ML13155A004: Difference between revisions
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| number = ML13155A004 | | number = ML13155A004 | ||
| issue date = 05/30/2013 | | issue date = 05/30/2013 | ||
| title = | | title = Response to Request for Additional Information (RAI 73) Regarding Confirmatory Action Letter Response | ||
| author name = Onge R J | | author name = Onge R J | ||
| author affiliation = Southern California Edison Co | | author affiliation = Southern California Edison Co |
Revision as of 13:51, 29 January 2019
ML13155A004 | |
Person / Time | |
---|---|
Site: | San Onofre ![]() |
Issue date: | 05/30/2013 |
From: | Onge R J Southern California Edison Co |
To: | Document Control Desk, Office of Nuclear Reactor Regulation |
References | |
TAC ME9727 | |
Download: ML13155A004 (29) | |
Text
J SOUTHERN CALIFORNIA EDISON 5 An EDISON INTERNATIONAL@
Company Proprietary Information Withhold from Public Disclosure Richard St. Onge Director, Nuclear Regulatory Affairs and Emergency Planning May 30, 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 (RAI 73) Regarding Confirmatory Action Letter Response (TAC No. ME 9727)San Onofre Nuclear Generating Station, Unit 2 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
References:
- 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. Letter from Mr. Richard J. St. Onge (SCE) to Document Control Desk (USNRC), dated April 2, 2013, Response to Request for Additional Information (RAI 13), Revision 1 Regarding Confirmatory Action Letter Response, San Onofre Nuclear Generating Station, Unit 2 4. Letter from Mr. James R. Hall (USNRC) to Mr. Peter T. Dietrich (SCE), dated May 10, 2013, San Onofre Nuclear Generating Station, Unit 2 -Request for Additional Information Regarding Response to Confirmatory Action Letter
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.
SCE provided the response to Request for Additional Information (RAI) 13 in a letter dated April 2, 2013 (Reference 3). By letter dated May 10, 2013 (Reference 4), the NRC issued RAI 73 regarding the response to RAI 13. Enclosure 2 of this letter provides the response to RAI 73.Proprietary Information Withhold from Public Disclosure Decontrolled Upon Removal of Enclosure 2 P.O. Box 128 San Clemente.
CA 92674 Proprietary Information Withhold from Public Disclosure Document Control Desk-2-May 30, 2013 Enclosure 2 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).
Enclosure 1 provides notarized affidavits from Westinghouse, 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.Enclosure 3 provides the non-proprietary version of Enclosure 2.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.Sincerely,
Enclosures:
- 1. Notarized Affidavits
- 2. Response to RAI 73 (Proprietary)
- 3. Response to RAI 73 (Non-Proprietary) cc: A. T. Howell Ill, 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 of Enclosure 2
ENCLOSURE 1 Notarized Affidavits
- Westinghouse U.S. Nuclear Regulatory Commission Document Control Desk 11555 Rockville Pike Rockville, MD 20852 Westinghouse Electric Company Nuclear Services 1000 Westinghouse Drive Cranberry Township, Pennsylvania 16066 USA Direct tel: (412) 374-4643 Direct fax: (724) 720-0754 e-mail: greshaja@westinghouse.com Proj letter: CONO-1 3-44 CAW-13-3724 May 23, 2013 APPLICATION FOR WITHHOLDING PROPRIETARY INFORMATION FROM PUBLIC DISCLOSURE
Subject:
LTR-LAM-13-34-P-Attachment, "Response to NRC Confirmatory Action Letter RAI #73 for SONGS Unit 2" (Proprietary)
The proprietary information for which withholding is being requested in the above-referenced report is further identified in Affidavit CAW-13-3724 signed by the owner of the proprietary information, Westinghouse Electric Company LLC. The affidavit, which accompanies this letter, sets forth the basis on which the information may be withheld from public disclosure by the Commission and addresses with specificity the considerations listed in paragraph (b)(4) of 10 CFR Section 2.390 of the Commission's regulations.
Accordingly, this letter authorizes the utilization of the accompanying affidavit by Southern California Edison.Correspondence with respect to the proprietary aspects of the application for withholding or the Westinghouse affidavit should reference CAW-13-3724, and should be addressed to James A. Gresham, Manager, Regulatory Compliance, Westinghouse Electric Company, Suite 310, 1000 Westinghouse Drive, Cranberry Township, Pennsylvania 16066.Very truly yours, e A. Gresham, Manager Regulatory Compliance Enclosures CAW-13-3724 AFFIDAVIT COMMONWEALTH OF PENNSYLVANIA:
ss COUNTY OF BUTLER: Before me, the undersigned authority, personally appeared James A. Gresham, who, being by me duly sworn according to law, deposes and says that he is authorized to execute this Affidavit on behalf of Westinghouse Electric Company LLC (Westinghouse), and that the averments of fact set forth in this Affidavit are true and correct to the best of his knowledge, information, and belief: James A. Gresham, Manager Regulatory Compliance Sworn to and subscribed before me this 23rd day of May 2013 Notary Public COMMONWEALTH OF PENNSYLVANIA I Notarial Seal Anne M. Stegman, Notary Public Unity Twp., Westmoreland County My Commlsslon Expires Aug, 7, 2016 MEMBER, PENNSYLVANIA ASSOCIATION OF NOTARIES 2 CAW-13-3724 (1) I am Manager, Regulatory Compliance, in Nuclear Services, Westinghouse Electric Company LLC (Westinghouse), and as such, I have been specifically delegated the function of reviewing the proprietary information sought to be withheld from public disclosure in connection with nuclear power plant licensing and rule making proceedings, and am authorized to apply for its withholding on behalf of Westinghouse.
(2) 1 am making this Affidavit in conformance with the provisions of 10 CFR Section 2.390 of the Commission's regulations and in conjunction with the Westinghouse Application for Withholding Proprietary Information from Public Disclosure accompanying this Affidavit.
(3) I have personal knowledge of the criteria and procedures utilized by Westinghouse in designating information as a trade secret, privileged or as confidential commercial or financial information.
(4) Pursuant to the provisions of paragraph (b)(4) of Section 2.390 of the Commission's regulations, the following is furnished for consideration by the Commission in determining whether the information sought to be withheld from public disclosure should be withheld.(i) The information sought to be withheld from public disclosure is owned and has been held in confidence by Westinghouse.(ii) The information is of a type customarily held in confidence by Westinghouse and not customarily disclosed to the public. Westinghouse has a rational basis for determining the types of information customarily held in confidence by it and, in that connection, utilizes a system to determine when and whether to hold certain types of information in confidence.
The application of that system and the substance of that system constitutes Westinghouse policy and provides the rational basis required.Under that system, information is held in confidence if it falls in one or more of several types, the release of which might result in the loss of an existing or potential competitive advantage, as follows: (a) The information reveals the distinguishing aspects of a process (or component, structure, tool, method, etc.) where prevention of its use by any of 3 CAW-13-3724 Westinghouse's competitors without license from Westinghouse constitutes a competitive economic advantage over other companies.(b) It consists of supporting data, including test data, relative to a process (or component, structure, tool, method, etc.), the application of which data secures a competitive economic advantage, e.g., by optimization or improved marketability.(c) Its use by a competitor would reduce his expenditure of resources or improve his competitive position in the design, manufacture, shipment, installation, assurance of quality, or licensing a similar product.(d) It reveals cost or price information, production capacities, budget levels, or commercial strategies of Westinghouse, its customers or suppliers.(e) It reveals aspects of past, present, or future Westinghouse or customer funded development plans and programs of potential commercial value to Westinghouse.(f) It contains patentable ideas, for which patent protection may be desirable.
There are sound policy reasons behind the Westinghouse system which include the following: (a) The use of such information by Westinghouse gives Westinghouse a competitive advantage over its competitors.
It is, therefore, withheld from disclosure to protect the Westinghouse competitive position.(b) It is information that is marketable in many ways. The extent to which such information is available to competitors diminishes the Westinghouse ability to sell products and services involving the use of the information.(c) Use by our competitor would put Westinghouse at a competitive disadvantage by reducing his expenditure of resources at our expense.
4 CAW-13-3724 (d) Each component of proprietary information pertinent to a particular competitive advantage is potentially as valuable as the total competitive advantage.
If competitors acquire components of proprietary information, any one component may be the key to the entire puzzle, thereby depriving Westinghouse of a competitive advantage.(e) Unrestricted disclosure would jeopardize the position of prominence of Westinghouse in the world market, and thereby give a market advantage to the competition of those countries.(f) The Westinghouse capacity to invest corporate assets in research and development depends upon the success in obtaining and maintaining a competitive advantage.(iii) The information is being transmitted to the Commission in confidence and, under the provisions of 10 CFR Section 2.390, it is to be received in confidence by the Commission.(iv) The information sought to be protected is not available in public sources or available information has not been previously employed in the same original manner or method to the best of our knowledge and belief.(v) The proprietary information sought to be withheld in this submittal is that which is appropriately marked in LTR-LAM-13-34-P Attachment, "Response to NRC Confirmatory Action Letter RAI #73 for SONGS Unit 2" (Proprietary), for submittal to the Commission, being transmitted by Southern California Edison letter and Application for Withholding Proprietary Information from Public Disclosure, to the Document Control Desk. The proprietary information as submitted by Westinghouse is that associated with a response to NRC RAI #73 and may be used only for that purpose.This information is part of that which will enable Westinghouse to: (a) Adequately support the response to the NRC RAI.
5 CAW-13-3724 Further this information has substantial commercial value as follows: (a) Westinghouse plans to sell the use of the information to its customers for the purpose of supporting responses to NRC RAIs.(b) Westinghouse can sell support and defense of safety analysis services.(c) The information requested to be withheld reveals the distinguishing aspects of a methodology which was developed by Westinghouse.
Public disclosure of this proprietary information is likely to cause substantial harm to the competitive position of Westinghouse because it would enhance the ability of competitors to provide similar technical evaluation justifications and licensing defense services for commercial power reactors without commensurate expenses.
Also, public disclosure of the information would enable others to use the information to meet NRC requirements for licensing documentation without purchasing the right to use the information.
The development of the technology described in part by the information is the result of applying the results of many years of experience in an intensive Westinghouse effort and the expenditure of a considerable sum of money.In order for competitors of Westinghouse to duplicate this information, similar technical programs would have to be performed and a significant manpower effort, having the requisite talent and experience, would have to be expended.Further the deponent sayeth not.
PROPRIETARY INFORMATION NOTICE Transmitted herewith are proprietary and/or non-proprietary versions of documents furnished to the NRC in connection with requests associated with a response to NRC RAI #73 and may be used only for that purpose.In order to conform to the requirements of 10 CFR 2.390 of the Commission's regulations concerning the protection of proprietary information so submitted to the NRC, the information which is proprietary in the proprietary versions is contained within brackets, and where the proprietary information has been deleted in the non-proprietary versions, only the brackets remain (the information that was contained within the brackets in the proprietary versions having been deleted).
The justification for claiming the information so designated as proprietary is indicated in both versions by means of lower case letters (a) through (f)located as a superscript immediately following the brackets enclosing each item of information being identified as proprietary or in the margin opposite such information.
These lower case letters refer to the types of information Westinghouse customarily holds in confidence identified in Sections (4)(ii)(a) through (4)(ii)(f) of the affidavit accompanying this transmittal pursuant to 10 CFR 2.390(b)(1).
COPYRIGHT NOTICE The reports transmitted herewith each bear a Westinghouse copyright notice. The NRC is permitted to make the number of copies of the information contained in these reports which are necessary for its internal use in connection with generic and plant-specific reviews and approvals as well as the issuance, denial, amendment, transfer, renewal, modification, suspension, revocation, or violation of a license, permit, order, or regulation subject to the requirements of 10 CFR 2.390 regarding restrictions on public disclosure to the extent such information has been identified as proprietary by Westinghouse, copyright protection notwithstanding.
With respect to the non-proprietary versions of these reports, the NRC is permitted to make the number of copies beyond those necessary for its internal use which are necessary in order to have one copy available for public viewing in the appropriate docket files in the public document room in Washington, DC and in local public document rooms as may be required by NRC regulations if the number of copies submitted is insufficient for this purpose. Copies made by the NRC must include the copyright notice in all instances and the proprietary notice if the original was identified as proprietary.
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 RAI 73 (NON-PROPRIETARY)
RAI 73: In Section 4.2, "Impact of the RSGs on the SBLOCA AOR," of Reference 1, SCE assesses the effects of differences between the original and replacement steam generators on the small-break loss of coolant accident (SBLOCA) analysis of record (AOR). Specifically, items (ii)through (vi) of Section 4.2 address the differences in tube geometry and material, primary and secondary side liquid inventory, elevation of components, and total metal mass, and provide the licensee's conclusions on the effects of each difference on the SBLOCA analysis, if any. The NRC staff reviewed available documentation for the S2M evaluation model (Reference
- 2) and did not identify a basis for these conclusions.
Please provide the basis for these conclusions.
If the basis is completely described by the RAI response, please qualify the conclusions with supplemental information.
RESPONSE: Note: RAI Reference 1 is letter from SCE to NRC titled "Response to Request for Additional Information (RAI 13) Regarding Confirmatory Action Letter Response," dated April 2, 2013. RAI Reference 2 is Westinghouse document CENPD-1 37, Supplement 2-P-A, "Calculative Methods for the ABB CE Small Break LOCA Evaluation Model," dated April 1998.SBLOCA sensitivity studies were performed and the results are provided as follows: 4.2 Impact of the Replacement Steam Generators (RSGs) on the SBLOCA AOR ii. Effect of the differences in SG tube geometry and material.R %,11 -Do 11ln DO)R 2k,,,,, D where: Rwaii = tube wall resistance to heat transfer, (Btu/hr-ft 2-oF)-1 Do = tube outside diameter, ft D, = tube inside diameter, ft kwaii = tube material thermal conductivity, Btu/hr-ft-°F shows[compared to the OSGs at 550 0 F. This [ ] since after the cessation of the subcooled forced convection mode of SG heat transfer early in the LOCA transient, the [ ] is generally the limiting resistance for SG heat transfer during a LOCA.Enclosure 3 Page 1 of 18 The impact on the SONGS limiting SBLOCA case with OSGs due to the differences in the SG tube geometry and SG tube material between the OSGs (Inconel 600) and RSGs (Inconel 690)Note: The SONGS SBLOCA limiting case with OSGs is the 0.04 ft 2 break with a PCT of 2077 *F. The PCT for the SBLOCA analysis is calculated in two steps. First, a no-clad rupture break spectrum analysis is run to determine the limiting break size. The limiting PCT for the no-rupture analysis is 1926.4 *F. Then, a parametric study on gap pressure for the limiting break case is run to determine the maximum PCT. For the parametric study shown in this RAI response only the no-rupture part of the analysis was rerun.iii. Effect of the differences in SG primary side liquid inventory and heat transfer area.The RSGs with 8% Steam Generator Tube Plugging (SGTP) have approximately
[] SG primary side than the OSGs with 21.4% SGTP. As noted in Item 4.2.i [ ] in the primary sides of SGs for the RSGs [ ] of core uncovery and the subsequent less severe core uncovery due to the decrease of the core decay heat at a later time.Evaluation of the impact of the increase in primary liquid inventory I iv. Effect of the differences in SG secondary side liquid inventory.
The nominal secondary side liquid inventory for the RSGs is approximately
] SBLOCA calculations with the Supplement 2 Model (RAI Reference
- 2) are Enclosure 3 Page 2 of 18 The impact of the difference on the SG heat transfer [ ] and its impact on core uncovery or time of core uncovery is [ I.The impact on the SONGS limiting SBLOCA case with OSGs due to the larger SG secondary side liquid inventory for the RSGs v. Effect of the differences in elevation of SG components.
The average SG tube length for the RSGs is [ ] The vertical rise for the longest tube for the RSGs is [ ] the OSGs.These differences in elevation
[ ] on a SBLOCA event since the impact on the elevation head difference between the hot and cold sides of the SGs is negligible.
The impact of the increase in vertical elevation of the RSG primary side components on the SONGS limiting SBLOCA case with OSGs vi. Effect of the differences in SG total metal mass.The SG metal mass for the RSGs is [ ] OSGs. This [] ECCS performance analyses were performed with the Supplement 2 Model (RAI Reference 2). SG secondary side wall heat is] the secondary side and has [ ] on the RCS.The impact on the SONGS limiting SBLOCA case with OSGs due to the larger SG secondary side metal mass Enclosure 3 Page 3 of 18 Figure 4.2-1. Effect of the Differences in SG Tube Geometry and Material.Core Pressure Enclosure 3 Page 4 of 18 Figure 4.2-2. Effect of the Differences in SG Tube Geometry and Material.Core Mixture Level Enclosure 3 Page 5 of 18 Figure 4.2-3. Effect of the Differences in SG Tube Geometry and Material.Hot Spot Cladding Temperature Enclosure 3 Page 6 of 18 Figure 4.2-4. Effect of the Differences in SG Primary Side Liquid Inventory and Heat Transfer Area.Core Pressure Enclosure 3 Page 7 of 18 Figure 4.2-5. Effect of the Differences in SG Primary Side Liquid Inventory and Heat Transfer Area.Core Mixture Level Enclosure 3 Page 8 of 18 Figure 4.2-6. Effect of the Differences in SG Primary Side Liquid Inventory and Heat Transfer Area.Hot Spot Cladding Temperature Enclosure 3 Page 9 of 18 Figure 4.2-7. Effect of the Differences in SG Secondary Side Liquid Inventory.
Core Pressure Enclosure 3 Page 10 of 18 Figure 4.2-8. Effect of the Differences in SG Secondary Side Liquid Inventory.
Core Mixture Level Enclosure 3 Page 11 of 18 Figure 4.2-9. Effect of the Differences in SG Secondary Side Liquid Inventory.
Hot Spot Cladding Temperature Enclosure 3 Page 12 of 18 Figure 4.2-10. Effect of the Differences in Elevation of SG Components.
Core Pressure Enclosure 3 Page 13 of 18 Figure 4.2-11. Effect of the Differences in Elevation of SG Components.
Core Mixture Level Enclosure 3 Page 14 of 18 Figure 4.2-12. Effect of the Differences in Elevation of SG Components.
Hot Spot Cladding Temperature Enclosure 3 Page 15 of 18 Figure 4.2-13. Effect of the Differences in SG Total Metal Mass.Core Pressure Enclosure 3 Page 16 of 18 Figure 4.2-14. Effect of the Differences in SG Total Metal Mass.Core Mixture Level Enclosure 3 Page 17 of 18 Figure 4.2-15. Effect of the Differences in SG Total Metal Mass.Hot Spot Cladding Temperature Enclosure 3 Page 18 of 18