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List of results

• ML19017A253  + (DCA - Chapter 18 SE with Open Items (Public))
• ML19340A065  + (DCA - Chapter 18 SER with No Open Items)
• ML19165A282  + (DCA - Chapter 2 SER with No Open Items)
• ML18214A195  + (DCA - Chapter 2 SER with Open Items)
• ML18220B313  + (DCA - Chapter 21 - Multi-Module Design Considerations - SE with Open Items)
• ML19169A272  + (DCA - Chapter 21 SER with No Open Items)
• ML19143A106  + (DCA - Safety Evaluation Report with No Open Items - Chapter 19, Probabilistic Risk Assessment and Severe Accident Evaluation for New Reactors)
• ML20013D437  + (DCA - Safety Evaluation Report with No Open Items for Chapter 1, Introduction and General Discussion)
• ML19073A071  + (DCA - Safety Evaluation Report with Open Items - Chapter 19, Probabilistic Risk Assessment and Severe Accident Evaluation for New Reactors)
• ML19143A105  + (DCA - Safety Evaluation with No Open Items for Chapter 19, Probabilistic Risk Assessment and Severe Accident Evaluation for New Reactors - Letter)
• ML19143A104  + (DCA - Safety Evaluation with No Open Items for Chapter 19, Probabilistic Risk Assessment and Severe Accident Evaluation for New Reactors - Memo)
• ML19192A011  + (DCA Advanced Safety Evaluation Reports)
• ML18060A144  + (DCA Chapter 8 SER with Open Items (May 2018))
• ML19084A286  + (DCA Chapter 9 Phase 2 Safety Evaluation Report with Open Items - Public)
• ML19191A196  + (DCA Safety Evaluation Reports with Open Items (Review Phase 2))
• ML19323F698  + (DCA Technical Specification Confirmatory Items - Email Commitments)
• ML20153F501  + (DCC-1/DCC-2 Degraded Core Coolability Analysis)
• ML20215N386  + (DCC-3 Degraded Core Coolability:Experiment and Analysis)
• ML19175A002  + (DCD Chapter 20 Preliminary Draft SER with Open Items Agenda)
• ML20147C126  + (DCH-2:RESULTS from the Second Experiment Performed in the Surtsey Direct Heating Test Facility)
• ML20070G469  + (DCM3D: a DUAL-CONTINUUM, THREE-DIMENSIONAL, GROUND-WATER Flow Code for Unsaturated, Fractured, Porous Media)
• ML071290574  + (DCP 80048085, Supplement 19, Extended Power Uprate Implementation & Power Ascension Test Plan)
• IR 05000275/2017007  + (DCPP - Inspection of the Implementation of Mitigation Strategies and Spent Fuel Pool Instrumentation Orders and Emergency Preparedness Communication/Staffing/ Multi Unit Dose Assessment Plans - Inspection Report (05000275/2017007 and 050003)
• ML060760384  + (DCPP 1&2 - Consideration of Amendments Regarding Antitrust License Conditions)
• 05000275/LER-2010-003, DCPP 230 Kv Historical Evaluation of Condition Prohibited by Technical Specification  + (DCPP 230 Kv Historical Evaluation of Condition Prohibited by Technical Specification)

• DCL-10-081, DCPP Data Format for Hourly Master Data  + (DCPP Data Format for Hourly Master Data)

• ML15355A079  + (DCPP Fsaru R22 File B Drawings - Combined (Redacted))
• ML15355A297  + (DCPP Fsaru R22 File a Drawings - Combined - (Redacted))
• ML101120117  + (DCPP License Renewal Aging Management Program Audit Plan)
• ML13171A064  + (DCPP Lr PM Change Letter)
• ML13135A010  + (DCPP Lr PM Change Letter)
• ML15344A432  + (DCPP Section 106 Checklist)
• ML061000417  + (DCPP Unit 2 Rv Head Inspection Relaxation Request TAC No. MD0024)
• ML21245A506  + (DCS Issp Review - Iob)
• ML20128C744  + (DCS Partial Record Format Rept)
• IA-92-478, DCS Partial Record Format Rept  + (DCS Partial Record Format Rept)
• ML20055G937  + (DCS Partial Record Format Rept for Regulatory History File AD38-1 Re Willful Misconduct by Unlicensed Persons)
• ML040630774  + (DD Cook Open Meeting Results of the NRC 2003 EOC Assessment)
• ML19259B276  + (DD Ebert Has Satisfactorily Completed 781218-21 Program in AGN-201 Reactor Operations Training.Recommends Individual for Operator License)
• ML25132A300  + (DD-001, Rev. 0, Decommissioning Plan for an ARC-100 Plant)
• 05000456/FIN-2010007-01  + (DDAFW Pump Battery Racks were not restored to their Design Basis Seismic Category I)
• ML21246A269  + (DDI-001-JSG-19 Final Update to 06/30/2019 and Application of Radionuclide Scaling Factors for Bldg. 21 04-18-2019 - Signed)
• ML20206L946  + (DE Minimis Waste Impacts Analysis Methodology.Volume 2. Impacts-BRC Users Guide and Methodology for Radioactive Wastes Below Regulatory Concern.This Is an NRC Staff Report Published as Volume 2 of Contractor Report)
• ML20086Q624  + (DE Minimis Waste Impacts Analysis Methodology)
• 05000400/LER-2007-004  + (DEC 1 7 2007 <br/> Serial: HNP-07-17 … DEC 1 7 2007 <br/> Serial: HNP-07-174 <br/>10 CFR 50.73 <br/>U.S. Nuclear Regulatory Commission <br/>ATTN: NRC Document Control Desk <br/>Washington, DC 20555 <br/>SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 </br><br/>DOCKET NO. 50-400/LICENSE NO. NPF-63 </br><br/>LICENSEE EVENT REPORT 2007-004-00 </br><br/>Ladies and Gentlemen: <br/>The enclosed Licensee Event Report 2007-004-00 is submitted in accordance with <br/>10 CFR 50.73. This report describes bare conductors on 'B' Steam Generator wide <br/>range level Barton transmitter as identified via the 10 CFR Part 21 process. Please <br/>refer any questions regarding this submittal to Mr. Dave Corlett, Supervisor <br/>Licensing/Regulatory Programs, at (919) 362-3137. <br/>Sincerely, <br/>/ /(e Iv:.. HCM.r Kelvin Henderson </br>Plant General Manager </br>Harris Nuclear Plant <br/>KH/khv <br/>Enclosure <br/>cc:MMr. P. B. O'Bryan, NRC Sr. Resident Inspector <br/>Ms. M. G. Vaaler, NRC Project Manager <br/>Mr. V. M. McCree, NRC Regional Administrator <br/>Progress Energy Carolinas, Inc. <br/>Harris Nuclear Plant <br/>P. 0. Box 165 </br><br/>New Hill, NC 27562 </br><br/>APPROVED BY OMB: NO. 3150-0104D EXPIRES: 08/31/2010, <br/>(9-2007) <br/>NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION' <br/>Estimated burden per response to comply with this mandatory collection <br/>request: 80 hours. Reported lessons learned are incorporated into the licensing <br/>process and fed back to industry. Send comments regarding burden estimate to <br/>the Records and FOIA/Privacy Service Branch (T-5 F52), U.S. Nuclear <br/>LICENSEE EVENT REPORT (LER) Regulatory Commission, Washington, DC 20555-0001, or by internet e-mail to infocollects@nrc.gov, and to the Desk Officer, Office of Information and <br/>RegulatoryAffairs, NEOB-10202, (3150-0104), Office of Management and Budget, <br/>Washington, DC 20503. If a means used to impose an information collection'(See reverse for required number of does not display a currently valid OMB control number, the NRC may not conduct <br/>or sponsor, and a person is not required to respond to, the informationdigits/characters for each block) collection. <br/>1. FACILITY NAME 2. DOCKET NUMBER 3. PAGE <br/>Harris Nuclear Plant - Unit 1 05000400 1DOF 3 <br/>4. TITLE <br/>Bare Conductors on `B' Steam Generator Wide Range Level Barton Transmitter as Identified via 10 CFR Part 21 Processch block) collection. <br/>1. FACILITY NAME 2. DOCKET NUMBER 3. PAGE <br/>Harris Nuclear Plant - Unit 1 05000400 1DOF 3 <br/>4. TITLE <br/>Bare Conductors on `B' Steam Generator Wide Range Level Barton Transmitter as Identified via 10 CFR Part 21 Process)
• ML19211A797  + (DECOST-Computer Routine for Decommissioning Cost & Funding Analysis)
• ML19257C733  + (DEFR-791213:loss of Adhesion Between Successive Layers of in-containment Coatings Detected.Caused Undetermined)
• ML20118B531  + (DENSITY-WAVE Instabilities in Boiling Water Reactors)
• ML20148M133  + (DEP Non Disclosure Declarations)
• ML20111A317  + (DEP Non-Disclosure Declarations)
• EPID:L-2020-LLE-0096  + (DEP Non-Disclosure Declarations)