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| issue date = 03/20/2013 | | issue date = 03/20/2013 | ||
| title = 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 | | author name = St.Onge R | ||
| author affiliation = Southern California Edison Co | | author affiliation = Southern California Edison Co | ||
| addressee name = | | addressee name = | ||
Line 18: | Line 18: | ||
=Text= | =Text= | ||
{{#Wiki_filter:I , SOUTHERN CALIFORNIA | {{#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 | ||
==Subject:== | ==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:== | ==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, | |||
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. | |||
SCE requests that this proprietary enclosure be withheld from public disclosure in accordance with 10 CFR 2.390(a)(4). | |||
Enclosure 3 provides the non-proprietary version of | |||
==Enclosures:== | ==Enclosures:== | ||
: 1. Notarized Affidavit 2. Response to RAI 33, 34, 35, 36, and 55 (Proprietary) | : 1. Notarized Affidavit | ||
: 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 | : 2. Response to RAI 33, 34, 35, 36, and 55 (Proprietary) | ||
ENCLOSURE 1 Notarized Affidavit AFFIDAVIT STATE OF NORTH CAROLINA )) ss.COUNTY OF MECKLENBURG | : 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 | ||
: 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. | ENCLOSURE 1 Notarized 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. | 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. | : 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. | : 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 | ||
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. | requested qualifies under 10 CFR 2.390(a)(4) "Trade secrets and'commercial or financial 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/ | : 6. The following criteria are customarily applied by AREVA NP to determine whether information should be classified as proprietary: | ||
Proprietary Information Withhold from Public Disclosure Proprietary Information Withhold from Public Disclosure RAI 33 Reference 1, Figure 5-5:] [Proprietary] | (a) The information reveals details of AREVA NP's research and development plans and programs or their results. | ||
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] | (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. | ||
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? | (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. | ||
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:[Proprietary] | (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. | ||
RESPONSE | (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. | ||
If not, explain why the approach is conservative. | The information in the Document is considered proprietary for the reasons set forth in paragraphs 6(c) and 6(d) above. | ||
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 | : 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. | |||
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. | : 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 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 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. | ||
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}} | Page 10 of 10}} |
Latest revision as of 21:28, 4 November 2019
ML13080A411 | |
Person / Time | |
---|---|
Site: | San Onofre ![]() |
Issue date: | 03/20/2013 |
From: | St.Onge R Southern California Edison Co |
To: | Document Control Desk, Office of Nuclear Reactor Regulation |
References | |
TAC ME9727 | |
Download: ML13080A411 (16) | |
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