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{{#Wiki_filter:June 26, 2012 Mr. Peter Dietrich Senior Vice President and Chief Nuclear Officer Southern California Edison Company San Onofre Nuclear Generating Station P.O. Box 128 San Clemente, CA 92674
-0128   
==SUBJECT:==
MEETING
==SUMMARY==
FOR AUGMENTED INSPECTION TEAM EXIT MEETING WITH SOUTHERN CALIFORNIA EDISON COMPANY Dear Mr. Dietrich
:
On June 18, 2012, NRC personnel met with representatives of Southern California Edison at the San Juan Capistrano Community Center Community Hall, located in San Juan Capistrano, California to present the Augmented Inspection Team exit issues and observations.
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its enclosure will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading
-rm/adams.html (the Public Electronic Reading Room).
Sincerely,  /RA/
Gregory Werner, Chief      Plant Support Branch 2 Division of Reactor Safety
Docket Nos. 0500050361, 0500050362 License Nos. NPF
-10, NPF-15 
==Enclosure:==
: 1. NRC Presentation
: 2. Southern California Edison Presentation    Electronic Distribution for SONGS U N I T E D S T A T E S N U C L E A R R E G U L A T O R Y C O M M I S S I O N R E G I O N I V1600 EAST LAMAR BLVD A R L I N G T O N , T E X A S 7 6 0 1 1-4511 
SUNSI Rev Compl.
Yes  No ADAMS Yes  No Reviewer Initials GEW Publicly Avail Yes  No Sensitive  Yes  No Sens. Type Initials GEW C:PSB2 PAO RSLO  C:PSB2 GEWerner VLDricks WAMaier  GEWerner /RA/ /RA/ /E/  /RA/ 6/20/2012 6/21/12 6/26/12  6/26/2012 NRC PRESENTATION Enclosure 1 1San Onofre Nuclear Generating StationAugmented Inspection Team Public Exit MeetingNuclear Regulatory Commission
-Region IVJune 18, 2012 2Purpose of Today's MeetingPresent the Status of the Augmented InspectionDiscuss Activities Going ForwardAnswer Questions from the Audience 3AgendaIntroduction Augmented Inspection Team DecisionAugmented Inspection Team CharterNRC Discussion on Augmented Inspection StatusLicensee Response to AIT StatusPath ForwardNRC Closing RemarksQuestion and Answer Session 4NRC RepresentativesElmo Collins, Regional Administrator, Region IVThomas Blount, Acting Director, Division Reactor Safety Greg Werner, Branch Chief , AIT Team LeadGreg Warnick, Senior Resident Inspector 5NRC Representatives (Cont)Michele Evans, Director, Division of Operating Reactor  LicensingRyan Lantz, Branch Chief, Region IVVictor Dricks, Senior Public Affairs Officer, Region IVJohn Reynoso, Resident Inspector, AIT Team MemberEmmett Murphy, Senior Materials Engineer, Office of Nuclear Reactor Regulation, AIT Team MemberCarl Thurston, Reactor Systems Engineer, Office of Research, AIT Team MemberJoel Rivera
-Ortiz, Senior Reactor  Inspector, Region II, AIT Team MemberMichael Bloodgood, Operations Engineer, Region IV 6SONGS RepresentativesPeter Dietrich, Senior Vice President and Chief Nuclear  Officer, SONGS, SCE Douglas Bauder, Vice President and Station Manager, SONGS, SCEThomas Palmisano, Vice President of Nuclear Engineering, Projects and Site Support, SONGS, SCE
NRC PRESENTATION Enclosure 1 7NRC Opening RemarksElmo Collins, Regional Administrator , Region IVThomas Blount, Acting Director, Division of Reactor Safety 8Steam Generator Tube LeakActual tube leak was of minor safety significance.Offsite radiation release was minimal.The plant operators responded properly and minimized the release.
9 10AIT DecisionManagement Directive 8.3
-Pre-Planning-Criteria-NRC Response 11AIT CharterTeam Members
-7 inspectors/engineers from 5 NRC officesKey Objectives Additional information and observations provided by the resident inspectors 12AIT Issues and ObservationsEight tubes failed pressure testing.SONGS used multiple independent consultants and S/G manufacturers.
NRC PRESENTATION Enclosure 1 13AIT Issues and Observations (cont)Mitsubishi's thermal/hydraulic computer simulation model did not accurately predict the behavior of the steam and water in the steam generators. Manufacturing differences  between the steam generators contributed to the difference in tube degradation.
14AIT Follow
-up ItemsTen items identified for follow
-up: 1.Post trip/transient procedure 2.Evaluation and disposition of numerous Unit 3 loose parts monitor alarms 3.Retainer bar design not evaluated for vibration impacts 4.Evaluation of and control of Unit 3 divider  plate repair 5.Unit 3 steam generator shipping requirements 15AIT Follow
-up Items (cont) 6.Lack of tube bundle support for steam  generators during shipment 7.Evaluation and disposition of shipping accelerometer data 8.50.59 evaluation 9.Control of manufacturing differences 10.Adequacy of Mitsubishi's computer simulation  model 16AIT SummaryThe NRC understands the steam generator thermal hydraulic conditions that resulted in the tube degradation.The thermal hydraulic conditions were not accurately predicted  during design. Additional actions to fix and prevent any additional tube-to-tube degradation due to excessive vibration are being evaluated and developed. The NRC has additional inspections to perform.The NRC will take as much time as needed to ensure the safety of the public.
17SONGS ResponsePeter DietrichSenior Vice President and Chief Nuclear Officer 18Path Forward
-Key NRC ActivitiesContinue review of steam generator tube wearConfirmatory Action Letter inspections Augmented Inspection followupinspectionAdditional public meetingsNRC decision about the acceptability of the resumption of power operationsRoutine process to recommend improvements to the inspection program
NRC PRESENTATION Enclosure 1 19NRC Closing RemarksElmo CollinsRegional AdministratorRegion IV 15 Minute Break 20 21Questions and Answers Contacting the NRCReport an emergency(301) 816-5100 (24/7 NRC Headquarter'sOperation Center)    (call collect)Report a safety concern
:  (800) 695-7403 (Toll
-free Safety Hotline) Allegation@nrc.govGeneral information or questionswww.nrc.govVictor Dricks, Public Affairs Officer, RIV817-200-1128Victor.Dricks@nrc.gov 22 SOUTHERN CALIFORNIA EDISON PRESENTATION Enclosure 2 SONGS EXCELLENCE 2012Steam Generator Recovery UpdateNuclear Safety in ActionJune 18, 2012 SONGS EXCELLENCE 2012We operate San Onofre Nuclear Generating Station (SONGS) safely and reliably to the highest standards to protect the health and safety of the public and our employeesWe will not restart either Unit 2 or Unit 3 until we and the NRC are satisfied it is safe to doSouthern California Edison Commitment SONGS EXCELLENCE 2012Current StatusUnit 2 Status:
-Shutdown on Jan. 9 for routine refueling and maintenance outage & reactor vessel head replacementUnit 3 Status:
-Operators safely shutdown Unit 3 after steam generator tube leak identified on January 31
-Shared learning with industry 3 SONGS EXCELLENCE 2012 4Pressurized Water Reactor Layout SONGS EXCELLENCE 2012Steam Generator Cut
-Away Elevation View 5 SONGS EXCELLENCE 2012Actions Taken to DateDiscovered unexpected tube
-to-tube wear in limited portions of Unit 3 steam generatorsDeferred Unit 2 restart pending investigationAssembled team of experts to inform, assist and challengeCompleted extensive tests and analysis on both units in all steam generators to support determining cause 6
SOUTHERN CALIFORNIA EDISON PRESENTATION Enclosure 2 SONGS EXCELLENCE 2012Technical Expertise Supporting SCEMitsubishi Heavy IndustriesWestinghouseMPR AssociatesAREVA                        B&W CanadaEPRI 7Other industry personnel, recognized academics and specialized consultants SONGS EXCELLENCE 2012Cause of Unexpected Tube
-to-Tube WearSpecific mechanism is Fluid Elastic Instability causing excessive tube vibration
-Most excessive wear occurring in limited area of Unit 3 steam generators This is due to: High steam flow velocities Very dry steamInadequate tube support structure in the U bend region for the tubes experiencing the wear 8 SONGS EXCELLENCE 2012Next StepsFollow up on Augmented Inspection Team's additional requestsImplement our corrective actionsDevelop additional information as stated in Confirmatory Action Letter Continue work to develop intermediate and long term solutions
-Will require extensive analysis, mock
-ups and testing 9 SONGS EXCELLENCE 2012 10There is no timeline on safety}}

Revision as of 00:42, 2 August 2018

6/18/2012 Meeting Summary for Augmented Inspection Team Exit Meeting with Southern California Edison Co
ML12179A447
Person / Time
Site: San Onofre  Southern California Edison icon.png
Issue date: 06/26/2012
From: Werner G E
NRC/RGN-IV/DRS/PSB-2
To: Peter Dietrich
Southern California Edison Co
vlm/Werner G E
References
Download: ML12179A447 (8)
v • d • e


Text

June 26, 2012 Mr. Peter Dietrich Senior Vice President and Chief Nuclear Officer Southern California Edison Company San Onofre Nuclear Generating Station P.O. Box 128 San Clemente, CA 92674

-0128

SUBJECT:

MEETING

SUMMARY

FOR AUGMENTED INSPECTION TEAM EXIT MEETING WITH SOUTHERN CALIFORNIA EDISON COMPANY Dear Mr. Dietrich

On June 18, 2012, NRC personnel met with representatives of Southern California Edison at the San Juan Capistrano Community Center Community Hall, located in San Juan Capistrano, California to present the Augmented Inspection Team exit issues and observations.

In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its enclosure will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading

-rm/adams.html (the Public Electronic Reading Room).

Sincerely, /RA/

Gregory Werner, Chief Plant Support Branch 2 Division of Reactor Safety

Docket Nos. 0500050361, 0500050362 License Nos. NPF

-10, NPF-15

Enclosure:

1. NRC Presentation
2. Southern California Edison Presentation Electronic Distribution for SONGS U N I T E D S T A T E S N U C L E A R R E G U L A T O R Y C O M M I S S I O N R E G I O N I V1600 EAST LAMAR BLVD A R L I N G T O N , T E X A S 7 6 0 1 1-4511

SUNSI Rev Compl.

Yes No ADAMS Yes No Reviewer Initials GEW Publicly Avail Yes No Sensitive Yes No Sens. Type Initials GEW C:PSB2 PAO RSLO C:PSB2 GEWerner VLDricks WAMaier GEWerner /RA/ /RA/ /E/ /RA/ 6/20/2012 6/21/12 6/26/12 6/26/2012 NRC PRESENTATION Enclosure 1 1San Onofre Nuclear Generating StationAugmented Inspection Team Public Exit MeetingNuclear Regulatory Commission

-Region IVJune 18, 2012 2Purpose of Today's MeetingPresent the Status of the Augmented InspectionDiscuss Activities Going ForwardAnswer Questions from the Audience 3AgendaIntroduction Augmented Inspection Team DecisionAugmented Inspection Team CharterNRC Discussion on Augmented Inspection StatusLicensee Response to AIT StatusPath ForwardNRC Closing RemarksQuestion and Answer Session 4NRC RepresentativesElmo Collins, Regional Administrator, Region IVThomas Blount, Acting Director, Division Reactor Safety Greg Werner, Branch Chief , AIT Team LeadGreg Warnick, Senior Resident Inspector 5NRC Representatives (Cont)Michele Evans, Director, Division of Operating Reactor LicensingRyan Lantz, Branch Chief, Region IVVictor Dricks, Senior Public Affairs Officer, Region IVJohn Reynoso, Resident Inspector, AIT Team MemberEmmett Murphy, Senior Materials Engineer, Office of Nuclear Reactor Regulation, AIT Team MemberCarl Thurston, Reactor Systems Engineer, Office of Research, AIT Team MemberJoel Rivera

-Ortiz, Senior Reactor Inspector, Region II, AIT Team MemberMichael Bloodgood, Operations Engineer, Region IV 6SONGS RepresentativesPeter Dietrich, Senior Vice President and Chief Nuclear Officer, SONGS, SCE Douglas Bauder, Vice President and Station Manager, SONGS, SCEThomas Palmisano, Vice President of Nuclear Engineering, Projects and Site Support, SONGS, SCE

NRC PRESENTATION Enclosure 1 7NRC Opening RemarksElmo Collins, Regional Administrator , Region IVThomas Blount, Acting Director, Division of Reactor Safety 8Steam Generator Tube LeakActual tube leak was of minor safety significance.Offsite radiation release was minimal.The plant operators responded properly and minimized the release.

9 10AIT DecisionManagement Directive 8.3

-Pre-Planning-Criteria-NRC Response 11AIT CharterTeam Members

-7 inspectors/engineers from 5 NRC officesKey Objectives Additional information and observations provided by the resident inspectors 12AIT Issues and ObservationsEight tubes failed pressure testing.SONGS used multiple independent consultants and S/G manufacturers.

NRC PRESENTATION Enclosure 1 13AIT Issues and Observations (cont)Mitsubishi's thermal/hydraulic computer simulation model did not accurately predict the behavior of the steam and water in the steam generators. Manufacturing differences between the steam generators contributed to the difference in tube degradation.

14AIT Follow

-up ItemsTen items identified for follow

-up: 1.Post trip/transient procedure 2.Evaluation and disposition of numerous Unit 3 loose parts monitor alarms 3.Retainer bar design not evaluated for vibration impacts 4.Evaluation of and control of Unit 3 divider plate repair 5.Unit 3 steam generator shipping requirements 15AIT Follow

-up Items (cont) 6.Lack of tube bundle support for steam generators during shipment 7.Evaluation and disposition of shipping accelerometer data 8.50.59 evaluation 9.Control of manufacturing differences 10.Adequacy of Mitsubishi's computer simulation model 16AIT SummaryThe NRC understands the steam generator thermal hydraulic conditions that resulted in the tube degradation.The thermal hydraulic conditions were not accurately predicted during design. Additional actions to fix and prevent any additional tube-to-tube degradation due to excessive vibration are being evaluated and developed. The NRC has additional inspections to perform.The NRC will take as much time as needed to ensure the safety of the public.

17SONGS ResponsePeter DietrichSenior Vice President and Chief Nuclear Officer 18Path Forward

-Key NRC ActivitiesContinue review of steam generator tube wearConfirmatory Action Letter inspections Augmented Inspection followupinspectionAdditional public meetingsNRC decision about the acceptability of the resumption of power operationsRoutine process to recommend improvements to the inspection program

NRC PRESENTATION Enclosure 1 19NRC Closing RemarksElmo CollinsRegional AdministratorRegion IV 15 Minute Break 20 21Questions and Answers Contacting the NRCReport an emergency(301) 816-5100 (24/7 NRC Headquarter'sOperation Center) (call collect)Report a safety concern

(800) 695-7403 (Toll

-free Safety Hotline) Allegation@nrc.govGeneral information or questionswww.nrc.govVictor Dricks, Public Affairs Officer, RIV817-200-1128Victor.Dricks@nrc.gov 22 SOUTHERN CALIFORNIA EDISON PRESENTATION Enclosure 2 SONGS EXCELLENCE 2012Steam Generator Recovery UpdateNuclear Safety in ActionJune 18, 2012 SONGS EXCELLENCE 2012We operate San Onofre Nuclear Generating Station (SONGS) safely and reliably to the highest standards to protect the health and safety of the public and our employeesWe will not restart either Unit 2 or Unit 3 until we and the NRC are satisfied it is safe to doSouthern California Edison Commitment SONGS EXCELLENCE 2012Current StatusUnit 2 Status:

-Shutdown on Jan. 9 for routine refueling and maintenance outage & reactor vessel head replacementUnit 3 Status:

-Operators safely shutdown Unit 3 after steam generator tube leak identified on January 31

-Shared learning with industry 3 SONGS EXCELLENCE 2012 4Pressurized Water Reactor Layout SONGS EXCELLENCE 2012Steam Generator Cut

-Away Elevation View 5 SONGS EXCELLENCE 2012Actions Taken to DateDiscovered unexpected tube

-to-tube wear in limited portions of Unit 3 steam generatorsDeferred Unit 2 restart pending investigationAssembled team of experts to inform, assist and challengeCompleted extensive tests and analysis on both units in all steam generators to support determining cause 6

SOUTHERN CALIFORNIA EDISON PRESENTATION Enclosure 2 SONGS EXCELLENCE 2012Technical Expertise Supporting SCEMitsubishi Heavy IndustriesWestinghouseMPR AssociatesAREVA B&W CanadaEPRI 7Other industry personnel, recognized academics and specialized consultants SONGS EXCELLENCE 2012Cause of Unexpected Tube

-to-Tube WearSpecific mechanism is Fluid Elastic Instability causing excessive tube vibration

-Most excessive wear occurring in limited area of Unit 3 steam generators This is due to: High steam flow velocities Very dry steamInadequate tube support structure in the U bend region for the tubes experiencing the wear 8 SONGS EXCELLENCE 2012Next StepsFollow up on Augmented Inspection Team's additional requestsImplement our corrective actionsDevelop additional information as stated in Confirmatory Action Letter Continue work to develop intermediate and long term solutions

-Will require extensive analysis, mock

-ups and testing 9 SONGS EXCELLENCE 2012 10There is no timeline on safety

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