|
|
| (6 intermediate revisions by the same user not shown) |
| Line 2: |
Line 2: |
| | number = ML13080A411 | | | number = ML13080A411 |
| | issue date = 03/20/2013 | | | issue date = 03/20/2013 |
| | title = San Onofre, Unit 2, Response to Request for Additional Information (RAIs 33, 34, 35, 36, and 55) Regarding Confirmatory Action Letter Response | | | title = Response to Request for Additional Information (RAIs 33, 34, 35, 36, and 55) Regarding Confirmatory Action Letter Response |
| | author name = St.Onge R J | | | author name = St.Onge R |
| | author affiliation = Southern California Edison Co | | | author affiliation = Southern California Edison Co |
| | addressee name = | | | addressee name = |
| Line 14: |
Line 14: |
| | page count = 16 | | | page count = 16 |
| | project = TAC:ME9727 | | | project = TAC:ME9727 |
| | stage = Other | | | stage = Response to RAI |
| }} | | }} |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:I , SOUTHERN CALIFORNIAEDISONAn EDISON INTERNATIONAL CompanyRichard I. St. OngeDirector, Nuclear Regulatory Affairs andEmergency PlanningProprietary InformationWithhold from Public DisclosureMarch 20, 201310 CFR 50.4U.S. Nuclear Regulatory CommissionATTN: Document Control DeskWashington, DC 20555-0001Subject:References:Docket No. 50-361Response to Request for Additional Information (RAIs 33, 34, 35, 36, and 55)Regarding Confirmatory Action Letter Response(TAC No. ME 9727)San Onofre Nuclear Generating Station, Unit 21. Letter from Mr. Elmo E. Collins (USNRC) to Mr. Peter T. Dietrich (SCE), datedMarch 27, 2012, Confirmatory Action Letter 4-12-001, San Onofre NuclearGenerating Station, Units 2 and 3, Commitments to Address Steam GeneratorTube Degradation2. Letter from Mr. Peter T. Dietrich (SCE) to Mr. Elmo E. Collins (USNRC), datedOctober 3, 2012, Confirmatory Action Letter -Actions to Address SteamGenerator Tube Degradation, San Onofre Nuclear Generating Station, Unit 23. Email from Mr. James R. Hall (USNRC) to Mr. Ryan Treadway (SCE), datedFebruary 1, 2013, Request for Additional Information (RAIs 33-37) RegardingResponse to Confirmatory Action Letter, San Onofre Nuclear GeneratingStation, Unit 24. Email from Mr. James R. Hall (USNRC) to Mr. Ryan Treadway (SCE), datedFebruary 21, 2013, Request for Additional Information (RAIs 53-67) RegardingResponse to Confirmatory Action Letter, San Onofre Nuclear GeneratingStation, Unit 2Dear Sir or Madam,On March 27, 2012, the Nuclear Regulatory Commission (NRC) issued a Confirmatory ActionLetter (CAL) (Reference 1) to Southern California Edison (SCE) describing actions that the NRCand SCE agreed would be completed to address issues identified in the steam generator tubesof San Onofre Nuclear Generating Station (SONGS) Units 2 and 3. In a letter to the NRC datedOctober 3, 2012 (Reference 2), SCE reported completion of the Unit 2 CAL actions andincluded a Return to Service Report (RTSR) that provided details of their completion.Proprietary InformationWithhold from Public DisclosureDecontrolled Upon Removal From Enclosure 2ADiP.O. Box 128San Clemente. CA 92672 Document Control Desk-2-March 20, 2013By email dated February 1, 2013 (Reference 3), the NRC issued Requests for AdditionalInformation (RAIs) 33-37 regarding the CAL response. By email dated February 21, 2013(Reference 4), the NRC issued RAts 53-67 regarding the CAL response. Enclosure 2 of thisletter provides the response to RAIs 33, 34, 35, 36, and 55.Enclosure 2 of this submittal contains proprietary information. SCE requests that thisproprietary enclosure be withheld from public disclosure in accordance with 10 CFR 2.390(a)(4).Enclosure 1 provides a notarized affidavit from AREVA NP Inc., which sets forth the basis onwhich the information in Enclosure 2 may be withheld from public disclosure by the NRC andaddresses with specificity the considerations listed by paragraph (b)(4) of 10 CFR 2.390.Proprietary information identified in Enclosure 2 was extracted from AREVA document51-9197672-002, SONGS Unit 2 Probability of FEI Operational Assessment RAI Responses,which is addressed in the affidavit. Enclosure 3 provides the non-proprietary version ofEnclosure 2.There are no new regulatory commitments contained in this letter. If you have any questions orrequire additional information, please call me at (949) 368-6240.cerely,Enclosures:1. Notarized Affidavit2. Response to RAI 33, 34, 35, 36, and 55 (Proprietary)3. Response to RAI 33, 34, 35, 36, and 55 (Non-Proprietary)cc: E. E. Collins, Regional Administrator, NRC Region IVJ. R. Hall, NRC Project Manager, SONGS Units 2 and 3G. G. Warnick, NRC Senior Resident Inspector, SONGS Units 2 and 3R. E. Lantz, Branch Chief, Division of Reactor Projects, NRC Region IVProprietary InformationWithhold from Public DisclosureDecontrolled Upon Removal From Enclosure 2 ENCLOSURE 1Notarized Affidavit AFFIDAVITSTATE OF NORTH CAROLINA )) ss.COUNTY OF MECKLENBURG1. My name is Dennis C. Williford. I am Manager, Product Licensing, forAREVA NP Inc. (AREVA NP) and as such I am authorized to execute this Affidavit.2. I am familiar with the criteria applied by AREVA NP to determine whethercertain AREVA NP information is proprietary. I am familiar with the policies established byAREVA NP to ensure the proper application of these criteria.3. I am familiar with the AREVA NP information contained in the document titled"51-9197672-002, 'SONGS Unit 2 Probability of FEI Operational Assessment RAI Responses',"and referred to herein as "Document." Information contained in this Document has beenclassified by AREVA NP as proprietary in accordance with the policies established by AREVANP for the control and protection of proprietary and confidential information.4. This Document contains information of a proprietary and confidential natureand is of the type customarily held in confidence by AREVA NP and not made available to thepublic. Based on my experience, I am aware that other companies regard information of thekind contained in this Document as proprietary and confidential.5. This Document has been made available to the U.S. Nuclear RegulatoryCommission in confidence with the request that the information contained in this Document bewithheld from public disclosure. The request for withholding of proprietary information is made inaccordance with 10 CFR 2.390. The information for which withholding from disclosure is requested qualifies under 10 CFR 2.390(a)(4) "Trade secrets and'commercial or financialinformation":6. The following criteria are customarily applied by AREVA NP to determinewhether information should be classified as proprietary:(a) The information reveals details of AREVA NP's research and developmentplans and programs or their results.(b) Use of the information by a competitor would permit the competitor tosignificantly reduce its expenditures, in time or resources, to design, produce,or market a similar product or service.(c) The information includes test data or analytical techniques concerning aprocess, methodology, or component, the application of which results in acompetitive advantage for AREVA NP.(d) The information reveals certain distinguishing aspects of a process,methodology, or component, the exclusive use of which provides acompetitive advantage for AREVA NP in product optimization or marketability.(e) The information is vital to a competitive advantage held by AREVA NP, wouldbe helpful to competitors to AREVA NP, and would likely cause substantialharm to the competitive position of AREVA NP.The information in the Document is considered proprietary for the reasons set forth inparagraphs 6(c) and 6(d) above.7. In accordance with AREVA NP's policies governing the protection and controlof information, proprietary information contained in this Document has been made available, ona limited basis, to others outside AREVA NP only as required and under suitable agreementproviding for nondisclosure and limited use of the information. | | {{#Wiki_filter:I , SOUTHERN CALIFORNIA Richard I. St. Onge EDISON Director, Nuclear Regulatory Affairs and Emergency Planning An EDISON INTERNATIONAL Company Proprietary Information Withhold from Public Disclosure March 20, 2013 10 CFR 50.4 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 |
| : 8. AREVA NP policy requires that proprietary information be kept in a securedfile or area and distributed on a need-to-know basis.9. The foregoing statements are true and correct to the best of my knowledge,information, and belief.SUBSCRIBED before me this //_/-7/_day of ____A, _ _'_ 2013.Thomas A. CasiasNOTARY PUBLIC, STATE OF NORTH CAROLINA, COUNTY OF MECKLENBURGMY COMMISSION EXPIRES: 14 December 2014 Proprietary InformationWithhold from Public DisclosureENCLOSURE 3SOUTHERN CALIFORNIA EDISONRESPONSE TO REQUEST FOR ADDITIONAL INFORMATIONREGARDING RESPONSE TO CONFIRMATORY ACTION LETTERDOCKET NO. 50-361TAC NO. ME 9727Response to RAIs 33, 34, 35, 36, and 55(NON-PROPRIETARY)Proprietary InformationWithhold from Public Disclosure Proprietary InformationWithhold from Public DisclosureRAI 33Reference 1, Figure 5-5:] [Proprietary]RESPONSENote: Request for Additional Information (RAI) Reference 1 is "SONGS U2C1 7 SteamGenerator Operational Assessment for Tube-to-Tube Wear," prepared by Areva NP Inc.Document No. 51-9187230-000, Revision 0, October 2012.[IPage 2 of 10Proprietary InformationWithhold from Public Disclosure Proprietary InformationWithhold from Public DisclosureRAI 34Reference 1, Section 6.4.2, page 60 of 129: [] [Proprietary]RESPONSEIPage 3 of 10Proprietary InformationWithhold from Public Disclosure Proprietary InformationWithhold from Public DisclosureRAI 35Reference 1, Section 7.3, page 98 of 129: The "upper bound contact forces" shown in Figure 7-2 are average values. Clarify whether these "average values" are averages of the upper boundcontact forces for each tube in the bundle at each AVB. Why is it acceptable that the calculatedupper bound contact force prevents motion for only 97.7 percent of the force spectrum fromturbulence? Finally, why has only turbulence excitation been considered in the development ofthese upper bound contact forces? [Only Figure 7-2 is proprietary, the question is not.]RESPONSE[IPage 4 of 10Proprietary InformationWithhold from Public Disclosure Proprietary InformationWithhold from Public DisclosureRAI 36Reference 1, Section 7.4, page 98 of 129:[Proprietary]RESPONSEIIPage 5 of 10Proprietary InformationWithhold from Public Disclosure Proprietary InformationWithhold from Public DisclosurePage 6 of 10Proprietary InformationWithhold from Public Disclosure Proprietary InformationWithhold from Public DisclosureProprietary InformationWithhold from Public DisclosurePage 7 of 10 Proprietary InformationWithhold from Public DisclosureProprietary InformationWithhold from Public DisclosurePage 8 of 10 Proprietary InformationWithhold from Public DisclosurerProprietary InformationWithhold from Public DisclosurePage 9 of 10 Proprietary InformationWithhold from Public DisclosureRAI 55In Reference 2, page 107 of 129, second to last paragraph, did total gap also include wear ofthe anti-vibration bars (AVBs) themselves? If not, explain why the approach is conservative. Ifso, how was wear of the AVBs determined? (This question is a follow-up on RAI No. 26 from theNRC's December 26, 2012, letter).RESPONSENote: RAI Reference 2 is "SONGS U2C1 7 Steam Generator Operational Assessment for Tube-to-Tube Wear," prepared by Areva NP Inc. Document No. 51-9187230-000, Revision 0,October 2012.Wear at tube to anti-vibration bar (AVB) intersections was included in the calculations of gapsand contact forces in RAI Reference 1. Both wear of the tube and wear of the AVB wereincluded. Based on wear test data, the wear volume of the AVB is [ ] of thecorresponding wear volume of the tube. Increased gaps due to wear were added to theABAQUS quarter model input in addition to the random selection of gaps from themanufacturing gap distributions.The sizes of wear induced gaps were based on eddy current inspection data for the worst casesteam generators, Unit 2 SG E-089 and Unit 3 SG E-089. The wear gaps were placed at thesame locations as found in the eddy current inspection.The wear level at any given location was adjusted for different time periods using theassumption that the work rate at that location was constant over time. The wear volume lossrate is constant over time at a given location. The wear volume loss rate at different locations iscalculated from the eddy current inspection wear depth and the total operating time at End ofCycle 16.Page 10 of 10 | | |
| }} | | ==Subject:== |
| | Docket No. 50-361 Response to Request for Additional Information (RAIs 33, 34, 35, 36, and 55) |
| | Regarding Confirmatory Action Letter Response (TAC No. ME 9727) |
| | San Onofre Nuclear Generating Station, Unit 2 |
| | |
| | ==References:== |
| | : 1. Letter from Mr. Elmo E. Collins (USNRC) to Mr. Peter T. Dietrich (SCE), dated March 27, 2012, Confirmatory Action Letter 4-12-001, San Onofre Nuclear Generating Station, Units 2 and 3, Commitments to Address Steam Generator Tube Degradation |
| | : 2. Letter from Mr. Peter T. Dietrich (SCE) to Mr. Elmo E. Collins (USNRC), dated October 3, 2012, Confirmatory Action Letter - Actions to Address Steam Generator Tube Degradation, San Onofre Nuclear Generating Station, Unit 2 |
| | : 3. Email from Mr. James R. Hall (USNRC) to Mr. Ryan Treadway (SCE), dated February 1, 2013, Request for Additional Information (RAIs 33-37) Regarding Response to Confirmatory Action Letter, San Onofre Nuclear Generating Station, Unit 2 |
| | : 4. Email from Mr. James R. Hall (USNRC) to Mr. Ryan Treadway (SCE), dated February 21, 2013, Request for Additional Information (RAIs 53-67) Regarding Response to Confirmatory Action Letter, San Onofre Nuclear Generating Station, Unit 2 |
| | |
| | ==Dear Sir or Madam,== |
| | |
| | On March 27, 2012, the Nuclear Regulatory Commission (NRC) issued a Confirmatory Action Letter (CAL) (Reference 1) to Southern California Edison (SCE) describing actions that the NRC and SCE agreed would be completed to address issues identified in the steam generator tubes of San Onofre Nuclear Generating Station (SONGS) Units 2 and 3. In a letter to the NRC dated October 3, 2012 (Reference 2), SCE reported completion of the Unit 2 CAL actions and included a Return to Service Report (RTSR) that provided details of their completion. |
| | Proprietary Information ADi Withhold from Public Disclosure P.O. Box 128 Decontrolled Upon Removal From Enclosure 2 San Clemente. CA 92672 |
| | |
| | Document Control Desk March 20, 2013 By email dated February 1, 2013 (Reference 3), the NRC issued Requests for Additional Information (RAIs) 33-37 regarding the CAL response. By email dated February 21, 2013 (Reference 4), the NRC issued RAts 53-67 regarding the CAL response. Enclosure 2 of this letter provides the response to RAIs 33, 34, 35, 36, and 55. of this submittal contains proprietary information. SCE requests that this proprietary enclosure be withheld from public disclosure in accordance with 10 CFR 2.390(a)(4). provides a notarized affidavit from AREVA NP Inc., which sets forth the basis on which the information in Enclosure 2 may be withheld from public disclosure by the NRC and addresses with specificity the considerations listed by paragraph (b)(4) of 10 CFR 2.390. |
| | Proprietary information identified in Enclosure 2 was extracted from AREVA document 51-9197672-002, SONGS Unit 2 Probability of FEI Operational Assessment RAI Responses, which is addressed in the affidavit. Enclosure 3 provides the non-proprietary version of . |
| | There are no new regulatory commitments contained in this letter. If you have any questions or require additional information, please call me at (949) 368-6240. |
| | cerely, |
| | |
| | ==Enclosures:== |
| | : 1. Notarized Affidavit |
| | : 2. Response to RAI 33, 34, 35, 36, and 55 (Proprietary) |
| | : 3. Response to RAI 33, 34, 35, 36, and 55 (Non-Proprietary) cc: E. E. Collins, Regional Administrator, NRC Region IV J. R. Hall, NRC Project Manager, SONGS Units 2 and 3 G. G. Warnick, NRC Senior Resident Inspector, SONGS Units 2 and 3 R. E. Lantz, Branch Chief, Division of Reactor Projects, NRC Region IV Proprietary Information Withhold from Public Disclosure Decontrolled Upon Removal From Enclosure 2 |
| | |
| | ENCLOSURE 1 Notarized Affidavit |
| | |
| | AFFIDAVIT STATE OF NORTH CAROLINA ) |
| | ) ss. |
| | COUNTY OF MECKLENBURG |
| | : 1. My name is Dennis C. Williford. I am Manager, Product Licensing, for AREVA NP Inc. (AREVA NP) and as such I am authorized to execute this Affidavit. |
| | : 2. I am familiar with the criteria applied by AREVA NP to determine whether certain AREVA NP information is proprietary. I am familiar with the policies established by AREVA NP to ensure the proper application of these criteria. |
| | : 3. I am familiar with the AREVA NP information contained in the document titled "51-9197672-002, 'SONGS Unit 2 Probability of FEI Operational Assessment RAI Responses'," |
| | and referred to herein as "Document." Information contained in this Document has been classified by AREVA NP as proprietary in accordance with the policies established by AREVA NP for the control and protection of proprietary and confidential information. |
| | : 4. This Document contains information of a proprietary and confidential nature and is of the type customarily held in confidence by AREVA NP and not made available to the public. Based on my experience, I am aware that other companies regard information of the kind contained in this Document as proprietary and confidential. |
| | : 5. This Document has been made available to the U.S. Nuclear Regulatory Commission in confidence with the request that the information contained in this Document be withheld from public disclosure. The request for withholding of proprietary information is made in accordance with 10 CFR 2.390. The information for which withholding from disclosure is |
| | |
| | requested qualifies under 10 CFR 2.390(a)(4) "Trade secrets and'commercial or financial information": |
| | : 6. The following criteria are customarily applied by AREVA NP to determine whether information should be classified as proprietary: |
| | (a) The information reveals details of AREVA NP's research and development plans and programs or their results. |
| | (b) Use of the information by a competitor would permit the competitor to significantly reduce its expenditures, in time or resources, to design, produce, or market a similar product or service. |
| | (c) The information includes test data or analytical techniques concerning a process, methodology, or component, the application of which results in a competitive advantage for AREVA NP. |
| | (d) The information reveals certain distinguishing aspects of a process, methodology, or component, the exclusive use of which provides a competitive advantage for AREVA NP in product optimization or marketability. |
| | (e) The information is vital to a competitive advantage held by AREVA NP, would be helpful to competitors to AREVA NP, and would likely cause substantial harm to the competitive position of AREVA NP. |
| | The information in the Document is considered proprietary for the reasons set forth in paragraphs 6(c) and 6(d) above. |
| | : 7. In accordance with AREVA NP's policies governing the protection and control of information, proprietary information contained in this Document has been made available, on a limited basis, to others outside AREVA NP only as required and under suitable agreement providing for nondisclosure and limited use of the information. |
| | : 8. AREVA NP policy requires that proprietary information be kept in a secured file or area and distributed on a need-to-know basis. |
| | : 9. The foregoing statements are true and correct to the best of my knowledge, information, and belief. |
| | SUBSCRIBED before me this //_/-7/_ |
| | day of ____A, _ _'_ 2013. |
| | Thomas A. Casias NOTARY PUBLIC, STATE OF NORTH CAROLINA, COUNTY OF MECKLENBURG MY COMMISSION EXPIRES: 14 December 2014 |
| | |
| | Proprietary Information Withhold from Public Disclosure ENCLOSURE 3 SOUTHERN CALIFORNIA EDISON RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING RESPONSE TO CONFIRMATORY ACTION LETTER DOCKET NO. 50-361 TAC NO. ME 9727 Response to RAIs 33, 34, 35, 36, and 55 (NON-PROPRIETARY) |
| | Proprietary Information Withhold from Public Disclosure |
| | |
| | Proprietary Information Withhold from Public Disclosure |
| | |
| | ===RAI 33=== |
| | Reference 1, Figure 5-5: |
| | ] [Proprietary] |
| | |
| | ===RESPONSE=== |
| | Note: Request for Additional Information (RAI) Reference 1 is "SONGS U2C1 7 Steam Generator Operational Assessment for Tube-to-Tube Wear," prepared by Areva NP Inc. |
| | Document No. 51-9187230-000, Revision 0, October 2012. |
| | [ |
| | I Page 2 of 10 Proprietary Information Withhold from Public Disclosure |
| | |
| | Proprietary Information Withhold from Public Disclosure |
| | |
| | ===RAI 34=== |
| | Reference 1, Section 6.4.2, page 60 of 129: [ |
| | ] [Proprietary] |
| | |
| | ===RESPONSE=== |
| | I Page 3 of 10 Proprietary Information Withhold from Public Disclosure |
| | |
| | Proprietary Information Withhold from Public Disclosure |
| | |
| | ===RAI 35=== |
| | Reference 1, Section 7.3, page 98 of 129: The "upper bound contact forces" shown in Figure 7-2 are average values. Clarify whether these "average values" are averages of the upper bound contact forces for each tube in the bundle at each AVB. Why is it acceptable that the calculated upper bound contact force prevents motion for only 97.7 percent of the force spectrum from turbulence? Finally, why has only turbulence excitation been considered in the development of these upper bound contact forces? [Only Figure 7-2 is proprietary, the question is not.] |
| | |
| | ===RESPONSE=== |
| | [ |
| | I Page 4 of 10 Proprietary Information Withhold from Public Disclosure |
| | |
| | Proprietary Information Withhold from Public Disclosure |
| | |
| | ===RAI 36=== |
| | Reference 1, Section 7.4, page 98 of 129: |
| | I |
| | [Proprietary] |
| | |
| | ===RESPONSE=== |
| | I Page 5 of 10 Proprietary Information Withhold from Public Disclosure |
| | |
| | Proprietary Information Withhold from Public Disclosure Page 6 of 10 Proprietary Information Withhold from Public Disclosure |
| | |
| | Proprietary Information Withhold from Public Disclosure Proprietary Information Withhold from Public Disclosure Page 7 of 10 |
| | |
| | Proprietary Information Withhold from Public Disclosure Proprietary Information Withhold from Public Disclosure Page 8 of 10 |
| | |
| | Proprietary Information Withhold from Public Disclosure r |
| | Proprietary Information Withhold from Public Disclosure Page 9 of 10 |
| | |
| | Proprietary Information Withhold from Public Disclosure |
| | |
| | ===RAI 55=== |
| | In Reference 2, page 107 of 129, second to last paragraph, did total gap also include wear of the anti-vibration bars (AVBs) themselves? If not, explain why the approach is conservative. If so, how was wear of the AVBs determined? (This question is a follow-up on RAI No. 26 from the NRC's December 26, 2012, letter). |
| | |
| | ===RESPONSE=== |
| | Note: RAI Reference 2 is "SONGS U2C1 7 Steam Generator Operational Assessment for Tube-to-Tube Wear," prepared by Areva NP Inc. Document No. 51-9187230-000, Revision 0, October 2012. |
| | Wear at tube to anti-vibration bar (AVB) intersections was included in the calculations of gaps and contact forces in RAI Reference 1. Both wear of the tube and wear of the AVB were included. Based on wear test data, the wear volume of the AVB is [ ] of the corresponding wear volume of the tube. Increased gaps due to wear were added to the ABAQUS quarter model input in addition to the random selection of gaps from the manufacturing gap distributions. |
| | The sizes of wear induced gaps were based on eddy current inspection data for the worst case steam generators, Unit 2 SG E-089 and Unit 3 SG E-089. The wear gaps were placed at the same locations as found in the eddy current inspection. |
| | The wear level at any given location was adjusted for different time periods using the assumption that the work rate at that location was constant over time. The wear volume loss rate is constant over time at a given location. The wear volume loss rate at different locations is calculated from the eddy current inspection wear depth and the total operating time at End of Cycle 16. |
| | Page 10 of 10}} |
Letter Sequence Response to RAI |
|---|
|
Initiation
- Request, Request, Request, Request, Request, Request, Request
- Acceptance
- Supplement, Supplement, Supplement, Supplement, Supplement, Supplement
|
MONTHYEARML12285A2652012-10-0101 October 2012
Attachment 4 - MHI Document L5-04GA564 - Tube Wear of Unit-3 RSG, Technical Evaluation Report
Project stage: Request
ML12285A2672012-10-0101 October 2012
Attachment 4: SG Tube Wear Analysis for Unit-2/3
Project stage: Request
ML12285A2662012-10-0101 October 2012
Attachment 4: Appendix-2 Attachment-1, Tube-to-TSP Wear Depth Diagram for Unit-2/3
Project stage: Request
ML12285A2642012-10-0101 October 2012
Attachment 3 - Areva Document 51-9180143-001 - SONGS Unit 3 February 2012 Leaker Outage Steam Generator Condition Monitoring Report
Project stage: Request
ML12285A2682012-10-0202 October 2012
Attachment 6 - Appendix B: SONGS U2C17 - Steam Generator Operational Assessment for Tube-to-Tube Wear
Project stage: Request
ML12285A2692012-10-0202 October 2012
Attachment 6: Appendix a: Estimates of FEI-Induced Ttw Rates
Project stage: Request
ML12285A2632012-10-0303 October 2012
Confirmatory Action Letter - Actions to Address Steam Generator Tube Degradation
Project stage: Request
ML12338A1102012-11-30030 November 2012
Email, Request for Additional Information Southern California Edison'S Response to Nrc'S Confirmatory Action Letter (CAL) 4-12-001 Dated March 27, 2012
Project stage: RAI
ML12341A1122012-12-0707 December 2012
Notice of Meeting with Southern California Edison to Discuss Its Response to Nrc'S Confirmatory Action Letter and Return to Service Report for San Onofre Nuclear Generating Station, Unit 2
Project stage: Meeting
ML12347A0662012-12-0707 December 2012
Revised Notice of 12/18/12 Meeting with Southern California Edison to Discuss Its Response to Nrc'S Confirmatory Action Letter and Return to Service Report for San Onofre Nuclear Generating Station, Unit 2
Project stage: Meeting
ML12345A4272012-12-10010 December 2012
Revised Email, Request for Additional Information Review of Southern California Edison'S Response to Nrc'S 3/27/2012 Confirmatory Action Letter (CAL) 4-12-001 and Return to Service Report
Project stage: RAI
ML12353A0972012-12-13013 December 2012
LTR-12-0795 - E-mail Don Leichtling Concerns Media Alert - Nuclear News - NRR Forthcoming Meeting with Southern California Edison Company
Project stage: Meeting
ML12352A3852012-12-18018 December 2012
Licensee Slides for 12/18/12 Public Meeting
Project stage: Meeting
ML12352A4112012-12-18018 December 2012
NRC Slides for 12/18/12 Meeting with Southern California Edison
Project stage: Meeting
ML12356A1982012-12-20020 December 2012
Email, Request for Additional Information, Round 3, Review of Southern California Edison'S Response to Nrc'S 3/27/2012 Confirmatory Action Letter (CAL) 4-12-001 and Return to Service Report
Project stage: RAI
ML13009A3492013-01-0808 January 2013
Response to Request for Additional Information Regarding Confirmatory Action Letter Response
Project stage: Response to RAI
ML13014A2512013-01-0909 January 2013
Response to Request for Additional Information (RAI 30) Regarding Confirmatory Action Letter Response
Project stage: Response to RAI
ML13014A2492013-01-0909 January 2013
Response to Request for Additional Information (RAI 15) Regarding Confirmatory Action Letter Response
Project stage: Response to RAI
ML13015A0042013-01-10010 January 2013
Response to Request for Additional Information (RAI 16), Regarding Confirmatory Action Letter Response (TAC No. Me 9727)
Project stage: Response to RAI
ML13022A0882013-01-16016 January 2013
Response to Request for Additional Information (RAI 19) Regarding Confirmatory Action Letter Response (TAC No. Me 9727)
Project stage: Response to RAI
ML13022A4132013-01-17017 January 2013
Response to Request for Additional Information (RAIs 10 and 17) Regarding Confirmatory Action Letter Response
Project stage: Response to RAI
ML13022A4812013-01-18018 January 2013
Response to Request for Additional Information (RAI 13), Regarding Confirmatory Action Letter Response
Project stage: Response to RAI
ML13022A4082013-01-18018 January 2013
Response to Request for Additional Information (RAI 12), Regarding Confirmatory Action Letter Response (TAC No. Me 9727)
Project stage: Response to RAI
ML13022A4112013-01-21021 January 2013
Response to Request for Additional Information (RAI 11) Regarding Confirmatory Action Letter Response (TAC Me 9727)
Project stage: Response to RAI
ML13022A4052013-01-21021 January 2013
Response to Request for Additional Information (RAI 28), Regarding Confirmatory Action Letter Response (TAC No. Me 9727)
Project stage: Response to RAI
ML13028A0982013-01-24024 January 2013
Response to Request for Additional Information (RAI 18) Regarding Confirmatory Action Letter Response
Project stage: Response to RAI
ML13028A4752013-01-25025 January 2013
Response to Request for Additional Information (RAI 27) Regarding Confirmatory Action Letter
Project stage: Response to RAI
ML13028A4742013-01-25025 January 2013
Response to Request for Additional Information (RAIs 5, 7, and 9) Regarding Confirmatory Action Letter Response
Project stage: Response to RAI
ML13032A0092013-01-29029 January 2013
Response to Request for Additional Information (RAI 14) Regarding Confirmatory Action Letter Response (TAC No. Me 9727)
Project stage: Response to RAI
ML13037A1122013-01-31031 January 2013
Response to Request for Additional Information (RAI 29) Regarding Confirmatory Action Letter Response
Project stage: Response to RAI
ML13053A3672013-02-0101 February 2013
E-mail, Draft Request for Additional Information Southern California Edison'S Response to Nrc'S Confirmatory Action Letter
Project stage: Draft RAI
ML13038A0102013-02-0404 February 2013
Response to Request for Additional Information (RAI 8) Regarding Confirmatory Action Letter Response
Project stage: Response to RAI
ML13038A0092013-02-0404 February 2013
Response to Request for Additional Information (RAI 6) Regarding Confirmatory Action Letter Response
Project stage: Response to RAI
ML13039A2782013-02-0606 February 2013
Response to Request for Additional Information (RAIs 20, 21, 22, 23, 24, 26 & 31), Confirmatory Action Letter
Project stage: Response to RAI
ML13039A3172013-02-0707 February 2013
Response to Request for Additional Information (RAI 25) Regarding Confirmatory Action Letter Response
Project stage: Response to RAI
ML13050A1892013-02-14014 February 2013
Supplemental Document Submittal Regarding Confirmatory Action Letter Response, Concerning Steam Generator Tubes
Project stage: Supplement
ML13051A1972013-02-15015 February 2013
Enclosure 6, LTR-SGDA-12-36, Rev. 3, Flow-Induced Vibration and Tube Wear Analysis of the San Onofre Nuclear Generating Station Unit 2 Replacement Steam Generators Supporting Restart. Cover Through Page 227 of 415
Project stage: Other
ML13051A1992013-02-15015 February 2013
Enclosure 6, LTR-SGDA-12-36, Rev. 3, Flow-Induced Vibration and Tube Wear Analysis of the San Onofre Nuclear Generating Station Unit 2 Replacement Steam Generators Supporting Restart. Page 228 of 415 Through End
Project stage: Other
ML13046A1232013-02-15015 February 2013
2/27/2013 Notice of Forthcoming Meeting with Southern California Edison Company to Discuss Confirmation Action Letter
Project stage: Meeting
ML13051A1932013-02-18018 February 2013
Enclosure 5, L5-04GA585, Rev. 2, Analytical Evaluations for Operational Assessment
Project stage: Other
ML13051A1922013-02-18018 February 2013
Enclosure 4, L5-04GA567, Rev. 6, Evaluation of Stability Ratio for Return to Service
Project stage: Other
ML13051A1902013-02-18018 February 2013
Supplemental Document Submittal Regarding Confirmatory Action Letter Response to Address Steam Generator Tube Degradation
Project stage: Supplement
ML13056A0922013-02-20020 February 2013
Email, Draft Request for Additional Information Nos. 38-52, Southern California Edison'S Response to Nrc'S Confirmatory Action Letter
Project stage: Draft RAI
ML13053A1732013-02-21021 February 2013
Email, Draft Request for Additional Information, Nos. 53-67, Southern California Edison'S Response to Nrc'S Confirmatory Action Letter
Project stage: Draft RAI
ML13053A1842013-02-21021 February 2013
Draft Request for Additional Information, Nos. 53-67, Southern California Edison'S Response to Nrc'S Confirmatory Action Letter
Project stage: Draft RAI
ML13058A0262013-02-25025 February 2013
Response to Request for Additional Information (Rals 2, 3, and 4) Regarding Confirmatory Action Letter Response (TAC No. Me 9727)
Project stage: Response to RAI
ML13056A6012013-02-25025 February 2013
Response to Request for Additional Information (RAI 32) Regarding Confirmatory Action Letter Response
Project stage: Response to RAI
ML13059A1572013-02-27027 February 2013
Licensee Slides from 2/27/13 Meeting Regarding a Request for Additional Information
Project stage: Meeting
ML13059A1522013-02-27027 February 2013
NRC Meeting Slides from 2/27/13 Public RAI Meeting
Project stage: RAI
ML13074A7932013-03-14014 March 2013
Operational Assessment for 100% Power Case Regarding Confirmatory Action Letter Response
Project stage: Other
2013-01-25
[Table View] |
|
|---|
Category:Letter
MONTHYEARML24240A1692024-09-18018 September 2024
Cy 2023 Summary of Decommissioning Trust Fund Status
IR 07200041/20244012024-08-16016 August 2024
San Onofe Nuclear Generating Station, Security Baseline Inspection Report 07200041/2024401
IR 05000361/20240042024-08-0909 August 2024
NRC Inspection Report 05000361/2024004 and 05000362/2024004
ML24191A2472024-07-0202 July 2024
(Songs), Units 1, 2, and 3, and the Independent Spent Fuel Storage Installation - Revision to the ISFSI-Only Emergency Plan and Associated Changes to Emergency Plan Implementing Procedures
ML24151A6482024-06-0303 June 2024
Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities
ML24141A0802024-05-15015 May 2024
(Songs), Units 1, 2 and 3 and Independent Spent Fuel Storage Installation - 2023 Annual Radiological Environmental Operating Report
IR 05000361/20240022024-04-0101 April 2024
– NRC Inspection Report 050-00361/2024-002 and 050-00362/2024-002
ML24094A0642024-03-27027 March 2024
Independent Spent Fuel Storage Installation, Decommissioning Funding Status Report 2023
ML24065A0152024-02-28028 February 2024
Generation Station Units 1, 2 and 3, Annual Radioactive Effluent Release Report for Independent Spent Fuel Storage Installation 2023
ML24044A0812024-02-14014 February 2024
LTR-24-0008: NRC Response to Paul Blanch Email Safety of Spent Nuclear Fuel at SONGS ISFSI
IR 05000361/20240012024-02-13013 February 2024
NRC Inspection Report 050-00361/2024-001 and 050-00362/2024-001 (1)
ML24037A0542024-01-30030 January 2024
(Songs), Units 2 and 3, Submittal of Annual Corporate Financial Reports
ML24022A1492024-01-17017 January 2024
Independent Spent Fuel Storage Installation, Revision 4 to the Physical Security Plan
ML24017A2432024-01-15015 January 2024
LTR-24-0008 Paul Blanch, E-mails Request for Formal Response to Requests for Meeting to Discuss Safety Issues with NRC Staff
IR 05000361/20230062023-11-29029 November 2023
NRC Inspection Report 05000361/2023-006 and 05000362/2023-006
ML23333A0682023-11-22022 November 2023
(SONGS) Units 1, 2, 3 and Independent Spent Fuel Storage Installation - Notification of Change in Nuclear Officer
IR 05000361/20230052023-10-11011 October 2023
NRC Inspection Report 05000361/2023005 and 05000362/2023005
ML23276A5942023-09-28028 September 2023
and Independent Spent Fuel Storage Installation - Supplement to Decommissioning Funding Status Reports
ML23268A0922023-09-20020 September 2023
Generation Station, Units 1, 2 and 3, and the Independent Spent Fuel Storage Facility (ISFSI) - Re-Registration of Dry Fuel Storage Casks for Amended Certificate of Compliance No. 1040
IR 05000361/20230012023-09-13013 September 2023
NRC Inspection Report 05000361 2023-001 and 05000362 2023-004
ML23240A5372023-08-18018 August 2023
Confirmatory Survey Activities Summary and Results for the Unit 2 and 3 Intake Structures at the San Onofre Nuclear Generating Station San Clemente CA
ML23129A1802023-06-14014 June 2023
Cover Letter to State of CA on Draft EA Regarding San Onofre ISFSI Updated DFPs
IR 05000361/20230032023-05-31031 May 2023
NRC Inspection Report 05000361/2023003 and 05000362/2023003
IR 05000361/20230022023-05-23023 May 2023
NRC Inspection Report 05000361/2023-002 and 05000362/2023-002
ML23137A1032023-05-11011 May 2023
(Songs), Units 1, 2 and 3, and Independent Spent Fuel Storage Installation - 2022 Annual Radiological Environmental Operating Report
ML23123A0932023-04-28028 April 2023
(Songs), Units 1, 2 and 3, Submittal of Annual Radioactive Effluent Release Report - 2022
ML23230A0882023-04-10010 April 2023
Independent Spent Fuel Storage Installation - Decommissioning Quality Assurance Plan
ML23094A1272023-03-29029 March 2023
Independent Spent Fuel Storage Installation - 10 CFR 50.82(a)(8)(v and VII) and 10 CFR 72.30(c) Decommissioning Funding Status Report 2021
ML23094A1332023-03-29029 March 2023
Nuclear Property Insurance
ML23062A1172023-02-28028 February 2023
Generation Station Units 1, 2 and 3, Annual Radioactive Effluent Release Report for Independent Spent Fuel Storage Installation - 2022
ML22361A1022023-02-24024 February 2023
Reactor Decommissioning Branch Project Management Changes for Some Decommissioning Facilities and Establishment of Backup Project Manager for All Decommissioning Facilities
ML23059A2812023-02-22022 February 2023
(Songs), Units 1, 2 and 3, 2022 Annual Turtle Incidental Take Report
ML23046A3792023-02-22022 February 2023
NRC Inspection Report 050-00361/2023-001 and 050-00362/2023-001
ML23045A2022023-02-0909 February 2023
Submittal of Annual Corporate Financial Reports for San Onofre Nuclear Generating Station (SONGS) Units 2 and 3 for Fy Ending June 30, 2022
ML22287A1352023-01-0505 January 2023
Issuance of Exemption from Title 10 of the Code of Federal Regulations Part 72.106(B), Independent Spent Fuel Storage Installation Controlled Area Boundary (L-2021-LLE-0056)
ML22348A0622023-01-0404 January 2023
NRC to SCE, Transmittal of the National Marine Fisheries Service'S December 12, 2022, Letter of Concurrence for Decommissioning of San Onofre Nuclear Generating Statiion, Units 2 and 3
IR 05000206/20220062022-12-15015 December 2022
NRC Inspection Report 05000206/2022006, 05000361/2022-006, and 05000362/2022-006
ML22347A2122022-12-12012 December 2022
NMFS to NRC, Endangered Species Act Section 7(a)(2) Concurrence Letter for Decommissioning of the San Onofre Nuclear Generating Station
ML22340A6652022-12-0505 December 2022
Letter from John Fassell, Chief; Re., State of California Department of Public Health Review and Comments on SONGS Draft Environmental Assessment
ML22333A8192022-11-21021 November 2022
Submittal of San Onofre Nuclear Generating Station, Units 2 and 3, Defueled Safety Analysis Report, Revised November 2022
IR 05000361/20220052022-11-17017 November 2022
NRC Inspection Report 05000361/2022-005 and 05000362/2022-005
ML22301A1462022-10-20020 October 2022
Report of Violations of the National Pollutant Discharge Elimination System Permit San Onofre Nuclear Generating Station (Songs), Units 2 and 3
ML22277A0162022-09-29029 September 2022
Independent Spent Fuel Storage Installation Response to Request for Additional Information Regarding Request for Exemption from 10 CFR 72.106(b)
IR 05000361/20220042022-09-26026 September 2022
NRC Inspection Report 05000361/2022-004 and 05000362/2022-004
ML22238A0552022-08-29029 August 2022
U.S. Nuclear Regulatory Commission'S Analysis of Southern California Edison'S Decommissioning Funding Status Report for San Onofre Nuclear Generating Station, Units 1, 2, and 3
ML22234A1602022-07-31031 July 2022
Final Report Per 10 CFR Part 21, Degraded Snubber SF1154 Hydraulic Fluid Batch No. 18CLVS431
ML22207B8612022-07-26026 July 2022
NRC (Public) Inspection Report 05000361/2022003; 05000362/2022003
IR 05000361/20220032022-07-26026 July 2022
NRC Inspection Report (Public) 05000361-2022003 and 05000362-2022003 (002)
IR 05000361/20220022022-05-12012 May 2022
NRC Inspection Report 05000361/2022-002 and 05000362/2022-002
ML22136A0842022-05-12012 May 2022
Independent Spent Fuel Storage Installation, 2021 Annual Radiological Environmental Operating Report
2024-09-18
[Table view] |
Text
I , SOUTHERN CALIFORNIA Richard I. St. Onge EDISON Director, Nuclear Regulatory Affairs and Emergency Planning An EDISON INTERNATIONAL Company Proprietary Information Withhold from Public Disclosure March 20, 2013 10 CFR 50.4 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
Subject:
Docket No. 50-361 Response to Request for Additional Information (RAIs 33, 34, 35, 36, and 55)
Regarding Confirmatory Action Letter Response (TAC No. ME 9727)
San Onofre Nuclear Generating Station, Unit 2
References:
- 1. Letter from Mr. Elmo E. Collins (USNRC) to Mr. Peter T. Dietrich (SCE), dated March 27, 2012, Confirmatory Action Letter 4-12-001, San Onofre Nuclear Generating Station, Units 2 and 3, Commitments to Address Steam Generator Tube Degradation
- 2. Letter from Mr. Peter T. Dietrich (SCE) to Mr. Elmo E. Collins (USNRC), dated October 3, 2012, Confirmatory Action Letter - Actions to Address Steam Generator Tube Degradation, San Onofre Nuclear Generating Station, Unit 2
- 3. Email from Mr. James R. Hall (USNRC) to Mr. Ryan Treadway (SCE), dated February 1, 2013, Request for Additional Information (RAIs 33-37) Regarding Response to Confirmatory Action Letter, San Onofre Nuclear Generating Station, Unit 2
- 4. Email from Mr. James R. Hall (USNRC) to Mr. Ryan Treadway (SCE), dated February 21, 2013, Request for Additional Information (RAIs 53-67) Regarding Response to Confirmatory Action Letter, San Onofre Nuclear Generating Station, Unit 2
Dear Sir or Madam,
On March 27, 2012, the Nuclear Regulatory Commission (NRC) issued a Confirmatory Action Letter (CAL) (Reference 1) to Southern California Edison (SCE) describing actions that the NRC and SCE agreed would be completed to address issues identified in the steam generator tubes of San Onofre Nuclear Generating Station (SONGS) Units 2 and 3. In a letter to the NRC dated October 3, 2012 (Reference 2), SCE reported completion of the Unit 2 CAL actions and included a Return to Service Report (RTSR) that provided details of their completion.
Proprietary Information ADi Withhold from Public Disclosure P.O. Box 128 Decontrolled Upon Removal From Enclosure 2 San Clemente. CA 92672
Document Control Desk March 20, 2013 By email dated February 1, 2013 (Reference 3), the NRC issued Requests for Additional Information (RAIs) 33-37 regarding the CAL response. By email dated February 21, 2013 (Reference 4), the NRC issued RAts 53-67 regarding the CAL response. Enclosure 2 of this letter provides the response to RAIs 33, 34, 35, 36, and 55. of this submittal contains proprietary information. SCE requests that this proprietary enclosure be withheld from public disclosure in accordance with 10 CFR 2.390(a)(4). provides a notarized affidavit from AREVA NP Inc., which sets forth the basis on which the information in Enclosure 2 may be withheld from public disclosure by the NRC and addresses with specificity the considerations listed by paragraph (b)(4) of 10 CFR 2.390.
Proprietary information identified in Enclosure 2 was extracted from AREVA document 51-9197672-002, SONGS Unit 2 Probability of FEI Operational Assessment RAI Responses, which is addressed in the affidavit. Enclosure 3 provides the non-proprietary version of .
There are no new regulatory commitments contained in this letter. If you have any questions or require additional information, please call me at (949) 368-6240.
cerely,
Enclosures:
- 1. Notarized Affidavit
- 2. Response to RAI 33, 34, 35, 36, and 55 (Proprietary)
- 3. Response to RAI 33, 34, 35, 36, and 55 (Non-Proprietary) cc: E. E. Collins, Regional Administrator, NRC Region IV J. R. Hall, NRC Project Manager, SONGS Units 2 and 3 G. G. Warnick, NRC Senior Resident Inspector, SONGS Units 2 and 3 R. E. Lantz, Branch Chief, Division of Reactor Projects, NRC Region IV Proprietary Information Withhold from Public Disclosure Decontrolled Upon Removal From Enclosure 2
ENCLOSURE 1 Notarized Affidavit
AFFIDAVIT STATE OF NORTH CAROLINA )
) ss.
COUNTY OF MECKLENBURG
- 1. My name is Dennis C. Williford. I am Manager, Product Licensing, for AREVA NP Inc. (AREVA NP) and as such I am authorized to execute this Affidavit.
- 2. I am familiar with the criteria applied by AREVA NP to determine whether certain AREVA NP information is proprietary. I am familiar with the policies established by AREVA NP to ensure the proper application of these criteria.
- 3. I am familiar with the AREVA NP information contained in the document titled "51-9197672-002, 'SONGS Unit 2 Probability of FEI Operational Assessment RAI Responses',"
and referred to herein as "Document." Information contained in this Document has been classified by AREVA NP as proprietary in accordance with the policies established by AREVA NP for the control and protection of proprietary and confidential information.
- 4. This Document contains information of a proprietary and confidential nature and is of the type customarily held in confidence by AREVA NP and not made available to the public. Based on my experience, I am aware that other companies regard information of the kind contained in this Document as proprietary and confidential.
- 5. This Document has been made available to the U.S. Nuclear Regulatory Commission in confidence with the request that the information contained in this Document be withheld from public disclosure. The request for withholding of proprietary information is made in accordance with 10 CFR 2.390. The information for which withholding from disclosure is
requested qualifies under 10 CFR 2.390(a)(4) "Trade secrets and'commercial or financial information":
- 6. The following criteria are customarily applied by AREVA NP to determine whether information should be classified as proprietary:
(a) The information reveals details of AREVA NP's research and development plans and programs or their results.
(b) Use of the information by a competitor would permit the competitor to significantly reduce its expenditures, in time or resources, to design, produce, or market a similar product or service.
(c) The information includes test data or analytical techniques concerning a process, methodology, or component, the application of which results in a competitive advantage for AREVA NP.
(d) The information reveals certain distinguishing aspects of a process, methodology, or component, the exclusive use of which provides a competitive advantage for AREVA NP in product optimization or marketability.
(e) The information is vital to a competitive advantage held by AREVA NP, would be helpful to competitors to AREVA NP, and would likely cause substantial harm to the competitive position of AREVA NP.
The information in the Document is considered proprietary for the reasons set forth in paragraphs 6(c) and 6(d) above.
- 7. In accordance with AREVA NP's policies governing the protection and control of information, proprietary information contained in this Document has been made available, on a limited basis, to others outside AREVA NP only as required and under suitable agreement providing for nondisclosure and limited use of the information.
- 8. AREVA NP policy requires that proprietary information be kept in a secured file or area and distributed on a need-to-know basis.
- 9. The foregoing statements are true and correct to the best of my knowledge, information, and belief.
SUBSCRIBED before me this //_/-7/_
day of ____A, _ _'_ 2013.
Thomas A. Casias NOTARY PUBLIC, STATE OF NORTH CAROLINA, COUNTY OF MECKLENBURG MY COMMISSION EXPIRES: 14 December 2014
Proprietary Information Withhold from Public Disclosure ENCLOSURE 3 SOUTHERN CALIFORNIA EDISON RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING RESPONSE TO CONFIRMATORY ACTION LETTER DOCKET NO. 50-361 TAC NO. ME 9727 Response to RAIs 33, 34, 35, 36, and 55 (NON-PROPRIETARY)
Proprietary Information Withhold from Public Disclosure
Proprietary Information Withhold from Public Disclosure
RAI 33
Reference 1, Figure 5-5:
] [Proprietary]
RESPONSE
Note: Request for Additional Information (RAI) Reference 1 is "SONGS U2C1 7 Steam Generator Operational Assessment for Tube-to-Tube Wear," prepared by Areva NP Inc.
Document No. 51-9187230-000, Revision 0, October 2012.
[
I Page 2 of 10 Proprietary Information Withhold from Public Disclosure
Proprietary Information Withhold from Public Disclosure
RAI 34
Reference 1, Section 6.4.2, page 60 of 129: [
] [Proprietary]
RESPONSE
I Page 3 of 10 Proprietary Information Withhold from Public Disclosure
Proprietary Information Withhold from Public Disclosure
RAI 35
Reference 1, Section 7.3, page 98 of 129: The "upper bound contact forces" shown in Figure 7-2 are average values. Clarify whether these "average values" are averages of the upper bound contact forces for each tube in the bundle at each AVB. Why is it acceptable that the calculated upper bound contact force prevents motion for only 97.7 percent of the force spectrum from turbulence? Finally, why has only turbulence excitation been considered in the development of these upper bound contact forces? [Only Figure 7-2 is proprietary, the question is not.]
RESPONSE
[
I Page 4 of 10 Proprietary Information Withhold from Public Disclosure
Proprietary Information Withhold from Public Disclosure
RAI 36
Reference 1, Section 7.4, page 98 of 129:
I
[Proprietary]
RESPONSE
I Page 5 of 10 Proprietary Information Withhold from Public Disclosure
Proprietary Information Withhold from Public Disclosure Page 6 of 10 Proprietary Information Withhold from Public Disclosure
Proprietary Information Withhold from Public Disclosure Proprietary Information Withhold from Public Disclosure Page 7 of 10
Proprietary Information Withhold from Public Disclosure Proprietary Information Withhold from Public Disclosure Page 8 of 10
Proprietary Information Withhold from Public Disclosure r
Proprietary Information Withhold from Public Disclosure Page 9 of 10
Proprietary Information Withhold from Public Disclosure
RAI 55
In Reference 2, page 107 of 129, second to last paragraph, did total gap also include wear of the anti-vibration bars (AVBs) themselves? If not, explain why the approach is conservative. If so, how was wear of the AVBs determined? (This question is a follow-up on RAI No. 26 from the NRC's December 26, 2012, letter).
RESPONSE
Note: RAI Reference 2 is "SONGS U2C1 7 Steam Generator Operational Assessment for Tube-to-Tube Wear," prepared by Areva NP Inc. Document No. 51-9187230-000, Revision 0, October 2012.
Wear at tube to anti-vibration bar (AVB) intersections was included in the calculations of gaps and contact forces in RAI Reference 1. Both wear of the tube and wear of the AVB were included. Based on wear test data, the wear volume of the AVB is [ ] of the corresponding wear volume of the tube. Increased gaps due to wear were added to the ABAQUS quarter model input in addition to the random selection of gaps from the manufacturing gap distributions.
The sizes of wear induced gaps were based on eddy current inspection data for the worst case steam generators, Unit 2 SG E-089 and Unit 3 SG E-089. The wear gaps were placed at the same locations as found in the eddy current inspection.
The wear level at any given location was adjusted for different time periods using the assumption that the work rate at that location was constant over time. The wear volume loss rate is constant over time at a given location. The wear volume loss rate at different locations is calculated from the eddy current inspection wear depth and the total operating time at End of Cycle 16.
Page 10 of 10
