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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
[Table view]
Category:TEXT-SAFETY REPORT
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).
ML19324B6831989-10-31031 October 1989
QA Program:Description of Nuclear Power Businesses QA Program, Rev 5
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
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
ML20246A2321989-04-28028 April 1989
Sser Re CESSAR Sys 80 Concerning Steam Generator Tube Vibration
ML20248F3341989-03-31031 March 1989
Design Certification Licensing Review Basis
ML20248B0021989-03-30030 March 1989
App 3A, Discussion of Finite Difference Analysis for Analysis of Pipe Whip, 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
ML20247H4701989-03-30030 March 1989
Chapter 16, Tech Specs, to CESSAR Sys 80+ Std Design
ML20247H4781989-03-30030 March 1989
Chapter 17, QA Program, to CESSAR Sys 80+ Std Design
ML20247J0591989-03-30030 March 1989
Chapter 18, Human Factors Engineering, 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
ML20248C3801989-03-30030 March 1989
App 3.11A, Environ Qualification for Structures & Components, to CESSAR Sys 80+ Std Design
ML20248C3921989-03-30030 March 1989
App 3.11B, Identification & Location of Mechanical & Electrical Safety-Related Sys Components, to CESSAR Sys 80+ Std Design
ML20247H2911989-03-30030 March 1989
Chapter 7, Instrumentation & Controls, to CESSAR Sys 80+ Std Design
ML20247H0331989-03-30030 March 1989
Chapter 6, Esfs, to CESSAR Sys 80+ Std Design.W/One Oversize Encl
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
ML20247H3361989-03-30030 March 1989
Chapter 10, Steam & Power Conversion Sys, to CESSAR Sys 80+ Std Design.W/One Oversize Encl
ML20247H3161989-03-30030 March 1989
Chapter 9, Auxiliary Sys, to CESSAR Sys 80+ Std Design. W/Four Oversize Encls
ML20247H3081989-03-30030 March 1989
Chapter 8, Electric Power, 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
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
ML20246M1121988-12-31031 December 1988
Vol Viii to Resolution of Outstanding Nuclear Fission Product Aerosol Transport & Deposition Issues Wbs 3.4.2
ML20206C7791988-09-30030 September 1988
QA Program
ML20151G1141988-07-15015 July 1988
Design Certification Licensing Review Bases
LD-88-049, Flow Distribution & Tube Vibration:Evaluation of Sys 80 Steam Generator Tube Lane/Economizer Corner Region1988-07-0101 July 1988
Flow Distribution & Tube Vibration:Evaluation of Sys 80 Steam Generator Tube Lane/Economizer Corner Region
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
LD-88-015, Nonproprietary Base Line Level 1 PRA for Sys 80R NSSS Design1988-01-31031 January 1988
Nonproprietary Base Line Level 1 PRA for Sys 80R NSSS Design
LD-88-005, Draft C-E Sys 80+TM Std Design, Design Certification Licensing Review Bases.Response to NRC Comments on Licensing Document Encl1988-01-18018 January 1988
Draft C-E Sys 80+TM Std Design, Design Certification Licensing Review Bases.Response to NRC Comments on Licensing Document Encl
ML20234C6451987-12-31031 December 1987
Safety Evaluation Report Related to the Final Design of the Standard Nuclear Steam Supply Reference System.Cessar System 80.Docket No. 50-470.(Combustion Engineering,Incorporated)
ML20235G9941987-09-30030 September 1987
Response to NRC Evaluation of CEN-315 for Sys 80R
ML20236W0531987-09-11011 September 1987
Amend 12 to CESSAR-F
ML20234D7241987-07-0101 July 1987
Draft Sys 80R Design Certification Licensing Basis Agreement
ML20137H1491985-06-28028 June 1985
Amend 10 to C-E Std Sar.W/Two Oversize Figures
1990-04-30
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l
- SUPPLEMENTAL SAFETY EVALUATION REPORT CESSAR SYSTEM 80 L
5.0'~ REACTOR COOLANT SYSTEM AND CONNECTED SYSTEMS 5.4- Component and Subsystem Design 5.4.2 Steam Generator 5.4.2.3 Steam Generator Tube Vibration
- 5.4'.2.3.1 Background t
[ \
l Supplement No. 3. to .the CESSAR. SEs tdentified steam generator tube vibration as '
a new issue that was under review by the staff. This issue first came to light-when-Palo Verde Unit l' experienced primary-to-secondary leakage during its initial operating cycle on' January 17, 1987. Mid-cycle and end-of-cycle 1 inspections at Palo' Verde Units 1 and 2 revealed dozens of tubes with tube wall thinning indications at egg crate supports 1 through 5. The affected tubes were
. located primarily in the corner region between the bundle periphery and the tube
. lane at the cold-leg side recirculating fluid inlet region. A small number of the affected tubes were located inboard of the corner region along the tube lane.
The wall thinning indications are the result of the tubes vibrating and rubbing against the tube supports.
5.4.2.3.2 Discussion The original tube and tube support vibration analysis performed in accordance with ASME Code,Section III (1986 edition), showed that the maximum average tube crossflow gap velocity in the cold-leg recirculating inlet region was 9.8 ft/sec, which is well below the critical velocity of 25.5 ft/sec for fluidelastic instability. These results'were consistent with test results from a 30' sector, full-scale model of this region. Hewever, although the analytical and test models were appropriate for assessing average flow conditions in this region, they were not capable of calculating local flow conditions at the corner region and tube
. lane.
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2-Subsequent to the occurrence of the wear indications at Palo Verde Unit 1, more detailed analyses were conducted to evaluate local flow conditions at the corner and tube lane regions. These analyses revealed locally high flow velocities in the corner region reaching 46.2 f t/sec. The locally high flow velocities are predicted to rapidly attenuate to non-critical levels within 10 rows of the periphery of the bundle along the tube lane.
Most tubes that have experienced wear indications to date appear to be located within the region where locally high flow velocities are predicted to occur.
There are a few instances of wear indications in tubes located near the tube lane extending down as far as the tie rod located approximately twenty rows in from the periphery where the flow velocities are not predicted to be abnormally high.
Indications in tubes adjacent to the tie rod are attributed to the limited gap between the tubes and the adjacent tie rod (apparently not modeled), resulting in higher flow velocities through these gaps. However, there are also isolated ,
instances of indications in tubes along the tube lane located between the corner region of locally high flow velocities and the immediate location of the tie rod.
By letter dated July 1,1988, Combustion Engineering submitted a CESSAR change package to document the potential for the subject vibration / wear phenomenon.
The CESSAR changes recommend that owners institute a program to plug and stake all susceptible tubes with indicated tube wear or preventively plug and stake tubes in the corner regions that have the potential to experience this wear.
It is also recomended that this program include monitoring and periodic inspections as part of the inservice inspection program. CE recommends that criteria be established so that tubes exhibiting wear are preventively plugged and staked.
5.4.2.3.3 Evaluation On the basis of its review of the CE analyses and the initial operating experience at Palo Verde Units 1, 2, and 3, the staff believes that programs similar to that recommended by CE can provide adequate assurance of tube integrity. However, the CE recommendations in the CESSAR change package are not specific as to which tubes should be preventively plugged before initial
d plant operation. hor are the CE recommendations specific as to the criteria for monitoring, inspecting, and plugging of tubes with respect to the vibration /
wear phenomenon. Therefore, the specifics of these programs most be addressed !
on a plant specific basis. For operating license (OL) applicants (e.g.,
WNP-3), these programs r.ust be submitted before issuance of an operating license. For operating plants, the staff is monitoring licensee actions to ensure that they are adequately effective in ensuring steam generator tube i ntegr-i ty. .
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