cc:

A. V. Carr, Esquire Mr, Dayne H. Brown, Director Duke Power Company Department of Environmental, 422 South Church Street Health and Natural Resources Charlotte, North Carolina 28242- Division of Radiation Protection 0001 P. O. Box 27687 Raleigh, North Carolina 27611-7687 County Manager of Mecklenberg County 720 East Fourth Street Mr. Alan R. Herdt, Chief Charlotte, North Carolina 28202 Project Branch #3 U. S. Nuclear Regulatory Commission Mr. R. O. Sharpe 101 Marietta Street, NW. Suite 2900 Compliance Atlanta, Georgia 30323 Duke Power Company McGuire Nuclear Site Ms. Karen E. Long 12700 Hagers Ferry Road Assistant Attorney General Huntersville, NC 28078-8985 North Carolina Department of Justice J. Michael McGarry, III, Esquire P. O. Box 629 Winston and Strawn Raleigh, North Carolina 27602 1400 L Street, NW.

Washington, DC 20005 Mr.. G. A. Copp Licensing - EC050 Senior Resident Inspector Duke Power Company-c/o U. S. Nuclear Regulatory 526 South Church Street Commission Charlotte, North Carolina 28242-12700 Hagers Ferry Road 0001 Huntersville, North Carolina 28078 Regional Administrator, Region'II Mr. T. Richard Puryear U.S. Nuclear Regulatory Commission Nuclear Technical Services Manager 101 Marietta Street, NW. Suite 2900 Westinghouse Electric Corporation Atlanta, Georgia 30323 Carolinas District 2709 Water Ridge Parkway, Suite 430 Charlotte, North Carolina 28217 Dr. John M. Barry Mecklenberg County Department of Environmental Protection 700 N. Tryon Street Charlotte, North Carolina 28202

o McGuire Nuclear Station .

Duke Power Company Catawba Nuclear Station CC:

Mr. 2. L. Taylor North Carolina Electric Membership Regulatory Compliance Manager Corporation Duke Power Company P. O. Box 27306 4800 Concord Road Raleigh, North Carolina 27611 York, South Carolina 29745 Senior Resident Inspector North Carolina Municipal Power Route 2, Box 179 N Agency Number 1 York, South Carolina 29745 1427 Meadowwood Boulevard P. O. Box 29513 Mr. David L. Rehn Raleigh, North Carolina 27626-0513 Vice President, Catawba Site Duke Power Company County Manager of York County 4800 Concord Road York County Courthouse York, South Carolian 29745 York. South Carolina 29745 Mr. T. C. McNeekin Richard P. Wilson, Esquire Vice President, McGuire Site Assistant Attorney General Duke Power Company South Carolina Attorney General's 12700 Hagers Ferry Road Office Huntersville, North Carolina 28078 P. O. Box 11549 Columbia, South Carolina 29211 Piedmont Municipal Power Agency 121 Village Drive Greer, South Carolina 29651 Saluda River Electric P. O. Box 929 Laurens, South Carolina 29360 Max Batavia, Chief Bureau of Radiological Health South Carolina Department of Health and Environmental Control 2600 Bull Street Columbia, South Carolina 29201 I

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ENCLOSURE 1 Attendees to DPC Presentation of the McGuire and Catawba Nuclear Stations SG Replacement Project-December 1, 1993 NAME ORGANIZATION V. Nerses NRC/NRR/McGuire PM Kulin Desai NRC/DSSA/SRXB John S. Ma NRC/DE Mary Hazeltit.e Duke Power /SGRP Julio Torre Duke Power /SGRP Caroll Robinson Duke Power /SGRP Chris Gratton NRR/DSSA/SPLB Charles Hinson NRR/DRSS/RPB Raj Goel NRR/DSSA/SCSB Gus Lainas NRR/ADRII Loren Plisco NRR/PDII-3 Jerome Blake NRC - Region II, DRS Geoff Hornseth NRC - Materials Engineer Bernard Carrick RG&E John F. Smith RG&E Stephen D. Routh Bechtel J. Rajan NRR/DE/EMEB Anne Cottingham Duke;(Winston & Strawn)

L. Zerr STS Bob Martin NRC/NRR Catawba PM

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I Ll3 Duke Power Company -

- McGuire and Catawba Nuclear Stations Steam Generator Replacement Project Meeting with NRC .

December 1,1993 N-ISteam Generator Replacement Project j

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DUKE POWER COMPANY .

McGUIRE AND CATAWBA NUCLEAR STATIONS-

. STEAM GENERATOR REPLACEMENT PROJECT.

AGENDA FOR MEETING WITH THE NRC - DECEMBER 1,~ 1993 -

INTRODUCTION PROJECT ORGANIZATION ,

REPLACEMENT SCHEDULE -

S/G DESIGN ,

DESIGN PHILOSOPHY

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COMPONENT SUPPLIER AND ANALYSIS DESIGN FEATURES .;

+- OPERATING PARAMETERS t

S/G REPLACEMENT REPLACEMENT METHODOLOGY LESSONS LEARNED l REPLACEMENT SIMULATION MOVIE- 4

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4 AGENDA FOR MEETING WITH THE NRC DECEMBER 1,1993 i PAGE 2 5

RIGGING AND HANDLING REMOVAL AND INSTALLATION t

SYSTEM MODIFICATIONS RETURN TO SERVICE TESTING '

ALARA CONSIDERATIONS

  • S/G DISPOSAL LICENSING OVERVIEW QUESTIONS AND ANSWERS F

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l l l lll Duke Power Company-McGuire and Catawba Nuclear Stations Steam Generator Replacement Project Meeting with NRC December 1,1993 Steam Generator Replacement Project 1

l I I Ill Duke Power Company .

INTRODUCTION  !

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Steam Generator Replacement Project

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ti l l l lliilntroduction -

Degradetion .l

. Significant on Three Units McGuire 1 and 2 '!

Catawba 1 o

. Main Types  ;

. PWSCC r

. OD attack

. Mid spancoldleg Ecnnomica

. FeasibilityStudies

.' Cost Estimates

. Financial /Technicalmodel .

Conclua190

. Replace as Soon as Possible -

t Steam Generator Replacement Project

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i l l I Ill Introduction \

B_e placement Team . r i

. Duke Power- Plant Design And Construction .

  • BWNT- French Replacement Experience - .l .

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. MK-Ferguson - SG Replacement Experience-I Steam Generator Replacement Project  :

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l I I Ill Duke Power Company f a PROJECT i ORGANIZATION I

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Steam Generator Replacement Project ,

I i !111 Project Organization -l

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Steam Generator Replacement Project Page 3 l

l I I Ill Project Organization JLl y .. .. ',-

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. I Steam Generator Replacement Project 5

3 I I I III Duke Power Company REPLACEMENT SCHEDULE  :

h Steam Generator Replacement Pro]ect '

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I I I III Replacement Schedule 1992 1993 1994 1995 1996 1997 1998 McGuire Units 1 & 2 Engineering . , ns .

Ucense submittal **"

Unit 1 Replacement *

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Unit 2 Replacement nen C3 unm Catawba Unit 1 Engineering 1 ata Ucense submittui '""

Replacement "" C ""

Steam Generator Replacement Project i

l l 1III Replacement Schedule BeplatemenLomtage  :,

. Currently Defined at 117 Days 17 Days Core Unload i

. 69 Days Replacement Activities .;

33 Days Core Reload & Testing ,

E Steam Generator Replacement Project .;

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l I I Ill Duke Power Company a

SG DESIGN -

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t Steam Generator Replacement Project l l l III SG Design Philosophy "

. Sixty Year Design Life '

. Improved Thermal Performance

. Interchangeability

. Proven Technology l

. Minimize impaci to Existing Plant '

. Minimize Life Cycle Costs Steam Generator Replacemen. Project

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a l I I III Component Supplier And-Analysis  ;

BWI- Significant RSG Manufacturing Experience

. Design Specification Based on BWNT And Duke Generated inputs ,

. Safety Analysis Performed By BWNT And Duke

. Plant Interactions Evaluated by BWNT And Duke Steam Generator Replacement Project.

i i I Ill SG Design Features Inbe3undle

  • 11/16" OD Tubing
  • Triangular Pitch Array ',

a Surface Area Approximately 80,000 SF Full Depth Hydraulically Expanded TS Joint TS Joint Optimization Program l Steam Generator Replacement Project l

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4 I I I Ill SG Design Features Iuke_taaterial

  • Alloy 690 TT
  • Manufactured by Sumitomo
  • Drawing Used for Final Cold Work
  • S/N > 15,100% ID ECT
  • Tubes Below 12" Bend Radius Stress Relieved Steam Generator Replacement Project l l l lll SG Design Features IMDS_SMDRQi13
  • No Drilled Plates
  • Stainless Steel Lattico Grids
  • Stainless Steel 10 Point Fan Type U-Bend Support
  • All Rows Supported
  • U-Bend Supports installed During Tubing Steam Generator Replacement Project j Page 8  !

4 l l l lll SG Design Features Etedwater Distribution

  • Internal Main Feed Ring
  • Incorporates Lessons Learned
  • Separate Auxillary Feodwater Water Comtection r

Steam Generator Replacement Project l l l lll SG Design Features Moisture Separators i

e Guaranteed MCO < 0.25%

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  • Expected MCO Approxirnately 0.10% ,
  • 9514" Centrifugal Primary Separators
  • 9514" Centrifugal Secondary Separators 1

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9 I I I Ill SG Design Features ETASSULQ_YRSSDI

  • Forged Tubesheet, Channel Head, Transition Cone, Stsam Dome
  • Rolled Plate Cylindrical Sections
  • Optimize Joint Designs to Min'imize ISI
  • Same Dimensional Envelope

l I I III Operating Parameters [

.t Preliminary SysicRLQptfallD9_EAfAlnattra MNS CNS

  • T-Hot (F) 614 614 e T Cold (F) - 557 557
  • RCS Flow (GPM) 400,000 400,000  ;
  • Fdw Temp (F) 438 441 4
  • Fdw Flow (Mlbm/hr) 15.26 15.33
  • Steam Pres (psia) 1020 1020  ;

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I I I III Duke Power Company SG REPLACEMENT Steam Generator Replacement Project '

I I I III Replacement Methodology PASCE_Model

. CAD Models Of SG, SG Enclosures, and RCS

. Input As-Built Dimensions From Containment Walkdowns

. Modeled Exterior Structures in Transport Areas

. Perform Motion Study And identify interference

. Verify Replacement Methodology Steam Generator Replacement Project .

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I I I III Replacement Methodology Conclusiona

  • Single Piece SG Replacement Methodology
  • Temporary Holst Required.
  • 2 cut (RCS system) replacement is feasible Steam Generator Replacement Profoct l I I Ill Lessons Leamed Team attendance at a Millstone

. North Anna 1 '

. Bugey 5

. Future outage attendance ,

. VC Summer

. Chooz B1

. Contact with other project teams

. DC Cook 2 Millstone 2

. North Anna 1 Ringhals 2

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I I I Ill Lessons Leamed  :

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. Each Replacement is Plant Specific

. Maintain Separation From Station Organization

. Define Station interfaces Clearly- ,

. Work Process Simplification ,

. Employ Measurement Programs Before Replacement

. RCS Pipe End Restraints Required '

. Extensive Use Of Mock-Ups and Training Steam Generator Replacement Project 4

l I I Ill Duke Power Company ,

t RIGGING AND HANDLING t

Steam Generator Replacement Project l

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I I Ill Rigging And Handling

~

I Inmporary_Lillin9Acyke_(ILD)

. Existing Whiting Trolley Has insufficient Lifting Capacity ( 175 Tons)

. Replacement SGs Weigh 407 Tons .

. Temporary Lifting Device Will Be Required Steam Generator Replacement Prv]ect I I I Ill Rigging And Handling LlILQualifkallon

. Planned Engineered Lift Performed per ASME B30.2a For Polar Crane Beams, End Trucks, and ,

Supporting Structure (Crane Wall)

. Polar Crane Beams and End trucks Designed To Lift 512 Tons On a Limited Basis

. Polar Crane Load Tested At 500 Tons During Construction Steam Generator Replacement Project Page 14

I I I Ill Rigging And Handling EolaLCrane_lamertion

. Inspection Of Polar Crane Performed By -

manufacturer

. Resolve items Which Affect The Replacement Outage

. TLD Loads imposed On PC Girders To Be Analyzed By Whiting Steam Generator Replacement Project I I I Iil Rigging And Handling a .

Iemanratyllitinglinylste

. TLD Designed Per ANSI N45.2.15

. TLD installed During No Mode

. Moblie Crane Used To Install And Remove TLD

. Loading Due To Mobile Crane On Existing Structures Analyzed And Approved Steam Generator Replacement Project i

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I I I III Rigging And Handling Iemporary_Lillin93cvicelesting Procedures Developed For Testing Of TLD Load-Tested Outside Containment To 110% of Lifted Load (per ANSI N45.2.15)

Inspection And Operational Test Mobile Crane Used For installation Of TLD Load Tested To 110% Manufacturer's Load Rating Per ANSI B30.5 Steam Generator Replacement Project E

I I I Ill Rigging And Handling Inmpsrary Lifilngfevice OpSration ,

Procedures Developed For Operation of TLD

. The TLD Will Be Operated By Qualified Personnel TLD Vendor Will Be involved in Training Personnel  ;

l Steam Generator Replacement Project l l

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4 l I I Ill Duke Power Company REMOVAL AND INSTALLATION .

Steam Generator Replacement Project l I I Ill Removal and Installation s_0_Elt-up

. Optical Measurement Process

- Topometric Survey Of New SG And RCS Piping

. . High Accuracy Required For RCS Beveling Machine And Narrow Gap Welding Fit Up Steam Generator Replacement Project Page 17

l I I Ill Removal and Installation RCE PIPE SEPARATION

  • Orbital Mechanical Cutting Tool
  • Modified Split Frame Pipe Lathe
  • Cutting Wheel Used To Shear Final Layer
  • Seal Plates and Shields Installation

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Steam Generator Replacement Project .

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b I I I I11 Removal and Installation .

_S G Beveling

  • Numerically Controlled Rotating Machine Mounted On inside of RCS Pipe
  • Orientation of Bevel Controlled Relative To Reference Ring Mounted On RC Pipe
  • Beveling Operations Are Remotely Controlled
  • Same Tool Used To Machine New S G Nozzle Bevels Steam Generator Replacement Project Page 18

4 l l l lll Removal And Installation GIAW_ Narrow _GapEcMins.Erstess Gas Tungsten Arc (GTA) Welding Narrow Gap Process GTA Weld Effector Attached to Orbital Weld Head

  • Bridge Pipe And Nozzle Bevel Surfaces With Each Weld Pass
  • Single Pass Tie-ins By Close Tolerance Fit-up Steam Generator Replacement Project I I I Ill Removal And Installation Advantagns_oLNarrow Gan_ Welding _P_Iotean '
  • Uniform Wold Quality
  • High Reliability
  • Less Filler Metal -
  • Shorter Welding Time '
  • Lower Radiation Exposure

- - = .

I I I III Duke Power Company SYSTEM ,

MODIFICATlONS P i

Steam Generator Replacement Project l I I Ill System Modifications SG_ insulation

  • Mirror Insulation Originally installed
  • Some Flexible Blanket Currently in Use
  • Change Out To Flexible Blanket System
  • Replacement insulation Meets Normal And Design Basis Environmental Conditions And is Seismically Qualified Steam Generator Replacement' Project Page 20

4 l I I I11 System Modifications Maln_Ecesvatettine_Befsnte

. Upper Feedring Nozzle Feedwater Supply

. Feedwater Piping Rerouted 33 Feet

. Chromium-Molybdenum Steel Material

. Feedwater Reroute Welds Wili Be Heat Treated

. Piping Analysis Will Be Performed

. Eliminate Reverse Purge For McGuire Units 1 and 2 Steam Generator Replacement Project W

l I I Ill System Modifications Main _steamMne separation _And_Be.cnnnection Main Steam Line is 100% Cold Pulled

. Main Steam Lines Restrained To Maintain Cold Pull

. Pipe Supports Reinforced

. Piping Analysis Will Be Updated

. One Pipe Cut And One Nozzle Cut Per Line Steam Generator Replacement Project E

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I I I Ill System Modifications .j AuxiliaryleedwateLEthorBeplacement

l l l lll System Modifications NucinaLSampilag_SyAtem Reroute

. Sampling Nozzles Are Higher For Replacement SGs

. Move Sampling Points Away From Turbulence Created l By U-Tubes And Auxiliary Feedwater Nozzle 1 i

Steam Generator Replacement Project 1

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T I I I III System Modifications ,

i Binwdnwn_BcSyde And Wet Lay-Up Recircujat[on '

_P_iping.Beto3ttas

. Wet Lay-Up Recirculation Nozzle Deleted

. Wet Lay-Up Drain Line Added To Blowdown .

Recycle System' ' '

Steam Generator Replacement Project {

l I I Ill Duke Power Company L

i RETURN TO  :

SERVICE TESTING Steam Generator Replacement Project . '

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I I I III Retum To Service Testing 1

Moisture Carryover .

. N C System Flow l

  • Calorimetric  !

I

  • Pressure

+ Ultrasonics

  • NaturalCirculation

. Thermal Performance

  • T Hot and T-Cold  !
  • HeatTransferCoefficient  ;
  • Venturi Fouling j l

Steam Generator Replacement Project I I I Ill Return To Service Testing

. Thermal Expansion a Shimming of NSSS During Cold Shutdown a Verified at Holding Points During Heat-Up

. Hydrostatic Testing f

  • Primary Section XI Hydro and Leak Test

. . Main Feedwater Testing l

. Auxillary Feedwater System Flow

. Bio-Shicid Survey Steam Generator Replacement Project Page 24

I .I I Ill Duke Power Company i

ALARA CONSIDERATIONS i

Steam Generator Replacement Project 4

T l l IIII ALARA Considerations l i

ALARA Progratti

. Dose Prevention

. Minimize Personnel Contaminations

. Minimize Radioactive Waste Steam Generator Replacement Project ,

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I I I III ALARA Considerations Lesanna_Lemned

. Maintain Secondary Water Level

. Clean Condition Upper Containment

. Dedicated RP Project Team' .

. Dedicated Radioactive Material Handling Team ,

. Realistic Mock-Up Training i

Steam Generator Replacement Project C

l I I III ALARA Considerations McGuite_Unli1 Dose Estimate.g

. - Temporary Power 10 rem

. Scaffolding 20 rem

. RP Decontamination 12 rem

. RP Job Coverage 25 rem

. Insulation 59 rem

. RCS Cutting And Welding 119 rem >-

. RCS Temporary Supports 46 rem

. CF Reroute 44 rem

. Other Activities 81 rem

. Total Project Dose 416 rem Steam Generator Replacement Project 4

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9 l l llll ALARA Considerations HQSJ_iping

. Mechanical Cutting Minimizes Exposure

. Negative Pressure Applied To RCS

. Local HEPA Units At Location

. Primary Nozzle Seal Plates And Shields

. Pipe End Decontamination

. Mock-Up Training Steam Generator Replacement Project I I I III ALARA Considerations RecontatDination Plan

. SG Cavities

. SG Surface Decontamination And Coating

. RC Pipe Ends

. Upper Containment To Clean Condition Steam Generator Replacement Project Page 27

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I IIII ALARA Considerations .

D# son 101Dina119tLEacilitlea Decontaminate Equipment Removed From Containment CO2 Blast Unit Dedicated Crew For Radioactive Material Handling ,

Steam Gcnerator Replacement Project -

l l l l lll ALARA Considerations Shicidlus .

Temporary Shielding

. RCS Pipe End Shield Plugs Maintain Secondary Water Level Steam Generator Replacement Project Page 28  ;

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t I I I Ill Duke Power Company 1

SG DISPOSAL F

Steam Generator Replacement Project t

V l 1 I III SG Disposal

. Disposal Facility May Not Be Available

. Stored On Site for Decay Until Decommissioning

. After Storage Significant Portion of the SGs can be Decontaminated and Free Released

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Steam Generator Replacement Project _

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4 I I I III S G Disposal

-i Retired RCtlemporary SloraggJMilding

. Concrete Building  !

. Located On-Site Outside Exclusion Area

. Passive HEPA Filter System

. Low Point Sump For Sampling

. No Power Provide'd

. Meets 10 CFR 20 Dose Requirements -

Steam Generator Replacement Project E

I I I I Ill Duke Power Company LICENSING OVERVIEW Steam Generator Replacement Project -

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l l I I IIl Licensing Overview l,

. i 1.19EDik19_S1[Alf9y I ,

+ Majority of Replacement Performed Per 10 C FR 50.59 .!

+ License Amendment For Technical Specification  !

Changes Related To New Operating Parameters t

f Steam Generator Replacement Project F

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I I I Ill Licensing Overviere )

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e ASMECodea

+ New SGs Designed, Fabricated And Tested in ,

Accordance With ASME Section Ill,1986 Edition .j

. SG Replacement Performed Per ASME Section XI  :

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+ MND1 - 1986 Editior, '

+ MNS2 - 1980 Edition, Winter 80 Add.

+ CNS1 - 1980 Edition, Winter 81 Add. :f J

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Steam Generator Replacement Project c i t

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l l l l11 Licensing Overview 10SEfLEO.ER.Mosfilications l

. Majority Of Design Changes And Replacement Activittre cerformed Under 50.59 10 CFR 50.59 Process Will include Site Roviews r

. Licensing Report Will Compile Documentation For All Licensing Activities

. Report Will Be Available To NRC For Information i

Steam Generator Replacement Project n .

l l l lll Licensing Overview ,

Lic e Amendment

. License Amendment Submitted For Each Station

. Submittal Will include Required TS Chen;;es.

f

. Environmental Evaluation Being Performed

. Submittal Of License Amendme..c For All 3 Units Targeted For September 30,1994

. Approval Requested For September 30,1995  :

1, Steam Generator Replacement Project . ,

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l I I Ill Licensing Overview i i

IransienLAnaJyses '

  • Duke to Perform 1 l
  • Chapter 15 Analyses Revisions to Topical Reports -k
  • Single Analysis Bounds All Three  !

Units '

Steam Generator Replacement Profi ct {

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.I l 1 I Ill Licensing Overview' a

10pl9ALBevisiona

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DPC-NE-3000 - DPC Ther(nal Hydraulle Analysis .;

Me'hodology 9 '

DPC-NE-3001 - Multi-Dimensional Reactor Transients  :

and Safety Analysis i

. DPC-NE-3002 - FSAR Chupter 15 Si i'em . Transient

- Methodology  ;

. New Topical will be submitted for mass and energy.  ;

release and Containment Response l Steam Generator Replacement Project

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