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 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-19-0223, Annual Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models Pursuant to 10CFR 50.4630 May 2019Annual Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models Pursuant to 10CFR 50.46
RA-18-0179, 90-Day Special Report4 October 201890-Day Special ReportOverspeed trip
ML18230A75918 August 2018Fault Investigation, Progress Report, Volume 1 of 2Coatings
Earthquake
ML18230A75618 August 2018Fault Investigation, Responses to Mr. W. R. Butler'S Letter of May 16, 1975Hydrostatic
Earthquake
HNP-18-023, Report of Changes Pursuant to 10 CFR 50.59 and Summary of Commitment Changes2 May 2018Report of Changes Pursuant to 10 CFR 50.59 and Summary of Commitment ChangesFuel cladding
Overspeed 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
HNP-17-006, Submittal of Cycle 20 Activity Report30 January 2017Submittal of Cycle 20 Activity ReportThrough Wall Leak
HNP-16-083, Mitigating Strategies Assessment Report for Flooding Hazard Information21 December 2016Mitigating Strategies Assessment Report for Flooding Hazard InformationUltimate heat sink
Safe Shutdown Earthquake
FLEX
Fukushima Dai-Ichi
Spent Fuel Pool Instrumentation
RA-16-0024, Supplemental Information for License Amendment Request Regarding Methodology Report DPC-NE-3008-P3 October 2016Supplemental Information for License Amendment Request Regarding Methodology Report DPC-NE-3008-PSafe Shutdown
Boric Acid
Shutdown Margin
Loop seal
Anticipated operational occurrence
Post Accident Monitoring
Nondestructive Examination
Annual Radiological Environmental Operating Report
Process Control Program
Fuel cladding
Coast down
Affidavit
Manual Operator Action
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
HNP-16-017, Transmittal of Summary of a 10 CFR 50.54(q) Evaluation29 February 2016Transmittal of Summary of a 10 CFR 50.54(q) Evaluation
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
ML15301A5572 November 2015Supplement to Staff Assessment of Response to 10 CFR 50.54(f) Information Request Flood Causing Mechanisms ReevaluationsTornado Missile
Fukushima Dai-Ichi
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
RA-15-0022, Annual Report of Changes Pursuant to 10 CFR 50.4614 May 2015Annual Report of Changes Pursuant to 10 CFR 50.46
ML15126A08930 April 2015EAL BasesSafe Shutdown
Boric Acid
Time of Discovery
High winds
Reactor Vessel Water Level
Packing leak
Ultimate heat sink
Offsite Dose Calculation Manual
Fire Barrier
Time to boil
Safe Shutdown Earthquake
Internal Flooding
Probabilistic Risk Assessment
Operating Basis Earthquake
Operator Manual Action
Spent Fuel Pool Instrumentation
Safeguards Contingency Plan
Earthquake
Fuel cladding
Pressure Boundary Leakage
Grace period
Power change
Unidentified leakage
HNP-15-027, Flood Hazard Reevaluation Report, Revision 11 April 2015Flood Hazard Reevaluation Report, Revision 1Safe Shutdown
Ultimate heat sink
Hydrostatic
HNP-14-035, Seismic Hazard and Screening Report (CEUS Sites), Response to NRC 10 CFR 50.54(f) Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.327 March 2014Seismic Hazard and Screening Report (CEUS Sites), Response to NRC 10 CFR 50.54(f) Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3Safe Shutdown Earthquake
Probabilistic Risk Assessment
Fukushima Dai-Ichi
Earthquake
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
HNP-13-083, Submittal of Summaries of 10 CFR 50.54(q) Evaluations1 August 2013Submittal of Summaries of 10 CFR 50.54(q) Evaluations
HNP-13-046, Report of Changes Pursuant to 10 CFR 50.5929 April 2013Report of Changes Pursuant to 10 CFR 50.59Safe Shutdown
Ultimate heat sink
Tornado Missile
Coatings
Tornado-Generated Missile
Tornado Generated Missile
ML12355A20218 December 2012Evacuation Time Estimates AnalysisSiren
HNP-12-119, Response to Recommendation 2.3 Seismic Walkdown of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident27 November 2012Response to Recommendation 2.3 Seismic Walkdown of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi AccidentSafe Shutdown
Unanalyzed Condition
Boric Acid
Ultimate heat sink
Safe Shutdown Earthquake
Operating Basis Earthquake
Fukushima Dai-Ichi
Spent Fuel Pool Instrumentation
Earthquake
Seismic Walkdown Report
ML12158A4528 June 2012Review of 60-Day Response to Request for Information Regarding Recommendation 9.3, of the Near-Term Task Force Related to Fukushima Daiichi Nuclear Power Plant AccidentEarthquake
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
ML1019304176 May 2010Tritium Database ReportOffsite Dose Calculation Manual
Hydrostatic
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
ML10203016231 December 2009Cooling Tower Blowdown Line Supplemental Groundwater Assessment Report, Shearon Harris Nuclear Power Plant
ML1019400968 July 2009Nrc/Harris Split Sample Results
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
HNP-09-056, Non-Security Sensitive Version of Original Request for License Amendment to Adopt NFPA 805 Performance-Based Standards for Fire Protection for Light Water Reactor Generating Plants (2001 Edition)22 May 2009Non-Security Sensitive Version of Original Request for License Amendment to Adopt NFPA 805 Performance-Based Standards for Fire Protection for Light Water Reactor Generating Plants (2001 Edition)Safe Shutdown
Fire Barrier
Time to boil
Emergency Lighting
Hemyc
Exemption Request
Earthquake
Power Operated Valves
Fire Protection Program
Fire Watch
ML10203016030 April 2009Cooling Tower Blowdown Line Assessment Report, Shearon Harris Nuclear Power Plant
ML0821900137 August 2008Monthly Operating Reports Second Quarter 2008Reserve Station Service Transformer
Power change
HNP-08-015, Supplemental Response to NRC GL-04-002, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-water Reactors28 February 2008Supplemental Response to NRC GL-04-002, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-water ReactorsLoop seal
Mission time
Safe Shutdown Earthquake
Hydrostatic
Coatings
Operating Basis Earthquake
Temporary Modification
Foreign Material Exclusion
Exemption Request
Earthquake
Maintenance Rule Program
Scaffolding
HNP-07-178, Revision 0a, Transition to 10 CFR 50.48(c) - NFPA 805 Performance- Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants, 2001 Edition10 January 2008Revision 0a, Transition to 10 CFR 50.48(c) - NFPA 805 Performance- Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants, 2001 EditionSafe Shutdown
Boric Acid
Shutdown Margin
Enforcement Discretion
Probabilistic Risk Assessment
Operator Manual Action
Multiple Spurious Operation
Fire Protection Program
ML0800705319 January 2008Review of the Fire Probabilistic Risk Assessment Model to Support Implementation of National Fire Protection Association (NFPA) Standard NFPA-805Safe Shutdown
Fire Barrier
Probabilistic Risk Assessment
Multiple Spurious Operation
Incorporated by reference
Large early release frequency
Fire Protection Program
ML07242025530 August 2007NRC Allegation Report RII-2005-A-0165
ML07198019530 July 2007Environmental Impact Statement Scoping Process Summary Report Shearon Harris Nuclear Power Plant - July 2007Aging Management
License Renewal
Environmental Justice
Fire Watch
ML07205021419 July 2007Afpb Staff Response to NFPA 805 Transition Pilot Plant FAQ 06-0008, Revision 5Safe Shutdown
Fire Barrier
Fire Protection Program
HNP-07-068, Day Special Report of the Metal Impact Monitoring System14 May 2007Day Special Report of the Metal Impact Monitoring System