ML20133J064
| ML20133J064 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood  |
| Issue date: | 01/13/1997 |
| From: | Dick G NRC (Affiliation Not Assigned) |
| To: | NRC (Affiliation Not Assigned) |
| References | |
| NUDOCS 9701170381 | |
| Download: ML20133J064 (77) | |
Text
_ _ _ .- _ . _ _ _ _ _ _ . _ - - . - . _ _ _ . - - - - - - - -
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\ g UNITED STATES NUCLEAR REGULATORY COMMISSION
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- / January 13, 1997 l LICENSEE: Commonwealth Edison Company (Comed) l j
FACILITIES: Byron Station, Unit I and Braidwood Station, Unit 1 i SuletARY: SultfARY OF STEAM GENERATOR REPLACEMENT MEETING-AUGUST 21, l 1996
! l
! On August 21, 1996, the subject meeting was held to provide an opportunity for the licensee to discuss the status of its steam generator replacement program l with the NRC staff. Major topics of discussion were the containment opening i engineering and installation work, and an update of the open items from the
! June 25, 1996, steam generator replacement meeting. Enclosure 1 includes a i list of the meeting attendees. A copy of the licensee's presentation is
! included in Enclosure 2.
1 i During the construction sequence, the license indicated that it intends to de-tension tendons and begin chipping the concrete from the outside of the l containment while reactor defueling is ongoing. The staff questioned the i j prudencey of that step, particularly because of the potential for damaging the !
, containment's steel liner. The licensee responded that since the reactor i j would be depressured, only an intact steel liner would be required in case of l a a fuel accident, and the tool to be used to remove concrete would be carefully j controlled so that no damage to the liner would occur. Nevertheless, the i licensee indicated that they would reevaluate the sequence of steps.
Several items were identified that will require staff review and approval:
3 (1) a TS amendment will be required to permit the plant to operate during the period prior to shutdown for the replacement outage with grease removed from the tendons in the area near where the containment opening will be made. The grease which would be removed during the summer of 1997, would facilitate
! tendon removal during the winter steam generator replacement outage at Byron; (2) the new steam generators will have a primary volume approximately 105 greater that the old ones. The new LOCA peak pressure will remain below the design value of 50 psi but will be approximately 3 psi over the current value thus requiring staff approval; and (3) approval of a new steam generator tube rupture analysis.
The licensee described the process for creating an opening 20 feet wide by 22 feet high in the side of the containment for the changeout of the steam generators. A three dimensional (3-D) finite element analysis model will be used to predict containment behavior under various kinds of loads and loading combinations, such as dead loads, partial prestressing, safe shutdown earthquake load, and heavy lifting and steam generator loads during the steam generator replacement activities. The licensee stated that the model has been used in previous containment analyses. The staff stated an interest in how the model was qualified for the particular application at Byron and Braidwood.
For application to unaltered containment configurations, in which there is a BC miC83 5 COPY ,
9701170381 970113 PDR ADOCK 05000454 P PDR
i '
Byron /Braidwood Power Stations I cc:
Ms. I. Johnson Mrs. Phillip B. Johnson l- Acting Manager, Nuclear Regulatory Services 1907 Stratford Lane Commonwealth Ediscn Company Rockford, Illinois 61107
- Executive Towers West III 4
1400 Opus Place, Suite 500 George L. Edgar
- Downers Grove, Illinois 60515 Morgan, Lewis and Bochius 1800 M Street, N.W.
Mr. William P. Poirier, Director Washington, DC 20036 l Westinghouse Electric Corporation i
! Energy Systems Business Unit Ms. Bridget Little Rorem l
! Post Office Box 355, Bay 236 West Appleseed Coordinator i Pittsburgh, Pennsylvania 15230 117 North Linden Street l
- Essex, Illinois 60935 l Joseph Gallo j Gallo & Ross Attorney General
- 1250 Eye St., N.W. 500 South Second Street j Suite 302 Springfield, Illinois 62701
- Washington, DC 20005 i EIS Review Coordinator i Michael I. Miller, Esquire U.S. Environmental Protection Agency l Sidley and Austin 77 W. Jackson Blvd.
j One First National Plaza Chicago, Illinois 60604-3590 i Chicago, Illinois 60603
- 1111nois Department of i Howard A. Learner NJClear Safety
. Environmental law and Policy Office of Nuclear Facility Safety i Center of the Midwest 1035 Outer Park Drive l 203 North LaSalle Street Springfield, Illinois 62704 i Suite 1390 l Chicago, Illinois 60601 Commonwealth Edison Company
! Byron Station Manager i U.S. Nuclear Regulatory Commission 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 i Regional Administrator, Region III Commonwealth Edison Station
! U.S. Nuclear Regulatory Cosuiission 4450 N. German Church Road I 801 Warrenville Road Byron, Illinois 61010 Lisle, Illinois 60532-4351 U.S. Nuclear Regulatory Conmiission l Ms. Lorraine Creek Sraidwood Resident Inspectors Office i
Rt. 1, Box 182 Rural Route #1, Box 79 l Manteno Illinois 60950 Braceville, Illinois 60407 l Chairman, Ogle County Board Mr. Ron Stephens i Post Office Box 357 Illinois Emergency Services j Oregon, Illinois 61061 and Disaster Agency 110 East Adams Street j Springfield, Illinois 02706 i
e 4
l Chairman Will County Board of Supervisors Will County Board Courthouse Joliet, Illinois 60434 Commonwealth Edison Company Braidwood Station Manager Rt. 1, Box 84 Braceville, Illinois 60407 Document Control Desk-Licensing Commonwealth Edison Company 1400 Opus Place, Suite 400 Downers Grove, Illinois 60515 Mr. H. G. Stanley i Site Vice President l Braidwood Station Commonwealth Edison Company RR 1, Box 84 Bracemille, IL 60407 I
i l
l l
LIST OF MEETING ATTENDEES AUGUST 21, 1996 E
Robert Capra Eric Weiss Raj Goel 1 John Ma James Gavula Chu-yu Liang Ramin Assa M. David Lynch George Dick Commonwealth Edison Daniel Shamblin Jerry Wagner John Schroeder Gary Voss San Mullins Haksoo Kim Bob Waninski David Lippard Frank Lentine Roger Guse David Rogowski Marcia Lesniak Denise Saccomando Saraent & Lundy Brgan Erler Steve Bertheau Bechtel C. L. Reid C. L. Weaver R. A. Hurt Brian Reilly Farhad Farzas Eugene Thomas Fr---tone Technolonies. Inc.
Martin Parece l
Enclosure 1 1
i Byron /BraidwoodReplacement l Steam Generator Project 1
Presentation to the NuclearRegulatory Commission August 21,1996 1
Enclosure 2
n/BraidwoodReplacementSteam '
t eratorProject Introduction t
l.
Dan Shamblin SGR Project Manager i
2 i
i 4l livCS t
+ Review the containment construction opening engineering and installation work with the NRC i
l
+ Provide an update on June 25,1996 meeting open items related to the replacement steam generator i
l 3
Commonwealth Edison Ccmpany high degree symmetry, the 3-D model_ becomes essentially a 2-D model, but with
.the opening in the containment, the symmetry is not present.
The staff indicated that the licensee's approach is consistent with that taken in other steam generator replacements, namely that the majority of the replacement is done under 10 CFR 50.59. However, since the staff and
. Commission are reviewing the entire 10 CFR 50.59 process, changes in acceptable implementation of the ~ precess could result from the reviews. If such changes occurred, the staff would inform the licensee of them as soon as they become known.,
The staff did conduct an audit of the 3-D model in the Bechtel offices on November 18, 1996. Four containment configurations are being analyzed:
(1) detensioned tendons both in the vertical and hoop directions within an area 50 feet wide by 100 feet wide around the opening to obtain the magnitude of the stresses remaining in the concrete near the opening; (2) concrete, tendons, and reinforcing rods removed from the area of the opening; (3) the steel liner removed and the containment subjected to the loads from lifting and transporting the steam generators; and (4) new liner welded in-place, new reinforcing rods and concrete, and all tendons restressed.
The staff determined that while there were a number of benchmarking examples, none precisely matched the situation of a containment structure with an opening as large as that planned for the replacement activities at Byron and Braidwood. A number of computer runs had been performed for the four conditions but the results had not been processed and analyzed to the degree that would permit an immediate assessment of their accuracy. However, the staff was able to make a general comparison of the shear deformations near the opening between B e unmodified containment and that of configuration 2, and found the changes tc be generally as expected. The staff was also able to assess certain types of stress distribution patterns and magnitudes under the area between the load and the opening for configuration 3 and found them to be reasonable. The staff requested that the licensee inform the staff when the i containment modeling is near completion so that the staff may complete its I audit.
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
Enclosures:
- 1. List of Attendees
- 2. Comed Presentation cc/encls: see next page DOCUMENT NAME: BB0821.MTS To r:mive a copy of this document, indicate in the box: "C" = Copy without enciphurgh *E",y Copy with enclosures "N" = No copy 0FFICE PM:PDIII/2 ,f /d LA:PDIII-2 Ed$Q l D:PDIII-2 F l NAME GDICK 7l ft' ( CM00RE P & W aL GBAGuil RCAPRA P DATE 01/09/97 01/( /97" ' '
01/ 0(/97 01/13 /97 0FFICIAL RECORD COPY
Introduction / Objective ..................................................... D. Shamblin Engineering / Licensing Overview .............................. D. Rogowski Containment Construction Opening ......................... J. Schroeder Containment Finite Element Analysis ...................... G. Thomas 4
i da (Continued) -
Containment Construction Issues .......................................... R. Guse Containment Opening Summary ............................................ D. Rogowski Component Engineering Update (Replacement Steam Generator) .
Containment P/T .................................. .. .... .. .... .. ............. M. Parece Response to LOCA and MSLB Steam Generator Tube Rupture .................................. R. Waninski Closing Remarks ...... .......... ........................................ .......... .......... D. Shamblin i
t 5
L
i L'.
' - -. gn/BraidwoodReplacement Steam '
erator Project Engineering andLicensing Overview '
I Dave Rogowski SGR Project Engineer t
l 6 i
Engineering andLicensing
+ Safety evaluation process -
+ Licensing determination effort
/ Engineering schedule
/ Comed review process - Installation engineering activities
+ Containment construction opening licensing determination i
7
I l
t Evaluation Process
+ Comed is critically reviewing the Safety Evaluation process and its application to the SGR Project
+ Sensitive to NRC/ Industry concerns
+ Believes project can be performed under 10CFR50.59 t
i 8
i
Engineering Schedule isos iner isos TaskName Qtr4 Qtr1 Qtr2 Qtr 3 Qtr4 Qtr1 lQtr2 Qtr 3 Qtr4 Qtr1 Otr2 lQtr3 [ Otr4 Detailed Design Work ==' ---neumummmmmmmagi ,
j I i :
Fabrication Engineering m mm iits ;i t
installation Engineering sit mm -
em 1.icensing Determination 1'i MMi 1 m i : I l.icensing Review Pkg Preps *1im m 82 l NRC Review it/I 311d 1 l i n Prepare Field Work Pw j 7i1 1 ,
m 2Js4 Byron Replacement Outage i 2r 4 8,P28 Braidwood Replacement Outage ! lW5 El mum im 9 I
singDetermination Effort Review Process - Installation Engineering Activities
+ Preliminary safety evaluation
+ Licensing issues summary document
+ Design input and analysis document i + Construction technique position paper l + Calculations and analyses
+ Independent technical experts 10
i 1
Evaluation Process :
CognizantEngineer i
+ Protect plant design and licensing basis
+ Review all contractor design deliverables
+ Representation at both sites l
11
i GinHtent Construction Opening
+ Required due to replacement steam generators i'
+ Selected approach - Will not use existing equipment hatch and will not allow movement over spent fuel pool
+ Similar to original containment construction opening 12
+Task Name Engineering Schedule nment Construction Opening Desipinput & Analysis Docurmet secNalProporseen Comed Review 1996 1997 1996 Qtr 4 Qtr 1lQtr2lQtr 3lQtr4 Qtr 1lQtr 2lQtr 3lQtr4 Qtr 1[Qtr2lQtr3lQtr4 1/2 mm 2/13 2/13 4/26 4
Concrete RemovalPoolgen Paper BechtelPropersGen 5/6 um5/31 !
Comed Review 6/3 gamm 8/16 ,
ucensing leeuse Summary Doc.
Bec M el F w i . 2/12usamum5/24 Comed Review :
SI27-m 9/13 ,
Preembery SeMy EM !
sechselProperaden 3/12 6/28 Comed Review 711 mum,10I18 Detailed Desip Acevules 1/2 5/20 13 [t i
+E valuation Process to Date: Containment Construction Opening
+ No unreviewed safety questions identified
+ No Technical Specification changes identified to support modification work
+ Technical Specification change required prior to replacement
/ Tendon grease removal prior to cold weather
/ Technical Specification requirement: "No voids in excess of 5% of the net duct volume"
+ Safety evaluation approach remains appropriate for SG replacement 14
i l
n raidwoodReplacement Steam
+/B erator Project r
Containment Construction Opening ,
John Schroeder SGR Cognizant Engineer i i
15
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I inment Structure & Construction ence
+ Features of Byron /Braidwood containment
+ Planned phases ofconstruction !
+ Analysis approach i
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4 ed Construction Sequence
+ Prior to shutdown
/ Score outline of opening on containment wall
+ During cold shutdown and defueling
/ De-tension and remove tendons
/ Chip concrete & cut rebar (liner plate intact)
+ After defueling
. / Remove liner plate
/ Install construction door
/ Remove / replace steam generators 22 t
inment Opening Restoration + Prior to refueling
/ Installliner plate / NDE liner plate
+ During refueling but prior to heat-up
/ Splice rebar and tendon sheathing / Place concrete / Reinstall and retension tendons /. Perform required testing
+ All work complete prior to entry into hot shutdown 23
inHient Anal 1 3 sis Approach
+ Establish correlation between the original and new containment analysis
+ Evaluate interim conditions consistent with construction -
i sequence
+ Evaluate restored condition ;
1 l, 24 6
. a
+
[ n/BraidwoodReplacement Steam erator Project Containment Finite Element Analysis Gene Thomas . Chief Civil / Structural Engineer Bechtel l 25 i t
i l i
+telRecent SGR & nalysis Experience
+ Palisades SGR - Opening Created in the Wall
/ 6-Buttress Post-Tensioned Containment
/ Vertical, Hoop, and Dome Post-Tensioning Tendons
+ Ginna SGR - Opening Created in the Dome ,
/ Vertical Post-Tensioning Only
/ Conventional Reinforced Dome
+ Turkey Point
/ 6-Buttress Post-Tensioned Containment
/ 3-D Finite Element Analysis of Containment Structure 26
- _- _ _ __ _ _7_
ElententAnalysis
+ 3-D Finite Element Model
/ BSAP Computer Program - Validated & Verified, and Used in Previous Containment Re-analyses
/ Plate /Shell Elements Represent Containment Wall, Buttresses and Dome
/ Fixed Boundary Conditions at Base Slab
/ Refined Mesh at the Opening and Adjacent Areas n
inment- Finite ElementModel sf/ l' ' \ 'TXx MSMV YbNm
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Elensent Analysis, Cont'ti
+ Analysis Approach
/ Baseline Analysis
+ Establish Correlation Between the Original 2-D Axisymmetric Model and the New 3-D Model
/ Interim Conditions (Consistent With Construction Sequence) ,
+ Structure De-tensioned (Concrete Intact) t
+ Structure De-tensioned (Concrete and Rebar Removed, Liner plate Intact) ,
+ Structure De-tensioned (Liner Plate Removed) i
i i Elentent Analysis, Cont'd
+ Analysis Approach, Cont'd
/ Restored Condition i i
+ Structure Retensioned (New Concrete Properties at
, the Opening) t i E l
n Codes andStandards
+ Consistent with the UFSAR
+ Referenced Code: Proposed ASME Section III, Division 2, (Issued for trial use and comment),
April 1973 31
Conditions
+ D =
Dead Load
+ F = Prestressing Loads '
+ T =
Thermal (Uniform and Gradient) Loads
+ E' =
Safe Shutdown Earthquake (SSE)
+ W' = Tornado Wind Load
+ SG = Steam Generator Rigging Loads t
32
I Combinations
+ Consistent with UFSAR
+ Service Load Combinations
/ D + F (With and Without "T")
/ D + F + SG (With and Without "T")
+ Factored Load Combinations !
/ 1.0D + 1.0F + 1.0E' or 1.0W' (With and Without "T") 1 i
33 i
A R Allowable Stresses Concrete Rebar Liner Plate Load Comb Memb Tension Memb Memb & or Memb & Comp Bending Comp Bending i Service Load 0.3 f c 0.45 fc 0.5Fy sc=0.002 sc=0.004 st=0.001 st=0.002 Factored Load 0.6 fc 0.75 fc 0.9 Fy sc=0.005 sc=0.014 st=0.003 st=0.01 1/3 stress allowable increase is allowed when primary loads are combined with j secondary loads (thermal) per ASME Section III, Division 2. 34 t
Elentent Analysis Results
+ Baseline Analysis Results (Calculation is being finalized)
+ Correlate Well With Original Analysis Results 35
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1 99998aes i i i 7 (U/sdp0 asaog genorppogy i 4
ine Analysis Results . Hoop Membrane Force - Internal Pressure 600 - (n500 -
*"*******+=+++**i +
3 400 - a ; i
+ BSAP 1
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a % S 2 8 a 3 3 8 n Height From Base Slab (ft) 37 L
Element Analysis Results
+ Analysis ofInterim Conditions (In progress)
+ Concrete and rebar stresses, and liner plate stress / strain will be demonstrated to be within .
allowable limits. 4
+ Analysis of Restored Conditions (In progress)
+ Tendons will im rmnsioned to the required level of prestressing to maintain their design basis 40-year minimum prestressing force.
+ It is expected that the creep effect of new concrete is .
insignificant and local to the area of the opening.
=
Stress Analysis - Concept Model A: De-tensioned Structure With Opening Model B: Retensioned Structure with New Concrete in Place Stresses in Restored Structure = Model A + Model B r adil l u m i l Hh . l I $
, - a 6 L J Model A Model B 39
. . r CententMaterials
+ Concrete
/ Original Concrete: 5500 psi at 91 days
~
/ New Concrete: 5500 psi at 7 days
+ Low Creep Characteristics
+ Creep Testing
+ Tendon Sheathing
/ Same Material as Original Construction
/ Splice Detail Identical to Original Construction (including the original construction opening) 40
CeMientMaterials, Cont'd
+ Tendon Grease
/ 2090P-4, Same Material as Original Construction
+ Rebar
/ ASTM A 615 (Grade 60), Same Material as Original Construction
/ Cadweld Splice Between New and Existing Rebar
/ Unstaggered Splice (original construction opening was restored using unstaggered Cadweld splice.)
/ Sister Splice Sampling (similar to previous SGR projects - accepted by the NRC) u
l CementMaterials, Cont'd 4
+ Liner Plate (ASTM A 516, Grade 60)
/ Reinstall Existing Liner Plate Section i
/ Spare Liner Plate, Same Material as Original Construction i
/ Butt Weld-(consistent with original design details)
/ NDE Consistent with Original Construction
+ Vacuum Box Test i
+ 100% Magnetic Particle Test i
+ Spot RT i
42 , i
l . - - . - - _ . - - - . . 1 i Hi2111015011
+ Tendon De-tensioning, Removal & Reinstallation
/ Experienced Contractor
/ Grease Removal Prior to SGRO
/ Storage of Removed Tendons
/ Spare Tendons 43
b k n Grease Removal
+ Cold weather effect on grease viscosity
+ To reduce potential tendon damage - grease removal will be performed during warm weather
+ Grease removal (prior to SGRO) from tendon sheathing by pumping l dry air into the sheathing
+ Tendon continues to have corrosion protection
/ End anchorage grease coverage will not be adversely affected
/ Tendon wires were individually coated with Visconorust 1601 Amber prior to installation
/ Tendon wires will have sufficient grease coverage 44
E I i on Grease RemovalMethod ; irmation ; t i
+ Confirmed in a hoop tendon during Byron 2 current refueling outage
+ Tendon Configuration (tensioned, grease cans intact)
+ Pressurize with dry air at one end
+ Monitor grease exiting at opposite end
+ Limited duration
+ Contply with requirements of TS
/ Measure grease volume removed / replaced
/ Inspect for abnormalities (e.g., water presence)
+ Tendon restored to initial condition 4s
)
Rientation, Cont'd
+ Concrete Removal Method
/ Similar to Ginna SGRP t
/ Machine Type - BROKK with Tramac Hammer (or Similar Manufacturer)
/ Mock-Up Test for Craft Training -
i I 46 l i i
a Mock-Up Test andAnalytical uatwns
+ Instrumented Test Block
/ No evidence of resonance build-up
+ AnalyticalStudies
/ Supporttestresults .
+ Visual Observation of Mock-up Test
/ No unusual / unacceptable damage along the chipped surfaces, or at concrete-rebar interface
/ No cracks along the core drill wall
+ FinalInspection of Actual Work
/ No unusual condition was observed 47
~
+n/BraidwoodReplace erator Project Containment Construction Issues i
\
Roger Guse i SGR Construction Engineer 48
es&M4i--hMh---hM e earem- 4+ M44. Eh6- WL4-4-M 4*-h*^*--Em +bNeEmuda= M a-Controland Venfication of ctorActivities .
+ Procedures ~
+ Nuclear Work Requests (NWRs) [
+ Approval ofMaterials i t
+ SIT /ILRT f l
l 49
+ Approximately 40 Construction Procedures
+ Review and Approval Process
/ Engineering Review
/ Construction Review
/ Maintenance Superintendent
~
/ Other Possible Reviews 6
i M i l
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5
)s
_- R ~ W , _ (N _ _ s t s _ e u q _ s e t n _ R i P o kr s _ s s _ o e n w e W s i t Wrv i v e _ r wd _ a i e nO a v y ed l Rl o a i _ 3 HD _. + + +
val ofMaterials and Concrete Design + Bechtel Purchase Specification + Audits + Joint Source Surveillance + Outside Expertise 52
LRT Testing + Structural Integrity Test (SIT)
/ Instrumentation Limited to Area of Construction Opening
+ Integrated Leak Rate Test (ILRT) L I t i i I 53 [
v inment Opening Summary: r its to Date
+ 3D finite element model baseline results correlate well with original analysis results
+ Analysis ofinterim conditions and restored conditions demonstrates all parameters will be within UFSAR and referenced code allowable limits
+ Replacement material will be consistent with original material
+ Determined no unreviewed safety questions
+ One-time technical specification change required for early tendon grease removal
4 enerator +n/BraidwoodStea cementProject Update on June 1996 Presentation to NRC
+ Containment P/T Response to MSLB + Containment P/T Response LOCA + Steam Generator Tube Rupture 55
+ n/BraidwoodReplacementSteam eratorProject ContainmentP/TResponse to LOCA andMSLB Marty Parece .
Principal Engineer - Framatome l s t
~
inmentResponse to LOCA + RSGs increase primary side volume by 10% + RSGs have larger stored energy + RSGs increase peak pressure through reflood by about 3 psi + RSGs increase peak temperature through reflood by about 4 F - + These penalties were applied to the design i basis response f 57 __ - --- -_--__- __ _t
l t inmentResponse to LOCA Conclusion
+ Pressure remains below the design value of 50.0 psi :
+ Temperature remains within the design /EQ envelope l i
i i t 58 l I f
_ . . . _ _ . ~ _ . _ _ _ _ _ __ _ .______. ..___.- -._ . _ . . _ _ _ . . . _ . - - . _ _ . _ . _ _ _ _ _ . . _ . _ . h h Limiting LBLOCA Containment Temperature Response (DEPS Break with klinimum ECCS)With RSG Penalty Applied 350 , r 300 \ , i i e E 2s0 p-- -f~ %. ^ y i 7 ,
\ %", %
l
's !
S i
> 200 s
N , c ,, m 150 N' 100 ! 1E+00 1E+01 1E+02 1E+03 1E+04 1E+05 1E+06 l OSG --- RSG - EQ Envokpo l l 59
esponse to Main Steam
+inment R Break (MSLB)
+ RSGs have greater heat transfer area l
+ RSGs have greater secondary side mass inventory at the proposed operating level
+ A spectrum of SLB cases was analyzed including:
/ Various power levels
/ A range ofbreak failures t
/ Different single failures -
/ With and without offsite power l + Mass & energy releases computed with RELAP5/ MOD 2-BW
+ Containment response computed with CONTEMPT 60 i l
+
i t I inmentResponse to MSLB Containment SLB Run Matrix l Case Brook Broek Power FeNure Offsite Type Site % Power j n' Aveu 1 DER' 4.4 102 MSIV' Y 2 N
" *
- 8 3 MFIV Y 4 DIE 8EL N i 5 SPRAY Y 6 COOLER Y 7 SPLI1* 1.1 DOESEL N 8 SPRAY Y t
9 COOLER Y. t 9e 1.2 Y 96 1.6 Y Sc 1.0 Y Dd 1.3 Y ,
*
- f in 1.1 MFIV Y 5 11 MSIV Y l
i 61 j i i l
+
I t inmentResponse to MSLB 12 SPUT 0.9 DIESEL N 13 SPRAY Y 14
- COOLER Y '
15
- MFIV Y 16 MSly Y 17 DER 4.4 70 DIESEL N 18 COOLER Y 19
- SPRAY Y 20
- MFIV Y 21 MSly Y 22 SPUT 0.9 70 DOESEL N 23 SPUT 0.9 70 SPRAY Y 24
- COOLER Y, M * *
- MV Y 26 MStV Y 27 SPUT 1.1 COOLER Y 28 DER 4.4 30 MSlV Y 29 SPUT 0.9 30 COOLER Y DER ineScotes e doutile ended ruptwo in wNch there le no communiceton between the two sidea 8
of thetreelt MSIV follwe le e follwe of the steem locleSon volve on the faulted steem generator.
- MFIV follwe lo e follwe of the main foodwater looienon volve on the faulted steem generator SPUT indcates e opNt ruptwo in which communicagon remaine between the two sides of the tweek. 62
inmentResponse to MSLB j Conclusion
+ Peak Pressure (36 psig) is within the design value (50 psig)
+ Temperature response is within desigq/EQ envelope i
t 63 i
+ O inmentResponse to MSLB ' l Containment Temperature Response for 1.1 Sq. Ft. Split SLB at Fedi Power 3.50E+02 ! l i 3.00E+02
\
- 2. 0E.02 e ~
Y f l TEMPERATURE "EQ ENVELOPE f 2.00E+02
/
1.50E+02
, /
" r*
/ .
1 I 1.00E+02 1 10 100 1000 10000 THIE. SEC 3 I f l
_, . . . _ . - . _ . . ,. - n. . - . . _ -- i l l l j l N M / j E w h2
.e i we EW kQ i J lI
+
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e BBERE EL . e e e e e gI m I I a I+ I- I a Ia I. Desd'ainssaud 1
)
1 l 1 1
de ContainnsentMSLB
+ A spectrum of MSLB cases was analyzed to calculate the temperature response of subcompartments outside containment (steam tunnel)
+ Cases include break sizes from 0.1 ft2 to 4.4 ft2
+ Powerlevels of102% and 70%
+ Limiting cases were found for subcompartment temperatures at i
/ time of MSIV closure -
/ long-term peak i
+ The calculated subcompartment vapor temperatures for all cases are less than the EQ limit i 66 .
l I n/BraidwoodReplacementSteam 4 eratorProject i Steam Generator Tube Rupture Bob Waninski
- i SGR Project Engineer i
w
- _ _ - - - _ - _ _ - - _ __ o
Generator Tube Rupture + Using NRC-approved RETRANO2 SGTR model (Byron /Braidwood-specific'i + RSGs physically different
/ Decreased secondary side volume / Smaller diameter tubes . / Larger heat transfer surface area
+ Using the RSG physical differences in the analysis, RSGs overfill j 68 ;
~
Generator Tube Rupture P
+ RSG physical characteristics are fixed ;
+ Analysis inputs that can be adjusted are:
/T gyg '
i
/ Operator actions i
+ RSG will have margin to overfill (MTO) t
+ Analysis to be submitted for NRC review and approval 69
+ n/BraidwoodReplacementSteam eratorProject ClosingRemarks Dan Shamblin - SGR Project Manager 70 j
iredLicensingReviews
+ Cleanup / administrative technical specification changes ,
/ Items relating to degraded steam generators
/ Revision to containment peak pressure - bases section only
/ Revision to RCS volume - design features section only
+ Changes intended to take advantage of additional design margin
/ Table 2.2-1 S/G water level low-low trip setpoint
+ Early tendon grease removal (limited time only) ,
+ Licensing basis associated with SG fube rupture analysis 71 l
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