Semantic search

Jump to navigation Jump to search
 Issue dateTitleTopic
RA-21-0097, Notification of Permit Revision Request Regarding Copper and Zinc Limits15 March 2021Notification of Permit Revision Request Regarding Copper and Zinc Limits
RA-20-0381, CFR 50.54( Q) Screening Evaluation Form for Revisions8 December 2020CFR 50.54( Q) Screening Evaluation Form for RevisionsSpent Fuel Pool Instrumentation
Exemption Request
Earthquake
Grace period
RA-20-0335, Response to Request for Additional Information Regarding License Amendment Request to Reduce the Minimum Required Reactor Coolant System Flow Rate and Update the List of Analytical Methods Used in .24 November 2020Response to Request for Additional Information Regarding License Amendment Request to Reduce the Minimum Required Reactor Coolant System Flow Rate and Update the List of Analytical Methods Used in .Time Critical Operator Action
Exemption Request
Fuel cladding
Exclusive Use
Affidavit
RA-20-0032, License Amendment Request to Reduce the Minimum Required Reactor Coolant System Flow Rate and Update the List of Analytical Methods Used in the Determination of Core Operating Limits6 March 2020License Amendment Request to Reduce the Minimum Required Reactor Coolant System Flow Rate and Update the List of Analytical Methods Used in the Determination of Core Operating LimitsBoric Acid
Shutdown Margin
Loop seal
Anticipated operational occurrence
Hydrostatic
Nondestructive Examination
Surveillance Frequency Control Program
Fuel cladding
Exclusive Use
Affidavit
Loss of condenser vacuum
RA-19-0403, Submittal of the Summary Technical Report for the Reactor Pressure Vessel Surveillance Program Capsule Z23 October 2019Submittal of the Summary Technical Report for the Reactor Pressure Vessel Surveillance Program Capsule ZAnticipated operational occurrence
Hydrostatic
RA-18-0179, 90-Day Special Report4 October 201890-Day Special ReportOverspeed trip
RA-17-0040, Providing Methodology Reports DPC-NE-1008-P, Revision 0, DPC-NF-2010, Revision 3, and DPC-NE-2011-P, Revision 2. (Non-Proprietary Versions)15 August 2017Providing Methodology Reports DPC-NE-1008-P, Revision 0, DPC-NF-2010, Revision 3, and DPC-NE-2011-P, Revision 2. (Non-Proprietary Versions)Boric Acid
Shutdown Margin
Anticipated operational occurrence
Post Accident Monitoring
Nondestructive Examination
Fuel cladding
Affidavit
Water rod
HNP-17-040, Snubber Program Plan1 June 2017Snubber Program PlanSafe Shutdown
Incorporated by reference
Earthquake
RA-16-0023, Supplemental Information for License Amendment Request Regarding Methodology Report DPC-NE-1008-P4 May 2016Supplemental Information for License Amendment Request Regarding Methodology Report DPC-NE-1008-PShutdown Margin
Reactor Vessel Water Level
Anticipated operational occurrence
Post Accident Monitoring
Nondestructive Examination
Annual Radiological Environmental Operating Report
Process Control Program
Fuel cladding
Affidavit
RA-15-0042, Application to Revise Technical Specifications to Adopt Methodology Report DPC-NE-3008-P, Revision 0, Thermal-Hydraulic Models for Transient Analysis.19 November 2015Application to Revise Technical Specifications to Adopt Methodology Report DPC-NE-3008-P, Revision 0, Thermal-Hydraulic Models for Transient Analysis.Safe Shutdown
Shutdown Margin
Loop seal
Anticipated operational occurrence
Post Accident Monitoring
Nondestructive Examination
Annual Radiological Environmental Operating Report
Process Control Program
Fuel cladding
Affidavit
RA-15-0031, Application to Revise Technical Specifications for Methodology Report DPC-NE-1008-P, Revision 0, Nuclear Design Methodology Using CASMO-5/Simulate-3 for Westinghouse Reactors.19 August 2015Application to Revise Technical Specifications for Methodology Report DPC-NE-1008-P, Revision 0, Nuclear Design Methodology Using CASMO-5/Simulate-3 for Westinghouse Reactors.Shutdown Margin
Anticipated operational occurrence
Post Accident Monitoring
Nondestructive Examination
Annual Radiological Environmental Operating Report
Process Control Program
Fuel cladding
Affidavit
ML13364A21412 February 2014Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies)Safe Shutdown
Boric Acid
High winds
Shutdown Margin
Ultimate heat sink
Tornado Missile
Safe Shutdown Earthquake
Internal Flooding
Operating Basis Earthquake
Emergency Lighting
FLEX
Fukushima Dai-Ichi
Frazil ice
Battery sizing
Earthquake
ML14030A10229 January 2014Mega-Tech Services, LLC, Technical Evaluation Report Regarding the Overall Integrated Plan for Shearon Harris Nuclear Power Plant, Unit 1, TAC No.: MF0874Safe Shutdown
Boric Acid
High winds
Shutdown Margin
Ultimate heat sink
Tornado Missile
Safe Shutdown Earthquake
Internal Flooding
Operating Basis Earthquake
Emergency Lighting
FLEX
Fukushima Dai-Ichi
Frazil ice
Battery sizing
Earthquake
ML12067A18029 February 2012ANP-3011Q1(NP), Revision 000, Harris Nuclear Plant Unit 1 Realistic Large Break LOCA Analysis. Enclosure 4 Response to Request for Additional Information (Non-Proprietary)Fuel cladding
Measurement Uncertainty Recapture
ML1008904242 March 2010NAI-1478-001, Revision 1, HNP CSAT Volume, Flow and Naoh Concentration Range Revisions.Boric Acid
ML10089059331 January 2010Application for Revision to Technical Specification Core Operating Limits Report References, ANP-2853(NP), Rev. 0, Realistic Large Break LOCA Summary Report.Loop seal
Fuel cladding
ML10025085818 January 2010Holtec Report, No. HI-2043321, Rev. 6, Critically Safety Analyses of BWR Fuel Without Credit for Boraflex in the Racks at the Harris Nuclear Power Station.Fuel cladding
Water rod
ML10034028412 January 2010NAI-1478-001, Revision 0, HNP CSAT Volume, Flow and Naoh Concentration Range RevisionsBoric Acid
ML09215005431 May 2009ANP-2693(NP), Revision 0, Loss of Forced Reactor Coolant Flow Analysis for Harris Nuclear Plant, Unit 1, Enclosure 4 to Serial: HNP-09-068Fuel cladding
Coast down
ML0821900137 August 2008Monthly Operating Reports Second Quarter 2008Reserve Station Service Transformer
Power change
HNP-06-128, Engineering Report on: Evaluation of Charging-Safety Injection Pump Motor Bearing Temperatures at Progress Energy Harris Nuclear Plant12 October 2006Engineering Report on: Evaluation of Charging-Safety Injection Pump Motor Bearing Temperatures at Progress Energy Harris Nuclear Plant
ML0632802415 October 2006Shearon Harris, Letter Report NAI-1282-001, Gothic Charging Pump Room Heatup Analysis for Shearon Harris.GOTHIC
ML05251050431 August 2005Framatome Anp, Inc 77-5069740-NP-00, Shearon Harris Criticality Evaluation.Exclusive Use
Affidavit
Water rod
ML03052026915 February 2003Follow-up Report, Reference Event #39516
ML18230B04016 September 1975Transmitting Aquatic & Fisheries Studies, Baseline Preoperational Biological Survey Conducted to Determine Existing Aquatic Terrestrial Populations with Figures of Sampling Points & Areas