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Category:REFERENCE SAFETY ANALYSIS REPORT & AMENDMENTS (RSAR)
MONTHYEARML20042E9171990-04-30030 April 1990
Amend G to C-E SAR Design Certification
ML20011D5171989-12-15015 December 1989
Amend F to C-E Std SAR - Design Certification (CESSAR-DC).
ML20248C3801989-03-30030 March 1989
App 3.11A, Environ Qualification for Structures & Components, to CESSAR Sys 80+ Std Design
ML20247G6661989-03-30030 March 1989
Chapter 1, Introduction & General Plant Description, to CESSAR Sys 80+ Std Design.W/One Oversize Encl
ML20247G6781989-03-30030 March 1989
Chapter 2, Site Envelope Characteristics, to CESSAR Sys 80+ Std Design
ML20247G7141989-03-30030 March 1989
Chapter 3, Design of Structures,Components,Equipment & Sys, to CESSAR Sys 80+ Std Design
ML20247G8511989-03-30030 March 1989
Chapter 4, Reactor, to CESSAR Sys 80+ Std Design
ML20247G8621989-03-30030 March 1989
App 4A Sys 80 Reactor Flow Model Test Program, to CESSAR Sys 80+ Std Design
ML20247G8681989-03-30030 March 1989
App 4B, Hot Loop Flow Testing of Sys 80 Fuel & Control Element Assembly Components, to CESSAR 80+ Std Design
ML20247G9131989-03-30030 March 1989
Chapter 5, RCS & Connected Sys, to CESSAR Sys 80+ Std Design.W/Two Oversize Encls
ML20247G9281989-03-30030 March 1989
App 5A, Overpressure Protection for C-E Sys 80 Pwrs, to CESSAR Sys 80+ Std Design
ML20247G9831989-03-30030 March 1989
App 5B, Structural Evaluation of Steam Line Break for Steam Generator Internals, to CESSAR Sys 80+ Std Design
ML20247G9891989-03-30030 March 1989
App 5C, Structural Evaluation of Feedwater Line Break for Steam Generator Internals, to CESSAR Sys 80+ Std Design
ML20247H0331989-03-30030 March 1989
Chapter 6, Esfs, to CESSAR Sys 80+ Std Design.W/One Oversize Encl
ML20247H2911989-03-30030 March 1989
Chapter 7, Instrumentation & Controls, to CESSAR Sys 80+ Std Design
ML20247H3081989-03-30030 March 1989
Chapter 8, Electric Power, to CESSAR Sys 80+ Std Design
ML20247H3361989-03-30030 March 1989
Chapter 10, Steam & Power Conversion Sys, to CESSAR Sys 80+ Std Design.W/One Oversize Encl
ML20248C3921989-03-30030 March 1989
App 3.11B, Identification & Location of Mechanical & Electrical Safety-Related Sys Components, to CESSAR Sys 80+ Std Design
ML20248B0021989-03-30030 March 1989
App 3A, Discussion of Finite Difference Analysis for Analysis of Pipe Whip, to CESSAR Sys 80+ Std Design
ML20247J0591989-03-30030 March 1989
Chapter 18, Human Factors Engineering, to CESSAR Sys 80+ Std Design
ML20247H4781989-03-30030 March 1989
Chapter 17, QA Program, to CESSAR Sys 80+ Std Design
ML20247H4701989-03-30030 March 1989
Chapter 16, Tech Specs, to CESSAR Sys 80+ Std Design
ML20247H4531989-03-30030 March 1989
App 15C, Analysis Methods for Steam Line Breaks, to CESSAR Sys 80+ Std Design
ML20247H4431989-03-30030 March 1989
App 15B, Methods for Analysis of Loss of Feedwater Inventory Events, to CESSAR Sys 80+ Sys Design
ML20247H4271989-03-30030 March 1989
App 15A, Loss of Primary Coolant Flow Methodology Description, to CESSAR Sys 80+ Std Design
ML20247H4171989-03-30030 March 1989
Chapter 15, Accident Analyses, to CESSAR Sys 80+ Std Design
ML20247H4031989-03-30030 March 1989
Chapter 14, Initial Test Program, to CESSAR Sys 80+ Std Design
ML20247H3971989-03-30030 March 1989
Chapter 13, Conduct of Operators, to CESSAR Sys 80+ Std Design
ML20247H3941989-03-30030 March 1989
Chapter 12, Radiation Protection, to CESSAR Sys 80+ Std Desing
ML20247H3601989-03-30030 March 1989
App 11A, Core Residence Times, to CESSAR Sys 80+ Std Design
ML20247H3531989-03-30030 March 1989
Chapter 11, Radwaste Mgt, to CESSAR Sys 80+ Std Design
ML20247H3161989-03-30030 March 1989
Chapter 9, Auxiliary Sys, to CESSAR Sys 80+ Std Design. W/Four Oversize Encls
ML20150B8181988-06-30030 June 1988
Amend C to CESSAR-DC
ML20151H8191988-04-11011 April 1988
CESSAR-DC Submittal Group B - Revs to Chapters 1,4,5 & 9
ML20236W0531987-09-11011 September 1987
Amend 12 to CESSAR-F
ML20054C1001982-03-31031 March 1982
Amend 7 to CESSAR-F
ML20039D4701981-11-20020 November 1981
Amend 6 to CESSAR-F
ML19350E0871981-06-15015 June 1981
Amend 3 to Chapter 4 of C-E CESSAR-F, Reactor.
ML20003C2771981-02-20020 February 1981
Amend 1 to CESSAR-F
1990-04-30
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML20210R2131997-05-31031 May 1997
Final Safety Evaluation Report Related to the Certification of the System 80+ Design.Docket No. 52-002.(Asea Brown Boveri-Combustion Engineering)
ML20148A8211997-01-31031 January 1997
Abb System 80+ Design Control Document - Volume 1
ML20078Q4311995-02-28028 February 1995
Revs to Sys 80+ Design Control Document
ML20080E2051995-01-0505 January 1995
Rev 2 to Technical Support Document for Amend to 10CFR51 Considering Severe Accidents Under NEPA for Plants of Sys 80+ Design
ML20076F3301994-10-0707 October 1994
Rev 1 of Technical Support Document for Amends to 10CFR51 Considering Severe Accidents Under NEPA for Plants of Sys 80+ Design
ML20069N4091994-06-20020 June 1994
System 80+ Certified Design Material
ML20029E1991994-05-0606 May 1994
Technical Support Document for Amends to 10CFR51 Considering Severe Accidents Under NEPA for Plants of Sys 80+ Design.
ML20062L8631993-12-31031 December 1993
Certified Design Matl
ML20058E9971993-11-15015 November 1993
Amend T to C-E Std SAR - Design Certification. W/31 Oversize Figures
ML20062J3551993-10-29029 October 1993
C-E Ssar - Design Certification,Amend S. W/15 Oversize Encls
ML20058N1001993-09-23023 September 1993
Rev 2 to Design Alternatives for Sys 80+ Nuclear Power Plant
ML20046B3621993-07-15015 July 1993
Session 3.7;Review of SG Tube Rupture Procedure at Borssele Nuclear Power Station.
ML20045D3421993-06-30030 June 1993
Rev 1 to Design Alternatives for Sys 80+ Nuclear Power Plant.
ML20045C4901993-06-30030 June 1993
Evaluation of Sys 80+ Std Design to Interfacing Sys LOCA Challenges, Special Rept
ML20045C6351993-06-15015 June 1993
Amend P to Sys 80+ Cessar - Design Certification.
ML20044G7061993-05-19019 May 1993
Common Mode Failure Evaluation for Limiting Fault Events.
ML20059F4751993-03-29029 March 1993
Application of Advanced Full Scope Simulators to Severe Accident Precursor Training, Presented at 1993 Simulation Multiconference on 930329-0401 in Washington,Dc
ML20044C0061993-03-17017 March 1993
ABB-C-E Sys 80+ Structural Analysis of Nuclear Island & Nuclear Annex Structures.
ML20044B9411993-02-23023 February 1993
Rev 0 to Human Factors Evaluation & Allocation of Sys 80+ Functions.
ML20012G3351993-02-16016 February 1993
Sys 80+ Advanced LWR PRA-Based Seismic Margin Evaluation.
ML20127M4171993-01-15015 January 1993
Control Complex Info Sys Bases for Nuplex 80+
ML20126F6771992-12-0808 December 1992
Review of CE 80+ FMEA & D&Did Analysis, Technical Ltr Rept
ML20126J0521992-10-30030 October 1992
Amend K to C-E Std SAR - Design Certification
ML20126E6191992-10-30030 October 1992
Amend K to CESSAR - Design Certification. W/50 Oversize Encls
ML20012G3361992-09-30030 September 1992
Draft Basis for Seismic Provisions of UCRL-15910.
ML20114F5611992-09-30030 September 1992
Evaluation of Defense-in-Depth & Diversity in ABB-C-E Nuplex 80+ Advanced Control Complex for Sys 80+ Std Design
ML20104A8501992-09-0202 September 1992
Sys 80+ Design Certification PRA Flood Protection Assessment
ML20104A8551992-09-0202 September 1992
Sys 80+ Design Certification Fire Hazard Risk Assessment
LD-92-095, Draft Sys 80+ Design Certification Piping Analysis Specification1992-08-31031 August 1992
Draft Sys 80+ Design Certification Piping Analysis Specification
ML20101S7281992-07-31031 July 1992
Criteria for Design of Main Control Room & Other Operating Stations for Sys 80+
ML20099D8031992-07-31031 July 1992
Final Sys 80+ Shutdown Risk Evaluation Rept
ML20099D8301992-07-25025 July 1992
Draft Sys 80+ Design Certification Distribution Sys Design Guide
ML20101G5261992-06-15015 June 1992
Draft Sys 80+ Shutdown Risk Evaluation Rept
ML20097A1251992-05-31031 May 1992
Human Factors Engineering Stds,Guidelines & Bases for Nuplex 80+
ML20096F7271992-05-0808 May 1992
Nuplex 80+ Human Factors Design Process Summary
ML20095L5041992-04-30030 April 1992
Draft Sys 80+ Shutdown Risk Evaluation Rept, Part 1
ML20095J2321992-04-30030 April 1992
Rev 0 to Design Alternatives for Sys 80+ Nuclear Power Plant
ML20095A9601992-04-15015 April 1992
Selection of Control Motion for ABB-C-E Sys 80+ Std Design
ML20090K4851992-03-12012 March 1992
QA Program Topical Rept
LD-92-031, Marked-up Copy of QA Program Topical Rept1992-03-12012 March 1992
Marked-up Copy of QA Program Topical Rept
ML20094E9431992-02-11011 February 1992
LOCA Aspects of C-E Advanced LWR - Sys 80+
ML20079C9641991-06-13013 June 1991
Description of Nuclear QA Program
ML20043H2201990-05-18018 May 1990
Seminar on Use of Unusual Event Repts for Improving Nuclear Power Plant Safety.
ML20042E9171990-04-30030 April 1990
Amend G to C-E SAR Design Certification
ML20106D7341990-01-15015 January 1990
Nuplex 80+ Advanced Control Complex Design Bases
ML20096F4761989-12-31031 December 1989
Nuplex 80+ Rev 2 to Verification Analysis Rept
ML20011D5171989-12-15015 December 1989
Amend F to C-E Std SAR - Design Certification (CESSAR-DC).
ML19324B6831989-10-31031 October 1989
QA Program:Description of Nuclear Power Businesses QA Program, Rev 5
NUREG-1044, Sser Supporting Vendor Responses to Confirmatory Item 1, Shutdown Cooling Sys1989-08-0404 August 1989
Sser Supporting Vendor Responses to Confirmatory Item 1, Shutdown Cooling Sys
NUREG-0852, Sser Supporting Vendor Responses to Confirmatory Issue 2, Steam Generator Tube Rupture. Calculated Radiological Consequences of Postulated Steam Generator Tube Rupture Accident Meets 10CFR100.11 Dose Ref Values1989-08-0404 August 1989
Sser Supporting Vendor Responses to Confirmatory Issue 2, Steam Generator Tube Rupture. Calculated Radiological Consequences of Postulated Steam Generator Tube Rupture Accident Meets 10CFR100.11 Dose Ref Values
1997-05-31
[Table view] |
Text
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CESSAR !!!nney,o 1
iO APPENDIX 5B STRUCTURAL EVALUATION OF STEAM LINE BREAK FOR STEAM GENERATOR INTERNALS O
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O APPENDIX 5B STRUCTURAL EVALUATION OF STEAM LINE BREAK FOR STEAM GENERATOR INTERNALS i I
ABSTRACT This report documents the structural adequacy of combustion Engineering's (C-E's) System 80+ ALWR steam generator internals D to withstand a steam line rupture.
The steam generator separator deck, shroud and tubes are subjected to a hypothetical steam line break accident. The lD resulting stresses in the structures are compared to ASME Boiler !
and Pressure Vessel Code,Section III allowables to determine the adequacy of the structure.
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O Amendment D September 30, 1988 l i
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(Shast 1 of 1)
CESSAR CERTIFICAT13N O
EFFECTIVE PAGE LISTING APPENDIE 5B I
Table of Contents j ZAgt Amendment Abstract D j i D 11 D Text Pace Amendment 5B-1 D 5B-2 D j Tables O 5B-1 Amendment D
SB-2 D 1
1 1
O Amendment D September 30, 1988
CESSARMinnema !
TABLE OF CONTENTS APPENDIX 5B l
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l; Section Subiect Pace No.
1.0 INTRODUCTION
SB-1 2.0 ANALYSIS SB-1 I
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2.1 DISCUSSION SB-1 2.1.1 HYDRODYNAMIC ANALYSIS 5B-1 D'
2.1.2 STRUCTURAL EVALUATION 5B-1
2.2 CONCLUSION
S 5B-2
3.0 REFERENCES
5B-2 IO l
Amendment D i September 30, 1988 ;
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l CESSAR !a'#"icario.
O LIST OF TABLES APPENDIX 5B Table Subiect 5B-1 Peak Pressure Loads SB-2 Comparison of SYSTEM 80 Margins to Anticipated D SYSTEM 80+ ALWR Margins O
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Amendment D 11 September 30, 1988
CESSAR nahuou 9
1.0 INTRODUCTION
The hydraulic loadings on the steam generator internals resulting from the rupture of one 28.0 inch I.D. main steam line nozzle are calculated using the CEFLASH computer code to perform the hydrodynamic analysis of the steam generator blowdown during the accident. The structural analysis of the System 80+ ALWR steam generator internal parts which are significantly loaded by the Main Steam Line Break (MSLB) accident, as established by the D above CEFLASH analysis, is accomplished by adjusting the stresses calculated for the System 80 steam generator by the differences in pressure loadings and size of the parts. The results of these adjustments show the expected margins of safety for the System 80+ ALWR steam generator to be smaller than the margins for the System 80 steam generator. However, the expected stress levels are still much less than the allowed stress levels defined by the ASME Code,Section III.
2.0 ANALYSIS 2.1 DISCUSSION
\
2.1.1 HYDRODYNAMIC ANALYSIS 9 The hydrodynamic analysis to establish hydraulic pressure loads on the steam generator internals is performed using the CEFLASH computer code. Details of this analysis are given in Reference
- 1. The analysis is done for the 15% and 0% power conditions.
Pressure loadings for the MSLB accident are given in Table SB-1.
The basic assumptions for the MSLB hydrodynamic analysis are:
A. Rupture of one 28.0 inch steam outlet nozzle.
B. A break opening time of .0094 seconds for the rupture of the steam line.
C. A Moody critical flow correlation with a discharge coefficient of 1.0.
2.1.2 STRUCTURAL EVALUATION The structural evaluation of the System 80+ ALWR steam generator internals is based on the structural analysis of the system 80 steam generator internals presented in References 2 and 3. The following internal parts are considered to be significantly loaded by the MSLB accident and are evaluated.
- 1. Separator Deck G 2.
3.
Shroud Tubes Amendment D 5B-1 September 30, 1988
i CESSARESa m O
The basis of evaluation and comparison is the margin of allowable l stress for the System 80 and System 80+ ALWR steam generators. j The margin is calculated as the percentage of remaining allowable j stress, or:
l g, ,
IAllowable Stress - Calculated Stress 1 X 100 Allowable Stress The allowable stress is the elastic allowable stress as defined in the ASME Code,Section III. The margins for the System 80+
ALWR steam generator are based on adjustments of the calculated System 80 stresses by the ratios of hydraulic pressure loading ,
and part size. A comparison of the margins is given in Tablo SB-2. Materials for the parts of the System 80+ ALWR generator are the same as materials for the System 80 generator, except for the tubing. The tube differential pressure is conservatively considered to be 2250 psi during the MSLB event. This is based on the operating pressure with the assumption that the secondary pressure has decayed to zero.
2.2 CONCLUSION
S The results of the evaluation, which are given in Table 5B-2, show that the anticipated margins of the parts for the System 80+
ALWR steam generator are smaller than the calculated margins for the System 80 steam generator. However, the smallest anticipated margin for the System 80+ ALWR generator is 60.0% for the shroud.
Therefore, the separator deck, tubes, and shroud are considered to be adequately designed to withstand a hypothetical Main Steam Line Break accident.
3.0 REFERENCES
- 1. Combustion Engineering Calculation, ST-801, Loads for Steam Line Break, July 1988.
- 2. System 80, CESSAR FSAR, Appendix SB, Amendment No. 7, March 31, 1982.
- 3. Combustion Engineering Report No. CENC-1479, Analytical ,
Report for Arizona Public Service Company, Palo Verde Unit '
No. 3 Steam Generators, August, 1981.
- 4. ASME Boiler and Pressure Vessel Code, Section III for Nuclear Vessels.
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Amendment D
! SB-2 September 30, 19.88 l 3 l
1 CESSARinMema )
l O TABLE 5B-1 l
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PZAE_ PRESSURE _ LOADS 0% and 15% Power AP Time Location (nsi) (sec) Direction l
Separator Deck 28.5 .10 Upward Upper Shroud 29.9 .30 Tension Lower Shroud 35.6 .40 Tension '
Tube Bend Region 26.6 .10 Upward D j s -
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Amendment D September 30, 1988
1 lw!b!h!hMklI !EN flCATCN s
V l TABLE 5B-2 l
COMPARISON OF SYSTEM 80 MARGINS TO ANTICIPATED SYSTEM 80+ ALWR MARGINS Allowable Anticipated Stress Stresa System 80 System 80+ ALWR Part CateqorY (ksil Margin (%) Marcin (%)
Separator Deck PM+PB 73.5 90.7 84.0 0 Stiffener PM+PB 73.5 87.8 80.0 Tubes PM 56.0 68.2 68.2 Shroud PM 49.0 90.8 60.0 O
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l Amendment D l September 30, 1988 ,
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