Letter Sequence Other |
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Results
Other: BSEP 10-0118, ANP-2950NP, Revision 0, Atrium 10XM Fuel Rod Thermal and Mechanical Evaluation for Brunswick Unit 2 Cycle 20 Reload BRK2-20., BSEP 10-0126, ANP-2956(NP), Rev. 0, Brunswick Unit 2 Cycle 20 Reload Safety Analysis, Enclosure 6 to BSEP 10-0126, BSEP 12-0018, Submittal of Confirmatory Evaluation for Cycle 19, BSEP 13-0004, Operability Assessment (CR 2012-8084 Revision 1) Identified an Issue with the Approved ACE Correlation for the Atrium 10XM Fuel Design with Regard to the Calculation of K-factor within the AEC Correlation, ML102920551, ML103260315, ML103260322, ML11102A048
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MONTHYEARBSEP 10-0052, Request for License Amendments - Addition of Analytical Methodology Topical Report to Technical Specification 5.6.5, Core Operating Limits Report2010-04-29029 April 2010 Request for License Amendments - Addition of Analytical Methodology Topical Report to Technical Specification 5.6.5, Core Operating Limits Report Project stage: Request BSEP 10-0057, Request for License Amendments - Addition of Analytical Methodology Topical Report to Technical Specification 5.6.5, Core Operating Limits Report2010-04-29029 April 2010 Request for License Amendments - Addition of Analytical Methodology Topical Report to Technical Specification 5.6.5, Core Operating Limits Report Project stage: Request ML1029205512010-10-12012 October 2010 Units, 1 and 2, Additional Information Supporting License Amendment Requests - Atrium 10XM Fuel Rod Thermal and Mechanical Evaluation for Unit 2, Cycle 20 Project stage: Other BSEP 10-0118, ANP-2950NP, Revision 0, Atrium 10XM Fuel Rod Thermal and Mechanical Evaluation for Brunswick Unit 2 Cycle 20 Reload BRK2-20.2010-10-12012 October 2010 ANP-2950NP, Revision 0, Atrium 10XM Fuel Rod Thermal and Mechanical Evaluation for Brunswick Unit 2 Cycle 20 Reload BRK2-20. Project stage: Other ML1029101672010-10-28028 October 2010 RAI Regarding License Amendment Requests for Addition of Analytical Methodology Topical Reports to TS 5.6.5, Core Operating Limits Report Project stage: RAI ML1032603222010-10-31031 October 2010 ANP-2948NP, Rev. 0, Mechanical Design Report for Brunswick Atrium 10XM Fuel Assemblies, Enclosure 3 to BSEP 10-0126 Project stage: Other BSEP 10-0126, ANP-2956(NP), Rev. 0, Brunswick Unit 2 Cycle 20 Reload Safety Analysis, Enclosure 6 to BSEP 10-01262010-10-31031 October 2010 ANP-2956(NP), Rev. 0, Brunswick Unit 2 Cycle 20 Reload Safety Analysis, Enclosure 6 to BSEP 10-0126 Project stage: Other ML1032603152010-11-0909 November 2010 Additional Information Supporting License Amendment Requests for Mechanical Design Report for Atrium 10XM Fuel Assemblies & Reload Safety Analysis Report for Unit 2 Cycle 20 Project stage: Other BSEP 10-0133, Response to Additional Information Request Supporting License Amendment Requests for Addition of Analytical Methodology Topical Reports to Technical Specification 5.6.5 (NRC TAC Nos. ME3856, ME3857, ME3858, and ME3859)2010-11-18018 November 2010 Response to Additional Information Request Supporting License Amendment Requests for Addition of Analytical Methodology Topical Reports to Technical Specification 5.6.5 (NRC TAC Nos. ME3856, ME3857, ME3858, and ME3859) Project stage: Request BSEP 10-0141, ANP-2978NP, Rev. 0, Areva Responses to RAIs on the Atrium 10XM Compliance Audit and Brunswick Lars.2010-12-16016 December 2010 ANP-2978NP, Rev. 0, Areva Responses to RAIs on the Atrium 10XM Compliance Audit and Brunswick Lars. Project stage: Response to RAI ML1036303342010-12-16016 December 2010 Response to Request for Additional Information Regarding License Amendment Requests for Addition of Analytical Methodology Topical Reports to Technical Specification 5.6.5 (NRC TAC Nos. ME3856, ME3857, ME3858, and ME3859) Project stage: Response to RAI ML1108202352011-03-16016 March 2011 Response to Request for Additional Information Regarding License Amendment Request for Addition of Analytical Methodology Topical Reports to Technical Specification 5.6.5 (NRC TAC Nos. ME3858 and ME3859) Project stage: Response to RAI BSEP 11-0031, Areva Report ANP-2992NP, Revision 0, Areva Response to Additional RAI on the Brunswick RODEX4 LAR2011-03-31031 March 2011 Areva Report ANP-2992NP, Revision 0, Areva Response to Additional RAI on the Brunswick RODEX4 LAR Project stage: Other BSEP 11-0040, Unit I & 2, Additional Information Supporting License Amendment Request to Add Analytical Methodology ANP-10298PA to Technical Specification 5.6.5,Core Operating Limits Report (COLR) (NRC TAC ME3856 & Me...2011-04-0606 April 2011 Unit I & 2, Additional Information Supporting License Amendment Request to Add Analytical Methodology ANP-10298PA to Technical Specification 5.6.5,Core Operating Limits Report (COLR) (NRC TAC ME3856 & Me... Project stage: Request ML11101A0432011-04-0808 April 2011 Issuance of Amendments Regarding Addition of Analytical Methodology Topical Report to Technical Specification 5.6.5 (TAC Nos. ME3858 and ME3859) - Redacted Project stage: Approval ML11102A0482011-04-12012 April 2011 Correction to Amendment No. 257 & 285 (TAC ME3856 & ME3857) Project stage: Other ML11102A0502011-04-12012 April 2011 Correction to Amendment No. 256 & 284 (TAC ME3858 & ME3859) Project stage: Other ML11091A0002011-04-14014 April 2011 Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance ML11089A0082011-04-14014 April 2011 Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance ML11097A0132011-04-15015 April 2011 Request for Withholding Information from Public Disclosure. Project stage: Withholding Request Acceptance ML11097A0162011-04-15015 April 2011 Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance BSEP 12-0018, Submittal of Confirmatory Evaluation for Cycle 192012-01-26026 January 2012 Submittal of Confirmatory Evaluation for Cycle 19 Project stage: Other BSEP 13-0004, Operability Assessment (CR 2012-8084 Revision 1) Identified an Issue with the Approved ACE Correlation for the Atrium 10XM Fuel Design with Regard to the Calculation of K-factor within the AEC Correlation2013-01-29029 January 2013 Operability Assessment (CR #2012-8084 Revision 1) Identified an Issue with the Approved ACE Correlation for the Atrium 10XM Fuel Design with Regard to the Calculation of K-factor within the AEC Correlation Project stage: Other 2011-03-16
[Table View] |
Units, 1 and 2, Additional Information Supporting License Amendment Requests - Atrium 10XM Fuel Rod Thermal and Mechanical Evaluation for Unit 2, Cycle 20ML102920551 |
Person / Time |
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Site: |
Brunswick |
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Issue date: |
10/12/2010 |
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From: |
Annacone M J Progress Energy Carolinas |
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To: |
Document Control Desk, Office of Nuclear Reactor Regulation |
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References |
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BSEP 10-0118, TAC ME3856, TAC ME3857, TAC ME3858, TAC ME3859, TSC-2010-01, TSC-2010-02 |
Download: ML102920551 (7) |
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Category:Letter
MONTHYEARIR 05000324/20240032024-11-13013 November 2024 Integrated Inspection Report 05000324/2024003 and 05000325/2024003 IR 05000324/20253012024-10-17017 October 2024 Notification of Licensed Operator Initial Examination 05000325/2025301 and 05000324/2025301 IR 05000324/20244012024-10-15015 October 2024 Security Baseline Inspection Report 05000324/2024401 and 05000325/2024401 ML24297A6262024-10-11011 October 2024 PCA Letter to NRC Brunswick Potential Tropical Storm Eight IR 05000324/20240102024-09-10010 September 2024 Focused Engineering Inspection Commercial Grade Dedication Report 05000324-2024010 and 05000325-2024010 ML24218A0862024-09-0909 September 2024 NRC to NMFS, Designation of Duke Energy Progress LLC as the Non-Federal Representative for Brunswick Steam Electric Plant, Units 1 and 2 ML24249A1362024-09-0404 September 2024 EN 57304 - Westinghouse Electric Company, LLC, Final Report - No Embedded Files. Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21 ML24242A0322024-08-29029 August 2024 Submittal of Updated Final Safety Analysis Report (UFSAR) Revision 29, 10 CFR 54.37 Update, Technical Requirements Manuals, Technical Specification Bases, 10 CFR 50.59 and 10 CFR 72.48 Evaluation Summaries, and Commitment Change IR 05000324/20240052024-08-23023 August 2024 Updated Inspection Plan for Brunswick Steam Electric Plant, Units 1 and 2 (Report 05000324/2024005 and 05000325/2024005) IR 05000324/20240022024-08-0505 August 2024 Integrated Inspection Report 05000324/2024002 and 05000325/2024002 and 07200006/2024001 ML24206A1062024-07-30030 July 2024 2024 Brunswick Requal Inspection Corporate Notification Letter ML24183A0972024-07-12012 July 2024 ISFSI; Catawba 1, 2 & ISFSI; McGuire 1, 2 & ISFSI; Oconee 1, 2, 3 & ISFSI; Shearon Harris 1; H. B. Robinson 2 & ISFSI; and Radioactive Package Shipping Under 10 CFR 71 (71-266 & 71-345) – Review of QA Program Changes EPID L-2024-LLQ-0002 IR 05000324/20244202024-07-0202 July 2024 – Security Baseline Inspection Report 05000324/2024420 and 05000325/2024420 ML24108A0702024-06-0505 June 2024 – Issuance of License Amendments to Revise the 10 CFR 50.69 Categorization Process to Reflect an Alternative Seismic Approach IR 05000324/20244022024-05-17017 May 2024 Plan Material Control and Accounting Program Inspection Report 05000324/2024402 and 05000325/2024402 - Cover Letter IR 05000324/20240012024-05-0909 May 2024 Integrated Inspection Report 05000324/2024001 and 05000325/2024001 05000325/LER-2024-002, Re Automatic Start of Emergency Diesel Generator Due to Emergency Bus De-energization2024-04-10010 April 2024 Re Automatic Start of Emergency Diesel Generator Due to Emergency Bus De-energization 05000325/LER-2024-001, Primary Containment Penetration Local Leak Rate Testing Failure2024-04-10010 April 2024 Primary Containment Penetration Local Leak Rate Testing Failure IR 05000324/20243012024-04-0303 April 2024 NRC Operator License Examination Report 05000325/2024301 and 05000324/2024301 ML24066A0132024-03-0505 March 2024 Bru 2024-002 Radiation Safety Baseline Inspection Information Request ML24026A0982024-03-0101 March 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0057 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) IR 05000324/20230062024-02-28028 February 2024 Annual Assessment Letter for Brunswick Steam Electric Plant, Units 1 and 2 – NRC Inspection Reports 05000324/2023006 and 05000325/2023006 IR 05000324/20244032024-02-14014 February 2024 Information Request for the Cybersecurity Baseline Inspection, Notification to Perm Inspection 05000325/2024403; 05000324/2024403 ML24032A1392024-02-12012 February 2024 Correction of Errors within Authorized Alternative Request RA-22-0308 IR 05000324/20230042024-02-0606 February 2024 Integrated Inspection Report 05000324/2023004 and 05000325/2023004 IR 05000324/20230112023-12-26026 December 2023 NRC Fire Protection Team Inspection - FPTI Report 05000324/2023011 and 05000325/2023011 IR 05000324/20234022023-12-14014 December 2023 Security Baseline Inspection Report 05000324-2023402 and 05000325-2023402 ML23297A0262023-11-27027 November 2023 – Proposed Alternatives to ASME Code Section XI Subsection IWE Requirements for Torus Metallic Liner Inspections 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 05000324/20230032023-11-0101 November 2023 Integrated Inspection Report 05000324/2023003 and 05000325/2023003 IR 05000324/20230102023-10-17017 October 2023 Biennial Problem Identification and Resolution Inspection Report 05000324/2023010 and 05000325/2023010 IR 05000325/20234012023-10-16016 October 2023 Security Baseline Inspection Report 05000324 and 05000325 2023401 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 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 05000324/20230052023-08-23023 August 2023 Updated Inspection Plan for Brunswick Steam Electric Plant, Units 1 and 2 (Report 05000324/2023005 and 05000325/2023005) IR 05000324/20230022023-08-0404 August 2023 Integrated Inspection Report 05000324/2023002 and 05000325/2023002 ML23201A2042023-07-28028 July 2023 Summary of Regulatory Audit in Support of Alternative Request RA-22-0308 for Inservice Inspection of the Torus Metallic Liner 05000324/LER-2023-001, Two Main Steam Line Safety Relief Valves Inoperable2023-07-17017 July 2023 Two Main Steam Line Safety Relief Valves Inoperable 05000325/LER-2023-001, Loss of Redundant Power Supply Operation Causes Turbine Trip and Subsequent Reactor Scram2023-06-15015 June 2023 Loss of Redundant Power Supply Operation Causes Turbine Trip and Subsequent Reactor Scram ML23212A9502023-05-24024 May 2023 Engine Systems, Inc., Part 21 Report Re Woodward EGB-35P Governor/Actuator with Foreign Material ML23146A0012023-05-24024 May 2023 EN 56538 - Engine Systems Inc and Brunswick ML23130A3902023-05-12012 May 2023 – Regulatory Audit Plan in Support of Alternative Request RA 22-0308 for Inservice Inspection of the Torus Metallic Liner IR 05000324/20230012023-05-10010 May 2023 – Integrated Inspection Report 05000324 2023001 and 05000325 2023001 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 IR 05000324/20220042023-04-0404 April 2023 Reissue - Brunswick Steam Electric Plant - Integrated Inspection Report 05000324/2022004 and 05000325/022004 ML22332A4932023-03-10010 March 2023 William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility IR 05000324/20220062023-03-0101 March 2023 Annual Assessment Letter for Brunswick Steam Electric Plant, Units 1 and 2 – NRC Inspection Reports 05000324/2022006 and 05000325/2022006 ML23033A5252023-02-0808 February 2023 Integrated Inspection Report 05000324/2022004 and 05000325/2022004 IR 05000324/20223012023-02-0303 February 2023 NRC Operator License Examination Report 05000325/2022301 and 05000324/2022301 2024-09-09
[Table view] |
Text
Michael J. Annacone , Progress Energy Vice President Brunswick Nuclear Plant OCT 1 2 2010 SERIAL: BSEP 10-0118 10 CFR 50.90 TSC-2010-01
& TSC-2010-02 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
Subject:
Brunswick Steam Electric Plant, Unit Nos. 1 and 2 Renewed Facility Operating License Nos. DPR-71 and DPR-62 Docket Nos. 50-325 and 50-324 Additional Information Supporting License Amendment Requests-ATRIUM 1 OXM Fuel Rod Thermal and Mechanical Evaluation for Brunswick Unit 2 Cycle 20 (NRC TAC Nos. ME3856, ME3857, ME3858, and ME3859)
References:
- 1. Letter from Michael J. Annacone to the U.S. Nuclear Regulatory Commission (Serial: BSEP 10-0052), "Request for License Amendments
-Addition of Analytical Methodology Topical Report to Technical Specification 5.6.5, "Core Operating Limits Report (COLR)," dated April 29, 2010 (ADAMS Accession Number ML 101310388)
- 2. Letter from Michael J. Annacone to the U.S. Nuclear Regulatory Commission (Serial: BSEP 10-0057), "Request for License Amendments
-Addition of Analytical Methodology Topical Report to Technical Specification 5.6.5, "Core Operating Limits Report (COLR)," dated April 29, 2010 (ADAMS Accession Number ML 101310389)
Ladies and Gentlemen:
By letters dated April 29, 2010 (i.e., References 1 and 2), Carolina Power & Light Company (CP&L), now doing business as Progress Energy Carolinas, Inc., requested license amendments to revise the Technical Specifications (TS) for the Brunswick Steam Electric Plant (BSEP), Unit Nos. 1 and 2. The proposed license amendments revise Technical Specification 5.6.5.b by adding: (1) AREVA Topical Report ANP-10298PA, A CE/ATRIUM 10XM Critical Power Correlation, Revision 0, March 2010, and (2) AREVA Topical Report BAW- 10247PA, Realistic Thermal-Mechanical Fuel Rod Methodology for Boiling Water Reactors, Revision 0, April 2008, to the list of analytical methods that have been reviewed and approved by the NRC for determining core operating limits.Progress Energy Carolinas, Inc.P.O. Box 10429 Southport, NC 28461 T> 910.457.3698 Document Control Desk BSEP 10-0118 / Page 2 In these requests, CP&L stated that the Mechanical Design Reports and Reload Safety Analysis Report would be provided to the NRC, for information, in November 2010. Two mechanical design reports will support the BSEP, Unit 2 Cycle 20 core reload. The first report, ANP-2950P, Revision 0, ATRIUM 10XM Fuel Rod Thermal and Mechanical Evaluation for Brunswick Unit 2 Cycle 20 Reload BRK2-20, dated October 2010, has been completed and is provided in Enclosure
- 1. ANP-2950P, Revision 0, contains information that AREVA considers to be proprietary, as defined by 10 CFR 2.390. AREVA, as the owner of the proprietary information, has executed the affidavit provided in Enclosure 2, which identifies that the enclosed proprietary information has been handled and classified as proprietary, is customarily held in confidence, and has been withheld from public disclosure.
AREVA requests that the enclosed proprietary information be withheld from public disclosure in accordance with the provisions of 10 CFR 2.390. A non-proprietary version of ANP-2950P, Revision 0 (i.e., ANP-2950NP, Revision 0), is provided in Enclosure 3.The second mechanical design report, which summarizes cycle-independent evaluations of the ATRIUM 1 OXM fuel assembly and channel structural design, and the Reload Safety Analysis Report will be provided to the NRC, through a separate letter, in November 2010.No regulatory commitments are contained in this letter. Please refer any questions regarding this submittal to Mr. Lee Grzeck, Acting Supervisor
-Licensing/Regulatory Programs, at (910) 457-2487.I declare, under penalty of perjury, that the foregoing is true and correct. Executed on October 12, 2010.Sincerely, Michael J. Annacone WRM/wrm
Enclosures:
- 1. AREVA Report ANP-2950P, Revision 0, ATRIUM lOXMFuel Rod Thermal and Mechanical Evaluation for Brunswick Unit 2 Cycle 20 Reload BRK2-20, dated October 2010 (Proprietary Information
-Withhold from Public Disclosure in Accordance With 10 CFR 2.390)2. AREVA Affidavit Regarding Withholding ANP-2950P, Revision 0, from Public Disclosure
- 3. AREVA Report ANP-2950NP, Revision 0, ATRIUM lOXM Fuel Rod Thermal and Mechanical Evaluation for Brunswick Unit 2 Cycle 20 Reload BRK2-20, dated October 2010 Document Control Desk BSEP 10-0118 / Page 3 cc (with all enclosures):
U. S. Nuclear Regulatory Commission, Region II ATTN: Mr. Luis A. Reyes, Regional Administrator 245 Peachtree Center Avenue, NE, Suite 1200 Atlanta, GA 30303-1257 U. S. Nuclear Regulatory Commission ATTN: Mr. Philip B. O'Bryan, NRC Senior Resident Inspector 8470 River Road Southport, NC 28461-8869 U. S. Nuclear Regulatory Commission (Electronic Copy Only)ATTN: Mrs. Farideh E. Saba (Mail Stop OWFN 8G9A)11555 Rockville Pike Rockville, MD 20852-2738 cc (with only Enclosures 2 and 3): Chair -North Carolina Utilities Commission P.O. Box 29510 Raleigh, NC 27626-0510 Mr. W. Lee Cox, III, Section Chief Radiation Protection Section North Carolina Department of Environment and Natural Resources 1645 Mail Service Center Raleigh, NC 27699-1645 BSEP 10-0118 Enclosure 2 AREVA Affidavit Regarding Withholding ANP-2950P, Revision 0, from Public Disclosure AFFIDAVIT STATE OF WASHINGTON
)) ss.COUNTY OF BENTON )1. My name is Alan B. Meginnis.
I am Manager, Product Licensing, for AREVA NP Inc. 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 report ANP-2950P Revision 0, entitled, "ATRIUM 10XM Fuel Rod Thermal and Mechanical Evaluation for Brunswick Unit 2 Cycle 20 Reload BRK2-20," dated October 2010 and referred to herein as"Document." Informationcontained 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), 6(d) and 6(e) 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 ____day of ,2010.Susan K. McCoy NOTARY PUBLIC, STATE OF WASHINGTON MY COMMISSION EXPIRES: 1/10/12