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MONTHYEARHNP-10-125, Request for Exemption in Accordance with 10 CFR 50.12 Regarding Use of M5 Alloy in Fuel Rod Cladding2011-01-19019 January 2011 Request for Exemption in Accordance with 10 CFR 50.12 Regarding Use of M5 Alloy in Fuel Rod Cladding Project stage: Request HNP-11-067, License Amendment Request for Revision to Technical Specification Core Operating Limits Report References for Realistic Large Break LOCA Analysis2011-08-22022 August 2011 License Amendment Request for Revision to Technical Specification Core Operating Limits Report References for Realistic Large Break LOCA Analysis Project stage: Request ML11238A0782011-08-31031 August 2011 ANP-3011(NP), Rev. 1, Harris Nuclear Plant Unit 1 Realistic Large Break LOCA Analysis. Project stage: Request ML11272A0642011-09-29029 September 2011 NRR E-mail Capture - Acceptance Review for ME6999- Shearon Harris Unit 1, Realistic LBLOCA Methodology (TS 6.9.1.6.2) Project stage: Acceptance Review ML11336A1592011-12-0202 December 2011 Notice of Closed Meeting with Carolina Power & Light Company Regarding Shearon Harris Nuclear Plant, Unit 1 (TAC ME6999), the Purpose of the Meeting Is to Discuss the August 22, 2011, Large Break Loss of Coolant Accident Submittal Project stage: Meeting ML11354A2912011-12-13013 December 2011 Meeting Slides - Meeting with Carolina Power and Light Discussion of ANP-3011 Project stage: Request ML11339A0502011-12-28028 December 2011 Acceptance of Requested Licensing Action Regarding Realistic Large Break Loss-of-Coolant Accident (TAC No. ME6999)(HNP-11-067) Project stage: Acceptance Review HNP-12-028, Realistic LBLOCA Question Response Meeting Handout, Enclosure 3 to HNP-12-0282012-01-11011 January 2012 Realistic LBLOCA Question Response Meeting Handout, Enclosure 3 to HNP-12-028 Project stage: Meeting ML12076A1422012-01-11011 January 2012 Meeting Topics - Suggested Discussion Items Regarding Large Break Loss-of-Coolant Accident Submittal - Shearon Harris Nuclear Power Plant, Unit 1 Project stage: Meeting ML12076A1652012-01-11011 January 2012 Meeting Slides - Harris Realistic LBLOCA Question Response Meeting Project stage: Meeting ML11354A3782012-02-0808 February 2012 Meeting Handout - Meeting with Carolina Power and Light Suggested Discussion Items Regarding Realistic Large Break Loss-of-Coolant Accident Project stage: Meeting ML11354A2892012-02-0808 February 2012 Summary of Meeting with Carolina Power and Light to Discuss Realistic Large Break Loss-of-Coolant-Accident Project stage: Meeting HNP-12-023, License Amendment Request for Revision to Technical Specification Core Operating Limits Report References for Realistic Large Break LOCA Analysis Response to Request for Additional Information2012-02-23023 February 2012 License Amendment Request for Revision to Technical Specification Core Operating Limits Report References for Realistic Large Break LOCA Analysis Response to Request for Additional Information Project stage: Response to RAI ML12073A2922012-02-24024 February 2012 License Amendment Request for Revision to Technical Specification Core Operating Limits Report for Realistic Large Break LOCA Analysis Project stage: Request ML12067A1802012-02-29029 February 2012 ANP-3011Q1(NP), Revision 000, Harris Nuclear Plant Unit 1 Realistic Large Break LOCA Analysis. Enclosure 4 Response to Request for Additional Information (Non-Proprietary) Project stage: Response to RAI ML12067A2322012-03-16016 March 2012 Request of Withholding Information from Public Disclosure Project stage: Other ML12067A2312012-03-20020 March 2012 Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance HNP-12-050, License Amendment Request for Revision to Technical Specification Core Operating Limits Report for Realistic Large Break LOCA Analysis Revised Technical Specification Page2012-04-0202 April 2012 License Amendment Request for Revision to Technical Specification Core Operating Limits Report for Realistic Large Break LOCA Analysis Revised Technical Specification Page Project stage: Request ML12076A1412012-04-0505 April 2012 Summary of Meeting Summary with Carolina Power & Light to Discuss Realistic Large Break Loss-of-Coolant Project stage: Meeting ML12076A1032012-05-30030 May 2012 Issuance of Amendment Regarding the Revision to Technical Specification Core Operating Limits Report References for Realistic Large Break Loss-of-Coolant Accident Analysis Project stage: Approval 2012-02-23
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Category:Legal-Affidavit
MONTHYEARRA-20-0335, Response to Request for Additional Information Regarding License Amendment Request to Reduce the Minimum Required Reactor Coolant System Flow Rate and Update the List of Analytical Methods Used in .2020-11-24024 November 2020 Response to Request for Additional Information Regarding License Amendment Request to Reduce the Minimum Required Reactor Coolant System Flow Rate and Update the List of Analytical Methods Used in . RA-19-0453, Response to Request for Additional Information Regarding License Amendment Request to Modify Departure from Nucleate Boiling Ratio Safety Limit to Address Transition to New Fuel Type2019-12-20020 December 2019 Response to Request for Additional Information Regarding License Amendment Request to Modify Departure from Nucleate Boiling Ratio Safety Limit to Address Transition to New Fuel Type RA-19-0017, License Amendment Request to Modify the Departure from Nucleate Boiling Ratio Safety Limit to Address Transition to New Fuel Type2019-04-10010 April 2019 License Amendment Request to Modify the Departure from Nucleate Boiling Ratio Safety Limit to Address Transition to New Fuel Type RA-18-0016, Response to Request for Additional Information Regarding Technical Specification Changes to Support Self-Performance of Core Reload Design and Safety Analyses2018-06-0505 June 2018 Response to Request for Additional Information Regarding Technical Specification Changes to Support Self-Performance of Core Reload Design and Safety Analyses HNP-18-045, Submittal of Relief Request I4R-18, Reactor Vessel Closure Head Nozzle Repair Technique, Inservice Inspection Program, Fourth Ten-Year Interval2018-04-18018 April 2018 Submittal of Relief Request I4R-18, Reactor Vessel Closure Head Nozzle Repair Technique, Inservice Inspection Program, Fourth Ten-Year Interval RA-17-0048, Transmittal of Response to Request for Additional Information Regarding Application to Revise Technical Specifications for Methodology Report DPC-NE-3009, Rev. 0 (Part 2)2017-10-30030 October 2017 Transmittal of Response to Request for Additional Information Regarding Application to Revise Technical Specifications for Methodology Report DPC-NE-3009, Rev. 0 (Part 2) RA-16-0023, Supplemental Information for License Amendment Request Regarding Methodology Report DPC-NE-1008-P2016-05-0404 May 2016 Supplemental Information for License Amendment Request Regarding Methodology Report DPC-NE-1008-P ML16112A2752016-04-19019 April 2016 Robinson Fuel Meth Pre-sub Meeting - Presentation Affidavit for Closed Pre-Submittal Meeting with Duke Energy Progress to Discuss Fuel Reload Design Methodology Reports and Proposed LAR Re H.B. Robinson and Shearon Harris Plants HNP-15-038, License Amendment Request for Main Steam Safety Valve Lift Setting Tolerance Change2015-12-17017 December 2015 License Amendment Request for Main Steam Safety Valve Lift Setting Tolerance Change RA-15-0042, Application to Revise Technical Specifications to Adopt Methodology Report DPC-NE-3008-P, Revision 0, Thermal-Hydraulic Models for Transient Analysis.2015-11-19019 November 2015 Application to Revise Technical Specifications to Adopt Methodology Report DPC-NE-3008-P, Revision 0, Thermal-Hydraulic Models for Transient Analysis. RA-15-0041, Attachment 1, Affidavit and Attachment 3, Pre-Submittal Meeting Presentation Materials on DPC-NF-2010-A and DPC-NE-2011-P Methodologies (Redacted)2015-09-18018 September 2015 Attachment 1, Affidavit and Attachment 3, Pre-Submittal Meeting Presentation Materials on DPC-NF-2010-A and DPC-NE-2011-P Methodologies (Redacted) RA-15-0037, Transmittal of Response to NRC Request for Additional Information (RAI) Regarding Application to Revise Technical Specifications for Methodology Report DPC-NE-2005-P, Revision 52015-09-0909 September 2015 Transmittal of Response to NRC Request for Additional Information (RAI) Regarding Application to Revise Technical Specifications for Methodology Report DPC-NE-2005-P, Revision 5 RA-15-0031, Application to Revise Technical Specifications for Methodology Report DPC-NE-1008-P, Revision 0, Nuclear Design Methodology Using CASMO-5/Simulate-3 for Westinghouse Reactors.2015-08-19019 August 2015 Application to Revise Technical Specifications for Methodology Report DPC-NE-1008-P, Revision 0, Nuclear Design Methodology Using CASMO-5/Simulate-3 for Westinghouse Reactors. RA-15-0004, Application to Revise Technical Specifications for Methodology Report DPC-NE-2005-P, Revision 5, Thermalhydraulic Statistical Core Design Methodology2015-03-0505 March 2015 Application to Revise Technical Specifications for Methodology Report DPC-NE-2005-P, Revision 5, Thermalhydraulic Statistical Core Design Methodology ML12073A2922012-02-24024 February 2012 License Amendment Request for Revision to Technical Specification Core Operating Limits Report for Realistic Large Break LOCA Analysis RA-11-008, Progress Energy - Evidence of Guarantee of Payment of Deferred Premiums2011-04-14014 April 2011 Progress Energy - Evidence of Guarantee of Payment of Deferred Premiums ML0721203582007-07-20020 July 2007 Supplemental Declarations of Robert L. Smith, Judy Hogan, Worth Glover, Jr., Tony A. Hackney, Elbert Green, Derry J. Smith, Jr. and Beverly Ann D'Aquanni ML0217001992002-06-0404 June 2002 Joint Appendix Volume III: Pages 1299 - 1556, Petition to Review a Final Decision of the Nrc. Affidavit of Eric A. Mccartney, Michael J. Devoe, Benjamin Wesley Morgan, and Deposition of Gordon R. Thompson Regarding Contention EC-6 Volmen 3 ML0037715352000-11-20020 November 2000 Affidavit of Gareth W. Parry, Stephen F. Lavie, Robert L. Palla and Christopher Gratton in Support of NRC Staff Brief and Summary of Relevant Facts, Data and Arguments Upon Which the Staff Proposes to Rely at Oral Argument on Environmental ML0036737512000-01-0404 January 2000 Affidavit of Kenneth C. Heck in Support of NRC Staff'S Written Summary ML18230A4841979-06-12012 June 1979 Transmitting Affidavit of J. A. Jones, Marked for Identification as Applicant Exhibit Pp, & Revisions to Applicant'S Proposed Findings of Fact & Conclusion of Law in Form of Supplemental Initial Decision (Construction Permits) ML18230A4911979-04-17017 April 1979 NRC Staff Motion to Accept Transcript Corrections ML18230A5241979-01-23023 January 1979 Applicant'S Response to Conservation Council of North Carolina and Wake Environment, Inc.'S Motion to Remand to Licensing Board for Further Hearings 2020-11-24
[Table view] Category:Letter
MONTHYEARIR 05000400/20230042024-01-30030 January 2024 Integrated Inspection Report 05000400/2023004 ML23317A3462023-11-14014 November 2023 Duke Fleet - Correction Letter to License Amendment Nos. 312 & 340 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000400/20230032023-11-0909 November 2023 Integrated Inspection Report 05000400/2023003 ML23346A1322023-10-0606 October 2023 Communication from C-10 Research & Education Foundation Regarding NextEra Common Emergency Fleet Plan License Amendment Request and Related Documents Subsequently Published ML23234A1702023-10-0303 October 2023 Issuance of Amendment No. 199 Regarding Administrative Changes to the Renewed Facility Operating License and Technical Specifications ML23256A0882023-09-25025 September 2023 Issuance of Alternative to Steam Generator Welds ML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000400/20230052023-08-23023 August 2023 Updated Inspection Plan for Shearon Harris Nuclear Power Plant, Unit 1 (Report 05000400/2023005) ML23234A2542023-08-22022 August 2023 RQ Inspection Notification Letter IR 05000400/20234022023-07-26026 July 2023 Security Baseline Inspection Report 05000400/2023402 IR 05000400/20230022023-07-24024 July 2023 Integrated Inspection Report 05000400/2023002 IR 05000400/20234402023-07-17017 July 2023 Special Inspection Report 05000400/2023440 and Preliminary Greater than Green Finding and Apparent Violation Cover Letter IR 05000400/20243012023-05-15015 May 2023 Notification of Licensed Operator Initial Examination 05000400/2024301 IR 05000400/20230012023-05-10010 May 2023 Integrated Inspection Report 05000400 2023001 IR 05000400/20234042023-05-0404 May 2023 Cyber Security Inspection Report 05000400/2023404 ML23118A0762023-05-0101 May 2023 Approval for Use of Specific Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML23118A1392023-04-28028 April 2023 Submittal of Updated Final Safety Analysis Report (Amendment 65), Technical Specification Bases Revision, Report of Changes Pursuant to 10 CFR 50.59 and Summary of Commitment Changes IR 05000400/20234032023-04-0505 April 2023 Security Baseline Inspection Report 05000400/2023403 IR 05000400/20230102023-03-15015 March 2023 Comprehensive Engineering Team Inspection (CETI) Inspection Report 05000400/2023010 ML22332A4932023-03-10010 March 2023 William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility IR 05000400/20220062023-03-0101 March 2023 Annual Assessment Letter for Shearon Harris Nuclear Power Plant - NRC Inspection Report 05000400/2022006 ML23033A5272023-02-0808 February 2023 Correction of Typographical Errors Incurred During Issuance of License Amendment No. 196 IR 05000400/20220042023-02-0707 February 2023 Integrated Inspection Report 05000400/2022004 ML23020A1252023-01-23023 January 2023 Notification of Target Set Inspection and Request for Information (NRC Inspection Report 05000400/2023403) ML22096A0032022-11-18018 November 2022 McGuire Nuclear Station and Shearon Harris Nuclear Power Plant Authorization of RA-19-0352 Regarding Use of Alternative for RPV Head Closure Stud Examinations ML22256A2532022-11-14014 November 2022 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-541, Rev. 2 IR 05000400/20220032022-11-10010 November 2022 Integrated Inspection Report 05000400/2022003 IR 05000400/20223012022-11-0202 November 2022 NRC Operator License Examination Report 05000400/2022301 ML22271A6202022-09-29029 September 2022 Notification of Shearon Harris Nuclear Power Plant Comprehensive Engineering Team Inspection - U.S. Nuclear Regulatory Commission Inspection Report 05000400/2023010 ML22258A1262022-09-14014 September 2022 NRC Operator Licensing Examination Approval 05000400/2022301 ML22242A0022022-09-12012 September 2022 Issuance of Amendments to Adopt TSTF 569, Revision 2, Revise Response Time Testing Definition ML22227A0682022-09-0202 September 2022 Alternative to Certain Inservice Testing Requirements in the American Society of Mechanical Engineers Code for Operation and Maintenance for Certain Target Rock Solenoid Valves IR 05000400/20220052022-08-24024 August 2022 Updated Inspection Plan for Shearon Harris Nuclear Power Plant (Report 05000400/2022005) IR 05000400/20224032022-08-23023 August 2022 Security Baseline Inspection Report 05000400/2022403 ML22126A0082022-08-0909 August 2022 Issuance of Amendment No. 194 Revise Technical Specifications Related to Reactor Protection System Instrumentation P7 IR 05000400/20220022022-08-0505 August 2022 Integrated Inspection Report 05000400/2022002 ML22161B0332022-07-28028 July 2022 Issuance of Amendment No. 193 Regarding Revision of Surveillance Requirements to Remove Shutdown Limitation IR 05000400/20220112022-07-20020 July 2022 Biennial Problem Identification and Resolution Inspection Report 05000400 2022011 IR 05000400/20224022022-06-30030 June 2022 Material Control and Accounting Program Inspection Report 05000400/2022402 (OUO Removed) IR 05000400/20220102022-06-13013 June 2022 Design Basis Assurance Inspection (Programs) Inspection Report 05000400/2022010 ML22138A4012022-05-26026 May 2022 Project Manager Reassignment ML22101A2822022-05-0606 May 2022 Regulatory Audit Summary Related to the Review of License Amendment Regarding Revising the Flood Hazard Protection Scheme IR 05000400/20220012022-05-0404 May 2022 Integrated Inspection Report 05000400/2022001 IR 05000400/20224012022-03-24024 March 2022 Security Baseline Inspection Report 05000400/2022401 ML22020A0072022-03-10010 March 2022 Issuance of Amendment No. 192 Regarding Removal of Extraneous Content and Requirements from the Renewed Facility Operating License and Technical Specifications ML22010A2812022-03-0404 March 2022 Issuance of Amendments to Adopt TSTF-577, Rev. 1 Revised Frequencies for Steam Generator Tube Inspections (EPID L-2021-LLA-0161 IR 05000400/20210062022-03-0202 March 2022 Annual Assessment Letter for Shearon Harris Nuclear Power Plant (Report No. 05000400/2021006) ML21351A4722022-02-10010 February 2022 Issuance of Amendment No. 190 Regarding Revision to Containment Spray Nozzle Test Frequency IR 05000400/20210042022-02-0404 February 2022 Integrated Inspection Report 05000400/2021004 ML22034A5352022-02-0202 February 2022 Notification of Licensed Operator Initial Examination 05000400/2022301 2024-01-30
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Letter Enclosure Contains Proprietary Information Withhold From Public Disclosure Under 10 CFR 2.390 SProgress Energy February 24, 2012 Serial: HNP-12-028 10 CFR 50.90 Attn: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Shearon Harris Nuclear Power Plant, Unit No. 1 Docket No. 50-400 / Renewed License No. NPF-63
Subject:
License Amendment Request for Revision to Technical Specification Core Operating Limits Report for Realistic Large Break LOCA Analysis TAC No. ME6999 Request for Withholding of Proprietary Information
Reference:
Letter from K. Holbrook to the U.S. NRC, "License Amendment Request for Revision to Technical Specification Core Operating Limits Report," Serial HNP- 11-067 dated August 22, 2011, ADAMS Accession No. ML 11238A077 Ladies and Gentlemen:
By letter dated August 22, 2011, Carolina Power & Light Company (CP&L), doing business as Progress Energy Carolinas, Inc., requested approval from the U.S. Nuclear Regulatory Commission (NRC) of a license amendment request (LAR). The proposed request would revise TS 6.9.1.6, "Core Operating Limits Report," to add a plant-specific methodology that implements AREVA's NRC-approved topical report EMF-2103(P)(A), "Realistic Large Break LOCA Methodology for Pressurized Water Reactors," Revision 0, and also EMF-2103(P)(A),"Realistic Large Break LOCA Methodology for Pressurized Water Reactors," Revision 2 or higher upon approval of the specific revision by the NRC.A meeting with CP&L and NRC staff, related to the referenced LAR, was held on January 11, 2012. CP&L provided a handout at that meeting, attached to this letter in Enclosure 2, containing information considered proprietary to AREVA NP Inc. On behalf of AREVA NP, CP&L requests that the NRC withhold the information in accordance with 10 CFR 2.390 per the affidavit for withholding proprietary information, Enclosure
- 1. Upon removal of Enclosure 2, the balance of this letter and enclosures are decontrolled.
Enclosure 3 contains a non-proprietary version of the handout.Progress Energy Carolinas, Inc.Harris Nuclear Plant P. 0. Box 165 New Hill, NC 27562 U.S. Nuclear Regulatory Commission HNP-12-028 Please refer any questions regarding this submittal to me at (919) 362-3137.Sincerely, David H. Corlett Supervisor, Licensing/Regulatory Programs Harris Nuclear Plant DHC/jrc Enclosures (3): Request for Withholding of Proprietary Information cc: Mr. J. D. Austin, NRC Sr. Resident Inspector, HNP Ms. A. T. Billoch Colon, NRC Project Manager, HNP Mr. V. M. McCree, NRC Regional Administrator, Region II Page 2 HNP- 12-028 Shearon Harris Nuclear Power Plant, Unit No. 1 Docket No. 50-400 / Renewed License No. NPF-63 License Amendment Request for Revision to Technical Specification Core Operating Limits Report References for Realistic Large Break LOCA Analysis TAC No. ME6999 Request for Withholding of Proprietary Information Enclosure 1 Affidavit Supporting Withholding of Proprietary Information AFFIDAVIT COMMONWEALTH OF VIRGINIA )) ss.CITY OF LYNCHBURG
)1. My name is Gayle F. Elliott. 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 viewgraphs presented to the NRC at a meeting between Progress Energy, AREVA NP and the NRC on January 11, 2012 entitled "Harris Realistic LBLOCA Question Response Meeting," 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(b) and 6(c) above.7. In accordance with AREVA NP's policies governing the protection and control of information, proprietary information contained in this Document have 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 z.c-z day of 4 _2012 Kathleen Ann Bennett NOTARY PUBLIC, COMMONWEALTH OF VIRGINIA MY COMMISSION EXPIRES: 8/31/15 Reg. # 110864-*dr p p p 0000ftftju of Wghuia Mv aim #=L Am 21 ui