ML16057A838: Difference between revisions
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| number = ML16057A838 | | number = ML16057A838 | ||
| issue date = 04/13/2016 | | issue date = 04/13/2016 | ||
| title = Shearon Harris Nuclear Power Plant ( | | title = Shearon Harris Nuclear Power Plant (Hnp), Unit 1 - Issuance of Amendment to Adopt Emergency Action Level Scheme Pursuant to NEI 00-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors (CAC No. MF6196) | ||
| author name = Barillas M | | author name = Barillas M | ||
| author affiliation = NRC/NRR/DORL/LPLII-2 | | author affiliation = NRC/NRR/DORL/LPLII-2 | ||
Line 13: | Line 13: | ||
| document type = Letter, License-Operating (New/Renewal/Amendments) DKT 50, Safety Evaluation | | document type = Letter, License-Operating (New/Renewal/Amendments) DKT 50, Safety Evaluation | ||
| page count = 25 | | page count = 25 | ||
}} | }} |
Revision as of 09:10, 27 February 2018
ML16057A838 | |
Person / Time | |
---|---|
Site: | Harris |
Issue date: | 04/13/2016 |
From: | Martha Barillas Plant Licensing Branch II |
To: | Waldrep B C Duke Energy Progress |
Martha Barillas, NRR/DORL/LPL2-2 | |
References | |
CAC MF6196 | |
Download: ML16057A838 (25) | |
Similar Documents at Harris | |
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Category:Letter
MONTHYEARML24290A1102024-10-24024 October 2024
[Table view]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. 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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 Category:License-Operating (New/Renewal/Amendments) DKT 50 MONTHYEARML24059A4252024-08-14014 August 2024
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MF8439 and MF8440; EPID L-2016-LLA-0012) ML17324B0482017-12-0606 December 2017 Correction to License Amendment No. 127 Regarding Changes to the Inservice Inspection and Testing Requirements and Establishment of a Technical Specifications Bases Control Program ML17188A3872017-08-21021 August 2017 Issuance of Amendments Regarding Application to Consolidate Emergency Operations Facilities and Associated Emergency Plan Changes (CAC Nos. MF7650 Through MF7660) ML17074A6722017-05-25025 May 2017 Issuance of Amendment Relocation of Explosion Gas Monitoring Program Technical Specifications ML17048A1842017-05-24024 May 2017 Issuance of Amendment on Changes to Technical Specifications Section 3.8, Electrical Power Systems and Section 6.8. Procedures and Programs ML17102A9232017-05-18018 May 2017 Nonproprietary Issuance of Amendments Revising Technical Specifications for Methodology Reports DPC Ne 1008 P Revision 0, DPC Nf 2010 Revision 3 and DPC Ne 2011 P Revision 2 (CAC Nos. 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Alternative to Use Encoded Phased Array Ultrasonic Examination in Lieu of Radiography ML19108A1732019-07-18018 July 2019 Issuance of Amendment No. 173 Regarding Emergency Plan Emergency Action Level Scheme Change ML19058A6322019-07-0101 July 2019 Issuance of Amendments to Revise Emergency Action Level Schemes to Incorporate Clarifications Provided by Emergency Preparedness FAQs ML19128A3262019-06-20020 June 2019 Alternative to Depth Sizing Qualification Examination of Welds ML18288A1392019-04-29029 April 2019 Issuance of Amendments 171, 263 Revising Technical Specifications to Support Self Performance of Core Reload Design and Safety Analyses ML19050A2972019-04-18018 April 2019 McGuire Nuclear Station, Units 1 and 2, Shearon Harris Nuclear Power Plant, Unit 1, H B. Robinson Steam Electric Plant, Unit 2 - Issuance of Amendments Regarding Removal ML18347A3852019-03-29029 March 2019 Issuance of Amendment No. 169, Revise Updated Final Safety Analysis Report to Incorporate Tornado Missile Risk Evaluator Methodology Into Licensing Basis ML19018A0252019-02-26026 February 2019 Relief Request I3R-18, Regarding Alternative Repair and Replacement Testing Requirements for the Containment Building Equipment Hatch Sleeve Weld, Inservice Inspection Program for Containment, Third Ten-Year Interval ML18303A0482018-12-0404 December 2018 Extension of Reactor Pressure Vessel Surveillance Report for Capsule Z ML18283B5442018-11-20020 November 2018 Relief from the Requirements of the ASME Code, Section XI, Reactor Vessel Closure Head Penetration Nozzle Repair Technique ML18262A3032018-11-19019 November 2018 Issuance of Amendment No. 168 Regarding License Amendment Request for Rod Control Movable Assemblies Technical Specifications Changes 2024-08-02 |
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