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Category:Legal-Affidavit
MONTHYEAR1CAN122301, Responses to Request for Additional Information for Request for Alternative for Implementation of Extended Reactor Vessel Inservice Inspection Interval (ANO1-ISl-037)2023-12-14014 December 2023 Responses to Request for Additional Information for Request for Alternative for Implementation of Extended Reactor Vessel Inservice Inspection Interval (ANO1-ISl-037) 1CAN062301, Request for Alternative for Implementation of Extended Reactor Vessel Inservice Inspection Interval (ANO1-ISI-037)2023-06-0808 June 2023 Request for Alternative for Implementation of Extended Reactor Vessel Inservice Inspection Interval (ANO1-ISI-037) ML23020A9442023-01-20020 January 2023 Enclosure 3: Affidavit 2CAN122103, Relief Request ANO2-RR-21-002, Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 46 - Submittal of Analyses - Affidavits and Calculation Summary Sheet2021-11-19019 November 2021 Relief Request ANO2-RR-21-002, Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 46 - Submittal of Analyses - Affidavits and Calculation Summary Sheet 2CAN102102, Relief Request ANO2-R&R-012: Support the Repair of the Reactor Vessel Closure Head Penetration 462021-10-10010 October 2021 Relief Request ANO2-R&R-012: Support the Repair of the Reactor Vessel Closure Head Penetration 46 0CAN092101, Unit 2 - Revised Proprietary Demarcation in Response to Request for Additional Information (Follow-up) - Proposed Alternative to ASME Section XI Requirements for Repair/Replacement of Emergency Cooling Pond Supply Piping2021-09-14014 September 2021 Unit 2 - Revised Proprietary Demarcation in Response to Request for Additional Information (Follow-up) - Proposed Alternative to ASME Section XI Requirements for Repair/Replacement of Emergency Cooling Pond Supply Piping 0CAN052103, Presentation Information for Pre-Submittal Meeting Regarding the Response to Request for Additional Information - Proposed Alternative to ASME Section XI Requirements for Repair/Replacement of Emergency .2021-05-25025 May 2021 Presentation Information for Pre-Submittal Meeting Regarding the Response to Request for Additional Information - Proposed Alternative to ASME Section XI Requirements for Repair/Replacement of Emergency . 0CAN022101, Response to Request for Additional Information - Proposed Alternative to ASME Section XI Requirements for Repair/Replacement of Emergency Cooling Pond Supply Piping2021-02-22022 February 2021 Response to Request for Additional Information - Proposed Alternative to ASME Section XI Requirements for Repair/Replacement of Emergency Cooling Pond Supply Piping 2CAN032001, Response to Request for Additional Information Related to License Amendment Request to Revise the Control Element Assembly Drop Times2020-03-11011 March 2020 Response to Request for Additional Information Related to License Amendment Request to Revise the Control Element Assembly Drop Times 1CAN121601, Arkansas Nuclear One Unit 1, Update to Evaluations Described Response to Request for Additional Information 14(a) Reactor Vessel Internals Aging Management Program Plan2016-12-21021 December 2016 Arkansas Nuclear One Unit 1, Update to Evaluations Described Response to Request for Additional Information 14(a) Reactor Vessel Internals Aging Management Program Plan 1CAN121601, Update to Evaluations Described Response to Request for Additional Information 14(a) Reactor Vessel Internals Aging Management Program Plan2016-12-21021 December 2016 Update to Evaluations Described Response to Request for Additional Information 14(a) Reactor Vessel Internals Aging Management Program Plan 1CAN121502, Evaluations Described Response to Requests for Additional Information 3, 5, 6(a), and 7, Reactor Vessel Internals Aging Management Program Plan2015-12-30030 December 2015 Evaluations Described Response to Requests for Additional Information 3, 5, 6(a), and 7, Reactor Vessel Internals Aging Management Program Plan ML15278A0242015-09-28028 September 2015 Attachment 2, Areva Document ANP-3417NP, Revision 0, MRP-227-A Applicant / Licensee Action Item No. 7 Analysis for Arkansas Nuclear One, Unit 1 (Non-Proprietary), Attachment 3, Affidavit, and Attachment 4, List of Commitments 2CAN051504, Revised Affidavit for Request for Relief ANO2-ISI-0162015-05-19019 May 2015 Revised Affidavit for Request for Relief ANO2-ISI-016 1CAN031504, Arkansas Nuclear One, Unit 1 - Responses to Request for Additional Information on Update of the Reactor Coolant System Pressure and Temperature and the Low Temperature Overpressure Protection System Limits2015-03-25025 March 2015 Arkansas Nuclear One, Unit 1 - Responses to Request for Additional Information on Update of the Reactor Coolant System Pressure and Temperature and the Low Temperature Overpressure Protection System Limits 1CAN031504, Responses to Request for Additional Information on Update of the Reactor Coolant System Pressure and Temperature and the Low Temperature Overpressure Protection System Limits2015-03-25025 March 2015 Responses to Request for Additional Information on Update of the Reactor Coolant System Pressure and Temperature and the Low Temperature Overpressure Protection System Limits ML15041A0742015-02-0606 February 2015 ANP-3300Q1NP, Rev. 0, Response to Request for Additional Information on Reactor Coolant System Pressure/Temperature and Low Temperature Overpressure Protection System Limits to 54 EFPY for Arkansas Nuclear One, Unit 1, Attachment 2 to 1CAN0 2CAN111402, Unit 2, Revised Affidavit for Request for Relief ANO2-ISI-0162014-11-11011 November 2014 Unit 2, Revised Affidavit for Request for Relief ANO2-ISI-016 2CAN041402, Successive Examination Plans, Request for Relief ANO2-ISI-016. Weld Scan Plans & Preliminary Coverage Estimates, Pdqs Number 783 & Affidavit Enclosed2014-04-15015 April 2014 Successive Examination Plans, Request for Relief ANO2-ISI-016. Weld Scan Plans & Preliminary Coverage Estimates, Pdqs Number 783 & Affidavit Enclosed 0CAN041401, NRC Augmented Inspection Team Follow-up Inspection Report 05000313/2013012 and 05000368/2013012; Preliminary Red and Yellow Findings2014-04-0101 April 2014 NRC Augmented Inspection Team Follow-up Inspection Report 05000313/2013012 and 05000368/2013012; Preliminary Red and Yellow Findings 0CAN071303, Units 1 and 2, Augmented Inspection Team Information Request2013-07-31031 July 2013 Units 1 and 2, Augmented Inspection Team Information Request ML12038A1772012-02-0303 February 2012 Units 1 and 2, HI-STORM 100 Cask System, Thermal Validation Test Using Air Mass Flow Rate ML0935005322009-12-11011 December 2009 Affidavit from Gayle F. Elliot, Manager of Product Licensing for Areva, Np Inc ML0828300342008-08-20020 August 2008 Affidavit of Gayle F. Elliott, for Areva Np Inc., Regarding NRC Presentation of August 2008 ML0627703182006-09-28028 September 2006 Transmittal of Draft Slide Presentation for Nrc/Entergy/Westinghouse Pre-Submittal Meeting (Proprietary/Non-Proprietary) ML0514603882005-05-10010 May 2005 Units 1 and 2, Request for Additional Information Concerning Request for Exemption from Holtec International Certificate of Compliance 2CAN010402, Revisions to Wesdyne Proprietary Reports in Support of Relaxation from Performing a Bare Metal Visual Inspection2004-01-16016 January 2004 Revisions to Wesdyne Proprietary Reports in Support of Relaxation from Performing a Bare Metal Visual Inspection ML15350A2151985-09-0505 September 1985 Overview Description of Core Operating Limit Supervisory System (Colss)(Rev 00-NP to CEN-312-NP) 2023-06-08
[Table view] Category:Letter type:
MONTHYEAR2CAN012401, U.S. Additional Protocol2024-01-17017 January 2024 U.S. Additional Protocol 2CAN012403, Supplemental Information - Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 42024-01-11011 January 2024 Supplemental Information - Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4 0CAN012401, Registration of Cask Use2024-01-10010 January 2024 Registration of Cask Use 1CAN122301, Responses to Request for Additional Information for Request for Alternative for Implementation of Extended Reactor Vessel Inservice Inspection Interval (ANO1-ISl-037)2023-12-14014 December 2023 Responses to Request for Additional Information for Request for Alternative for Implementation of Extended Reactor Vessel Inservice Inspection Interval (ANO1-ISl-037) 2CAN112302, Submittal of Amendment 31 to Safety Analysis Report2023-11-16016 November 2023 Submittal of Amendment 31 to Safety Analysis Report 0CAN102303, Registration of Cask Use2023-10-24024 October 2023 Registration of Cask Use 0CAN102302, (ANO) Emergency Plan Revision 49 and Emergency Plan On-Shift Staffing Analysis Revision 32023-10-11011 October 2023 (ANO) Emergency Plan Revision 49 and Emergency Plan On-Shift Staffing Analysis Revision 3 0CAN102301, Evacuation Time Estimate (ETE) Study2023-10-0404 October 2023 Evacuation Time Estimate (ETE) Study 1CAN092301, Supplemental Information - Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 42023-09-21021 September 2023 Supplemental Information - Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4 0CAN092302, Supplement to Request for Alternative Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (ANO-CISI-002)2023-09-14014 September 2023 Supplement to Request for Alternative Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (ANO-CISI-002) 2CAN092301, Reply to a Notice of Violation2023-09-0808 September 2023 Reply to a Notice of Violation 0CAN092301, Emergency Plan Implementing Procedure Revision2023-09-0505 September 2023 Emergency Plan Implementing Procedure Revision 0CAN082301, Units 1 and 2 - Changes to the Quality Assurance Program Approval Form for Radioactive Material Package No. 03412023-08-17017 August 2023 Units 1 and 2 - Changes to the Quality Assurance Program Approval Form for Radioactive Material Package No. 0341 2CAN082301, Inservice Inspection Summary Report for the Arkansas Nuclear One, Unit 2, Twenty-Ninth Refueling Outage (2R29)2023-08-10010 August 2023 Inservice Inspection Summary Report for the Arkansas Nuclear One, Unit 2, Twenty-Ninth Refueling Outage (2R29) 0CAN072301, Registration of Cask Use2023-07-18018 July 2023 Registration of Cask Use 1CAN062304, Supplement Related to License Amendment Request to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation2023-06-29029 June 2023 Supplement Related to License Amendment Request to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation 0CAN062301, Status of Actions to Return to Compliance2023-06-26026 June 2023 Status of Actions to Return to Compliance 0CAN062302, Submittal of Revision 22 of the ANO Fire Hazards Analysis2023-06-20020 June 2023 Submittal of Revision 22 of the ANO Fire Hazards Analysis 1CAN062301, Request for Alternative for Implementation of Extended Reactor Vessel Inservice Inspection Interval (ANO1-ISI-037)2023-06-0808 June 2023 Request for Alternative for Implementation of Extended Reactor Vessel Inservice Inspection Interval (ANO1-ISI-037) 0CAN052303, Annual 10 CFR 50.46 Report for Calendar Year 20222023-05-24024 May 2023 Annual 10 CFR 50.46 Report for Calendar Year 2022 0CAN052302, Emergency Plan Rev. 482023-05-11011 May 2023 Emergency Plan Rev. 48 0CAN052301, Units 1 and 2 - Annual Radiological Environmental Operating Report for 20222023-05-0909 May 2023 Units 1 and 2 - Annual Radiological Environmental Operating Report for 2022 2CAN052301, Cycle 30 Core Operating Limits Report (COLR)2023-05-0303 May 2023 Cycle 30 Core Operating Limits Report (COLR) 0CAN042302, Annual Occupational Radiation Exposure Report for 20222023-04-27027 April 2023 Annual Occupational Radiation Exposure Report for 2022 0CAN042301, Radioactive Effluent Release Report for 20222023-04-14014 April 2023 Radioactive Effluent Release Report for 2022 2CAN042301, License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 42023-04-0505 April 2023 License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4 1CAN032301, License Amendment Request to Modify the Arkansas Nuclear One, Unit 1, Technical Specification 3.3.1, Reactor Protection System Instrumentation, Turbine Trip Function on Low Control Oil Pressure2023-03-30030 March 2023 License Amendment Request to Modify the Arkansas Nuclear One, Unit 1, Technical Specification 3.3.1, Reactor Protection System Instrumentation, Turbine Trip Function on Low Control Oil Pressure 2CAN032303, Responses to Request for Additional Information Concerning the Request for Alternative Regarding the Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 462023-03-29029 March 2023 Responses to Request for Additional Information Concerning the Request for Alternative Regarding the Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 46 2CAN032304, Supplement to the Request for Alternative Regarding the Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 462023-03-29029 March 2023 Supplement to the Request for Alternative Regarding the Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 46 2CAN032305, 03 Post Examination Analysis2023-03-23023 March 2023 03 Post Examination Analysis 1CAN032302, Inspection Summary Report for the Thirtieth Refueling Outage (1R30)2023-03-20020 March 2023 Inspection Summary Report for the Thirtieth Refueling Outage (1R30) 1CAN012301, Responses to Request for Additional Information for Request for Relief ANO1-ISI-0352023-01-30030 January 2023 Responses to Request for Additional Information for Request for Relief ANO1-ISI-035 2CAN012303, U.S. Additional Protocol2023-01-23023 January 2023 U.S. Additional Protocol 2CAN012302, Relief Request ANO2-RR-23-001, Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 462023-01-20020 January 2023 Relief Request ANO2-RR-23-001, Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 46 1CAN122201, License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 42022-12-22022 December 2022 License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4 0CAN122202, Registration of Cask Use2022-12-21021 December 2022 Registration of Cask Use 0CAN122201, Reply to a Notice of Violation; EA-22-0992022-12-0808 December 2022 Reply to a Notice of Violation; EA-22-099 0CAN112201, Request for Alternative Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (ANO-CISI-002)2022-11-10010 November 2022 Request for Alternative Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (ANO-CISI-002) 1CAN102202, Application to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation2022-10-31031 October 2022 Application to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation 1CAN102203, Cycle 31 Core Operating Limits Report2022-10-24024 October 2022 Cycle 31 Core Operating Limits Report 1CAN102201, Supplement to Proposed Technical Specifications 3.4.12 and 3.4.13 Revised Dose Calculations2022-10-13013 October 2022 Supplement to Proposed Technical Specifications 3.4.12 and 3.4.13 Revised Dose Calculations 0CAN092201, Supplement to License Amendment Request for Approval of Changes to the Emergency Plan Staffing Requirements2022-09-29029 September 2022 Supplement to License Amendment Request for Approval of Changes to the Emergency Plan Staffing Requirements 1CAN092201, Supplement to Request for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fifth 10-Year Interval, First Period2022-09-0808 September 2022 Supplement to Request for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fifth 10-Year Interval, First Period 0CAN082201, License Amendment Request for Approval of Changes to the Emergency Plan Staffing Requirements2022-08-30030 August 2022 License Amendment Request for Approval of Changes to the Emergency Plan Staffing Requirements 1CAN082201, Request for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fifth 10-Year Interval, First Period2022-08-24024 August 2022 Request for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fifth 10-Year Interval, First Period 2CAN072201, Response to Request for Additional Information Requests for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fourth 10-Year Interval, Second and Third Periods2022-07-20020 July 2022 Response to Request for Additional Information Requests for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fourth 10-Year Interval, Second and Third Periods 0CAN072201, Registration of Cask Use2022-07-14014 July 2022 Registration of Cask Use 0CAN062202, Registration of Cask Use2022-06-0909 June 2022 Registration of Cask Use 1CAN062201, Response to the Request for Additional Information Proposed Technical Specifications 3.4.12 and 3.4.13 Revised Dose Calculations2022-06-0202 June 2022 Response to the Request for Additional Information Proposed Technical Specifications 3.4.12 and 3.4.13 Revised Dose Calculations 1CAN052201, Request for Relief Related to American Society of Mechanical Engineers (ASME) Code Case N-729-6 Augmented Examination Requirements ANO1-ISI-0352022-05-31031 May 2022 Request for Relief Related to American Society of Mechanical Engineers (ASME) Code Case N-729-6 Augmented Examination Requirements ANO1-ISI-035 2024-01-17
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Text
'% Entergy Entergy Operations, Inc.
1448 S.R. 333 Russellville, AR 72802 Tel 479-858-3110 Jeremy G. Browning Vice President - Operations Arkansas Nuclear One 1 CAN031504 March 25, 2015 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
SUBJECT:
Responses to Request for Additional Information Update the Reactor Coolant System Pressure and Temperature and the Low Temperature Overpressure Protection System Limits Arkansas Nuclear One, Unit 1 Docket No. 50-313 License No. DPR-51
REFERENCES:
- 1. Entergy letter to NRC, "License Amendment Request Update the Reactor Coolant System Pressure and Temperature and the Low Temperature Overpressure Protection System Limits," dated November 21, 2014 (1CAN111401) (ML14330A249)
- 2. NRC email to Entergy dated March 20, 2015, "Arkansas Nuclear One, Unit No. 1, Request for Additional Information ( 2 nd Round) License Amendment Request (TAC No. MF5292)"
Dear Sir or Madam:
In accordance with the provisions of Title 10 of the Code of Federal Regulations (10 CFR)
Section 50.90, Entergy Operations, Inc. (Entergy) submitted a request for an amendment to the Arkansas Nuclear One, Unit 1 (ANO-1) Technical Specifications (TS) to revise the Reactor Coolant System Pressure and Temperature (P/T) Limits (TS 3.4.3); Pressurizer (TS 3.4.9);
Pressurizer Safety Valves (TS 3.4.10); and Low Temperature Overpressure Protection (LTOP)
System (TS 3.4.11) requirements (Reference 1). The proposed changes would extend the applicability of the limits from 31 Effective Full Power Years (EFPY) to 54 EFPY.
In the course of its review, the NRC staff has determined that additional information is required to complete its evaluation of the request (Reference 2). Entergy's response to the NRC's request for additional information (RAI) is included in attachment to this letter.
Attachments I and 3 to this letter contains proprietary information -
Attachments I and 3 are withheld from public disclosure per 10 CFR 2.390 A6b(
I CAN031504 Page 2 of 3 AREVA document ANP 3300Q3P, Revision 0, "Response to Request for Additional Information on Reactor Coolant System Pressure/Temperature and Low Temperature Overpressure Protection System Limits to 54 EFPY for Arkansas Nuclear One, Unit 1" has been prepared with the response to the request. The information contained in the AREVA document is considered proprietary to AREVA. Attachment 1 is the proprietary version of the document.
A non-proprietary version of the AREVA document is included in Attachment 2.
During a conference call on March 23, 2015, the NRC requested a copy of the AREVA LTOP calculation. Attachment 3 is a copy of AREVA's proprietary calculation 32-9220706-002, "ANO-1 LTOP P-T Limits for 54 EFPY". A non-proprietary version of this calculation is not available.
AREVA requests that the proprietary information provided in Attachments 1 and 3 be withheld from public disclosure in accordance with 10 CFR 2.390. AREVA has provided Entergy with authorization to provide the proprietary information. An affidavit by the information owner, AREVA, supporting the request for non-disclosure is provided in Attachment 4. Therefore, Entergy requests that Attachments 1 and 3 of this submittal be withheld from public disclosure in accordance with 10 CFR 2.390.
With respect to the original Entergy request, the information contained in this submittal has been evaluated and Entergy has determined that the assessment of the no significant hazards consideration provided in Reference 1 is not invalidated by this additional information.
In accordance with 10 CFR 50.91 (b)(1), a copy of this application is being provided to the designated Arkansas state official.
No new commitments have been identified in this letter.
If you have any questions or require additional information, please contact Stephenie Pyle at 479-858-4704.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on March 25, 2015.
Sincerely, JGB/rwc Attachments 1 and 3 to this letter contains proprietary information -
Attachments 1 and 3 are withheld from public disclosure per 10 CFR 2.390
1CAN031504 Page 3 of 3 Attachments
- 1. AREVA document ANP 3300Q3P, Revision 0, "Response to Request for Additional Information on Reactor Coolant System Pressure/Temperature and Low Temperature Overpressure Protection System Limits to 54 EFPY for Arkansas Nuclear One, Unit 1" PROPRIETARY
- 2. AREVA document ANP 3300Q3NP, Revision 0, "Response to Request for Additional Information on Reactor Coolant System Pressure/Temperature and Low Temperature Overpressure Protection System Limits to 54 EFPY for Arkansas Nuclear One, Unit 1" NON-PROPRIETARY
- 3. AREVA Calculation 32-9220706-002, "ANO-1 LTOP P-T Limits for 54 EFPY" PROPRIETARY
- 4. Affidavit cc: Mr. Marc L. Dapas Regional Administrator U. S. Nuclear Regulatory Commission Region IV 1600 East Lamar Boulevard Arlington, TX 76011-4511 NRC Senior Resident Inspector Arkansas Nuclear One P. 0. Box 310 London, AR 72847 U. S. Nuclear Regulatory Commission Attn: Ms. Andrea E. George MS O-8B1 One White Flint North 11555 Rockville Pike Rockville, MD 20852 Mr. Bernard R. Bevill Arkansas Department of Health Radiation Control Section 4815 West Markham Street Slot #30 Little Rock, AR 72205 Attachments I and 3 to this letter contains proprietary information -
Attachments I and 3 are withheld from public disclosure per 10 CFR 2.390 to 1CAN031504 Affidavit
For Information Only AFFIDAVIT COMMONWEALTH OF VIRGINIA )
) ss.
CITY OF LYNCHBURG )
- 1. My name is Gayle Elliott. I am Manager, Product Licensing, for AREVA Inc.
(AREVA) and as such I am authorized to execute this Affidavit.
- 2. I am familiar with the criteria applied by AREVA to determine whether certain AREVA information is proprietary. I am familiar with the policies established by AREVA to ensure the proper application of these criteria.
- 3. I am familiar with the AREVA information contained in the documents ANP-3300Q3P, Revision 0, entitled, "Response to Request for Additional Information on Reactor Coolant System Pressure/Temperature and Low Temperature Overpressure Protection System Limits to 54 EFPY for Arkansas Nuclear One, Unit 1," and 32-9220706-002, entitled, "ANO-1 LTOP P-T Limits for 54 EFPY," both dated March 2015 and referred to herein as "Documents."
Information contained in these Documents has been classified by AREVA as proprietary in accordance with the policies established by AREVA Inc. for the control and protection of proprietary and confidential information.
- 4. These Documents contain information of a proprietary and confidential nature and is of the type customarily held in confidence by AREVA and not made available to the public. Based on my experience, I am aware that other companies regard information of the kind contained in these Documents as proprietary and confidential.
- 5. These Documents have been made available to the U.S. Nuclear Regulatory Commission in confidence with the request that the information contained in these Documents be withheld from public disclosure. The request for withholding of proprietary information is
For Information Only 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 to determine whether information should be classified as proprietary:
(a) The information reveals details of AREVA'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.
(d) The information reveals certain distinguishing aspects of a process, methodology, or component, the exclusive use of which provides a competitive advantage for AREVA in product optimization or marketability.
(e) The information is vital to a competitive advantage held by AREVA, would be helpful to competitors to AREVA, and would likely cause substantial harm to the competitive position of AREVA.
The information in these Documents is considered proprietary for the reasons set forth in paragraphs 6(c), 6(d) and 6(e) above.
-7. Iniaccardanrce-ith-ARE policAies.gern -_heprotecteion..ancl-cntrol of information, proprietary information contained in these Documents has been made available, on a limited basis, to others outside AREVA only as required and under suitable agreement providing for nondisclosure and limited use of the information.
- 8. AREVA policy requires that proprietary information be kept in a secured file or area and distributed on a need-to-know basis.
j
For Information Only
- 9. The foregoing statements are true and correct to the best of my knowledge, information, and belief.
'-, AL"Irb SUBSCRIBED before me this d-D day of VAXLrc , 2015.
Sherry L. McFaden NOTARY PUBLIC, COMMONWEALTH OF VIRGINIA MY COMMISSION EXPIRES: 10/31/18 Reg. # 7079129 I
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SHERRY L MCFAVN Notay Publi convnm"U~m of virois 7071201 ouINS"l horMs Oct 31. 2015 my0M~
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