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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20202H8821997-12-0303 December 1997
Final Response to FOIA Request for Documents.Records in App a Being Made Available in PDR & Encl
IA-97-428, Final Response to FOIA Request for Documents.Records in App a Being Made Available in PDR & Encl1997-12-0303 December 1997
Final Response to FOIA Request for Documents.Records in App a Being Made Available in PDR & Encl
ML20202H8981997-10-27027 October 1997
FOIA Request for Listed Pages from Section 19 of General Electric ABWR Ssar
ML20210J3591997-08-11011 August 1997
Transmits Revised Fda for Us ABWR Std Design,Per App 0 of 10CFR52.FDA Allows ABWR Std Design to Be Ref in Application for Const Permit or Operating License,Per 10CFR50 or in Application for Combined License,Per 10CFR52
ML20149J7101997-07-23023 July 1997
Requests That R Simard Be Removed from Service Lists & R Bell Be Added to Svc Lists,Due to Recent NEI Reorganization
ML20148A5701997-05-0202 May 1997
Forwards Affirmation Ltr Complying W/Filing Requirements of 10CFR52.45(d) & 50.30(b) Re Application for Review of ABWR Design Control Document,Rev 4 for Design Certification
ML20196F8771997-03-28028 March 1997
Forwards Licensee ABWR Design Control Document,Rev 4 to Incorporate Changes Needed to Reflect Commission SRM Decisions & Subsequent Discussion W/Staff & to Support Ssar
ML20137G3161997-03-28028 March 1997
Forwards Rev 4 to Ge'S ABWR Design Control Document to Incorporate Changes That Are Needed to Reflect Commission SRM Decisions & Subsequent Discussions W/Staff
ML20147C1041997-01-23023 January 1997
Responds to Requesting Opportunity to Review Design Certification Rule for ABWR Before Sent to Ofc of Fr for Publication.Request Denied
ML20133A9791996-12-18018 December 1996
Approves Rules Certifying Asea Brown Boveri-Combustion Engineering Sys 80+ & General Electric Nuclear Energy Advanced Boiling Water Reactor
ML20133A9811996-12-18018 December 1996
Informs That NRC Has Approved Rules Certifying Two Evolutionary Reactor Designs:Asea Brown Boveri-Combustion Engineering Sys 80+ & GE Nuclear Energy ABWR
ML20133A9871996-12-18018 December 1996
Informs of NRC Approval of Rules Certifying Two Evolutionary Reactor Designs,Asea Brown Boveri-CE Sys 80+ & GE Nuclear Energy ABWR
ML20133A9901996-12-18018 December 1996
Informs That NRC Has Approved Asea Brown Boveri CE Sys 80+ & GE Nuclear Energy ABWR as Evolutionary Reactor Designs
ML20133B0191996-12-18018 December 1996
Informs of Approval of Rules Certifying Two Evolutionary Reactor Designs,Asea Brown Boveri-Combustion Engineering Sys 80+ & GE Nuclear Energys Advanced BWR
ML20128P4981996-09-23023 September 1996
Forwards Proposed Rule Language for 3 Design Certifications Discussed at 960827 NRC Briefing
ML20128N6001996-09-16016 September 1996
Provides Addl Info in Response to Several Questions Raised by Commission During 960827 Briefing on Design Certification Rulemaking
ML20117H3311996-08-30030 August 1996
Forwards GE ABWR Dcd,Rev 3 (Filed in Category A),Abwr Cdm, Rev 8 (Filed in Category a) & ABWR Ssar,Amend 37,Rev 9 (Filed in Category K) to Incorporate Changes Ref in 960701 & s from Jf Quirk
ML20115C0861996-07-0101 July 1996
Forwards GE Providing Background for Need for Proposed Changes to ABWR Design Control Document (Dcd), Markups Incorporating Comments Resulting from Interactions W/Nrc & DCD Markups for Addl Proposed Change
ML20115G2201996-06-10010 June 1996
Provides Comments from Two NRR Organizations on Cdm & Ssar Change Pages.Markups of DCD & Ssar Encl
ML20108D4481996-04-26026 April 1996
Responds to Staff Ltr Re ABWR DCD Change Package Which Recommends That GE Submit All Changes Identified by Foake Program.Ltr Contrary to Previous Understandings
ML20107H3241996-04-16016 April 1996
Forwards marked-up Proposed Changes to ABWR Design Description Resulting from Info Developed in Course of ABWR Engineering Program
ML20108D3111996-04-0303 April 1996
Forwards Marked Up Proposed Changes to ABWR Design Description Resulting from Info Developed in Course of ABWR First-Of-A-Kind Engineering Program
ML20101G9021996-03-22022 March 1996
Forwards Amend 36 to Rev 8 to 23A6100, ABWR Ssar & Rev 7 to 25A5447, Certified Design Matl
ML20101P1231996-03-15015 March 1996
Expresses Appreciation for Opportunity on 960308 to Brief Commission on Views on Design Certification Rules, Particularly W/Respect to Issue of Applicable Regulations
ML20092G0171995-09-15015 September 1995
Forwards Missing Pp 103-117 from Attachment B of from SR Specker on Behalf of GE Nuclear Energy Re Response to Proposed RM for Std Design Certification of Us Advanced BWR Design
LD-95-041, Forwards Response to Ocre 950812 Comment on Design Features of GE Abwr.Disagrees W/Any Suggestion That NRC Extend Favorable Consideration of Comment to Sys 80+ Std Plant Design1995-09-0505 September 1995
Forwards Response to Ocre 950812 Comment on Design Features of GE Abwr.Disagrees W/Any Suggestion That NRC Extend Favorable Consideration of Comment to Sys 80+ Std Plant Design
ML20092B6431995-09-0101 September 1995
Forwards Analysis of Ocre 950812 Supplemental Comments on Design of Abwr,Notice of Final Rule & Statement of Considerations,In Order to Ensure That NRC Has Complete Technical Info on Subj
ML20086G7981995-07-12012 July 1995
Informs of Changes to Svc List,Per Request of Jn Fox
ML20084Q0621995-05-31031 May 1995
Forwards Revised Effective Page Listing for ABWR Design Control Document
ML20078F4271995-01-26026 January 1995
Provides Info for Closure of ABWR FSER Confirmatory Item F1.2.2-2 Previously Addressed in 941222 Closure Ltr
ML20077R9141995-01-17017 January 1995
Forwards Rev 2 to ABWR Design Control Document. Rev of Design Control Document Accompanied by List of Currently Effective Pages.List Provided as Attachment 2
ML20081K9361994-12-22022 December 1994
Documents Closure of ABWR FSER Confirmatory Items
ML20080D3341994-12-22022 December 1994
Forwards Rev 1 to Advanced BWR Design Control Document
ML20077A7471994-11-23023 November 1994
Forwards Revised Fda for Us ABWR Std Design,Per App O of 10CFR52 & Notice of Issuance of Fda
ML20081K9031994-11-18018 November 1994
Forwards Rev 0 to Technical Support Document (Tsd) for ABWR & Updated ABWR Ssar App 19P Markup.Updated Version of App 19P Incorporated as Attachment a to Tsd,As Agreed During 941006 Meeting W/Nrc
ML20073M7221994-11-0404 November 1994
Forwards Proposed Rev to Section 3.8 of DCD Introduction for ABWR Re GE Meeting on 941102
ML20078E6391994-11-0101 November 1994
Forwards Description of Proposed Process for Controlling Changes to Severe Accident Evaluations & Explains Bases for Proposed Process
ML20149G9751994-10-31031 October 1994
Requests That Encl Ltrs Be Distributed to Controlled Copy of Licensee QA Program
ML20149G7081994-10-28028 October 1994
Forwards Rev 0 to ABWR Design Control Document (Dcd). DCD Comprised of Introduction,Certified Design Matl & Approved Safety Analysis Matl.Responses to NRC Comments Requested by Also Encl
ML20081K8881994-10-13013 October 1994
Maintains That Proposition That GE Be Designated in Notice of Proposed Rulemaking as Source from Which Public Could Request Copies of Design Control Document (DCD) Inappropriate.Public Should Obtain Access to DCD from NRC
ML20076F8451994-10-0505 October 1994
Responds to Re Root Cause & Corrective Measures on Unidentified Changes That Occurred in Design Control Document
ML20081K8721994-09-20020 September 1994
Requests That ABWR Final Design Approval (Fda) Be Amended to Provide for Term of 15 Years from Date of Issuance & That,As Provided in SRM on COM-SECY-95-025,FDA Be Updated as Needed to Conform to Any Changes Resulting from Certification RM
ML20149F7681994-09-0707 September 1994
Forwards Rev 0 to Advanced BWR Design Control Document
ML20072T2691994-08-30030 August 1994
Advises That Industry Intends to Comment in Opposition to Applicable Regulations Approach & Proposed Text of Applicable Regulations in Design Certification Rulemaking Proceeding for Both ABWR & Sys 80+
ML20072Q2811994-08-30030 August 1994
Submits mark-up of Previous Version of Design Control Document Introduction Together W/Typed Rev
ML20072C9821994-08-12012 August 1994
Responds to Re NRC Fee Regulations for Design Certification & Request Confirmation of Understanding of 10CFR170
ML20072E3381994-08-0909 August 1994
Requests Addition of Author Name to Svc List for Advanced BWR
ML20072A8451994-08-0303 August 1994
Forwards Chapter 21 17x22 Inch Drawings to Replace Temporary 11x17 Drawings Provided in
ML20071Q9091994-08-0202 August 1994
Forwards Ten Copies of Draft ABWR Design Control Document
ML20070H9651994-07-20020 July 1994
Forwards Rev 7 to 23A6100, ABWR Ssar, Amend 35 & Rev 6 to 25A5447, ABWR Certified Design Matl
1997-08-11
[Table view]
Category:INCOMING CORRESPONDENCE
MONTHYEARML20202H8981997-10-27027 October 1997
FOIA Request for Listed Pages from Section 19 of General Electric ABWR Ssar
ML20149J7101997-07-23023 July 1997
Requests That R Simard Be Removed from Service Lists & R Bell Be Added to Svc Lists,Due to Recent NEI Reorganization
ML20148A5701997-05-0202 May 1997
Forwards Affirmation Ltr Complying W/Filing Requirements of 10CFR52.45(d) & 50.30(b) Re Application for Review of ABWR Design Control Document,Rev 4 for Design Certification
ML20196F8771997-03-28028 March 1997
Forwards Licensee ABWR Design Control Document,Rev 4 to Incorporate Changes Needed to Reflect Commission SRM Decisions & Subsequent Discussion W/Staff & to Support Ssar
ML20137G3161997-03-28028 March 1997
Forwards Rev 4 to Ge'S ABWR Design Control Document to Incorporate Changes That Are Needed to Reflect Commission SRM Decisions & Subsequent Discussions W/Staff
ML20128P4981996-09-23023 September 1996
Forwards Proposed Rule Language for 3 Design Certifications Discussed at 960827 NRC Briefing
ML20128N6001996-09-16016 September 1996
Provides Addl Info in Response to Several Questions Raised by Commission During 960827 Briefing on Design Certification Rulemaking
ML20117H3311996-08-30030 August 1996
Forwards GE ABWR Dcd,Rev 3 (Filed in Category A),Abwr Cdm, Rev 8 (Filed in Category a) & ABWR Ssar,Amend 37,Rev 9 (Filed in Category K) to Incorporate Changes Ref in 960701 & s from Jf Quirk
ML20115C0861996-07-0101 July 1996
Forwards GE Providing Background for Need for Proposed Changes to ABWR Design Control Document (Dcd), Markups Incorporating Comments Resulting from Interactions W/Nrc & DCD Markups for Addl Proposed Change
ML20115G2201996-06-10010 June 1996
Provides Comments from Two NRR Organizations on Cdm & Ssar Change Pages.Markups of DCD & Ssar Encl
ML20108D4481996-04-26026 April 1996
Responds to Staff Ltr Re ABWR DCD Change Package Which Recommends That GE Submit All Changes Identified by Foake Program.Ltr Contrary to Previous Understandings
ML20107H3241996-04-16016 April 1996
Forwards marked-up Proposed Changes to ABWR Design Description Resulting from Info Developed in Course of ABWR Engineering Program
ML20108D3111996-04-0303 April 1996
Forwards Marked Up Proposed Changes to ABWR Design Description Resulting from Info Developed in Course of ABWR First-Of-A-Kind Engineering Program
ML20101G9021996-03-22022 March 1996
Forwards Amend 36 to Rev 8 to 23A6100, ABWR Ssar & Rev 7 to 25A5447, Certified Design Matl
ML20101P1231996-03-15015 March 1996
Expresses Appreciation for Opportunity on 960308 to Brief Commission on Views on Design Certification Rules, Particularly W/Respect to Issue of Applicable Regulations
ML20092G0171995-09-15015 September 1995
Forwards Missing Pp 103-117 from Attachment B of from SR Specker on Behalf of GE Nuclear Energy Re Response to Proposed RM for Std Design Certification of Us Advanced BWR Design
LD-95-041, Forwards Response to Ocre 950812 Comment on Design Features of GE Abwr.Disagrees W/Any Suggestion That NRC Extend Favorable Consideration of Comment to Sys 80+ Std Plant Design1995-09-0505 September 1995
Forwards Response to Ocre 950812 Comment on Design Features of GE Abwr.Disagrees W/Any Suggestion That NRC Extend Favorable Consideration of Comment to Sys 80+ Std Plant Design
ML20092B6431995-09-0101 September 1995
Forwards Analysis of Ocre 950812 Supplemental Comments on Design of Abwr,Notice of Final Rule & Statement of Considerations,In Order to Ensure That NRC Has Complete Technical Info on Subj
ML20086G7981995-07-12012 July 1995
Informs of Changes to Svc List,Per Request of Jn Fox
ML20084Q0621995-05-31031 May 1995
Forwards Revised Effective Page Listing for ABWR Design Control Document
ML20078F4271995-01-26026 January 1995
Provides Info for Closure of ABWR FSER Confirmatory Item F1.2.2-2 Previously Addressed in 941222 Closure Ltr
ML20077R9141995-01-17017 January 1995
Forwards Rev 2 to ABWR Design Control Document. Rev of Design Control Document Accompanied by List of Currently Effective Pages.List Provided as Attachment 2
ML20080D3341994-12-22022 December 1994
Forwards Rev 1 to Advanced BWR Design Control Document
ML20081K9361994-12-22022 December 1994
Documents Closure of ABWR FSER Confirmatory Items
ML20081K9031994-11-18018 November 1994
Forwards Rev 0 to Technical Support Document (Tsd) for ABWR & Updated ABWR Ssar App 19P Markup.Updated Version of App 19P Incorporated as Attachment a to Tsd,As Agreed During 941006 Meeting W/Nrc
ML20073M7221994-11-0404 November 1994
Forwards Proposed Rev to Section 3.8 of DCD Introduction for ABWR Re GE Meeting on 941102
ML20078E6391994-11-0101 November 1994
Forwards Description of Proposed Process for Controlling Changes to Severe Accident Evaluations & Explains Bases for Proposed Process
ML20149G9751994-10-31031 October 1994
Requests That Encl Ltrs Be Distributed to Controlled Copy of Licensee QA Program
ML20149G7081994-10-28028 October 1994
Forwards Rev 0 to ABWR Design Control Document (Dcd). DCD Comprised of Introduction,Certified Design Matl & Approved Safety Analysis Matl.Responses to NRC Comments Requested by Also Encl
ML20081K8881994-10-13013 October 1994
Maintains That Proposition That GE Be Designated in Notice of Proposed Rulemaking as Source from Which Public Could Request Copies of Design Control Document (DCD) Inappropriate.Public Should Obtain Access to DCD from NRC
ML20076F8451994-10-0505 October 1994
Responds to Re Root Cause & Corrective Measures on Unidentified Changes That Occurred in Design Control Document
ML20081K8721994-09-20020 September 1994
Requests That ABWR Final Design Approval (Fda) Be Amended to Provide for Term of 15 Years from Date of Issuance & That,As Provided in SRM on COM-SECY-95-025,FDA Be Updated as Needed to Conform to Any Changes Resulting from Certification RM
ML20149F7681994-09-0707 September 1994
Forwards Rev 0 to Advanced BWR Design Control Document
ML20072Q2811994-08-30030 August 1994
Submits mark-up of Previous Version of Design Control Document Introduction Together W/Typed Rev
ML20072T2691994-08-30030 August 1994
Advises That Industry Intends to Comment in Opposition to Applicable Regulations Approach & Proposed Text of Applicable Regulations in Design Certification Rulemaking Proceeding for Both ABWR & Sys 80+
ML20072C9821994-08-12012 August 1994
Responds to Re NRC Fee Regulations for Design Certification & Request Confirmation of Understanding of 10CFR170
ML20072E3381994-08-0909 August 1994
Requests Addition of Author Name to Svc List for Advanced BWR
ML20072A8451994-08-0303 August 1994
Forwards Chapter 21 17x22 Inch Drawings to Replace Temporary 11x17 Drawings Provided in
ML20071Q9091994-08-0202 August 1994
Forwards Ten Copies of Draft ABWR Design Control Document
ML20070H9651994-07-20020 July 1994
Forwards Rev 7 to 23A6100, ABWR Ssar, Amend 35 & Rev 6 to 25A5447, ABWR Certified Design Matl
ML20070D9381994-07-12012 July 1994
Forwards D-RAP Design Description & ITAAC for Inclusion in Section 3.6 of Cdm & Cdm & Ssar Markups Addressing Minor Corrections
ML20069Q3001994-06-23023 June 1994
Forwards Rev 6 for Ssar Amend 35 & Rev 5 for Certified Design Matl
ML20070E1981994-06-0808 June 1994
Forwards Ssar Markup Indicating Applicable Edtion to UBC, AISI SG-673 & NEMA FB1 to ABWR Ssar.Changes Will Be Included in Amend 35 Mod Package.Notifies That Applicable Edition of Bechtel Rept BC-TOP-3-A Is Rev 3
ML20070E1891994-06-0808 June 1994
Forwards Ssar Markup of Section 1A.2.34 Which Responds to TMI Item III.D.1(1).Mod Makes Section Consistent W/Ts 5.5.2.2.Change Will Be Included in Amend 35 Mod Package Scheduled for Distribution Later This Month
ML20070D9331994-05-26026 May 1994
Forwards Results of Analyses to Assess Impact of Drywell Spray Actuation Following LOCA to Ensure Bounding Scenario
ML20069H2101994-05-25025 May 1994
Forwards 25A5447,Rev 4, ABWR Certified Design Matl & Nonproprietary & Proprietary Version of 23A6100,Rev 5, ABWR Ssar. Proprietary Version of Ssar Withheld
ML20069G9301994-05-25025 May 1994
Submits non-proprietary Ssar Amend 35 & Certified Design Material Rev 4 to Listed NRR Recipients
ML20069B1831994-05-25025 May 1994
Resubmits Affidavit for GE Abwr,Proprietary Info Section 18H, Supporting Analysis for Emergency Control Operation Info
ML20069A7371994-05-20020 May 1994
Forwards Proprietary Ssar Sections 11A.2 & 11A.4 to Specified NRR Recipients Listed on Attachment 1.Encl Withheld
ML20029D4211994-04-29029 April 1994
Forwards Revised Ssar Markups Responding to Commitments Made at 940415 Meeting in Rockville,Md,Including Addl Info Reflecting Locking Mechanisms of Subassemblies & European Experience & Finalized TS for CRD Removal - Refueling
1997-07-23
[Table view] |
Text
n GENucicar Energy l
, Genera Electnc Company 175 Curtre Amae. San Jose, CA 95125 June 14,1993 Docket No. STN 52-001 Chet Poslusny, Senior Project Manager Standardization Project Directorate Associate Directorate for Advanced Reactors and License Renewal Office of the Nuclear Reactor Regulation
Subject:
Submittal Supporting Accelerated ABWR Schedule - Appendices 3C and 19F
Dear Chet:
Enclosed are markups of SSAR Appendix 3C reflecting the FINEL Code and Appendix 19F which mainly incorporates liner tearing.
Please provide a copy of this transmittal to Hans Ashar.
Sincere ,
X J ek Fox Advanced Reactor Programs cc: Norman Fletcher (DOE)
Ai-Shen Liu (GE) i300C2 got0
/b W 9306240460 930614 P
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- ? ABM 2 461 oars 'l Standard Plant REV.A 1
APPENDIX 3C
<- TABLE OF CONTENTS Section 11tle Ease 3C COMPUTER PROGRAMS USEDINTHE l DESIGN AND ANALYSIS OF SEISMIC CATEGORYI STRUCTURES ;
3C.1 INTRODUCTION 3C.1-1 3C.2 STATIC AND DYNAMIC STRUC1 URAL ANALYSIS SYS'IEMS (STARDYNE) 3C.21 l
3C.2.1 Description 3C.2-1 3C.2.2 Validation 3C.21 3C.23 Extent of Application 3C.21 3CJ CONCRETE ELEMENT CR4CKING ANALYSIS PROGRAM (CECAPI 3C3-1 I 3C3.1 Description 3C31 3C3.2 Validation 3C3-1 .!
3C33 Extent of Application 3C3-1 3C.4 FIpiTE EliiMeuT TRoGRAM FOR CRActlOg Adotyst.s ( FIN et) j 3CA, \ h scrtyM en }
3 c . + 2. %Laak 3 C. 4. 3 Ex64 4 Appptug ;
3 3C-il
.i ~
. Amendment 1 I
23A6101 G Standard Plant REV A 3Q.1 INTRODUCTION The following Seismic Category I Structures 4 and their foundations of the nuclear island are analyzed and/or designed using the computer programs described in this appendix.
(1) Reactor Building (2) Concrete Containment Structure (3)bnkYok3Mcky&
i l
l l
l l
Amendment 1 3C-1 I
. ~ _ , _ _ , - __ _ _ . . _
^
23A6100AE Rimederd Plant REV.A 3C.3 ' CONCRETE ELEMENT CRACKING ANALYSIS PROGRAM (CECAP)
' 3C.3.1 Description CECAP computes stresses in a concrete element under thermal and/or nonthermal (real) loads, considering effects of concrete' cracking. _The element represents a section of a concrete shell or slab, and may include two layers of reinforcing, transverse reinforcing, prestressing tendons, and a liner plate.
The program outputs stresses and strains along the element in the concrete, reinforcement, and ,
liner plate, and resultant forces and moments for the composite concrete element.
CECAP assumes linear stress-strain -
relationships for steel and for concrete in !
compression. ' Concrete is assumed to have no !
tensile strength. The solution is an iterative !
process, whereby tensile stresses found initially in concrete are relieved (by cracking) and redistributed in the element. The equilibrium of nonthermal loads is preserved. For thermal effects, the element is assumed free to expand
- inplane, but is fixed against rotation. The capability for' expansion and cracking generally results in a reduction in thermal forces and moments from the initial condition.
3C.3.2 Validation
. 1 CECAP is written and maintained by Bechtel i Power. Corporation (BPC) of San Francisco, l California. Program validation documentation is 1 '
available at BPC in San Francisco.-
3C.3.3 Extent ofApplication This' progra'm is used for the analysis of the reactor building and containment structure.
nSef { h . .,
l
i 1
Amendment 1 ' 3C31
.- . . _ .. x , -
_ . , , . _ , _ _ , - , . _4 . 4 ., -
3C.4 FINITE ELEMENT PROGRAH FOR CRACKING ANALYSIS (FINEL) )
'C.4.1 3 Description FINEL is a proprietary computer program of Bechtel Power Corporation, San Francisco, California. The FINEL program performs a static analysis of stresses and strains in plane and axisymmetric structures by the finite element method. The program performs the non-linear static analysis utilizing a stepwise linear iteration solution I technique. Within each solution cycle, status of all elements is determined and their stiffness adjusted by the program prior to the next iteration cycle. The Von Mises yield criterion is used to determino the status of all ductile materials and brittle materials which are in compression. A ductile material is assumed to yield in all directions when the yield criterion is exceeded. A brittle material is assumed to be cracked in the direction in which the maximum principal stress exceeds the specified tensile stress. The modulus of elasticity for each material is adjusted for the next )
solution cycle to conform to the secant modulus corresponding to the calculated strain in the element following the bilinear stress strain relationship specified. The numerical algorithm assumes that the state of stress which exists when the converged solution is achieved is independent of the stress history of the loading.
i
& CCcnhinued}
3C.4.2 Validation The FINEL code has been extensively used in the past to design reinforced concrete containment structures and to predict the strains and deflections during their structural integrity tests (SIT). The correlation between the predicted and observed deflections and strains during such tests has been very satisfactory. FINEL code predictions have been on the conservative side.
The FINEL code was validated by comparing results based on FINEL with results based on classical solutions. and/or experimental results existing in literature. A further confirmation of its validity is provided by comparison of predicted strains and deformations based on FINEL with the experimental results obtained during SIT on various Bechtel designed containments.
3C.4.3 Extent of Application This program is used for the static load analysis of the reactor building and containment to determine stresses and strains in the various structural elements and resultant forces and moments at selected sections; and is used to evaluate the ultimate strength of the containment.
, w ,- --