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Category:Letter
MONTHYEARML24290A1102024-10-24024 October 2024 Notification of Licensed Operator Initial Examination 05000400/2025301 05000400/LER-2024-001-01, Automatic Reactor Trip Due to Main Generator Lock-Out2024-10-23023 October 2024 Automatic Reactor Trip Due to Main Generator Lock-Out IR 05000400/20240112024-09-10010 September 2024 NRC Inspection Report 05000400/2024011 IR 05000400/20240052024-08-26026 August 2024 Updated Inspection Plan for Shearon Harris Nuclear Power Plant, Unit 1 (Report 05000400-2024005) Rev 1 ML24059A4252024-08-14014 August 2024 Issuance of Amendment No. 202 Regarding Alignment of Certain Technical Specifications with Improved Standard Technical Specifications ML24213A0522024-08-0202 August 2024 Issuance of Amendment No. 201 to Extend Completion Time of Inoperable Reactor Coolant System Accumulator Using Consolidated Line Item Improvement Process ML24212A3412024-07-31031 July 2024 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection IR 05000400/20240022024-07-29029 July 2024 – Integrated Inspection Report 05000400/2024002 ML24170A7312024-07-29029 July 2024 – Exemption from the Requirements of 10 CFR 50.55a(H)(2) Using the Risk-Informed Process for Evaluations Letter 05000400/LER-2024-001, Automatic Reactor Trip Due to Main Generator Lock-Out2024-07-22022 July 2024 Automatic Reactor Trip Due to Main Generator Lock-Out 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 05000400/20243022024-06-27027 June 2024 – NRC Operator Licensing Examination Approval 05000400/2024302 IR 05000400/20244012024-06-25025 June 2024 – Security Baseline Inspection Report05000400/2024401 ML24162A1372024-06-24024 June 2024 – Regulatory Audit Summary Related to the Review of Exemption Request from Certain Requirements in 10 CFR 50.55a(h)(2)(EPID L-2024-LLE-00040) ML24136A1382024-05-20020 May 2024 – Notification of an NRC Fire Protection Team Inspection (FPTI) (NRC Inspection Report 05000400/2024011) and Request for Information (RFI) ML24116A2592024-05-14014 May 2024 Staff Evaluation Related to Aging Management Plan and Inspection Plan for Reactor Vessel Internals ML24127A1592024-05-0808 May 2024 – Notification of Licensed Operator Initial Examination 05000400/2024302 IR 05000400/20240012024-05-0505 May 2024 Integrated Inspection Report 05000400/2024001 ML24100A0912024-04-10010 April 2024 Operator License Examination Report ML24058A2462024-03-18018 March 2024 – Supplemental Information Needed for Using the Risk-Informed Process for Evaluations for the Request for Exemption from Certain Requirements in 10 CFR 50.55a(h)(2) IR 05000400/20230062024-02-28028 February 2024 Annual Assessment Letter for Shearon Harris Nuclear Power Plant - NRC Inspection Report 05000400/2023006 ML24032A2632024-02-23023 February 2024 – Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0044 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) IR 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 05000400/LER-2022-006-02, Auxiliary Feedwater Pump Inoperability2023-07-11011 July 2023 Auxiliary Feedwater Pump Inoperability 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 05000400/LER-1922-006-01, Auxiliary Feedwater Pump Inoperability2023-03-10010 March 2023 Auxiliary Feedwater Pump Inoperability 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 05000400/LER-2022-007-01, Automatic Reactor Trip Due to Loss of Power from the a Auxiliary Bus2023-01-26026 January 2023 Automatic Reactor Trip Due to Loss of Power from the a Auxiliary Bus ML23020A1252023-01-23023 January 2023 Notification of Target Set Inspection and Request for Information (NRC Inspection Report 05000400/2023403) 05000400/LER-2022-006, Auxiliary Feedwater Pump Inoperability2022-12-20020 December 2022 Auxiliary Feedwater Pump Inoperability 2024-09-10
[Table view] Category:Meeting Summary
MONTHYEARML24124A0342024-05-0101 May 2024 Summary of Public Meeting Concerning Annual Assessment of Catawba Nuclear Station Units 1 and 2, McGuire Nuclear Station Units 1 and 2, Oconee Nuclear Station Units 1, 2, and 3, Brunswick Steam Electric Plant Units 1 and 2, Shearon Harris ML24011A1652024-02-12012 February 2024 December 11, 2023, Summary of Meeting with Duke Energy to Discuss a Shearon Harris Nuclear Power Plant, Unit 1 Planned Exemption Request Related to Turbine Control System and Reactor Protection System Circuitry ML23157A3202023-06-26026 June 2023 Summary of April 26, 2023, Meeting with Duke Energy to Discuss a Shearon Harris Nuclear Power Plant, Unit 1 Planned License Amendment Request Related to Turbine Control System and Reactor Protection System Circuitry ML23151A1232023-05-31031 May 2023 Public Meeting Summary - 2022 Annual Assessment Meeting Regarding Shearon Harris Nuclear Plant ML22167A1852022-06-30030 June 2022 Summary of June 6, 2022, Meeting with Duke Energy to Discuss Shearon Harris Nuclear Power Plant, Unit 1 Closeout of Generic Safety Issue (GSI) 191 ML22129A0062022-05-10010 May 2022 Summary of April 20, 2022, Meeting with Duke Energy Progress, LLC, to Discuss Proposed License Amendment Request to Revise Reactor Coolant System Pressure Isolation Valve Operational Leakage Surveillance Requirement Frequency (L-2022-LRM 00 ML22130A0302022-05-0909 May 2022 Summary of Public Meeting on 2021 Annual Assessment Meeting Regarding Brunswick Steam Electric Plant, Docket Nos. 50-325 and 50-324; and Shearon Harris Nuclear Power Plant, Docket No. 50-400, Meeting Number 20220350 ML21341A5542021-12-29029 December 2021 Summary of November 29, 2021, Meeting with Duke Energy Progress, LLC and Duke Energy Carolinas, LLC to Discuss a Planned License Amendment Request to Relocate ML21172A2672021-08-13013 August 2021 Regulatory Audit Summary Related to the Review of LAR to Revise 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors, Categorization Process to Reflect an Alternative Seis ML21131A1472021-05-11011 May 2021 Public Meeting Summary 2020 Annual Assessment Meeting Regarding Brunswick Steam Electric Plant, Docket Nos. 50-325 and 50-324; and Shearon Harris Nuclear Power Plant, Docket No. 50-400, Meeting Number 20210385 ML20136A2222020-05-15015 May 2020 Har - Bru 2019 Aam Meeting Summary ML19331A8062020-01-29029 January 2020 Summary of November 13, 2019 Closed Meeting with Duke Energy Carolinas, LLC and Duke Energy Progress, LLC, to Discuss Security-Related Information for Its Licensed Facilities ML19329A0232019-11-27027 November 2019 Summary of October 29, 2019 Conference Call with Duke Energy Progress, LLC Regarding the Fall 2019 Steam Generator Tube Inspections ML19241A2902019-09-24024 September 2019 Summary of August 22, 2019, Meeting with Duke Energy Progress, LLC Proposed License Amendment Request to Adopt Risk-Informed Completion Times ML19220A6702019-08-26026 August 2019 Summary of August 7, 2019, Meeting with Duke Energy Progress, LLC and Duke Energy Carolinas, LLC to Discuss a Proposed License Amendment Request for a Common Emergency Plan ML19113A0652019-05-14014 May 2019 Summary of Meeting with Duke Energy to Discuss Proposed License Amendment Request for Shearon Harris, Unit 1, Technical Specification Changes Associated with Departure from Nucleate Boiling Ratio Safety Limit ML19120A1342019-05-0606 May 2019 3/15/19 Summary of Public Meeting with Nuclear Entergy Institute, Duke Energy, and Southern Nuclear Operating Company Post-Pilot Implementation of Tornado Missile Risk Evaluator Methodology at Vogtle, Units 1 and 2 and Shearon Harris, Unit ML19123A3522019-05-0202 May 2019 Public Meeting Summary - Shearon Harris Nuclear Plant, Docket No. 50-400 ML19087A0622019-04-11011 April 2019 Summary of March 25, 2019, Public Teleconference with Duke Energy to Discuss the Request for Additional Information Response Regarding the Proposed Alternative to the Depth Sizing Qualification Requirement (Duke Energy Fleet Relief Request ML18352A3572019-01-0808 January 2019 Summary of Meeting with Duke Energy Progress, LLC to Discuss Proposed License Amendment Request for Shearon Harris Nuclear Power Plant, Unit 1, Regarding Emergency Plan Changes ML18361A6712019-01-0808 January 2019 Summary of Meeting with Duke Energy Progress, LLC to Discuss License Amendment Request for Shearon Harris Unit 1, Regarding 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, ML18355A8142019-01-0707 January 2019 Summary of December 20, 2018, Teleconference Meeting with Duke Energy Progress, LLC to Discuss a Proposed License Amendment Request for Shearon Harris Unit 1, Regarding a Risk-Informed Essential Services Chilled Water System TS ML18094A2632018-08-17017 August 2018 Summary of 01/18/2018, Public Meeting with Nuclear Energy Institute, Duke Energy, Southern Nuclear Operating Co., Entergy Operations, Inc. to Discuss Development of Tornado Missile Risk Evaluator Methodology ML18109A0912018-04-19019 April 2018 Summary of 2017 Annual Assessment Public Meeting Regarding Shearon Harris Nuclear Plant, Docket No. 50-400 ML18088A0732018-04-0303 April 2018 March 27, 2018, Summary of Presubmittal Meeting with Duke Energy Progress, LLC to Discuss a Proposed Relief Request for Shearon Harris Nuclear Power Plant, Unit 1 ML18064A1332018-03-19019 March 2018 Summary of February 27, 2018, Meeting with Duke Energy Progress, LLC to Discuss Proposed License Amendment Request for Shearon Harris Nuclear Power Plant, Unit 1, Regarding Emergency Plan Emergency Action Level Scheme Changes (L-2017-LRM-00 ML17340A1302017-12-22022 December 2017 Summary of November 29, 2017, Meeting with Duke Energy Progress, LLC to Discuss Proposed License Amendment Requests to Implement the Requirement of 10 CFR 50.69 at Brunswick, Shearon Harris, and H. B. Robinson ML17340A0612017-12-0808 December 2017 11/8/17 Summary of Teleconference with Entergy Operations, Inc., Tornado Missile Risk Evaluator with Applicability to Submittals from Duke Energy and Southern Nuclear Operating Co, Inc. ML17244A0742017-09-28028 September 2017 8/17/2017 Summary of Public Meeting with Nuclear Energy Institute and Licensees to Discuss the Tornado Missile Risk Evaluation Tool for Grand Gulf, Shearon Harris, and Vogtle, Units 1 and 2 ML17257A0992017-09-26026 September 2017 Summary of Public Meeting with Nuclear Energy Institute and Licensees to Discuss the Tornado Missile Risk Evaluation Tool for Grand Gulf, Shearon Harris, and Vogtle, Units 1 and 2 ML17223A1212017-08-17017 August 2017 Summary of August 3, 2017, Meeting with Duke Energy Progress, LLC on Proposed License Amendment Request to Implement Fuel Reload Design Methodology Reports for Shearon Harris and H. B. Robinson ML17145A3142017-05-25025 May 2017 EOC Meeting Summary ML16286A0152016-11-0101 November 2016 Summary Of September 29, 2016, Duke Energy Progress, LLC. To Discuss Proposed License Amendment Request Regarding Shearon Harris Nuclear Power Plant, Unit 1, BWR Storage Rack Inserts And The Spent Fuel Pool Criticality Analysis (CAC No. MF8327) ML16235A2382016-10-17017 October 2016 Summary of the July 12-13, 2016 Audit Supporting the U.S. Nuclear Regulatory Commission Review of DPC-NE-1008-P, Nuclear Design Methodology Using CASMO-5/SIMULATE-3 for Westinghouse Reactors ML16125A0992016-05-20020 May 2016 Summary of May 2, 2016, Meeting with Duke Energy Progress, Inc. to Discuss Fuel Reload Design Methodology Reports and Proposed Supplement to a License Amendment Request Regarding Shearon Harris and H.B. Robinson ML16134A1552016-05-12012 May 2016 Public Meeting Summary - 2015 Annual Assessment Public Meeting Regarding Shearon Harris Nuclear Plant ML16112A3772016-04-25025 April 2016 Summary of Meeting with Duke Energy Progress, Inc. to Discuss the Shearon Harris Nuclear Plant, Unit 1, TSTF-425 LAR Request for Additional Information Reponses ML16034A5242016-03-11011 March 2016 Summary of February 1, 2016, Pre-submittal Meeting with Duke Energy Regarding Consolidation of Emergency Operations Facilities ML16035A4802016-02-12012 February 2016 Jsc Meeting Summary Attachment ML15280A2532015-11-25025 November 2015 Summary of Mtg. with Duke Energy Progress Inc. to Discuss Fuel Reload Design Methodology Reports & Proposed License Amendment Request Shearon Harris Nuclear Power Plant Unit 1 and H.B. Robinson Steam Electric Plant Unit No. 2 (MF6701/MF6702 ML15202A4752015-09-24024 September 2015 Summary of Meeting with Duke Energy Progress, Inc. to Discuss Shearon Harris Nuclear Power Plant, Unit 1, Proposed License Amendment Request Regarding Technical Specifications for the Pressurizer and Main Steam Line Safety Valves (MF6233) ML14129A3352014-05-0909 May 2014 Summary of Category 1 Public Meeting - Annual Assessment of Shearon Harris Nuclear Plant ML13312A9882013-11-0808 November 2013 Summary of Public Meeting with Duke Energy Carolinas, LLC, to Provide Opportunities to Discuss the Planned Fukushima-Related Modifications ML13204A2672013-09-27027 September 2013 07/09/13 Summary of Meeting with Duke Energy Regarding a Nonconservative Technical Specification Loss of Offsite Power Voltage Setpoint License Amendment Request ML13218B3692013-09-27027 September 2013 7/30/2013 - Summary of Meeting with Duke Energy Regarding a Change to the Emergency Response Facility Activation Timeliness and Criteria ML13225A2932013-08-12012 August 2013 7/23-24/2013, Summary of Meeting 2013 U.S. Nuclear Regulatory Commission (NRC) Initial Exam Writers' Workshop ML13171A3292013-06-20020 June 2013 Public Meeting Summary, Category 3, NRC Special Inspection on Reactor Vessel Head Nozzle Repair of Shearon Harris Nuclear Plant ML13155A1052013-06-12012 June 2013 May 2, 2013, Summary of Meeting with Duke Energy Concerning the Relocation of the Emergency Operating Facilities ML13151A2262013-05-30030 May 2013 Meeting Summary - Category 1 Public Meeting Annual Assessment - Shearon Harris Nuclear Plant - Docket 50-400 ML12277A0252012-11-0202 November 2012 10/2/12 Summary of Meeting with Duke Energy Carolinas to Discuss Nonconservative Technical Specifications License Amendment Requests 2024-05-01
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24212A3412024-07-31031 July 2024 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML24101A0522024-04-10010 April 2024 NRR E-mail Capture - Shearon Harris Nuclear Power Plant, Unit 1 - Request for Additional Information - ITS Alignments LAR (L-2023-LLA-0078) ML24058A2462024-03-18018 March 2024 – Supplemental Information Needed for Using the Risk-Informed Process for Evaluations for the Request for Exemption from Certain Requirements in 10 CFR 50.55a(h)(2) ML24025A1592024-01-25025 January 2024 NRR E-mail Capture - Shearon Harris Nuclear Power Plant, Unit 1 - Request for Additional Information - Rvi AMP and Inspection Plan (L-2023-LLL-0016) ML23151A3482023-05-30030 May 2023 Duke Fleet - Request for Additional Information Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) ML23142A2732023-05-22022 May 2023 Duke Fleet - Request for Additional Information Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1) ML23082A0432023-03-23023 March 2023 002 Radiation Safety Baseline Inspection Information Request Final ML23020A1252023-01-23023 January 2023 Notification of Target Set Inspection and Request for Information (NRC Inspection Report 05000400/2023403) ML22115A1412022-04-25025 April 2022 NRR E-mail Capture - Duke Common EOF Relocation - Request for Addition Information ML21354A8612021-12-15015 December 2021 NRR E-mail Capture - Request for Additional Information - Duke Fleet Request RA-19-0352 - Alternative for RPV Closure Stud Exams (L-2020-LLR-0156) ML21258A3652021-09-15015 September 2021 Notification of an NRC Fire Protection Team Inspection (FPTI) (NRC Inspection Report 05000400/2021011) and Request for Information (RFI) ML21172A2432021-06-21021 June 2021 NRR E-mail Capture - Request for Additional Information - Harris RA-20-0252 - LAR to Remove Extraneous Requirements from OL and TS (L-2021-LLA-0027) ML21036A1142021-02-0505 February 2021 NRR E-mail Capture - Request for Additional Information - Harris - Relief Request RA-20-0312 - SW Pinhole Leak (L-2020-LLR-0143) ML21049A2632021-02-0404 February 2021 NRR E-mail Capture - Request for Additional Information - Duke Energy Fleet License Amendment Request to Revise Emergency Plan ML21032A0492021-02-0101 February 2021 NRR E-mail Capture - Request for Additional Information - Duke Fleet RA-20-0263 - Use of Later ASME B&Pv, XI for Repair - Replacement (L-2020-LLR-0124) ML20323A4072020-11-18018 November 2020 NRR E-mail Capture - Request for Additional Information - Brunswick License Exemption Request from 10CFR73 Annual Force on Force Exercise Requirements (EPIC L-2020-LLE-0180) ML20297A3072020-10-13013 October 2020 NRR E-mail Capture - Request for Additional Information - Shearon Harris Nuclear Power Plant, Unit 1 - RCS Flowrate Reduction/Lbloca LAR ML20274A0462020-09-29029 September 2020 Request for Additional Information Regarding License Amendment Request to Adopt TSTF-505, Revision 2 ML20247J3822020-09-0303 September 2020 Request for Additional Information - Shearon Harris Nuclear Power Plant, Unit 1 - Revise TS Related to Accident Monitoring and RFO Instrumentation ML19331A4002019-11-27027 November 2019 Request for Additional Information Regarding Licensing Action to Modify the Departure from Nucleate Boiling Ratio Safety Limit to Address Transition to New Fuel Type ML19204A2682019-07-23023 July 2019 NRR E-mail Capture - Shearon Harris Nuclear Power Plant, Unit 1 Request for Additional Information for the Escw System TS AOT Extension and Removal of an Expired Note in TS Risk Informed LAR (L-2019-LLA-0025) ML19136A2712019-05-28028 May 2019 Supplemental Information Needed for Acceptance of Requested Licensing Action Regarding License Amendment Request to Modify the Departure from Nucleate Boiling Ratio Safety Limit to Address Transition to New Fuel Type ML19060A0912019-03-18018 March 2019 Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML19011A1372019-01-10010 January 2019 NRR E-mail Capture - Duke Energy Fleet RAIs - Relief Request 18-GO-001 - Proposed Alternative for Depth Sizing Qualification Examination of Welds (L-2018-LLR-0117) ML19007A3422018-12-21021 December 2018 NRR E-mail Capture - Duke Energy Fleet Draft RAIs - Relief Request 18-GO-001 - Proposed Alternative for Depth Sizing Qualification Examination of Welds (L-2018-LLR-0117) ML18332A4392018-11-28028 November 2018 NRR E-mail Capture - Shearon Harris Nuclear Power Plant, Unit 1 Request for Additional Information for EAL Scheme Changes ML18337A1272018-11-28028 November 2018 NRR E-mail Capture - Shearon Harris Nuclear Power Plant, Unit 1 Request for Additional Information Regarding the Rts/Esfas Trip Setpoints Modification LAR ML18264A0282018-10-0909 October 2018 RAI Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk Informed Categorization Aad Treatment of Structures, Systems and Components for Nuclear Power Reactors ML18145A1812018-06-18018 June 2018 Request for Additional Information, License Amendment Request to Revise Updated Final Safety Analysis Report to Incorporate Tornado Missile Risk Evaluator Methodology Into Licensing Basis RA-18-0011, Response to Request for Supplemental Information Regarding Duke Energy'S Response to GL 2016-01 Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools2018-05-30030 May 2018 Response to Request for Supplemental Information Regarding Duke Energy'S Response to GL 2016-01 Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools ML18116A1052018-04-25025 April 2018 NRR E-mail Capture - Harris/Robinson RAIs - Change Technical Specifications to Support Performance of Core Reload Design and Safety Analyses (L-2017-LLA-0356) ML18108A7602018-04-18018 April 2018 NRR E-mail Capture - Harris/Robinson Draft RAIs - Change Technical Specifications to Support Performance of Core Reload Design and Safety Analyses (L-2017-LLA-0356) ML18058B2242018-02-26026 February 2018 Emailed Radiation Safety RFI ML18005A5482018-01-0808 January 2018 Request for Additional Information Regarding License Amendment Request for Spent Fuel Storage Pool Criticality Analyses (CAC No. MF9996; EPID L-2017-LLA-0303) ML17345A8772017-12-11011 December 2017 NRR E-mail Capture - Harris and Robinson Supplemental RAI - LAR to Adopt DPC-NE-3009-P, Revision 0, Thermal-Hydraulic Models for Transient Analysis, (L-2016-LLA-0012) ML17339A0722017-12-0404 December 2017 NRR E-mail Capture - Subject: Harris and Robinson Draft Supplemental RAIs - LAR to Adopt DPC-NE-3009-P, Revision 0, Thermal-Hydraulic Models for Transient Analysis, (L-2016-LLA-0012) ML17289A3062017-10-23023 October 2017 Shearon Harris Nuclear Plant, Unit 1 - Request for Additional Information Regarding License Amendment Request Proposing Changes to Emergency Diesel Generator Technical Specifications Surveillance Requirements (CAC No. MF9828; EPID L-2017-LLA-0244) ML17250B0172017-09-18018 September 2017 Shearon Harris, Unit 1 - Request for Additional Information Re: License Amendment Request Proposing New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods that Exceed the LHGR Limit Detailed in RG 1.183, Table 3 (CAC No. MF9740) ML17241A0182017-08-30030 August 2017 Supplemental Information Needed for Acceptance of Requested Licensing Action Regarding Spent Fuel Storage Pool Criticality Analyses ML17192A4842017-07-11011 July 2017 NRR E-mail Capture - Duke Energy Fleet RAIs Alternative for Reactor Pressure Vessel Flange Threads Examination (MF9513 to MF9521) ML17123A1332017-05-0909 May 2017 Shearon Harris Nuclear Plant, Unit 1 - Request for Additional Information Re: License Amendment Request to Relocate Specific TS Parameters to the COLR, Remove Reference to a Plant Procedure as it Pertains to the COLR in TSs, etc. (CAC No. MF8894) ML17109A2912017-04-19019 April 2017 NRR E-mail Capture - Shearon Harris Nuclear Power Plant, Unit 1 Final Request for Additional Information Concerning LAR to Adopt TSTF-339, TSTF-5 and Other Administrative Changes ML16363A0112016-12-27027 December 2016 Notification of Shearon Harris Nuclear Power Plant Design Basis Assurance Inspection - U.S. Nuclear Regulatory Commission Inspection Report 05000400/2017007 ML16335A0462016-12-0606 December 2016 Shearon Harris Nuclear Power Plant, Unit 1 - Request for Additional Information Regarding License Amendment Request to Modify Diesel Fuel Oil Testing Surveillance Requirements (CAC No. MF7775) ML16288A0782016-10-26026 October 2016 Shearon Harris Nuclear Power Plant, Unit 1, and H.B. Robinson Steam Electric Plant, Unit No. 2 - Redacted, Request for Additional Information Re: Request to Adopt DPC-NF-2010 and DPC-NF-2011 Nuclear Design Methodology (CAC Nos. MF7693 and MF7694) ML16288A0042016-10-26026 October 2016 Shearon Harris Nuclear Plant, Unit 1 - Request For Additional Information Regarding License Amendment Request To Relocate The Explosive Gas Mixture And Liquid Holdup Tanks Technical Specifications Requirements (CAC No. MF8067) ML16223A4172016-08-0808 August 2016 Notification of Inspection and Request for Information ML16209A2642016-08-0202 August 2016 Shearon Harris Nuclear Plant, Unit 1 - Second Request For Additional Information Regarding License Amendment Request For A Temporary Change To Technical Specifications For The 'A' Emergency Service Water Pump Replacement (CAC No. MF7017) ML16028A1972016-02-0808 February 2016 Request for Additional Information Regarding License Amendment Request for a Temporary Change to Technical Specifications for the 'A' Emergency Service Water Pump Replacement ML15344A0302015-12-17017 December 2015 Request for Additional Information Application to Revise Technical Specifications for Methodology Report DPC-NE-2005-P, Revision 5, Thermal Hydraulic Statistical Core Design Methodology (MF5872/MF5873) 2024-07-31
[Table view] |
Text
January 7, 2008LICENSEE:Carolina Power & Light CompanyFACILITY:Shearon Harris Nuclear Power Plant, Unit 1
SUBJECT:
SUMMARY
OF TELEPHONE CONFERENCE CALL HELD ON AUGUST 13, 2007, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND CAROLINA POWER & LIGHT COMPANY, CONCERNING DRAFT REQUESTS FOR ADDITIONAL INFORMATION PERTAINING TO THE SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1, LICENSE RENEWAL APPLICATIONThe U.S. Nuclear Regulatory Commission and representatives of Carolina Power & LightCompany held a telephone conference call on August 13, 2007, to discuss and clarify the staff's draft requests for additional information (D-RAIs) concerning the Shearon Harris Nuclear Power Plant, Unit 1, license renewal application. The telephone conference call was useful in clarifying the intent of the staff's D-RAIs.Enclosure 1 provides a listing of the participants and Enclosure 2 contains a listing of theD-RAIs discussed with the applicant, including a brief description on the status of the items.The applicant had an opportunity to comment on this summary./RA/Maurice Heath, Project ManagerLicense Renewal Branch A Division of License Renewal Office of Nuclear Reactor RegulationDocket No. 50-400
Enclosures:
- 1. List of Participants
- 2. List of Draft Requests for Additional Informationcc w/encls: See next page
ML072430282OFFICEPM:RLRA:DLRLA:DLRBC:RLRA:DLRNAMEMHeathIKingLLundDATE09/05/0709/04/0701/07/08 TELEPHONE CONFERENCE CALLSHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1LICENSE RENEWAL APPLICATIONLIST OF PARTICIPANTSAUGUST 13, 2007PARTICIPANTSAFFILIATIONSMaurice HeathU.S. Nuclear Regulatory Commission (NRC)Stanley GardockiNRC Steve PopeInformation Systems Laboratories (ISL)
John WoodfieldISL Roger StewartProgress Energy Chris MallinerProgress Energy DRAFT REQUESTS FOR ADDITIONAL INFORMATIONSHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1LICENSE RENEWAL APPLICATIONAUGUST 13, 2007The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of CarolinaPower & Light Company held a telephone conference call on August 13, 2007, to discuss and clarify the following draft requests for additional information (D-RAIs) concerning the Shearon Harris Nuclear Power Plant (HNP), Unit 1, license renewal application (LRA). D-RAI 2.1.1.2-1LRA Section 2.1 Scoping and Screening MethodologyIn LRA Section 2.1.1.2, "Non-Safety Related Criteria Pursuant to 10 CFR 54.4(a)(2)," theapplicant describes the methodology in identifying applicable structures, systems, and components (SSCs) in LRA Section 2.1.1.2 contains guidance for "10 CFR 54.4(a)(2) Scoping Based on NRC Scoping Guidance for Spatial Interactions and Seismic-Connected Piping."
Additionally, in LRA Section 2.1.1.2, the applicant describes "Spatial Interactions," and on page 2.1-10, the applicant states that the non-connected, non-safety related systems be brought within the scope of license renewal to protect safety related SSCs from the consequences of failures of the non-safety related systems. On LRA pages 2.1-9 and 11, the applicant states in the guidance that the turbine buildingcontains safety related components and that this information is used to identify non-safety related systems having potential for adverse spatial interactions. On LRA page 2.1-11, the applicant describes that feedwater system flow transmitters, the feedwater regulating valves, associated bypass valves, etc., in the Turbine Building as designated safety related in the Pass Port equipment data base (EDB). However, the applicant makes the conclusion, "Therefore, no systems in the Turbine Building are brought into scope per the current guidance regarding special interactions."On LRA pages 2.1-9 and 11, the applicant states in the guidance that the Waste ProcessingBuilding contains safety-related components and that this information is used to identify non-safety related systems having potential for adverse spatial interactions. On LRA page 2.1-11, the applicant describes that the waste gas decay tanks and associated piping and valves and radiation monitor components as designated safety related in the Pass Port EDB. Although, there are non-safety related SSCs within the Waste Processing Building and withinthe Turbine Building that may have the potential for adverse spatial interaction with safety-related components, the applicant has excluded them from 10 CFR 54.4(a)(2) for spatial interactions. The applicant's evaluation has determined that the safety-related components do not meet the license renewal definition of "safety related." Provide the details of the evaluation that allowed the exclusion of the non-safety relatedSSC's within the Turbine Building and within the Waste Processing Building from the 10 CFR 54.4(a)(2) criterion for spatial interactions. Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as aformal RAI.D-RAI 2.1.1.2-2In LRA Section 2.1.1.2, page 2.1-13, under the topic of Seismic-Connected Piping, theapplicant states, "These air/gas piping systems with seismically-connected piping include the Instrument Air System [Section 2.3.3.27], Service Air System [Section 2.3.3.28], Bulk Nitrogen Storage System [Section 2.3.3.29], Hydrogen Gas System [Section 2.3.3.30], and Penetration Pressurization System [Section 2.3.3.62]." These systems have non-safety related piping connected to safety-related piping that are included in the scope of license renewal up to the first seismic anchor or equivalent anchor past the safety/non-safety interface. It is expected all of these systems should have an intended function of "M-4 structural support" in LRA Tables 2.3.3-23, 2.3.3-24, 2.3.3-25, 2.3.3-26 respectively.
Explain why the intended function M-4 Structural Support (i.e. provide structuralsupport/seismic integrity) is not shown also in LRA tables mentioned above for thecomponents subject to an Aging Management Review (AMR).Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as aformal RAI.D-RAI 2.1.2.1-1In LRA Section 2.1.2.1, "Mechanical Components," the applicant describes the process used toidentify mechanical components subject to Aging Management Review (AMR). In LRA Section 2.1.2.1 paragraph 5, on page 2.1-22, the applicant states, "In-scope mechanical components with no mechanical intended function are assigned a screening result of 'no mechanical intended function,' and they are not subjected to Aging Management Review." However, the applicant states, "In a limited number of cases, there are in-scope mechanical components that do not support a mechanical system intended function but are in the scope because of their potential to damage safety related components through direct impact during a seismic event."Please Identify the in-scope mechanical components with "no mechanical intendedfunction" that are not subject to an AMR and describe why they are not subject to anAMR. Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as aformal RAI.D-RAI 2.3-1LRA Section 2.3 Scoping and Screening Results - Mechanical SystemsIn several LRA section descriptions and associated licensee renewal scoping drawings, theapplicant describes and highlights various components indicating that they are within the scope of the license renewal and subject to an AMR. The staff notes that many component/commodity types are not included in the associated LRA tables. The highlighted components include: valves, piping, accumulators closure bolting, drain traps, detectors,pumps, etc. In the associated LRA tables, the applicant did not identify the following component/commodity types:Section 2.3.3.6Circulating Water System - expansion joints, temperature elements, thermowells Section 2.3.3.21Emergency Diesel Generator System - expansion joints, flexible connections Section 2.3.3.27 Instrument Air System - valves Section 2.3.3.28 Service Air System - valves, drain trap(s), closure bolting Section 2.3.3.29 Bulk Nitrogen Storage System - valves, accumulator tank Section 2.3.3.30 Hydrogen Gas System - valves, excess flow check valve Section 2.3.3.18 Emergency Screen Wash System - buried piping Section 2.3.4.14 Turbine System - valves Section 2.3.3.37 Laundry and Hot Shower System - piping, piping components, and pipingelementsSection 2.3.3.54 Spent Fuel Cask Decontamination and Spray System - filters, pumps, tanks,valvesSection 2.3.3.81 Mechanical Components in Electrical Systems - detector, sample cooler Sections 2.3.3.6, 7, 8, 9, 10, 11, 12, 14, etc. - valves and/or pumps Section 2.3.4.4 Main Steam Dump System - silencersSpecifically explain how each of these components is represented in the LRA.Additionally, explain what components the term "piping, piping components, and piping elements" includes for each system.Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as aformal RAI.D-RAI 2.3.3.12-12.3.3.12 Normal Service Water SystemIn final safety analysis report (FSAR) Section 9.2.1.2, page 9.2.1-3, the applicant describes thenormal service water pumps as follows:Normal Service Water (NSW) Pumps - Two 100 percent capacity pumps are providedwith one pump normally supplying all service water requirements. One single supply header will normally furnish the two redundant loops serving the essential plant components. Pumps are sized such that the water requirements for Unit start-up and normal operation can be met by one pump. Both pumps may be required after fourhours have elapsed from the plant normal shutdown initiation (see Table 9.2.1-1). Inthis case both loops serving the essential plant components will be in service.In LRA Section 2.3.3.12, pages 2.3-70 & 71, the applicant describes the NSW pumps asfollows:Two 100-percent capacity NSW pumps are provided. During Unit start-up, shutdown,and normal operation, Service Water (SW) requirements will be met by one of the NSW pumps. The pump furnishes all normal operating SW requirements for the Unit througha single supply line.Explain the discrepancy in operating requirements of one or two pumps, between thedescriptions in FSAR Section 9.1.2 and LRA Section 2.3.3.12.Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as aformal RAI.D-RAI 2.3.3.13-12.3.3.13 Emergency Service Water SystemIn LRA Section 2.3.3.13, the applicant, identifies that under emergency operation, the servicewater booster pumps start. However, the booster pumps are not identified in either LRA Table 2.3.3-11 or LRA Table 2.3.3-10 (Section 2.3.3.12) as one of the component/commodity types subject to an AMR.Explain why the service water booster pumps are not identified as acomponent/commodity type in either LRA Tables 2.3.3-10 or 2.3.3-11.Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as aformal RAI.D-RAI 2.3.3.16-12.3.3.16 Essential Services Chilled Water SystemOn license renewal scoping drawing 5-G-0499, location L-16, for the essential services chilledwater system, a flag is shown with a "3" in it indicating that the piping and valves beyond it are designed to meet Safety Class 3 and Seismic Category I requirements. The piping beyond the piping class flag (line number 3CX4-71SB-1) is partially highlighted as in the scope of license renewal for 10 CFR 54.4(a)(1) criterion. There is no piping class flag indicating a change in pipe class at the location along the pipe where the highlighting stops. Since pipe line 3CX4-71SB-1 is designed to meet Safety Class 3 and Seismic Category Irequirements, explain why pipe line 3CX4-71SB-1 is not highlighted along its total length; thereby, indicating that it is not within the scope of license renewal for 10 CFR 54.4(a)(1) criterion.Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as aformal RAI.D-RAI 2.3.3.21-12.3.3.21 Emergency Diesel Generator System In LRA Table 2.3.3.17, the applicant identifies, for the emergency diesel generator system, thecomponent/commodity type of "piping, piping components, and piping elements." It is unclear why the words "piping components" were listed twice. Please clarifywhether this is a typographical error and what the intended verbiage should be.Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as aformal RAI.D-RAI 2.3.3.22-12.3.3.22 Diesel Generator Fuel Oil Storage and Transfer SystemIn LRA Section 2.3.3.22, the applicant describes that buried fuel oil piping is coated andcathodically protected. The buried piping is required in order for the system to perform its intended function of supplying fuel oil to the emergency diesel generators for all modes of operation. In LRA Table 2.2-3, License Renewal Scoping Results for Electrical/I&C Systems,the applicant identifies that the cathodic protection system is not within the scope of license renewal. Explain whether the cathodic protection for the diesel generator fuel oil storage andtransfer system buried piping is included within the system identified in LRA Table 2.2-3, or if it should be added or included into LRA Table 2.3.3-18. If it is included in Table 2.2-3, explain why the cathodic protection system is not within the scope of license renewal.Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as aformal RAI.D-RAI 2.3.3.22-2On license renewal scoping drawing 5-G-0133-LR, the applicant depicts the diesel generatorfuel oil day tanks 1A-SA and AB-SB for emergency diesel generators 1A-SA and 1B-SB respectively. Each day tank has a supply line from its respective fuel oil transfer pump which is required for the system to perform its intended function. Piping Sections 3FO1-237SA-1 and 3FO1-238SB-1 are not highlighted on the license renewal scoping drawing, even though their failure could prevent the transfer of fuel oil to the day tanks. Explain whether these piping sections are intended to be excluded from the scope oflicense renewal. If they are, then explain the effects of their failure on the diesel generator fuel oil storage and transfer system.Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as aformal RAI.D-RAI 2.3.3.28-1 2.3.3.28 Service Air System On license renewal scoping drawing 5-G-0300, location B-2, for the service air system, the applicant depicts valve 7SA-V79-1 as attached to the continuation piping required for containment isolation at penetration M-41. The piping required for the containment isolation atpenetration M-41 is highlighted as in the scope of license renewal for 10 CFR 54.4(a)(1) criteria; and the continuation piping has been highlighted as in the scope of license renewal for 10 CFR 54.4(a)(2) criteria for functional support (seismic continuity). Explain why valve 7SA-V79-1 is not highlighted as within the scope of license renewalfor 10 CFR 54.4(a)(2) criterion since it may be a part of the continuation piping needed for seismic continuity.Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as aformal RAI.D-RAI 2.3.3.28-2In LRA Section 2.3.3.28, page 2.3-109, the applicant states that the service air system includessafety-related system piping associated with the containment penetration as well as supply piping for the essential services chilled water system. On page 2.3-110, the applicant states that the license renewal scoping boundaries for the service air system are shown on the following boundary drawing 5-G-0300-LR. In addition, the staff noted that service air system piping and components are highlighted on license renewal scoping drawings 8-G-0498-S02-LR, HVAC essential services chilled water condenser flow diagram Unit 1-SA and 8-G-0499-S02-LR, HVAC essential services chilled water condenser flow diagram Unit 1-SB, indicating they are within the scope of license renewal.Explain why the license renewal scoping drawings 8-G-0498-S02-LR and 8-G-0499-S02-LR are not included on LRA page 2.3-110 as license renewal scoping drawings for the service air system.Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as aformal RAI.
D-RAI 2.3.3.34-12.3.3.34 Radioactive Floor Drains SystemIn Section 2.3.3.34, the applicant has included "system strainers" as a component/commoditytype in LRA Tables 2.3.3-30 and 3.3.2-30. This component has intended functions of filtration and pressure boundary. On license renewal scoping drawings 5-G-0816-LR at location F-3, and 5-G-0866-LR at locations F-2, 4 and 6, pump strainers were found, however these strainers are not indicated on the drawings as being within the scope of license renewal. Additionally, if these strainers as indicated in Tables 2.3.3-30 and 3.3.2-30 have a pressure boundary intended function, the surrounding piping would also need to also have a pressure boundary function. Clarify if these strainers and the surrounding piping are the specified componentsindicated in LRA Tables 2.3.3-30 and 3.3.2-30 that are subject to AMR or justify their exclusion.Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as aformal RAI.D-RAI 2.3.3.43-12.3.3.43 Oily Waste Collection and Separation SystemOn the license renewal scoping drawing titled "Scoping Notes for Miscellaneous Systems," alsoknown as "System Boundary Drawing Scoping Discussions," CALC HNP-P/LR-0002, , Revision 2, the applicant states that highlighted flow paths in the "Oily Drains System" are intended to indicate flow paths for draining fire fighting water when needed.
However, on license renewal scoping drawing 5-G-0485-LR, the applicant does not highlight portions of the system downstream of the oil water separator. Explain why the piping downstream of the oil water separator is not needed to supportthe intended function of draining fire fighting water. If piping is to be included in the scope of license renewal, identify the piping downstream of the oil water separator necessary to support the fire protection intended function.Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as aformal RAI.D-RAI-2.3.3.45-12.3.3.45 Secondary Waste Treatment SystemIn LRA Section 2.3.3.45, the applicant states that the Secondary Waste Treatment System onlyperforms the system intended function of containing components that have the potential for spatial interactions with safety-related SSC's or are relied on for seismic continuity in accordance with 10 CFR 54.4(a)(2). However, on license renewal scoping drawing titled "Scoping Notes for Miscellaneous Systems", the applicant states that highlighted flow paths in the "Liquid Waste Processing System" are intended to indicate flow paths for draining fire fighting water when needed. In FSAR Section 11.2.2.6, the applicant describes the Secondary Waste Treatment System as a subsystem of the Liquid Waste Processing System. Explain the exclusion of the system intended function associated with fire protection, 10 CFR 50.48, for the secondary waste treatment system in accordance with 10 CFR 54.4(a)(3).Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as aformal RAI.D-RAI 2.3.4.1-12.3.4.1 Steam Generator Blowdown System In LRA Section 2.3.4.1, the applicant identifies the steam generator blowdown system as inscope of license renewal because, in part, it contains components that are relied on during postulated fires and station blackout events, and components that are part of the environmental qualification program. In FSAR Section 10.4.8, the applicant describes the steam generator blowdown system, but does not identify how the system is credited in fire protection, station blackout, and environmental qualification.Provide a list of all the components and their intended function(s) within this system thatare within the scope of license renewal and are relied on during postulated fires, station blackout events, or part of the environmental qualification program.Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as aformal RAI.
Letter to Carolina Power & Light Company, from M. Heath dated January 7, 2008
SUBJECT:
SUMMARY
OF TELEPHONE CONFERENCE CALL HELD ON AUGUST 13, 2007, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND CAROLINA POWER & LIGHT COMPANY, CONCERNING DRAFT REQUESTS FOR ADDITIONAL INFORMATION PERTAINING TO THE SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1, LICENSE RENEWAL APPLICATIONDISTRIBUTION
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MHeath SHernandez LRegner Shearon Harris Nuclear Power Plant, Unit 1 cc:David T. ConleyAssociate General Counsel II -
Legal Department Progress Energy Service Company, LLC P.O. Box 1551 Raleigh, NC 27602-1551Resident Inspector / Harris NPSc/o U. S. Nuclear Regulatory Commission 5421 Shearon Harris Road New Hill, NC 27562-9998Ms. Margaret A. ForceAssistant Attorney General State of North Carolina P.O. Box 629 Raleigh, NC 27602Public Service CommissionState of South Carolina P.O. Drawer 11649 Columbia, SC 29211Ms. Beverly Hall, Section ChiefDivision of Radiation Protection N.C. Department of Environment and Natural Resources 3825 Barrett Drive Raleigh, NC 27609-7721Mr. J. Paul Fulford, ManagerPerformance Evaluation and Regulatory Affairs PEB 5 Carolina Power & Light Company P.O. Box 1551 Raleigh, NC 27602-1551Mr. Eric McCartneyPlant General Manager Shearon Harris Nuclear Power Plant Carolina Power & Light Company P.O. Box 165, Mail Zone 3 New Hill, NC 27562-0165Mr. Chris L. BurtonDirector of Site Operations Carolina Power & Light Company Shearon Harris Nuclear Power Plant P.O. Box 165, Mail Zone 1 New Hill, NC 27562-0165Mr. Robert P. GruberExecutive Director Public Staff NCUC 4326 Mail Service Center Raleigh, NC 27699-4326Chairman of the North Carolina Utilities Commission P.O. Box 29510 Raleigh, NC 27626-0510Mr. Herb Council, ChairBoard of County Commissioners of Wake County P.O. Box 550 Raleigh, NC 27602Mr. Tommy Emerson, ChairBoard of County Commissioners of Chatham County P.O. Box 87 Pittsboro, NC 27312Mr. Thomas J. Natale, ManagerSupport Services Carolina Power & Light Company Shearon Harris Nuclear Power Plant P.O. Box 165, Mail Zone 1 New Hill, NC 27562-0165Mr. David H. Corlett, SupervisorLicensing/Regulatory Programs Shearon Harris Nuclear Power Plant Carolina Power & Light Company P.O. Box 165, Mail Zone 1 New Hill, NC 27562-0165 Shearon Harris Nuclear Power Plant, Unit 1 cc:-2-Mr. John H. O'Neill, Jr.Shaw, Pittman, Potts & Trowbridge 2300 N Street, NW Washington, DC 20037-1128