ML20198G460

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Summary of 971210 Meeting W/Licensee Re SG Replacement for Unit 1.List of Attendees & Handout Matls Provided by Licensee Encl
ML20198G460
Person / Time
Site: South Texas STP Nuclear Operating Company icon.png
Issue date: 12/19/1997
From: Alexion T
NRC (Affiliation Not Assigned)
To:
NRC (Affiliation Not Assigned)
References
NUDOCS 9801130041
Download: ML20198G460 (62)
v • d • e


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O' UNITED STATES g ,; NUCLEAR REGULATORY COMMISSION

, o WASHINGTON, D.C. 30MH001

4 4***** December 19, 1997 LICENSEE: STP Nuclear Operating Company FACILITY: SOUTH TEXAS PROJECT, UNIT 1

SUBJECT:

SUMMARY

OF DECEMBER 10,1997, MEETING ON STEAM GENERATOR (SG)

REPLACEMENT FOR UNIT 1 On December 10,1997, the licmsee met with the NRC to discuss their progress towards SG l replacement at Unit 1. Meeting attendees are listed in Attachment 1. The handout provided by the licensee is in Attachment 2.

The fabrication of the replacement SGs is about 45% complete (delivery scheduled for mid.

1999), the licensing engineering is about 78% complete (with proposed technical 4pecification ,

changes to be submitted in May 1998), SG replacement engineering is about 70% complete (all design change packages to be issued by June 1998), and plant preparations are ur:derway. SG replacement is planned for refueling outage 9 in early 2000.

The doign characteristics of the detta 94 replacement SGs, compared to the current SGs, include increased reactor coolant system (RCS) flow, increased RCS volume, increased heat transfer area, increased mass / weight, increased secondary inventory and an elevated feedring instead of a preheater The licensee presented the status of the various evaluations and analyses to support the delta 94 SG design. The licensee is performing evaluations when existing analyses remain bounding with the delta 94 design New analyses are performed when the existing analyses are no longer bounding.

The licensee plans to submit technical specification changes in May 199C, for RCS flow, RCS volume, SG water level, auxiliary feedwater storage tank volume, and SG surveillances. The licensee also plans to submit an unreviewed safety question on dose consequences (they indicated there is a small increase in doses). In uddition, the licensee noted that the implementation methodologies in WCAP 14882 (for the Retran Code) and WCAP 14565 (for the Vipre Code), which are being used for various reanalyses, are currently under NRC review.

During the course of the meeting the staff asked questions and requested clarifications on the material presented, in addition, we staff Indicated a desire for further discussion on ti,9 circumferential temperature distribution and resulting stress distribution on the delta 94 SG tubes due to the broached hole configuration. The staff also indicated that the dose consequence results will need to be adequately supported with the analytical assumptions and other data (i.e.,

describe methodology, show calculations) sufficient for the staff to perform confirmatory calculations.

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- __- _ - _ . - .. .. . . . _ _ = . - . - _ = _ _ _ _ _ _ _ . . _ _ _ _ _. _ - _ ___

. 2 The licensee indicated a desire for a follow-up meeting to discuss progress on the supporting small-break and large break loss of-coolant accident (LOCA) analyses, and a desire to meet ,

again with the staff to present the rernaining analytical work and installation details in March

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Thomas W. Alexion, Project Manager Project Directorate IV 1 Division of Reactor Projects Ill/IV Office of Nucionr Reactor Regulation Docket No. 50-498 Attachments: 1. List of Meeting Attendees

2. Meeting Handout cc w/stts: See next page

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t The licensee indicated a desire for a follow-up meeting to discuss progress on the supporting small-break and large break loss-of coolant accident (LOCA) analyses, and a desire to meet again with the staff to present the remaining analytical work and installation details in March 1998.

ORIGINAL SIGNED BY: 1 Thomas W. Alexion, Project Manager Project Directorate IV 1 Division of Reactor Projects Ill/IV Office of Nuclear Reactor Regulation

- Docket No. 50-498 Attachments: 1. List of Meeting Attendees

2. Meeting Handout cc w/stis: See next page DISTRIBUTION-HARD COPY E-MAIL Docket File S. Collins /F, Miraglia (SJC1/FJM)

PUBLIC R. Zimmerman (RPZ)

PD41 r/f E. Adensam (EGA1; OGC C. Hawes (CMH2)

ACRS T. Martin (SLM3)

T. Alexion (TWA)

J. Tsao (JCT)

A. Keim ( ATK)

M. Hartzman (MXH)

C. Hinson (CSH)

1. Bames (IXB)

M. Shuaibi(MAS 4)

+

/, Document Name: ST121097.MTS ,

OFC PM/ PDM LA/PD41 -

NAME- TEkexic hTHaN

  • DATE~ N7 fk97 /2//f/97 COPY [kES)NO YES/NO OFPtC4AL RECORD COPY 4-V

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. STP Nuclear Operating Company South Texas, Units 1 & 2 cc:

Mr. David P. Loveless Jack R. Newman, Esq.

Senior Resident inspector Morgan, Lewis & Bocklus i U.S. Nuclear Regulatory Commission 1600 M Street, N.W.

P. O. Box gio Washington, DC 20036 5869 Bay City, TX 77414 Mr. Lawrence E. Martin Mr. J. C. Lanier/M. B Lee Vice President, Nuc. Assurance & Licensing Cityof Austin STP Nuclear Operating Company Electric Utility Department P. O. Box 289 721 Barton Springs Road Wadsworth,TX 77483 Austin, TX 78704 Rufus S. Scott Mr. M. T. Hardt Associate General Counsel Mr. W. C. Gunst STP Nuclear Operating Company City Public Service Board P. O. Box 61867 P. O. Box 1771 Houston, TX 77208 San Antonio, TX 78296 Joseph R. Egan, Esq.

Mr. G. E. Vaughn/C. A. Johnson Egan & Associates, P.C.

Central Power and Light Company 2300 N Street, N.W.

P. O. Box 28g Washington, DC 20037 Mail Code: N5012 Wadsworth, TX 74483 Office of the Govemor ATTN: Andy Barrett, Director >

INPO Environmental Policy Records Center P. O. Box 12428 700 Galleria Parkway Austin, TX 78711 .

Atlanta, GA 3033g-3064 Arthur C. Tate, Director Regional Administrator, Region IV Division of Compliance & Inspection U.S. Nuclear Regulatory Commission Bureau of Radiation Control 611 Ryan Plaza Drive, Suite 400 Texas Department of Health Artington, TX 76011 1100 West doth Street Austin, TX 78756 Dr. Bertram Wolfe 15453 Via Vaquero Texas Public Utility Commission Monte Sereno, CA g5030 ATTN: Mr. Glenn W. Dishong 7800 Shoal Creek Blvd.

Judge, Matagorda County Suite 400N Matagorda County Ccurthouse Austin, TX 7tl7571024 1700 Seventh Street Bay City, TX 7741 A Mr. William T. Cottle President and Chief Executive Officer STP Nuclear Operating Company South Texas Project Electric Generating Statien P. O. Box 28g Wadsworth, TX 77483

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MEETING BETWEEN STP NUCLEAR OPERATING COMPANY AND NRC REPLACEMENT OF UNIT 1 STEAM GENERATORS December 10,1997 ,

Ornanization i Namt T. Alexion NRC ,

j A. Keim NRC M. Hertzman NRC G. Hinson NRC

1. Bames NRC M. Shuaibi NRC J. Tsao NRC J. Conty STP C. Albury STP i C. Pham STP S. Patel STP M. McBumett STP A. McIntyre STP D. Dominicis Westinghouse B. McFetridge Westinghouse D. Dhowmick Westinghouse C. Reid Bechtel F. Farzam Bechtel R. Pomisi Bechtel i

A. Pa radopoulos Bechtel J. Well McGraw Hill l

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l' ATTACHMENT 1 t

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1-

SOUTH TEXAS PROJECT ,

i ELECTRIC GENERATING STATION 4

! UNIT 1 STEAM GENERATOR i

REPLACEMENT PROJECT 1

i NRC -

BRIEFING i DECEMBER 10,1997 4

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SOUTII TEXAS PROJECT ELECTRIC GENERATING STATION UNIT 1 STEAM GENERATOR REPtACEMENT PROJECT '

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AGENDA i i- INTRODUCTION Chet McIntyre

, t j LICENSING ENGINEERING APPROACH Chet McIntyre  ;

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j FOLLOW-UPTO APRIL 1997 BRIEFING Chet McIntyre F

NON-LOCA ANALYSIS Charlie Albury PRESSURE /rEMPERATURE ANALYSIS Charlie Albury c

INTRODUCTION TO PIPING AND SUPPORTS ANALYSIS Sam Patel l

REACTOR COOLANT SYSTEM PIPING ANALYSIS Sam Patel l 1

MAIN STEAM PIPING STRESS EVALUATION' Cong Pham

, FW/AFPIPING REROUTING Cong Pham L NSSS/ BOP INTERFACE SYSTEMS EVALUATION

Bob McFetridge l j RCP AND CRDM EVALUATIONS Bob McFetridge t

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STEAM GENERATOR REPLACEMENT SEQUENCE Sam Patel l, I-LICENSING APPROACH Mark McBurnett i

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SOUTil TIIXAS PROJECT ELECTRIC GENERATING STATION UNIT I STEAM GENERATOR REPLACBMENT PROJECT INTRODUCTION 2

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Solfill TEX AS l'ROJECT ELECTRIC GENERATING STATION UNIT I STEAM GENERATOR REPLACEMENT PROJECT .

INTRODUCTION DESIRED BRIEFING OUTCOME

= COMMUNICATE PROJECT STATUS AND TECHNICAL INFORMATION e DETERMINE AREAS OF SPECIAL INTEREST TO THE NRC PROJECT STATUS

= RSG FABRICATION ~ 45% COMPLETE; DELIVERY MID-1999

. LICENSING ENGINEERING ~ 78% COMPLETE; TECH SPEC CHANGE SUBMITTAL MAY 1998

= SGR ENGINEERING ~ 70% COMPLETE; ALL DCPs ISSUED BY JUNE 1998

. PLANT PREPARATIONS UNDERWAY

-- TEMPORARY FACILITIES

-- BARGE SLIP

-- CONTRACTOR MOBILIZATION JUNE 1998 3

SOUTil TEXAS PROJECT ELECTRIC GENERATING STATION *

PROJECT SCHEDULE OVERVIEW 1996 1997 1998 1999 2000 Licensing Engineering Activities 'i RSG Fabrication / Delivery

! l SGR Engineering I Tech Spec Submittal -

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NRC Review IREO7

  • Plant Preparation Iff8 y i

l Replacement Outage (IREO9)  ;

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O SOUTil TEXAS PROJECT ELECTRIC GENERATING STATION UNIT 1 STEAM GENERATOR REPLACEMENT PROJECT .

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l LICENSING ENGINEERING APPROACH l

5

SOUTil TEXAS PROJECT ELECTRIC GENERATING STATION -

UNIT I STEAM GENERATOR REPLACBMENT PROJEcr LICENSING ENGINEERING APPROACII EVALUATIONS PERFORMED TO DEMONSTRATE EXISTING ANALYSES l REMAIN BOUNDING WHEN A94 DESIGN DOES NOT ADVER3ELY AFFECT RESULTS ANALYSES PERFORMED WHEN A94 DESIGN ADVERSELY AFFECTS RESULTS A94 RSG DESIGN CHARACTERISTICS l

= INCREASED MASS / WEIGHT

  • INCREASED SECONDARY INVENTORY

+ ELEVATED FEEDRING INSTEAD OF PREHEATER 6

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t SOUTII TEXAS PROJECT ELECTRIC GENERATLNG STATION "

UNIT 1 STEAM GENERATOR REPLACEMENT PROJECT -

1REO7 STEAM GENERATOR TUBE INDICATION

SUMMARY

Steam Circumferential Axial Volumetric Preventive Tubes Generator Indications Indications Indications Plugging Plugged A 19(') 3 8(2) 5 36 B 14 11 3 0 28 C 22 9 14 3 47 D 20 8(3) 15 0 43 Total 75 32 39 8 154 (1) One tube had a circumferential indication and a volumetric indication at the hot leg tubesheet (2) One tube had a volumetric indication at both the hot and cold leg tubesheet (3) One tube had an axial indication at the hot leg tubesheet and in the cold leg freespan 8

Enhanced Design Features '

i Single Tier Double

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- Pocket Dryers Elevated Feedwater Ring with

- W elded Thermal Liner a o r i

- Perforated Discharge Nozzles q j 20" Model F Style

_ Primary M oisture Separators

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u-405 SS U-Bend Supports (AVBs)

Sludge Collector i

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i Broached Flat Contact ,

405 Stainless Steel Alloy 690 TT Tubes Tube Support Plates ( i i

y7 triangular pitch i I l

P Broached Flat Contact 405 Stainless Steel N m Flow Distribution Baffle @W '

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Full Depth liydraulic Expanded Tube /Tubesheet Joint

O Deita 92-/Model E Comparison

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, Model E Delta 94 b ,!,

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=g 3 Preheater SG Design

{ Feedring

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i 4,864 No.of Tubes  ! -

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pig ] , 0.750' TubeO.D. gjl i kQ)

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.043' Tube Wall .040' ,

Alloy 600 MA Tube Material Alloy 690 TT

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'1 Square Tube Pitch *! '

Triangular 7

68,000 f t2 H. T. Area 94,500 ft2 ] l 9 440' Bundle Height "

3.25- uin u-send nadius 3.25-i  ;

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O riginal Unit Replacement Unit

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  • Broacaec Hole Configuration l

l TRIANGULAR TRIANGULAR TRIANGULAR TRIANGULAR P1TCH CH PITCH PITCH O a

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v FLAT L FLAT TUBE CONTACT s TUBE CONTACT

- TYPICAL TYPICAL

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Flow Distribution Baffle Tube Support Plate

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SOtfril TEXAS PROJECT ELECTRIC GENERATING STATION '  :.

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, UNIT I STEAM GENERATOR REPLACGMFMT PROJECT,

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l s SoUTIf TEXAS PROJECT ELECTRIC GENERATING STATION *

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SCOPE Analyses Evaluations Feedwater Malfunction Loss of RCS Flow Steam Line Break Locked RCP Rotor Loss of Load / Turbine Trip RCS Depressurization Loss of Normal FW/ LOOP Excessive Load Increase Feedwater Pipe Break Rod Withdrawal from Power Fire Hazards / LOOP Rod Ejection ,

CVCS Malfunction / Boron Dilution Dropped Rod Startup ofInactive Loep 1 OT/AP, OP/AT Trip Setpoints Feedwater Temperature Reduction  :

Increased Inventory from CVCS Inadvertent ECCS Operation i

CONCLUSION RESULTS CONTINUE TO COMPLY WITH EXISTING DESIGN BASES 13

O-SoUTIi TEXAS PROJECT ELECTRIC GENERATING STATION '

UNIT I STEAM GENERATOR REPl.ACEMENT PROJECT '

COMPARISON OF OPERATING PARAMETERS Model E A94 Core Power (MWth) 3800 3800 NSSS Nominal Power (MWth) 3817 3821 RCS Pressure (psia) 2250 2250 Thermal Design Flow (gpm) 381,600 392,000 Core Bypass Flow (%) 4.5 8.5 Cold Leg Temperature ( F) 549.0 - 560.4 549.8 - 561.2 Average Temperature ( F) 582.3 - 593.0 582.3 - 593.0 Hot Leg Temperature ( F) 615.6 - 625.6 614.8 - 624.8 No-Load Temperature ( F) 567 567 Pressurizer Level, Hi Tav (% span) 25 - 60 25 - 57 Pressurizer Level, Lo Tay (% span) 32.9 - 47.0 25 - 40 S/G Temperature ( F) 542.9 - 558.0 539.3 - 552.4 Steam Pressure (psia) 986 - 1115 957 - 1066 S/G Nominal HFP Fluid Mass (Ibm) ~137,000 ~ 162,000 6

l Steam Flow (10 lbm/hr) 16.86 - 16.96 15.74 - 16.92 l Feedwater Temperature ( F) 440 390 -440 S/G Tube Plugging (%) 0 - 10 0 - 10 l

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SOUTil TEXAS l'ROJECT ELECTRIC GENERATING STATION * "

UNIT I STEAM GENERATOR REPLACEMENT PROJECT '

NON-LOCA ANALYSIS A94 DESIGN DIFFERENCES AFFECTING NON-LOCA ANALYSIS e FEEDRING vs. PREHEATER '

. INCREASED RCS VOLUME

=

INCREASED HEAT TRANSFER SURFACE AREA INCREASED RCS FLOW INCREASED CORE BYPASS FLOW e DELETED THIMBLE PLUGS

  • UPPER HEAD T-COLD CONVERSION REDUCED MINIMUM FEEDWATER TEMPERATURE 9

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l SOUTil TEXAS PROJECT ELECTRIC GENERATING STATION '

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UNIT I STEAM GENERATOR REPLACEMENT PROJECT -

t NON-LOCA ACCEPTANCE CRITERIA

= MINIMUM DNBR LIMIT REACTOR COOLANT SYSTEM OVERPRESSURIZATION MAIN STEAM OVERPRESSURIZATION

  • PRESSURIZER OVERFILL  ;

SELECTION CRITERIA FOR EVALUATION OR ANALYSIS e

SECONDARY-SIDE INITIATED EVENTS *

  • APPARENT MARGIN WITH RESPECT TO ACCEPTANCE CRITERIA  ;

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SOUTII TEXAS PROJECT ELECTRIC GENERATING STATION - '

UNIT I STEAM GENERATOR REPLACEMENT PROJECT -

RETRAN CODE e '

RETRAN-02/ MOD 5.2 CORRECTS ERRORS IN MOD T 1 (NRC APPROVED)

IMPLEMENTATION METHODOLOGY IN WCAP-14882 VIPRE CODE  !

e VIPRE-01 APPROVED BY NRC i

e IMPLEMENTATION METHODOLOGY IN WCAP-14565 RETRAN/VIPRE USED TO REANALYZE i e

FEEDWATER MALFUNCTION (INCREASED FEEDWATER FLOW)

STEAM LINE BREAK (CORE RESPONSE)

LOSS OF EXTERNAL ELECTRICAL LOAD / TURBINE TRIP e

LOSS OF NORMAL FEEDWATER/ LOSS OF OFFSITE POWER

= FEEDWATER PIPE BREAK 1

e FIRE IIAZARDS/ LOSS OF OFFSITE POWER I

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SOUTil TEXAS PROJECT ELECTRIC GENERATING STATION ,  :.

UNIT I STEAM GENERATOR REPLACEMENT PROJECT ..,

REANALYZED CVCS MALFUNCTION WITH BORON DILUTION EVENT.

NON-LOCA EVENT EVALUATIONS

. LOSS OF REACTOR COOLANT SYSTEM FLOW

. LOCKED REACTOR COOLANT PUMP ROTOR -!

= REACTOR COOLANT SYSTEM DEPRESSURIZATION

. EXCESSIVE LOAD INCREASE -

. ROD WITHDRAWAL FROM POWER

. ROD EJECTION

= DROPPED ROD

. STARTUP OF INACTIVE REACTOR COOLANT LOOP

. OVERTEMPERATURE/ OVERPOWER AT REACTORTRIP SETPOINTS

. FEEDWATERTEMPERATURE REDUCTION

= INADVERTENT ECCS OPERATION DURING POWER OPERATION.

. INCREASED INVENTORY FROM CVCS MALFUNCTION .

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l l SOUTII TEXAS PROJECT ELECTRIC GENERATING STATION -

j UNIT 1 STEAM GENERATOR REPLACEMENT PROJECT l l

l

SUMMARY

OF NON-LOCA WORK L

FOR WORK COMPLETED TO DATE, RESULTS CONTINUE TO COMPLY WITH l

EXISTING DESIGN BASES LOCA

  • LARGE BREAK EVALUATED DUE TO PEAK CLADDING TEMPERATURE l BENEFIT FROM RSG INCREASED NUMBER OF TUBES
  • SMALL BREAK TO BE DISCUSSED IN FUTURE MEETING I

1 19

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=-

=

= . . . . . . . - -

SOUTil TEXAS PROJECT ELECTRIC GENERATING STATION  ;

~- '

UNIT 1 STEAM GENERATOR REPLACEMENT PROJECT li i

i PRESSURE / TEMPERATURE ANALYSIS l

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SOUTil TEXAS PROJECT ELECTRIC GENERATING STATION -

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UNIT I STEAM GENERATOR REPLACEMENT PROJECT PRESSURE / TEMPERATURE ANALYSIS 1

SCOPE

  • INCREASED RCS VOLUME MORE LIMITING FOR LOCA M/E RELEASES, POTENTIALLY LEADING TO INCREASED PEAK CONTAINMENT PRESSURE e INCREASED SECONDARY INVENTORY MORE LIMITING FOR MSLB M/E RELEASES, POTENTIALLY LEADING TO INCREASED PEAK CONTAINMENT TEMPERATURE

= OTHER ISSUES ADDRESSED FOR COMPLETENESS CONCLUSIONS

  • CONTAINMENT P/r RESPONSE CONTINUES TO COMPLY WITH EXISTING EQ LIMITS
  • CONTAINMENT PEAK PRESSURE LOWER THAN CURRENT DESIGN BASIS l

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SOUTil TEXAS PROJECT ELECTRIC GENERATING STATION -

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UNIT 1 STEAM GENERATOR REPLACEMENT PROJEC*

LOCA LONG-TERM CONTAINMENT P/T ANALYSIS

. M/E RELEASE METHODOLOGY SATAN, REFLOOD, FROTH, AND EPITOME COMPUTER CODES NRC-APPROVED METHODOLOGY (WCAP-10325-P-A)

IMPROVED INITIAL CORE STORED ENERGY ESTIMATE DECAY HEAT MODEL CHANGED FROM ANS 1971 + 20% TO ANS 1979 + 20 NO SUPERHEAT OCCURS BECAUSE OF CONDENSATION IN S/G TUBES IMPROVED ESTIMATE OF SUMP WATER TEMPERATURE IN M/E RELEASES 22

SOUTil TEXAS PROJECT ELECTRIC GENERATING STATION *

  • P/T METHODOLOGY CONTEMPT 4/ MOD 5 COMPUTER CODE SATISFIES ANSI /ANS 56.4-1983, NUREG-0800, AND NUREG-0588 BENCHMARKED AGAINST EXISTING ANALYSIS OF RECORD (COPATTA CODE)
  • RESULTS LOWER PEAK PRESSURE LONG-TERM PfI' RESPONSE CONFIRMED WITHIN EQ LIMITS t l

7 >

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SOUTil TEXAS PROJECT ELECTRIC GENERAT'NG STATION *

MSLB LONG-TERM CONTAINMENT P/T ANALYSIS M/E RELEASE METHODOLOGY DOUBLE-ENDED RUPTURE AND SPLIT BREAK RETRAN-02/ MOD 5.2 USED

= P/T METHODOLOGY CONTEMPT 4 METHODOLOGY UNCHANGED e RESULTS SIMILAR M/E RELEASE RATES PEAK CONTAINMENT TEMPERATURE WITHld 1 F CONTAINMENT TEMPERATURE PROFILE REMAINS BOUNDED BY EXISTING EQ LIMIT 24

SOUTH TEXAS PROJECT ELECTRIC GENERATLNG STATION * '

UNIT I STEAM GENERATOR REPLAC8 MENT PROJECT

  • OTHER P/r ISSUES
  • SHORT-TERM (PEAK) PRESSURE ANALYSIS
  • - OUTSIDE CONTAINMENT P/T ANALYSIS
  • GENERIC LETTER 96-06 EVALUATION 25

b SOUTil TEXAS PROJECT ELECTRIC GENERATING STATION -

UNIT I STEAM GENERATOR REPLACUMENT PROJECT

  • l l

l PIPING AND SUPPORTS ANALYSES 26

SOUTil Tl!XAS PROJECT ELECTRIC GENERATING STATION -

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UNIT I STEAM GENERATOR REPLACEMENT PROJECT 1 INTRODUCTION TO PIPING AND SUPPORTS ANALYSES SCOPE l

  • RCS PIPING e LARGE BORE SECONDARY PIPING

= AUXILIARY PIPING ATTACHED TO RCS

  • PIPING SUPPORTS e EQUIPMENT SUPPORTS
  • BUILDING STRUCTURES CONCLUSIONS
  • CONFIRMED THAT RCS PIPING AND SUPPORTS, EQUIPMENT SUPPORTS, AND SECONDARY PIPING REMAIN IN COMPLIANCE WITH EXISTING DESIGN BASES i

27 L-.--.-.____ m . t

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SOUTil TEXAS PROJECT ELECTRIC GENERATING STATION *

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UNIT I STEAM GENERATOR REPLACEMENT PROJECT

  • BEACTOR COOLANT SYSTEM ANALYSES
  • RCB SEISMIC ANALYSIS WITH WESTINGHOUSE NSSS MODEL

-- LESS THAN 1% CHANGE IN TOTAL MASS

-- CONCLUSIONS DYNAMIC CHARACTERISTICS OF RCB AND INTERNAL STRUCTURE UNCHANGED DESIGN BASIS RESPONSE SPF.CTRA FOR RCB AND INTERNAL STRUCTURE UNCHANGED 28

SOUTil TEXAS PROJECT ELECIRIC GENERATING STATION '

UNIT 1 STEAM GENERATOR REPLACEMENT PROJECT

. RSG FINITE ELEMENT MODEL

-- RSG MASS ~11% GREATER

-- MINOR CHANGE IN RSG CENTER OF GRAVITY LOCATION

-- FREQUENCIES OF OSG AND RSG IN FUNDAMENTAL MODES ARE ANALYTICALLY EQUIVALENT

-- PARTICIPATION FACTORS FOR OSG AND RSG IN FUNDAMENTAL MODES ARE SIMILAR

-- CONCLUSIONS EXISTING DESIGN BASIS RESPONSE SPECTRA CURVES UNCHANGED DESIGN BASIS RESPONSE SPECTRA AT RSG NOZZLES UNCHANGED 29

! E SOUTil TEXAS PROJECT ELECTRIC GENERATING STATION -

~- I UNrr I STEAM GENERATOR REPLACEMENT PROJECT l

l LARGE BORE SECONDARY PIPING ANALYSIS

  • NOZZLE SPECTRA

= NOZZLE DISPLACEMENT SEISMIC ANCHOR MOVEMENTS THERMAL DISPLACEMENTS LOCA DISPLACEMENTS DYNAMIC ANALYSIS REQUIRED WHEN MASS REDISTRIBUTED e DISPLACEMENTS REVISED L

30

l L

SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION

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UNIT 1 STEAM UENERATOR REPLACEMENT PROJECT REACTOR COOLANT SYSTEM ANALYSIS EXISTING PIPING ANALYSIS REVIEWED FOR CHANGES

  • REANALYZED FOR RSG INCREASED MASS

= REANALYZED FOR HOT AND COLD LEG TEMPERATURES AND DESIGN BASIS TRANSIENTS

  • REANALYZED SEISMIC INERTIA FOR RSG INCREASED MASS
  • DESIGN RESPONSE SPECTRA FOR ALL RCB ELEVATIONS UNCHANGED

- USED ENVELOPED RESPONSE SPECTRA

-- CRITICAL DAMPING UNCHANGED 31

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SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION - -  !

UNTT 1 STEAM GENERATOR REPLACEMFET PROJECT ~*

j LOCA l

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  • SURGE AND ACCUMULATOR NOZZLE BREAK ANALYSES NOT i REQUIRED DUE TO LBB IN EXISTING LICENSING BASIS
  • REANALYZED LOCA BREAKS TO INCORPORATE RSG HYDRAULIC i FORCES '

i t

- RESIDUAL HEAT REMOVAL

- SAFETY INJECTION i t

- PRESSURIZER SPRAY I 4

- NORMAL LETDOWN  !

-- NORMAL CHARGING PRELIMINARY RESULTS i

= RCS PIPING STRESSES REMAIN IN COMPLIANCE WITH EXISTING DESIGN BASES  !

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  • EQUIPMENT NOZZLE LOADS REMAIN IN COMPLIANCE WITH EXISTING DESIGN BASES 4 a i . 32 f i l 4  !
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l SOUTII TEXAS PROJECT ELECTRIC GENERATLNG STATION ~ '

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UNIT I STEAM GENERATOR REPLACEMENT PROJECT c

! i i WORK IN PROGRESS

  • ADDITIONAL EVALUATION REQUIRED AFTER COMPARTMENT PRESSURIZATION FORCES ARE FINALIZED

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= EVALUATING AUXILIARY LINES FOR INCREASED SEISMIC ANCHOR '

!. MOVEMENTS

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SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION - * *

. UNIT I STEAM GENERATOR REPLACEMENT PROJECT ^* I I

RCS EOUIPMENT SUPPORTS ANALYSIS '

  • INCLUDED RSG, RCP, AND ' REACTOR VESSEL SUPPORTS
  • SUPPORTS REANALYZED FOR RSG DEADWEIGHT, THERMAL,

. . SEISMIC, AND PIPE RUPTURE LOADS I

  • RESULTS l

SUPPORT LOADS INCREASE  !

SUPPORTS REMAIN IN COMPLIANCE WITH EXISTING DESIGN BASES  :

NO SUPPORT MODIFICATIONS ANTICIPATED 2

i

RCB INTERNAL STRUCTURES BEING EVALUATED FOR INCREASED LOADS

-l i

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1 I 34

SOUTII TEXAS PROJECT ELECTRIC GENERATING STATION -

LEAK-BEFORE-BREAK EVALUATION I

. SRP 3.6.3 METHODOLOGY WITH RCS ANALYSIS LOADS AND PLANT SPECIFIC CMTRs

  • PIPE GEOMETRY, LOADING, AND FRACTURE TOUGHNESS i DETERMINED CRITICAL LOCATION
  • CRITICAL LOCATION REMAINS IN COMPLIANCE WITH SRP 3.6.3 MARGINS
  • EXISTING LBB ANALYSIS CONCLUSIONS REMAIN VALID .

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1 1 35 i i

I _ _ _ -

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' SOUTil TEXAS PROJECT ELECTRIC GENERATING STATION -

~

UNIT I STEAM GENERATOR REPLACEMENT PROJECT '

MAIN STEAM PIPING STRESS EVALUATION l

36 e -

SOUTli TEXAS PROJECT ELECTRIC GENT. RATING STATION -

UNTT I STEAM GENERATOR REPLACEMENT PROJECT -

MAIN STEA.M PIPING STRESS EVALUATION .

I EXISTING PIPING ANALYSIS REVIEWED FOR CHANGES

  • LOAD COMPONENTS EVALUATED -

- WEIGHT

- THERMAL  ;

i

- SEISMIC INERTIA '

- DESIGN BASIS ACCIDENT

- STEAM HAMMER

- LOCA EFFECTS

  • SEISMIC ANCHOR MOVEMENTS ANALYZED -

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SOUTII TEXAS PROJECT ELECTRIC GENERATING STATION -

)

i 1

PRELIMINARY RESULTS l = SUPPORT LOADS AND PIPING STRESSES REMAIN IN COMPLIANCE c WITH EXISTING DESIGN BASES  ;

3 i

WORK IN PROGRESS

  • L = SEISMIC ANCHOR MOVEMENTS TO BE REVIEWED AFTER COMPARTMENT PRESSURIZATION FORCES ARE FINALIZED i

{

  • IMPACT OF FW/AFW BREAK JET IMPINGEMENT i I

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38 i

SOUT!! TEXAS PROJECT ELECTRIC GENERATLNG STATION -

UNIT 1 STEAM GENERATOR PIPLAC5 MENT PROJECT ~'

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\

FEEDWATER/ AUXILIARY FEEDWATER PIPING .-

REROUTING 1

I I I i

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SOUTil TEXAS PROJECT ELECIRIC GENERATING STATION - "

UNIT I STEAM GENERATOR REPLACliMENT PROJECT '*

FEEDWATER/ AUXILIARY FEEDWATER PIPING REROUTING INTRODUCTION OF VIDEOTAPE

  • REROUTING DUE TO ELEVATED FEEDRING DESIGN AND AUXILIARY FEEDWATER NOZZLE AZIMUTH CHANGE FW/AF PIPING, SUPPORT, AND MATERIAL MODIFICATIONS

. ADDED NEW FW AND AF SUPPORTS

  • MODIFIED EXISTING FW AND AF SUPPORTS

= PIPING MATERIAL CHANGED AT NOZZLES TO PROVIDE ADDITIONAL STRENGTH AND REDUCE FLOW-ACCELERATED CORROSION EFFECTS 40

~

SOUTII TEXAS PROJECT ELECTRIC GENERATING STATION UNIT 1 STEAM GENERATOR REPLAC MENT PROJECT '*

SUMMARY

OF FW/AF STRESS ANALYSIS

  • ANALYSIS PERFORMED TO EXISTING DESIGN BASES (DESIGN CODES, ASSOCIATED CODE CASES, AND COMMITMENTS)
  • PIPING AND SUPPORT ANALYSIS RESULTS REMAIN IN COMPLIANCE -

WITH EXISTING DESIGN BASES

  • HELB EFFECTS ATRSG NOZZLE LOCATIONS BEING EVALUATED i

I i

}

ai

SOUTil TEXAS PROJECT ELECTRIC GENERATING STATION - -

UNIT I STEAM GENERATOR REPLACEMENT PROJECT '-

t NSSS/ BOP INTERFACE SYSTEMS EVALUATION .

i I

1 42 l

SOUTII TEXAS PR9]ECT ELECTRIC GENERATLNG STATION

NSSS/ BOP INTERFACE SYSTEMS EVALUATION .

t EVALUATED DUE TO A94 OPERATING PARAMETERS l

t Model E A94 S/G Temperature ( F: 542.9 - 558.0 539.3 - 552.4 Steam Pressure (psia) 986 - 1115 957 - 1066 6

Steam Flow (l0 lbm/hr) 16.40 - 16.96 15.74 - 16.92 Feedwater Temperature ( F) 440 390 -440  :

S/G Tube Plugging (%) 0-10 0 - 10 i i

. 43 ,

^

SOUTil TEXAS PROJECT ELECTRIC GENERATING STATION -

NSSS/ BOP INTERFACE COMPONENTS EVALUATED

e' MAIN STEAM ISOLATION VALVES e' STEAM DUMP VALVES i e

4 FEEDWATER ISOLATION VALVES FEEDWATER CONTROL VALVES f r.

i.
  • S/G BLOWDOWN FLOW CONTROL VALVES

, l j

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o SOUTII TEXAS PROJECT ELECTRIC GENERATLNG STATION .

UNIT 1 STEAM GENERATOR REPLACEMENT PROJECT -*

RESULTS

=

EXISTING S/G SAPETY VALVE AND PORV SETPOINTS AND CAPACITIES REMAIN IN COMPLIANCE WITH EXISTING DESIGN BASES EXISTING MSIV CLOSURE TIME AND MAXIMUM PIPING LOADS l REMAIN BOUNDING 4

STEAM DUMP VALVE CAPACITY SUPPORTS 50% DESIGN BASIS LOAD l REJECTION WITHOUT REACTOR TRIP

=

EXISTING FWIV CLCJURE TIME AND MAXIMUM PIPING LOADS REMAIN BOUNDING e

REQUIRED TECH SPEC MINIMUM AUXILIARY FEEDWATER STORAGE  :

TANK INVENTORYINCREASES SLIGHTLY i

  • EXISTING S/G BLOWDOWN CONTROL VALVE CAPACITY REMAINS BOUNDING i

45

SOUTil TEXAS PROJECT ELECTRIC GENERATING STATION .

l 1

RCP AND CRDM EVALUATIONS

. 46

-l SOUTIf TEXAS PROJECT ELECTRIC GENERATING STATION -

RCP AND CRDM EVALUATIONS PRESSURE BOUNDARY CONSIDERATIONS MINOR NSSS DESIGN OPERATING PARAMETER RANGE REVISIONS  ;

e I REVISIONS TO RCP AND CRDM DESIGN TRANSIENTS DUE TO RSG i

DESIGN OPERATING PARAMETER AND DESIGN TRANSIENT REVISIONS .

= MINOR CHANGES IN HOT AND COLD LEG OPERATING TEMPERATURES BOUNDED BY EXISTING ANALYSES

= FOUR UPSET AND THREE FAULTED DESIGN TRANSIENTS POTENTIALLY IMPACTED RCP AND CRDM i

. TRANSIENT REVISIONS ENVELOPED BY CONSERVATIVE RANGE OF  :

TRANSIENT CONDITIONS IN EXISTING DOCUMENTATION 1

47

.~,

SOUTil TEXAS PROJECT ELECTRIC GENERATING STATION - - i UNIT I STEAM GENERATOR REPLACEMENT PROJECT 1

i 1 RCP BRAKE HORSEPOWER AND HYDRAULIC THRUST fi i-l

  • BRAKE HORSEPOWER REDUCED SLIGHTLY  !

a

. HYDRAULIC THRUST LOAD INCREASE INCLUDED IN ANALYSIS j CONCLUSION  !

l t

I
RCPs AND CRDMs REMAIN IN COMPLIANCE WITH DESIGN BASES i t

SOUTil TEXAS PROJECT ELECTRIC GENERATING STATION

49 '

< J SNUBBERS

.w

.a #v

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(9 UPPER LATERAL SUPPORT LOWER LATERAL SUPPORT

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I s , WIDE FLANGE COLUMNS ha 1/

M0502.001

, . . r SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION - --

UNIT I STEAM GENERATOR REPLACEMEST PROJECT -*

STEAM GENERATOR REPLACEMENT SEQUENCE OSG REMOVAL-MODE 6 AND DEFUELED MODE 3 REMOVE S/G AND RC PIPING INSULATION i

I e CUTSECONDARY PIPING AT S/G NOZZLES e

i REMOVE S/G UPPER SUPPORT SNUBBERS UNBOLT S/G UPPER SUPPORT RING GIRDERS AT SPLICE PLATE e

INSTALL TEMPORARY S/G SUPPORTS (WEDGES, SCREWJACKS, AND CABLES) AT LOWER AND UPPER LATERAL SUPPORTS i

i,

. INSTALL TEMPORARY S/G COLUMN SUPPORTS l

l

  • INSTALL TEMPORARY HOT LEG DEADWEIGHT SUPPORTS j = INSTALL TEMPORARY CROSSOVER LEG DEADWEIGHT SUPPORTS AND TIE-DOWNS
  • INSTALL TEMPORARY FW/AFPIPING SUPPORTS i

51

i.

50UTli TEXAS PROJECT ELECTRIC GENERATING STATION - * -

j ..

UNIT I STEAM GENERATOR REPUsCEMENT PROJECT '*

L OSG REMOVAL e

CUT PRIMARY PIPING AT S/G INLET AND OUTLET NOZZLES '

= ATTACH TEMPORARY LIFTING DEVICE- .

REMOVE COLUMN-TO-LOWER SUPPORT FLANGE BOLTS "

=

REMOVE TEMPORARY S/G SUPPORTS i

e RIG S/G OUT OF CUBICLE i i

REACTOR COOLANT SYSTEM PIPING PREPARATION  !

(

L = DECONTAMINATE PIPING i

l .

I e TEMPLATE PIPING FOR NOZZLE WELD  !

  • TEMPLATE RSG NOZZLES

! e Dli1 ERMINE WELD PREP LOCATIONS BASED ON BEST FIT TEMPLATING -

( ,

  • MACHINE PIPING FOR S/G NOZZLE WELDS t

)

52 i

)

8

] i SOUT11 TEXAS PROJECT ELECTRIC GENERATING STATION - *

UNIT I SW.AM GENERATOR REPLACEMENT PROJECT -*

I 4

RSG INSTALLATION SEOUENCE  !

c

  • RIG S/G INTO CUBICLE i

SECURE BEST FIT CONDITIONS BETWEEN PIPING AND NOZZLES

= SHIM COLUMN SUPPORTS; BOLT LOWER SUPPORT FLANGE i

INSTALL TEMPORARY RESTRAINTS e

REMOVE TEMPORARY LIFTING DEVICE j = MAKE INITIAL WELD PASS AT NOZZLES  !

j -.

COMPLETE FIRST THIRD OF REQUIRED WELDING i e n REMOVE TEMPORARY SUPPORTS AS WELDING IS COMPLETED j e CONNECT MS, FW, SGBD PIPING AND INSTRUMENTATION  !

e INSTALL UPPER RING GIRDER SUPPORTS, SPLICE CONNECTIONS,

SHIMMING, HYDRAULIC SNUBBERS '

i I i i 4

53

.-- _ .__ ~ - _ . . . _______i

~O 50tml TEXA5 IHOJECT ELECTRIC GENERATING STATION - -

[*

UNIT I STEAM GENERATOR REPLACEMENT PROJECT -*

THERMAL EXPANSION TESTING MONITOR / ADJUST THERMAL GAPS DURING PLANT HEATUP

= REACTOR COOLANT PUMP SUPPORTS i-

  • S/G UPPER AND LOWER LATERALS

i i

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. , . ,. s - , ,. _ _ - . . . _ -. -_., .__ -, , _ . _ . . . , _ - , . . _ . , _ . , - . . .-

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' SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION - *

[*

UNIT I STEAM GENERATOR REPLACEMENT PROJECT -'

LICENSING APPROACH 55

C SOUTII TEXAS PFOJECT ELECTRIC GENERATING STATION

  • a UNIT I STEAM GENERATOR REPLACEMENT PROJECT LICENSING APPROACH TECH SPEC CHANGE TO BE SUBM11TED MAY 1998

= REACTOR COOLANT SYSTEM VOLUME

  • STEAM GENERATOR SURVEILLANCES TECH SPEC CHANGE PACKAGE APPLIES TO BOTH UNITS e

MODIFICATIONS TO BE EVALUATED UNDER 10CFR50.59 l

UNREVIEWED SANTY QUESTION ON DOSE CONSEQUENCES WILI BE i SUBMITTED RETRAN WCAP-14882 AND VIPRE WCAP-14565 UNDER NRC REVIEW 56

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