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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: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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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 December 28, 2011 Christopher Burton, Vice President Shearon Harris Nuclear Power Plant Carolina Power & Light Company Post Office Box 165, Mail Zone 1 New Hill, North Carolina 27562-0165
SUBJECT:
SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1 -ACCEPTANCE OF REQUESTED LICENSING ACTION REGARDING REALISTIC LARGE BREAK LOSS-OF-COOLANT ACCIDENT (TAC NO. ME6999) (HNP-11-067)
Dear Mr. Burton:
By letter dated August 22,2011, Carolina Power & Light Company, the licensee, submitted a license amendment request for Shearon Harris Nuclear Power Plant, Unit 1. The amendment request would revise Technical Specification (TS) 6.9.1.6, "Core Operating Limits Report," to add a plant-specific methodology that implements AREVA's Nuclear Regulatory Commission (NRC)-approved topical report, EMF-2103(P)(A), "Realistic Large Break LOCA Methodology for Pressurized Water Reactors." The amendment request will also add EMF-2103(P)(A),
"Realistic Large Break LOCA [Ioss-of-coolant accident] Methodology for Pressurized Water Reactors," Revision 2 (or higher, upon approval of the specific revision by the NRC) to the TS 6.9.1.6.2 listing of analytical methods used to determine the core operating limits, and will eliminate extraneous detail in TS 6.9.1.6 that cross references each method to the applicable specifications and parameters of TS Section 3.0 The purpose of this letter is to provide the results of the NRC staff's acceptance review of this license amendment request. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant. An initial confirmation of the NRC staff's acceptance was provided by electronic mail to Mr. John Caves of your staff on September 29,2011.
Consistent with Section 50.90 of Title 10 of the Code of Federal Regulations (10 CFR), an amendment to the license (including the technical specifications) must fully describe the changes requested, and following as far as applicable, the form prescribed for original applications. Section 50.34 of 10 CFR addresses the content of technical information required.
This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations.
The NRC staff finds that while clearly based on extensive study, significant research, and judicial selection of modeling assumptions, the justification for omission of a clad ballooning and rupture, and fuel pellet relocation model, remains questionable. The complexity of this request will require a significant amount of information to be reviewed. The NRC staff recognizes that
C.Burton -2 the requested review schedule for this request is extremely tight and appears to be need-based.
Timely support in providing responses to any information requests will be crucial to meeting your requested approval date. However, the NRC notes that, given the complexity and the tie to a topical report currently under review, approval of this request in the timeframe requested may not be achievable.
The NRC staff has, reviewed your application and concluded that it provides technical information in sufficient detail to enable the staff to proceed with its detailed technical review and make an independent assessment regarding the acceptability of the proposed amendment in terms of regulatory requirements and the protection of public health and safety and the environment. If additional information is need for the NRC staff to complete its technical review, you will be advised by separate correspondence.
If you have any questions, please feel free to contact me, at (301) 415-2020.
Sincerely, Brenda L. Mozafari, Senior Project Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-400 cc: Distribution via Listserv
ML11339A050 OFFICE LPUI-2/PM LPUI-2/LA SRXB/BC SNPB/BC DORULPU 1-2/BC DBroaddus NAME BMozafari RSoia AUlses AMendiola (SLingam for)
DATE 12/19/11 12/16/11 12/23111 12/27/11 12/28/11