|
|
(One intermediate revision by the same user not shown) |
Line 9: |
Line 9: |
| | docket = 05000361, 05000362 | | | docket = 05000361, 05000362 |
| | license number = NPF-010, NPF-015 | | | license number = NPF-010, NPF-015 |
| | contact person = Benney B J | | | contact person = Benney B |
| | case reference number = G20120891, TAC MF0060, TAC MF0061 | | | case reference number = G20120891, TAC MF0060, TAC MF0061 |
| | package number = ML13016A077 | | | package number = ML13016A077 |
Line 19: |
Line 19: |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:!" | | {{#Wiki_filter:1 |
| 2.206 PRESENTATION San Onofre Units 2 and 3 Replacement Steam Generators MEETING WITH PETITIONER FRIENDS OF THE EARTH, REQUESTING ENFORCEMENT ACTION AGAINST SOUTHERN CALIFORNIA EDISON UNDER 10 CFR 2.206 January 16, 2013 Presented For Friends of the Earth By Fairewinds Associates Inc, Burlington VT Based Upon Non-Proprietary Information Sequence of Presentation | | 2.206 PRESENTATION San Onofre Units 2 and 3 Replacement Steam Generators MEETING WITH PETITIONER FRIENDS OF THE EARTH, REQUESTING ENFORCEMENT ACTION AGAINST SOUTHERN CALIFORNIA EDISON UNDER 10 CFR 2.206 January 16, 2013 Presented For Friends of the Earth By Fairewinds Associates Inc, Burlington VT Based Upon Non-Proprietary Information |
| #"SECTION 1:
| |
| Chronology of Events SECTION 2:
| |
| Magnitude of Design Changes SECTION 3:
| |
| Conclusions SECTION 1 CHRONOLOGY OF EVENTS
| |
| $"
| |
| Prior To Analysis And Design Of RSGs, Edison Applied To CPUC For RSG Permits According to Southern California Edison s 2004 Annual Report, its application for its Unit 2 and 3 Replacement Steam Generators was filed with the State of California s PUC on February 27, 2004, which was prior to the contract with MHI on September 30, 2004. %"
| |
| In 2004 Edison Contract Language Directed MHI That CFR50.59 Would Not Apply An Edison Whistleblower released the San Onofre Design Specification for RSG. This specification required that CFR50.59 would not apply to the San Onofre RSG s even though an analysis had not yet been completed.
| |
| &"EXCERPTS FROM SONGS Replacement Steam Generator Design & Performance Specifications SO23-617-1 Originator James Chan IRE Jun Gaor FLS David Calhoun SLS Craig Herberts PE Tom Pierno NO& A Bill Kotekkaskos
| |
|
| |
|
| '"
| | Sequence of Presentation SECTION 1: Chronology of Events SECTION 2: Magnitude of Design Changes SECTION 3: Conclusions 3
|
| San Onofre Design Specification For RSG | | |
| #1 3.6.1.1 Edison intends to replace the steam generators under the 10 CFR 50.59 rule. | | SECTION 1 CHRONOLOGY OF EVENTS 4
|
| 3.6.1.2 | | |
| Éthe Supplier shall guarantee in writing that the RSG design is licensable and provide all support necessary to achieve that end.
| | Prior To Analysis And Design Of RSGs, Edison Applied To CPUC For RSG Permits According to Southern California Edisons 2004 Annual Report, its application for its Unit 2 and 3 Replacement Steam Generators was filed with the State of Californias PUC on February 27, 2004, which was prior to the contract with MHI on September 30, 2004. |
| 3.6.1.3 Any deviations from these requirements shall require Edisons approval. | | 5
|
| ("
| | |
| San Onofre Design Specification For RSG | | In 2004 Edison Contract Language Directed MHI That CFR§50.59 Would Not Apply An Edison Whistleblower released the San Onofre Design Specification for RSG. This specification required that CFR§50.59 would not apply to the San Onofre RSGs even though an analysis had not yet been completed. |
| #2 !"#"$% Licensing Topical Report:
| | EXCERPTS FROM SONGS Replacement Steam Generator Design & Performance Specifications SO23-617-1 Originator - James Chan IRE - Jun Gaor FLS - David Calhoun SLS - Craig Herberts PE Tom Pierno NO& A Bill Kotekkaskos 6
|
| The Supplier shall prepare and submit for Edison s approval a Licensing Topical Report demonstrating compliance of the RSG design with all SONGS licensing requirements. The report shall include an engineering evaluation, including all necessary analyses and evaluations, justifying that the RSGs can be replaced under the provisions of 10 CFR 50.59 (without prior NRC approval). ÉThe 10 CFR 50.59 evaluation shall be performed by Edison. | | |
| )"
| | 7 |
| Edison Official Notification To NRC June 2006 Edison Notified NRC of 50.59 Decision in June 2006 A meeting was held on Wednesday, June 7, 2006, between the Nuclear Regulatory Commission (NRC) staff and the SCE, the licensee for SONGS 2 and 3. The meeting was held at the request of the licensee to provide to the NRC staff an overview of the various aspects of its steam generator (SG) replacement project. | | San Onofre Design Specification For RSG #1 3.6.1.1 Edison intends to replace the steam generators under the 10 CFR 50.59 rule. |
| *+,-&!&'-!$-.""!-"
| | 3.6.1.2 the Supplier shall guarantee in writing that the RSG design is licensable and provide all support necessary to achieve that end. |
| JUNE 2006 Edison Presentation to NRC | | 3.6.1.3 Any deviations from these requirements shall require Edisons approval. |
| !!"
| | 8
|
| 2006 NRC Informed of AImprovements Aÿ !/" | | |
| 2006 Edison Accepts Responsibility | | San Onofre Design Specification For RSG #2 3.6.2
Licensing Topical Report: |
| !#"
| | The Supplier shall prepare and submit for Edisons approval a Licensing Topical Report demonstrating compliance of the RSG design with all SONGS licensing requirements. The report shall include an engineering evaluation, including all necessary analyses and evaluations, justifying that the RSGs can be replaced under the provisions of 10 CFR 50.59 (without prior NRC approval). The 10 CFR 50.59 evaluation shall be performed by Edison. |
| Mitsubishi Heavy Industries Was Constrained By The Contract Between the contract award in 2004 and NRC kickoff meeting in 2006, Mitsubishi Heavy Industries had to force fit the RSG analysis and design in order to support Edison s earlier decision determining that 10CFR50.59 did not apply. !$" | | 9
|
| The 10CFR50.59 Process In its January 9, 2013 Response to the NRC, Edison said "As discussed in Section 1.3 of NEI 96-07, changes are evaluated under 10 CFR 50.59 using a multi-step process. !First, a licensee must determine that a proposed change is safe and effective through appropriate engineering and technical evaluations. | | |
| Aÿ>Page 5 ¥!Fairewinds agrees with Edison that this is the correct approach, and it should have been implemented.
| | Edison Official Notification To NRC June 2006 Edison Notified NRC of 50.59 Decision in June 2006 A meeting was held on Wednesday, June 7, 2006, between the Nuclear Regulatory Commission (NRC) staff and the SCE, the licensee for SONGS 2 and 3. The meeting was held at the request of the licensee to provide to the NRC staff an overview of the various aspects of its steam generator (SG) replacement project. |
| ¥!However, this approach was not applied during the RSG Project. Rather this "multistep process" was thwarted by Edison. ¥!No Aappropriate engineering and technical evaluation Aÿ was performed by Edison when the contractual decision was made that 10CFR50.59 would not apply.
| | (ML061670140)
|
| !%"
| | 10
|
| Standard Technical Specifications License Amendment 2009: During the San Onofre Standard Technical Specification License Amendment, Edison identified many areas where the San Onofre Replacement Steam Generator was dramatically different than the Original Steam Generator. | | |
| !&"
| | JUNE 2006 Edison Presentation to NRC 11
|
| San Onofre RSG s Were Not Like-For-Like | | |
| !'"
| | 2006 NRC Informed of Improvements 12
|
| Edison Identified Numerous San Onofre Design Changes | | |
| ¥!Remove Stay Cylinder
| | 2006 Edison Accepts Responsibility 13
|
| ¥!Add 377 Tubes
| | |
| ¥!Change Tube Support Structure
| | Mitsubishi Heavy Industries Was Constrained By The Contract Between the contract award in 2004 and NRC kickoff meeting in 2006, Mitsubishi Heavy Industries had to force fit the RSG analysis and design in order to support Edisons earlier decision determining that 10CFR§50.59 did not apply. |
| ¥!Add New Anti-Vibration Bars
| | 14
|
| ¥!Dozens More ChangesÉ
| | |
| !(" 2011 Edison and MHI Report tout all the design changes implemented in the San Onofre RSG:
| | The 10CFR§50.59 Process In its January 9, 2013 Response |
| !)"SECTION 2 MAGNITUDE OF DESIGN CHANGES
| | * Fairewinds agrees with Edison to the NRC, Edison said that this is the correct approach, and it should have "As discussed in Section 1.3 of been implemented. |
| | NEI 96-07, changes are |
| | * However, this approach was evaluated under 10 CFR 50.59 not applied during the RSG using a multi-step process. First, Project. Rather this "multistep a licensee must determine that process" was thwarted by a proposed change is safe Edison. |
| | and effective through |
| | * No appropriate engineering appropriate engineering and and technical evaluation technical evaluations. Page 5 was performed by Edison when the contractual decision was made that 10CFR§50.59 would not apply. |
| | 15
|
| | |
| | Standard Technical Specifications License Amendment 2009: During the San Onofre Standard Technical Specification License Amendment, Edison identified many areas where the San Onofre Replacement Steam Generator was dramatically different than the Original Steam Generator. |
| | 16
|
| | |
| | San Onofre RSGs Were Not Like-For-Like 17
|
| | |
| | Edison Identified Numerous San Onofre Design Changes 2011 Edison and MHI Report tout all the design changes implemented in the San Onofre RSG: |
| | * Remove Stay Cylinder |
| | * Add 377 Tubes |
| | * Change Tube Support Structure |
| | * Add New Anti-Vibration Bars |
| | * Dozens More Changes 18
|
| | |
| | SECTION 2 MAGNITUDE OF DESIGN CHANGES 19
|
| | |
| | In and of themselves, Edisons design changes to the Replacement Steam Generators should have triggered the 10CFR§50.59 process. |
| | 20 |
| | * The San Onofre tubes and tube sheets are part of the containment boundary and are safety related. |
| | * San Onofre claimed to the NRC that new improved anti-vibration bars would reduce wear on these important components and would not adversely impact their design function. |
| | 21
|
| | |
| | h1p://www.fairewinds.com/content/san-onofres-steam-generator-failures-could-have-been-prevented
22 |
| | Mitsubishi Heavy Industries Should Not Be The Scapegoat If the RSGs had been designed and manufactured in accordance with the procurement specification, the leak and tube wear would never had occurred. Page 12, 1/9/13 Edison Letter to NRC |
| | * The replacement steam generator design developed by Mitsubishi in accordance with the licensees design specification was translated into the same set of design and fabrication drawings. AIT Report, Page 27 |
| | * No matter who fabricated the RSGs for San Onofre, the tube damage would have occurred. The root cause of this problem was the design, not the fabrication. |
| | 23
|
| | |
| | Edison 2003 Annual Report: |
| | San Onofre Identical To Palo Verde Palo Verde Steam Generators The steam generators at the Palo Verde Nuclear Generating Station (Palo Verde), in which SCE owns a 15.8% interest, have the same design and material properties as the San Onofre units. During 2003, the Palo Verde Unit 2 steam generators were replaced. |
| | (Edison 2003 Annual Report, Page 21) h1p://www.edison.com/images/cms_images/c6452_2003_annual_eix_5543.pdf |
| | 24
|
| | |
| | Stay Cylinder: Retained On Palo Verde And Eliminated On San Onofre 25
|
| | |
| | Egg Crate Design Retained On Palo Verde/ |
| | Eliminated On San Onofre BROACHED TUBE SUPPORT EGG CRATE TUBE SUPPORT 26
|
| | |
| | San Onofre Problem Was Foreseeable |
| | * Stay Cylinder removal and Tube addition placed too much heat in the center of San Onofres Replacement Steam Generators |
| | * San Onofre added 4% more tubes at the center of its RSGs |
| | * Palo Verde added 10% to the periphery and added 2.9% more heat |
| | * Palo Verde has no FEI problems |
| | * Edisons Design destroyed San Onofres RSGs 27
|
| | |
| | Contour Of Steam Quality Condition Report: 201836127, Revision 0, 5/7/2012, Figure 2: Contour of steam quality at the height of the maximum quality in U-bend region for T-hot = 598"F (Figure 8.1-2 (a) in Reference [2]), Page 74. |
| | 28
|
| | |
| | What Did The 10CFR§50.59 Review Say? |
| | Edison is parsing its words! |
| | * At the time the RSGs were |
| | * Removing the stay cylinder designed, MHI evaluated the allowed 377 extra tubes flow patterns and into the center void, determined that fluid elastic creating more interior heat instability (FEI) would not |
| | * The riser column water void occur. 1/9/13 Edison brief to above the tube sheet was NRC, page 14 also eliminated |
| | * There was nothing on the |
| | * MHI provided a thermal- steam side to facilitate and hydraulic analysis as part of bias the flow direction. The the original design of the steam side flow patterns RSGs that showed there were never established. |
| | would be no FEI. page 17 |
| | * The 10CFR§50.59 analysis should identify high void fractions and confused in/ |
| | out-of-plane FEI. |
| | 29
|
| | |
| | Friends Of The Earth Consultants Reached A Different 10CFR§50.59 Conclusion |
| | " design changes may be |
| | * Fairewinds agrees with this screened out under 10 CFR approach, but it is not the 50.59 if the changes do not approach used by Edison at adversely affect a design San Onofre. |
| | function Page 9, Edison |
| | * The totality of RSG changes Response, 1/9/13 Edison proposed in 2004 created an unacceptable void "The adverse condition that fraction at the top of the hot later resulted in the tube leak side of the tubes that then was a deficiency associated created the FEI. |
| | with the design and was not |
| | * Fairewinds and John Large both known at the time the 50.59 agree that it should have been evaluation was performed. foreseeable to Edison in 2004 Page 9, Edison Response, that this combination of 1/9/13 changes would cause FEI to occur. |
| | 30
|
| | |
| | Edisons Cause Report Was Wrong |
| | * Former NRC Chairman Gregory Jaczko promised Senator Boxer and the public a complete Root Cause Analysis. This has not been conducted. |
| | * Kepner Tregoe Cause Analysis is severely flawed. |
| | * If they can get you asking the wrong questions, they don't have to worry about answers. Thomas Pynchon, Gravitys Rainbow |
| | * Statement upon which Edison based its Cause Report: |
| | What is different or has changed when comparing SONGS Replacement SGs to Another US plants Replacement SG (page 43, Condition Report) 31
|
| | |
| | What Root Cause Question Should Edison Have Asked? |
| | There are no changes to compare among Edisons RSG and other RSGs nationwide. Its an apples and oranges comparison. |
| | The changes Edison should have analyzed and compared are those between the OSG and the RSG or between San Onofre and Palo Verde, since Edison has acknowledged that Palo Verdes RSG is identical to San Onofres OSG. |
| | 32
|
| | |
| | Exclusions From Edisons Kepner Tregoe (KT) Analysis Process Extracted from the Edison Kepner Tregoe Exclusion Table: Condition Report: 201836127, Revision 0, 5/7/2012, Root Cause Evaluation: Unit 3 Steam Generator Tube Leak and Tube-to-Tube Wear, San Onofre Nuclear Generating Station, Page 52 33
|
| | |
| | SECTION 3 CONCLUSIONS 34
|
| | |
| | THE CHANGES EDISON MADE CREATED FORESEEABLE PROBLEMS During the past eight years, the NRC had extensive evidence from multiple sources that the replacement steam generators at San Onofre were not the like-for-like replacements for the original designs, as Edison committed during the 10CFR50.59 processes. And, as demonstrated by the significant damage in the San Onofre Replacement Steam Generators, the design changes did have a significant impact upon key design functions and in fact degraded the containment boundary. |
| | Edison should have notified the NRC that the significance of all the changes required a 10CFR50.59 license amendment. |
| | 35
|
| | |
| | San Onofre Was A Near Miss The tube failures at San Onofre are the worst nuclear equipment failures since the near miss at Davis Bessie in 2002. |
| | 36
|
| | |
| | San Onofre Technical Specifications San Onofre Technical Specifications states that the limiting design basis accident is a "double ended rupture of a single tube. |
| | Page 510 37
|
|
| |
|
| In and of themselves, Edison Aûs design changes to the Replacement Steam Generators should have triggered the 10CFR50.59 process.
| |
| /-"
| |
| ¥!The San Onofre tubes and tube sheets are part of the containment boundary and are safety related.
| |
| ¥!San Onofre claimed to the NRC that new improved anti-vibration bars would reduce wear on these important components and would not adversely impact their design function.
| |
| /!"
| |
| 0123445556789:;59<=>6?@A4?@<B;<B4>8<C@<@7:;
| |
| Aû>C>B;8ACD;<;:8B@:C789EF:;>C?@FE=C08G;CH;;<C2:;G;<B;="//"
| |
| Mitsubishi Heavy Industries Should Not Be The Scapegoat
| |
| /#" AIf the RSGs had been designed and manufactured in accordance with the procurement specification, the leak and tube wear would never had occurred.
| |
| Aÿ Page 12, 1/9/13 Edison Letter to NRC
| |
| ¥!The replacement steam generator design developed by Mitsubishi É in accordance with the licensee Aûs design specification was translated into the same set of design and fabrication drawings. AIT Report, Page 27
| |
| ¥!No matter who fabricated the RSG s for San Onofre, the tube damage would have occurred. The root cause of this problem was the design, not the fabrication.
| |
| Edison 2003 Annual Report: San Onofre Identical To Palo Verde Palo Verde Steam Generators The steam generators at the Palo Verde Nuclear Generating Station (Palo Verde), in which SCE owns a 15.8% interest, have the same design and material properties as the San Onofre units. During 2003, the Palo Verde Unit 2 steam generators were replaced. (Edison 2003 Annual Report, Page 21
| |
| )! 0123445556;=9>@<6?@A49A8D;>4?A>I9A8D;>4?&$%/I/--#I8<<F8EI;9JI%%$#62=7
| |
| "/$"
| |
| Stay Cylinder: Retained On Palo Verde And Eliminated On San Onofre
| |
| /%"
| |
| Egg Crate Design Retained On Palo Verde/ Eliminated On San Onofre
| |
| /&"BROACHED TUBE SUPPORT EGG CRATE TUBE SUPPORT San Onofre Problem Was Foreseeable
| |
| /'"¥!Stay Cylinder removal and Tube addition placed too much heat in the center of San Onofres Replacement Steam Generators
| |
| ¥!Palo Verde added 10% to the periphery and added 2.9% more heat
| |
| ¥!Palo Verde has no FEI problems
| |
| ¥!Edisons Design destroyed San Onofres RSGs
| |
| ¥!San Onofre added 4% more tubes at the center of its RSGs Contour Of Steam Quality Condition Report: 201836127, Revision 0, 5/7/2012, Figure 2: Contour of steam quality at the height of the maximum quality in U-bend region for T-hot = 598"F (Figure 8.1-2 (a) in Reference [2]), Page 74.
| |
| /("
| |
| What Did The 10CFR50.59 Review Say? Edison is parsing its words!
| |
| ¥!AAt the time the RSGs were designed, MHI evaluated the flow patterns and determined that fluid elastic instability (FEI) would not occur.Aÿ 1/9/13 Edison brief to NRC, page 14
| |
| ¥!AMHI provided a thermal-hydraulic analysis as part of the original design of the RSGs that showed there would be no FEI.
| |
| Aÿ page 17 ¥!Removing the stay cylinder allowed 377 extra tubes into the center void, creating more interior heat
| |
| ¥! The riser column water void above the tube sheet was also eliminated
| |
| ¥!There was nothing on the steam side to facilitate and bias the flow direction. The steam side flow patterns were never established.
| |
| ¥!The 10CFR50.59 analysis should identify high void fractions and confused in/out-of-plane FEI.
| |
| /)"
| |
| Friends Of The Earth Consultants Reached A Different 10CFR50.59 Conclusion
| |
| !"É design changes may be screened out under 10 CFR 50.59 if the changes do not adversely affect a design function Aÿ Page 9, Edison Response, 1/9/13 !"The adverse condition that later resulted in the tube leak was a deficiency associated with the design and was not known at the time the 50.59 evaluation was performed.
| |
| Aÿ Page 9, Edison Response, 1/9/13 ¥!Fairewinds agrees with this approach, but it is not the approach used by Edison at San Onofre. ! ¥!The totality of RSG changes Edison proposed in 2004 created an unacceptable void fraction at the top of the hot side of the tubes that then created the FEI.
| |
| ¥!Fairewinds and John Large both agree that it should have been foreseeable to Edison in 2004 that this combination of changes would cause FEI to occur. #-"
| |
| Edisons Cause Report Was Wrong
| |
| #!"¥!Former NRC Chairman Gregory Jaczko promised Senator Boxer and the public a complete Root Cause Analysis. This has not been conducted.
| |
| ¥!Kepner Tregoe Cause Analysis is severely flawed.
| |
| ¥!If they can get you asking the wrong questions, they don't have to worry about answers.
| |
| Thomas Pynchon, Gravitys Rainbow
| |
| ¥!Statement upon which Edison based its Cause Report:
| |
| What is different or has changed when comparing SONGS Replacement SGs to Another US plant s Replacement SG (page 43, Condition Report)
| |
| What Root Cause Question Should Edison Have Asked? There are no changes to compare among Edisons RSG and other RSGs nationwide. Its an apples and oranges comparison.
| |
| The changes Edison should have analyzed and compared are those between the OSG and the RSG or between San Onofre and Palo Verde, since Edison has acknowledged that Palo Verdes RSG is identical to San Onofres OSG. #/"
| |
| Exclusions From Edison s Kepner Tregoe (KT) Analysis Process Extracted from the Edison Kepner Tregoe Exclusion Table: Condition Report: 201836127 , Revision 0, 5/7/2012, Root Cause Evaluation: Unit 3 Steam Generator Tube Leak and Tube-to-Tube Wear, San Onofre Nuclear Generating Station, Page 52
| |
| ##"
| |
| SECTION 3 CONCLUSIONS
| |
| #$"
| |
| THE CHANGES EDISON MADE CREATED FORESEEABLE PROBLEMS During the past eight years, the NRC had extensive evidence from multiple sources that the replacement steam generators at San Onofre were not the like-for-like replacements for the original designs, as Edison committed during the 10CFR50.59 processes. And, as demonstrated by the significant damage in the San Onofre Replacement Steam Generators, the design changes did have a significant impact upon key design functions and in fact degraded the containment boundary. Edison should have notified the NRC that the significance of all the changes required a 10CFR50.59 license amendment.
| |
| #%"
| |
| San Onofre Was A Near Miss The tube failures at San Onofre are the worst nuclear equipment failures since the near miss at Davis Bessie in 2002. #&"
| |
| San Onofre Technical Specifications San Onofre Technical Specifications states that the limiting design basis accident is a "double ended rupture of a single tube
| |
| . Page 510 #'"
| |
| Edisons San Onofre: | | Edisons San Onofre: |
| Operating Outside Design Basis Eight Tubes failed their pressure test, not one! The evidence shows that San Onofre was operating outside of its design basis and the NRC has done nothing to address this major violation. | | Operating Outside Design Basis Eight Tubes failed their pressure test, not one! |
| AAlthough in this case the degraded condition of the tubes was manifested as a small primary to secondary leak, it is possible that a full-blown rupture could have been the first indication.
| | The evidence shows that San Onofre was operating outside of its design basis and the NRC has done nothing to address this major violation. |
| Aÿ Page 57, NRC AIT Report
| | Although in this case the degraded condition of the tubes was manifested as a small primary to secondary leak, it is possible that a full-blown rupture could have been the first indication. Page 57, NRC AIT Report 38
|
| #("
| | |
| Arnie Gundersen, Chief Engineer Fairewinds Associates, Inc | | Arnie Gundersen, Chief Engineer Fairewinds Associates, Inc Nuclear Engineering, Safety, and Reliability Expert 42-years of nuclear industry experience and oversight ME NE Master of Engineering Nuclear Engineering Rensselaer Polytechnic Institute, 1972 U.S. Atomic Energy Commission Fellowship Thesis: Cooling Tower Plume Rise BS NE Bachelor of Science Nuclear Engineering Rensselaer Polytechnic Institute, 1971, Cum Laude James J. Kerrigan Scholar RO Licensed Reactor Operator U.S. Atomic Energy Commission License # OP-3014 39}} |
| #)"Nuclear Engineering, Safety, and Reliability Expert 42-years of nuclear industry experience and oversight ME NE Master of Engineering Nuclear Engineering Rensselaer Polytechnic Institute, 1972 U.S. Atomic Energy Commission Fellowship Thesis: Cooling Tower Plume Rise BS NE Bachelor of Science Nuclear Engineering Rensselaer Polytechnic Institute, 1971, Cum Laude James J. Kerrigan Scholar RO Licensed Reactor Operator U.S. Atomic Energy Commission License # OP-3014}}
| |
Letter Sequence Meeting |
---|
|
|
MONTHYEARML12325A7482012-11-16016 November 2012 G20120891 - Richard Ayres Ltr. 2.206 - 10 CFR Part 50.59 Review for the Replacement Steam Generators at San Onofre Units 2 and 3 Project stage: Request ML13002A2362012-12-27027 December 2012 Revised Forthcoming Meeting with Petitioner Requesting Action Against Southern California Edison Company Project stage: Meeting ML12347A2682012-12-27027 December 2012 G20120891 - 1/11/2013 - Forthcoming Meeting with Petitioner 2.206 Petition, Richard Ayres, Friends of the Earth 11/16/12 Letter and 10 CFR 50.59 Review for the Replacement Steam Generators at San Onofre, Units 2 and 3 Project stage: Meeting ML13015A2082013-01-15015 January 2013 Public Feedback Form Regarding 1/16/13 Meeting with Friends of the Earth to Provide an Opportunity to Address the NRC PRB, Pursuant to 10 CFR 2.206 Project stage: Request ML13029A6432013-01-16016 January 2013 Official Transcript - Nuclear Regulatory Commission 10 CFR 2.206 Petition Review Board Pre-Meeting with Friends of the Earth San Onofre, Units 2 and 3 (TAC Nos. MF0060 and MF0061) Project stage: Meeting ML13016A0922013-01-16016 January 2013 G20120891, Friends of the Earth Presentation for 1/16/13 Meeting with to Provide an Opportunity to Address the NRC PRB, Pursuant to 10 CFR 2.206. Project stage: Meeting ML13016A0862013-01-16016 January 2013 Fairwinds Presentation for 1/16/13 Meeting with Friends of the Earth to Provide an Opportunity to Address the NRC PRB, Pursuant to 10 CFR 2.206 (TAC Nos. MF0060 & MF0060) Project stage: Meeting ML13016A0822013-01-16016 January 2013 G20120891/San Onofre Nuclear Generating Station,Units 2 and 3- Email from Petitioner Regarding Presentation for 1/16/13 Meeting with Friends of the Earth to Provide an Opportunity to Address the NRC PRB, Pursuant to 10 CFR 2.206(TAC NOS.MF0 Project stage: Meeting ML13109A0752013-02-0606 February 2013 Submission by Friends of the Earth Supplementing Its 10 CFR 2.206 Petition and Responding to Southern California Edison'S 2.206 Response Project stage: Request ML13029A6162013-02-0707 February 2013 G20120891 - San Onofre, Units 2 and 3, Memo to File Audio Recording of 1/16/2013 Public Meeting with Friends of the Earth Regarding Its 10 CFR 2.206 Petition Requesting Action Against Southern California Edison Project stage: Meeting ML13116A2652013-02-12012 February 2013 Request for Disclosure of Mhl Report in the 2.206 Petition Review Process Regarding the 10 CFR Section 50.59 Review for the Replacement Steam Generators at San Onofre, Units 2 and 3 Project stage: Request ML13017A1122013-02-13013 February 2013 G20120891 - Summary of 1/16/2013 Meeting with Petitioner 2.206 Petition, Richard Ayres, Friends of the Earth 11/16/12 Letter and 10 CFR 50.59 Review for the Replacement Steam Generators at San Onofre Project stage: Meeting ML13116A2672013-03-27027 March 2013 Declaration by John Large in Support of 2.206 Petition by Friends of the Earth SONGS Units 2 & 3 Project stage: Request ML13116A2662013-04-0404 April 2013 Ayres Law Group, Submittal of MHI Root Cause Analysis Report and Related Documents Into the Record for the 2.206 Petition Review Process Project stage: Request ML13106A1932013-04-30030 April 2013 G20120891 - San Onofre Nuclear Generating Station, Units 2 and 3 - Acknowledgement Letter to 2.206 Petitioner Friends of the Earth Regarding Steam Generator Tube Leak Project stage: Other ML13106A1952013-04-30030 April 2013 G20120891 - Federal Register Notice, San Onofre Nuclear Generating Station, Units 2 and 3 - Acknowledgement to 2.206 Petitioner Friends of the Earth Regarding Steam Generator Tube Leak Project stage: Other 2013-02-13
[Table View] |
|
---|
Category:Meeting Briefing Package/Handouts
MONTHYEARML21053A4412021-02-23023 February 2021 NRC Staff Slides: Feb 23, 2021 Pre-submission Meeting for San Onofre Nuclear Generating Station (SONGS) ML21042A0772021-02-11011 February 2021 Public-Watchdogs-Langley-Final-02-11-2021 ML20149K4992020-07-0101 July 2020 California Coastal Commission July 2020 Meeting on San Onofre Nuclear Generating Station Independent Spent Fuel Storage Installation Inspection and Maintenance Program ML20178A2482020-06-24024 June 2020 Public Watchdogs 10 CFR 2.206 Petition - E-mail from Public Watchdogs with Presentations for June 24th Public Meeting with the NRC ML20178A2492020-06-24024 June 2020 Public Watchdogs - 10 CFR 2.206 Meeting with NRC - Petition Review Board, June 23, 2020 ML19234A0082019-08-20020 August 2019 Southern California Edison Company, San Onofre Nuclear Generating Station, August 20 2019 NRC Town Hall Meeting Sjc ML19154A1372019-06-0303 June 2019 June 3, 2019, Webinar Slides ML19084A1342019-03-25025 March 2019 NRC Slides for March 25 2019 Public Webinar ML19029B5092019-01-24024 January 2019 Final NRC Presentation for SCE Enforcement Conference ML18353A7492018-12-12012 December 2018 Presentation Slides: NRC SONGS Presentation December 2018, Victor ML18340A1762018-11-29029 November 2018 Southern California Edison Company; San Onofre Nuclear Generating Station; SONGS Community Engagement Panel, November 29, 2018 ML18318A0642018-11-0808 November 2018 Public Meeting Slides with Extra Content ML18312A1182018-11-0808 November 2018 Presentation for San Onofre Special Inspection Webinar November 8, 2018 ML17088A6572017-03-28028 March 2017 2017 RIC Presentation from Yamir Diaz-Castillo Entitled, Current NRC Vendor Findings and the Results from the 1st SONGS Lessons Learned Inspection. ML14216A4512015-02-0909 February 2015 7/31/14 Summary of Closed Meeting with Southern California Edison to Discuss Scope and Schedule Related to Cyber Security License Amendment Request for San Onofre Nuclear Generating Station, Units 2 and 3 ML14303A6392014-10-27027 October 2014 NRC Slides - SONGS PSDAR Public Meeting October 27, 2014 ML14303A6242014-10-27027 October 2014 Licensee'S Slides - SONGS PSDAR Public Meeting October 27, 2014 ML14272A4152014-09-25025 September 2014 SONGS EP RAI Response Review Slides - Public Meeting September 25, 2014 ML14272A4652014-09-24024 September 2014 SONGS Public Meeting Slides (Non-Public Portion) - Public Meeting September 24, 2014 ML14239A4642014-08-28028 August 2014 August 28, 2014, Public Meeting Slides Concerning San Onofre Nuclear Generating Station (SONGS) Decommisioning Quality Assurance Program ML14199A0982014-07-17017 July 2014 SONGS Cep Meeting Slides- Reactor Decommissioning Process ML13268A0032013-09-25025 September 2013 Reactor Decommissioning Process- Presentation for San Onofre 2&3 PSDAR Public Meeting ML13092A2882013-04-0202 April 2013 Licensee Slides for 4/3/13 Pre-Submittal Meeting to Discuss License Amendment Request ML13059A1572013-02-27027 February 2013 Licensee Slides from 2/27/13 Meeting Regarding a Request for Additional Information ML13059A1522013-02-27027 February 2013 NRC Meeting Slides from 2/27/13 Public RAI Meeting ML13016A0922013-01-16016 January 2013 G20120891, Friends of the Earth Presentation for 1/16/13 Meeting with to Provide an Opportunity to Address the NRC PRB, Pursuant to 10 CFR 2.206. ML13016A0862013-01-16016 January 2013 Fairwinds Presentation for 1/16/13 Meeting with Friends of the Earth to Provide an Opportunity to Address the NRC PRB, Pursuant to 10 CFR 2.206 (TAC Nos. MF0060 & MF0060) ML12352A4112012-12-18018 December 2012 NRC Slides for 12/18/12 Meeting with Southern California Edison ML12352A3852012-12-18018 December 2012 Licensee Slides for 12/18/12 Public Meeting ML12346A1162012-12-10010 December 2012 Meeting Summary for November 30, 2012, Meeting with Southern California Edison Company ML12311A0492012-09-18018 September 2012 Part 26 Public Meeting NEI Presentation Slides ML12157A2722012-06-11011 June 2012 5/31/2012 Summary of Telephone Conference with Licensees Regarding Near Term Task Force Recommendation 2.1 Seismic Reevaluations - Diablo Canyon, 1 and 2, San Onofre, Units 2 and 3, Columbia Generating Station, and Palo Verde, Units 1, 2, a ML1115304302011-06-0101 June 2011 Meeting Summary for Public Meeting with Southern California Edison to Present & Discuss the Performance Results for San Onofre Nuclear Generating Station Units 2 & 3 for Period of January 1 Through December 31, 2010 ML1101206302011-01-12012 January 2011 License Amendment Request to Support Use of Areva Nuclear Fuel, Slides from 1/12/2011 Meeting ML1027304522010-09-30030 September 2010 Meeting Summary for 09/16/2010 Public Meeting with Southern California Edison ML0932402122009-11-20020 November 2009 Summary of Public Meeting with Southern California Edison Company on San Onofre Nuclear Generating Station 2009 Performance ML0926502992009-09-22022 September 2009 Summary of Public Meeting with Southern California Edison Regarding Site Improvement Initiatives ML0914905092009-05-28028 May 2009 Summary of Meeting with Southern California Edison Company Several Initiatives That Were Being Implemented to Improve Licensed Operator Training at San Onofre Nuclear Generating Station ML0832408342008-10-30030 October 2008 Licensee Handout for 10-31-08 Call ML0819303742008-06-11011 June 2008 Attachment 2: Presentation Slides by James Shepherd, NRC from June 11, 2008 Public Meeting with SONGS ML0819305432008-06-11011 June 2008 Attachment 3: Presentation Slides, Emilio Garcia, NRC from June 11, 2008 Public Meeting with SONGS ML0819305802008-06-11011 June 2008 Attachment 4: Presentation Slides, James Reilly, SONGS from June 11, 2008 Public Meeting with SONGS ML0729806642007-10-24024 October 2007 Meeting Presentation on Update on Generic Safety Issue 191 Plant Audits ML0727500132007-09-25025 September 2007 9/25/2007 Licensee Handouts for Meeting Re San Onofre Nuclear Generating Station, Unit 3 - Reclassification of Control Rod Drive Mechanism 56 NDE (Non Destructive Examination) Indication ML0720703362007-07-20020 July 2007 Summary of San Onofre Nuclear Generating Station End-Of-Cycle Public Meeting ML0634600722006-11-17017 November 2006 Licensee Information in Support of 11/17/2006 Discussions Steam Generator Tube Inspections - Refueling Outage 14 ML0613604892006-05-0303 May 2006 Meeting Slides, Southern California Edison for San Onofre Nuclear Generating Station (Enclosure 2) M060502, M060502-Briefing on Status of Emergency Planning Activities (Slides)2006-05-0202 May 2006 M060502-Briefing on Status of Emergency Planning Activities (Slides) ML0609601982006-01-23023 January 2006 SONGS 2, Handouts, Information Supplied by SCE in Support of Discussion ML0712401852005-12-31031 December 2005 Reactor Decommissioning Program Lessons-Learned 2021-02-23
[Table view] Category:Slides and Viewgraphs
MONTHYEARML21053A2382021-02-22022 February 2021 Southern California Edison Slides for Feb 23, 2021, Pre-submission Meeting for SONGS Proposed Exemption- 10 CFR 72.106b ML21042A0772021-02-11011 February 2021 Public-Watchdogs-Langley-Final-02-11-2021 ML20178A2482020-06-24024 June 2020 Public Watchdogs 10 CFR 2.206 Petition - E-mail from Public Watchdogs with Presentations for June 24th Public Meeting with the NRC ML20178A2492020-06-24024 June 2020 Public Watchdogs - 10 CFR 2.206 Meeting with NRC - Petition Review Board, June 23, 2020 ML19255F6182019-09-17017 September 2019 Presentation Slides: SONGS Recent Dry Storage Operating Experience ML19235A1892019-08-29029 August 2019 Final NEIMA Meeting Slides - SONGS Presentation ML19234A0082019-08-20020 August 2019 Southern California Edison Company, San Onofre Nuclear Generating Station, August 20 2019 NRC Town Hall Meeting Sjc ML19154A1372019-06-0303 June 2019 June 3, 2019, Webinar Slides ML19084A1342019-03-25025 March 2019 NRC Slides for March 25 2019 Public Webinar ML19029B5092019-01-24024 January 2019 Final NRC Presentation for SCE Enforcement Conference ML19023A0332019-01-24024 January 2019 Southern California Edison Company; San Onofre Nuclear Generating Station, Pre-Decisional Enforcement Conference Slides ML19023A2492019-01-23023 January 2019 NRC Slides for Southern California Edison Conference January 24, 2019 ML18353A7492018-12-12012 December 2018 Presentation Slides: NRC SONGS Presentation December 2018, Victor ML18340A1762018-11-29029 November 2018 Southern California Edison Company; San Onofre Nuclear Generating Station; SONGS Community Engagement Panel, November 29, 2018 ML18318A0642018-11-0808 November 2018 Public Meeting Slides with Extra Content ML18312A1182018-11-0808 November 2018 Presentation for San Onofre Special Inspection Webinar November 8, 2018 ML17088A6572017-03-28028 March 2017 2017 RIC Presentation from Yamir Diaz-Castillo Entitled, Current NRC Vendor Findings and the Results from the 1st SONGS Lessons Learned Inspection. ML14216A4512015-02-0909 February 2015 7/31/14 Summary of Closed Meeting with Southern California Edison to Discuss Scope and Schedule Related to Cyber Security License Amendment Request for San Onofre Nuclear Generating Station, Units 2 and 3 ML14303A6392014-10-27027 October 2014 NRC Slides - SONGS PSDAR Public Meeting October 27, 2014 ML14303A6242014-10-27027 October 2014 Licensee'S Slides - SONGS PSDAR Public Meeting October 27, 2014 ML14272A4152014-09-25025 September 2014 SONGS EP RAI Response Review Slides - Public Meeting September 25, 2014 ML14272A4652014-09-24024 September 2014 SONGS Public Meeting Slides (Non-Public Portion) - Public Meeting September 24, 2014 ML14239A4642014-08-28028 August 2014 August 28, 2014, Public Meeting Slides Concerning San Onofre Nuclear Generating Station (SONGS) Decommisioning Quality Assurance Program ML14199A0982014-07-17017 July 2014 SONGS Cep Meeting Slides- Reactor Decommissioning Process ML13268A0032013-09-25025 September 2013 Reactor Decommissioning Process- Presentation for San Onofre 2&3 PSDAR Public Meeting ML13227A1102013-08-13013 August 2013 8/13/13 Michael F. Weber, Deputy Executive Director for Materials, Waste, Research, State, Tribal, and Compliance Programs Testimony on: the U.S. Nrc'S Power Reactor Decommissioning Process ML13092A2882013-04-0202 April 2013 Licensee Slides for 4/3/13 Pre-Submittal Meeting to Discuss License Amendment Request ML13059A1522013-02-27027 February 2013 NRC Meeting Slides from 2/27/13 Public RAI Meeting ML13016A0922013-01-16016 January 2013 G20120891, Friends of the Earth Presentation for 1/16/13 Meeting with to Provide an Opportunity to Address the NRC PRB, Pursuant to 10 CFR 2.206. ML13016A0862013-01-16016 January 2013 Fairwinds Presentation for 1/16/13 Meeting with Friends of the Earth to Provide an Opportunity to Address the NRC PRB, Pursuant to 10 CFR 2.206 (TAC Nos. MF0060 & MF0060) ML12352A4112012-12-18018 December 2012 NRC Slides for 12/18/12 Meeting with Southern California Edison ML12352A3852012-12-18018 December 2012 Licensee Slides for 12/18/12 Public Meeting ML12346A1162012-12-10010 December 2012 Meeting Summary for November 30, 2012, Meeting with Southern California Edison Company ML12311A0492012-09-18018 September 2012 Part 26 Public Meeting NEI Presentation Slides ML12179A4472012-06-26026 June 2012 6/18/2012 Meeting Summary for Augmented Inspection Team Exit Meeting with Southern California Edison Co ML12157A2722012-06-11011 June 2012 5/31/2012 Summary of Telephone Conference with Licensees Regarding Near Term Task Force Recommendation 2.1 Seismic Reevaluations - Diablo Canyon, 1 and 2, San Onofre, Units 2 and 3, Columbia Generating Station, and Palo Verde, Units 1, 2, a ML1101206302011-01-12012 January 2011 License Amendment Request to Support Use of Areva Nuclear Fuel, Slides from 1/12/2011 Meeting ML0932402122009-11-20020 November 2009 Summary of Public Meeting with Southern California Edison Company on San Onofre Nuclear Generating Station 2009 Performance ML0926502992009-09-22022 September 2009 Summary of Public Meeting with Southern California Edison Regarding Site Improvement Initiatives ML0914905092009-05-28028 May 2009 Summary of Meeting with Southern California Edison Company Several Initiatives That Were Being Implemented to Improve Licensed Operator Training at San Onofre Nuclear Generating Station ML11216A2442008-12-12012 December 2008 0523 - R504P - Westinghouse Advanced Technology - 07.3 - Water Hammer at San Onofre ML0832408342008-10-30030 October 2008 Licensee Handout for 10-31-08 Call ML0828804352008-10-14014 October 2008 Summary of Meeting with Southern California Edison to Discuss Performance at San Onofre Nuclear Generating Station ML0822602532008-08-12012 August 2008 Summary of Meeting on with Southern California Edison Co Regarding the End-of-Cycle Assessment of San Onofre Nuclear Generating Station ML0819303742008-06-11011 June 2008 Attachment 2: Presentation Slides by James Shepherd, NRC from June 11, 2008 Public Meeting with SONGS ML0819305802008-06-11011 June 2008 Attachment 4: Presentation Slides, James Reilly, SONGS from June 11, 2008 Public Meeting with SONGS ML0819305432008-06-11011 June 2008 Attachment 3: Presentation Slides, Emilio Garcia, NRC from June 11, 2008 Public Meeting with SONGS ML0729806642007-10-24024 October 2007 Meeting Presentation on Update on Generic Safety Issue 191 Plant Audits ML0727500132007-09-25025 September 2007 9/25/2007 Licensee Handouts for Meeting Re San Onofre Nuclear Generating Station, Unit 3 - Reclassification of Control Rod Drive Mechanism 56 NDE (Non Destructive Examination) Indication ML0720703362007-07-20020 July 2007 Summary of San Onofre Nuclear Generating Station End-Of-Cycle Public Meeting 2021-02-22
[Table view] |
Text
1
2.206 PRESENTATION San Onofre Units 2 and 3 Replacement Steam Generators MEETING WITH PETITIONER FRIENDS OF THE EARTH, REQUESTING ENFORCEMENT ACTION AGAINST SOUTHERN CALIFORNIA EDISON UNDER 10 CFR 2.206 January 16, 2013 Presented For Friends of the Earth By Fairewinds Associates Inc, Burlington VT Based Upon Non-Proprietary Information
Sequence of Presentation SECTION 1: Chronology of Events SECTION 2: Magnitude of Design Changes SECTION 3: Conclusions 3
SECTION 1 CHRONOLOGY OF EVENTS 4
Prior To Analysis And Design Of RSGs, Edison Applied To CPUC For RSG Permits According to Southern California Edisons 2004 Annual Report, its application for its Unit 2 and 3 Replacement Steam Generators was filed with the State of Californias PUC on February 27, 2004, which was prior to the contract with MHI on September 30, 2004.
5
In 2004 Edison Contract Language Directed MHI That CFR§50.59 Would Not Apply An Edison Whistleblower released the San Onofre Design Specification for RSG. This specification required that CFR§50.59 would not apply to the San Onofre RSGs even though an analysis had not yet been completed.
EXCERPTS FROM SONGS Replacement Steam Generator Design & Performance Specifications SO23-617-1 Originator - James Chan IRE - Jun Gaor FLS - David Calhoun SLS - Craig Herberts PE Tom Pierno NO& A Bill Kotekkaskos 6
7
San Onofre Design Specification For RSG #1 3.6.1.1 Edison intends to replace the steam generators under the 10 CFR 50.59 rule.
3.6.1.2 the Supplier shall guarantee in writing that the RSG design is licensable and provide all support necessary to achieve that end.
3.6.1.3 Any deviations from these requirements shall require Edisons approval.
8
San Onofre Design Specification For RSG #2 3.6.2
Licensing Topical Report:
The Supplier shall prepare and submit for Edisons approval a Licensing Topical Report demonstrating compliance of the RSG design with all SONGS licensing requirements. The report shall include an engineering evaluation, including all necessary analyses and evaluations, justifying that the RSGs can be replaced under the provisions of 10 CFR 50.59 (without prior NRC approval). The 10 CFR 50.59 evaluation shall be performed by Edison.
9
Edison Official Notification To NRC June 2006 Edison Notified NRC of 50.59 Decision in June 2006 A meeting was held on Wednesday, June 7, 2006, between the Nuclear Regulatory Commission (NRC) staff and the SCE, the licensee for SONGS 2 and 3. The meeting was held at the request of the licensee to provide to the NRC staff an overview of the various aspects of its steam generator (SG) replacement project.
(ML061670140)
10
JUNE 2006 Edison Presentation to NRC 11
2006 NRC Informed of Improvements 12
2006 Edison Accepts Responsibility 13
Mitsubishi Heavy Industries Was Constrained By The Contract Between the contract award in 2004 and NRC kickoff meeting in 2006, Mitsubishi Heavy Industries had to force fit the RSG analysis and design in order to support Edisons earlier decision determining that 10CFR§50.59 did not apply.
14
The 10CFR§50.59 Process In its January 9, 2013 Response
- Fairewinds agrees with Edison to the NRC, Edison said that this is the correct approach, and it should have "As discussed in Section 1.3 of been implemented.
NEI 96-07, changes are
- However, this approach was evaluated under 10 CFR 50.59 not applied during the RSG using a multi-step process. First, Project. Rather this "multistep a licensee must determine that process" was thwarted by a proposed change is safe Edison.
and effective through
- No appropriate engineering appropriate engineering and and technical evaluation technical evaluations. Page 5 was performed by Edison when the contractual decision was made that 10CFR§50.59 would not apply.
15
Standard Technical Specifications License Amendment 2009: During the San Onofre Standard Technical Specification License Amendment, Edison identified many areas where the San Onofre Replacement Steam Generator was dramatically different than the Original Steam Generator.
16
San Onofre RSGs Were Not Like-For-Like 17
Edison Identified Numerous San Onofre Design Changes 2011 Edison and MHI Report tout all the design changes implemented in the San Onofre RSG:
- Change Tube Support Structure
- Add New Anti-Vibration Bars
SECTION 2 MAGNITUDE OF DESIGN CHANGES 19
In and of themselves, Edisons design changes to the Replacement Steam Generators should have triggered the 10CFR§50.59 process.
20
- The San Onofre tubes and tube sheets are part of the containment boundary and are safety related.
- San Onofre claimed to the NRC that new improved anti-vibration bars would reduce wear on these important components and would not adversely impact their design function.
21
h1p://www.fairewinds.com/content/san-onofres-steam-generator-failures-could-have-been-prevented
22
Mitsubishi Heavy Industries Should Not Be The Scapegoat If the RSGs had been designed and manufactured in accordance with the procurement specification, the leak and tube wear would never had occurred. Page 12, 1/9/13 Edison Letter to NRC
- The replacement steam generator design developed by Mitsubishi in accordance with the licensees design specification was translated into the same set of design and fabrication drawings. AIT Report, Page 27
- No matter who fabricated the RSGs for San Onofre, the tube damage would have occurred. The root cause of this problem was the design, not the fabrication.
23
Edison 2003 Annual Report:
San Onofre Identical To Palo Verde Palo Verde Steam Generators The steam generators at the Palo Verde Nuclear Generating Station (Palo Verde), in which SCE owns a 15.8% interest, have the same design and material properties as the San Onofre units. During 2003, the Palo Verde Unit 2 steam generators were replaced.
(Edison 2003 Annual Report, Page 21) h1p://www.edison.com/images/cms_images/c6452_2003_annual_eix_5543.pdf
24
Stay Cylinder: Retained On Palo Verde And Eliminated On San Onofre 25
Egg Crate Design Retained On Palo Verde/
Eliminated On San Onofre BROACHED TUBE SUPPORT EGG CRATE TUBE SUPPORT 26
San Onofre Problem Was Foreseeable
- Stay Cylinder removal and Tube addition placed too much heat in the center of San Onofres Replacement Steam Generators
- San Onofre added 4% more tubes at the center of its RSGs
- Palo Verde added 10% to the periphery and added 2.9% more heat
- Palo Verde has no FEI problems
- Edisons Design destroyed San Onofres RSGs 27
Contour Of Steam Quality Condition Report: 201836127, Revision 0, 5/7/2012, Figure 2: Contour of steam quality at the height of the maximum quality in U-bend region for T-hot = 598"F (Figure 8.1-2 (a) in Reference [2]), Page 74.
28
What Did The 10CFR§50.59 Review Say?
Edison is parsing its words!
- At the time the RSGs were
- Removing the stay cylinder designed, MHI evaluated the allowed 377 extra tubes flow patterns and into the center void, determined that fluid elastic creating more interior heat instability (FEI) would not
- The riser column water void occur. 1/9/13 Edison brief to above the tube sheet was NRC, page 14 also eliminated
- MHI provided a thermal- steam side to facilitate and hydraulic analysis as part of bias the flow direction. The the original design of the steam side flow patterns RSGs that showed there were never established.
would be no FEI. page 17
- The 10CFR§50.59 analysis should identify high void fractions and confused in/
out-of-plane FEI.
29
Friends Of The Earth Consultants Reached A Different 10CFR§50.59 Conclusion
" design changes may be
- Fairewinds agrees with this screened out under 10 CFR approach, but it is not the 50.59 if the changes do not approach used by Edison at adversely affect a design San Onofre.
function Page 9, Edison
- The totality of RSG changes Response, 1/9/13 Edison proposed in 2004 created an unacceptable void "The adverse condition that fraction at the top of the hot later resulted in the tube leak side of the tubes that then was a deficiency associated created the FEI.
with the design and was not
- Fairewinds and John Large both known at the time the 50.59 agree that it should have been evaluation was performed. foreseeable to Edison in 2004 Page 9, Edison Response, that this combination of 1/9/13 changes would cause FEI to occur.
30
Edisons Cause Report Was Wrong
- Former NRC Chairman Gregory Jaczko promised Senator Boxer and the public a complete Root Cause Analysis. This has not been conducted.
- Kepner Tregoe Cause Analysis is severely flawed.
- If they can get you asking the wrong questions, they don't have to worry about answers. Thomas Pynchon, Gravitys Rainbow
- Statement upon which Edison based its Cause Report:
What is different or has changed when comparing SONGS Replacement SGs to Another US plants Replacement SG (page 43, Condition Report) 31
What Root Cause Question Should Edison Have Asked?
There are no changes to compare among Edisons RSG and other RSGs nationwide. Its an apples and oranges comparison.
The changes Edison should have analyzed and compared are those between the OSG and the RSG or between San Onofre and Palo Verde, since Edison has acknowledged that Palo Verdes RSG is identical to San Onofres OSG.
32
Exclusions From Edisons Kepner Tregoe (KT) Analysis Process Extracted from the Edison Kepner Tregoe Exclusion Table: Condition Report: 201836127, Revision 0, 5/7/2012, Root Cause Evaluation: Unit 3 Steam Generator Tube Leak and Tube-to-Tube Wear, San Onofre Nuclear Generating Station, Page 52 33
SECTION 3 CONCLUSIONS 34
THE CHANGES EDISON MADE CREATED FORESEEABLE PROBLEMS During the past eight years, the NRC had extensive evidence from multiple sources that the replacement steam generators at San Onofre were not the like-for-like replacements for the original designs, as Edison committed during the 10CFR50.59 processes. And, as demonstrated by the significant damage in the San Onofre Replacement Steam Generators, the design changes did have a significant impact upon key design functions and in fact degraded the containment boundary.
Edison should have notified the NRC that the significance of all the changes required a 10CFR50.59 license amendment.
35
San Onofre Was A Near Miss The tube failures at San Onofre are the worst nuclear equipment failures since the near miss at Davis Bessie in 2002.
36
San Onofre Technical Specifications San Onofre Technical Specifications states that the limiting design basis accident is a "double ended rupture of a single tube.
Page 510 37
Edisons San Onofre:
Operating Outside Design Basis Eight Tubes failed their pressure test, not one!
The evidence shows that San Onofre was operating outside of its design basis and the NRC has done nothing to address this major violation.
Although in this case the degraded condition of the tubes was manifested as a small primary to secondary leak, it is possible that a full-blown rupture could have been the first indication. Page 57, NRC AIT Report 38
Arnie Gundersen, Chief Engineer Fairewinds Associates, Inc Nuclear Engineering, Safety, and Reliability Expert 42-years of nuclear industry experience and oversight ME NE Master of Engineering Nuclear Engineering Rensselaer Polytechnic Institute, 1972 U.S. Atomic Energy Commission Fellowship Thesis: Cooling Tower Plume Rise BS NE Bachelor of Science Nuclear Engineering Rensselaer Polytechnic Institute, 1971, Cum Laude James J. Kerrigan Scholar RO Licensed Reactor Operator U.S. Atomic Energy Commission License # OP-3014 39