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ML21316A24819 January 2022Issuance of Amendment No. 188, Regarding Revision of 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors
RA-20-0321, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-505, Revision 2, Provide Risk-Informed Extended Comple11 November 2020Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-505, Revision 2, Provide Risk-Informed Extended Completi
ML20147A02215 May 2020Amendment 63 to Final Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems
ML20147A02415 May 2020Amendment 63 to Final Safety Analysis Report, Chapter 7, Instrumentation and Controls
ML20147A02515 May 2020Amendment 63 to Final Safety Analysis Report, Chapter 8, Electric Power
ML20147A02715 May 2020Amendment 63 to Final Safety Analysis Report, Chapter 10, Summary Description
ML20147A02615 May 2020Amendment 63 to Final Safety Analysis Report, Chapter 9, New and Spent Storage and Handing (Redacted)
ML20147A02115 May 2020Amendment 63 to Final Safety Analysis Report, Chapter 4, Reactor
ML20147A03515 May 2020Amendment 63 to Update Final Safety Analysis Report, Chapter 18, Final Safety Analysis Supplement for License Renewal
RA-19-0067, License Amendment Request to Revise Technical Specifications for the Adoption of 10 CFR 50, Appendix J, Option B for Type B and C Testing and for Permanent Extension of Type a, B and C Leak Rate Test Frequencies8 November 2019License Amendment Request to Revise Technical Specifications for the Adoption of 10 CFR 50, Appendix J, Option B for Type B and C Testing and for Permanent Extension of Type a, B and C Leak Rate Test Frequencies
RA-19-0007, License Amendment Request for Extension of the Essential Services Chilled Water System Allowed Outage Time and Removal of an Expired Note from Technical Specifications18 February 2019License Amendment Request for Extension of the Essential Services Chilled Water System Allowed Outage Time and Removal of an Expired Note from Technical Specifications
ML18204A28622 October 2018Issuance of Amendment No. 167 Regarding (CAC MF9996; EPID 2017-LLA-0303)
HNP-18-003, Response to Request for Additional Information Regarding License Amendment Request for Spent Fuel Storage Pool Criticality Analyses18 January 2018Response to Request for Additional Information Regarding License Amendment Request for Spent Fuel Storage Pool Criticality Analyses
HNP-17-072, License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into Licensing Basis19 October 2017License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into Licensing Basis
ML17250B23830 August 2017TMRE Presubmittal NRC
ML18337A37910 May 2017Shearon Harris UFSAR Rev 61, Drawings Part 1
HNP-16-083, Mitigating Strategies Assessment Report for Flooding Hazard Information21 December 2016Mitigating Strategies Assessment Report for Flooding Hazard Information
ML16291A15819 October 2016Staff Review of Mitigation Strategies Assessment Report of the Impact of the Reevaluated Seismic Hazard Developed in Response to the March 12, 2012, 50.54(f) Letter
ML16215A2273 August 2016Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: August 16, 2016
NRC-2016-0161, Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: August 16, 20163 August 2016Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: August 16, 2016
HNP-16-047, Supplement to Notification of Full Compliance with Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events and with Order EA-12-051, Order....29 June 2016Supplement to Notification of Full Compliance with Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events and with Order EA-12-051, Order....
ML15364A54418 February 2016Staff Review of High Frequency Confirmation Associated with Reevaluated Seismic Hazard Implementating Near-Term Task Force Recommendation 2.1 Seismic for Specific Licensees
HNP-16-004, Supplement to Response to Request for Additional Information Regarding License Amendment Request to Revise Emergency Action Level Scheme to One Based on Revision 6 of Nuclear Energy Institute 99-01, Development of Emergency....28 January 2016Supplement to Response to Request for Additional Information Regarding License Amendment Request to Revise Emergency Action Level Scheme to One Based on Revision 6 of Nuclear Energy Institute 99-01, Development of Emergency....
ML15349A14918 December 2015Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f) Seismic Hazard Reevaluation for Recommendation 2.1 of the Near-Term Task Force Review
HNP-15-102, High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima..17 December 2015High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima..
HNP-15-091, Response to Request for Additional Information Regarding License Amendment Request to Revise Emergency Action Level Scheme to One Based on Revision 6 of NEI 99-01, Development of Emergency Action Levels for Non-Passive Reactors19 November 2015Response to Request for Additional Information Regarding License Amendment Request to Revise Emergency Action Level Scheme to One Based on Revision 6 of NEI 99-01, Development of Emergency Action Levels for Non-Passive Reactors
HNP-15-086, License Amendment Request for Temporary Changes to Technical Specifications for the 'A' Emergency Service Water Pump Replacement29 October 2015License Amendment Request for Temporary Changes to Technical Specifications for the 'A' Emergency Service Water Pump Replacement
ML15126A08930 April 2015EAL Bases
ML15083A02414 April 2015Report for the Audit Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051
ML15022A65326 January 2015Biweekly Sholly FRN - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: February 3, 2015
ML14111A1479 May 2014Seismic Screening and Prioritization Results Regarding Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Review of Insights
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, 2.3
ML13364A21412 February 2014Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies)
ML14030A10229 January 2014Mega-Tech Services, LLC, Technical Evaluation Report Regarding the Overall Integrated Plan for Shearon Harris Nuclear Power Plant, Unit 1, TAC No.: MF0874
RA-13-018, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident - 1.5 Year Response for CEUS Site11 September 2013Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident - 1.5 Year Response for CEUS Site
ML13112A02028 February 2013Overall Integrated Plan in Response to March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Event (Order Number EA-12-049)
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 Accident
ML12053A34012 March 2012Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident
ML12056A04712 March 2012Enclosure 1 - Recommendation 2.1: Seismic
ML12056A04912 March 2012Enclosure 3 - Recommendation 2.3: Seismic
HNP-11-038, License Amendment Request for Extension of Refueling Water Storage Tank Allowed Outage Time2 September 2011License Amendment Request for Extension of Refueling Water Storage Tank Allowed Outage Time
ML10175060428 June 2010Redacted - Regarding Adoption of National Fire Protection Association Standard 805
HNP-10-008, Response to Second Request for Additional Information Regarding License Amendment Request to Anfp Association Standard 805, Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants.4 February 2010Response to Second Request for Additional Information Regarding License Amendment Request to Anfp Association Standard 805, Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants.
ML10013025414 January 2010Second Request for Additional Information Regarding the License Amendment Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plant
HNP-09-067, Response to Request for Additional Information Regarding the License Amendment Request to Revise Technical Specification 3.7.5a, Ultimate Heat Sink Main Reservoir Minimum Level30 June 2009Response to Request for Additional Information Regarding the License Amendment Request to Revise Technical Specification 3.7.5a, Ultimate Heat Sink Main Reservoir Minimum Level
HNP-08-119, Non-Security Sensitive Version of Supplement to Request for License Amendment to Adopt NFPA 805 Performance-Based Standards for Fire Protection for Light Water Reactor Generating Plants (2001) Edition5 February 2009Non-Security Sensitive Version of Supplement to Request for License Amendment to Adopt NFPA 805 Performance-Based Standards for Fire Protection for Light Water Reactor Generating Plants (2001) Edition
ML09002042030 November 2008NUREG-1916 Vol. 2, Safety Evaluation Report - Related to the License Renewal of Shearon Harris Nuclear Power Plant, Unit 1.
ML09005017230 November 2008NUREG-1916, Volume 1, (1:2) Cover - Chpt 2, Safety Evaluation Report Related to the License Renewal of Shearon Harris Nuclear Power Plant, Unit 1
HNP-08-075, Request for License Amendment Technical Specifications 5.6.1.3.a and 5.6.1.3.b - Incorporation of Updated Criticality Analyses to Reflect Removal of Credit for Boraflex in BWR Spent Fuel Pool Storage Racks29 September 2008Request for License Amendment Technical Specifications 5.6.1.3.a and 5.6.1.3.b - Incorporation of Updated Criticality Analyses to Reflect Removal of Credit for Boraflex in BWR Spent Fuel Pool Storage Racks
HNP-08-049, Request for License Amendment Technical Specification 3.7.5a30 April 2008Request for License Amendment Technical Specification 3.7.5a
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 Reactors
ML0802805677 January 2008January 2008 - Transition to National Fire Protection Association (NFPA) 805 - Example Table B-1, Shearon Harris Nuclear Power Plant, Unit 1, January 7, 2008
HNP-07-122, Responses to Requests for Additional Information License Renewal Application - Additional Questions Related to Scooping and Screening Methodology & Results18 September 2007Responses to Requests for Additional Information License Renewal Application - Additional Questions Related to Scooping and Screening Methodology & Results
HNP-07-119, License Renewal Application, Amendment 2: Changes Resulting from Responses to Site Audit Questions Regarding Time-Limited Aging Analyses31 August 2007License Renewal Application, Amendment 2: Changes Resulting from Responses to Site Audit Questions Regarding Time-Limited Aging Analyses
ML06335027630 November 2006Applicant'S Environmental Report - Operating License Renewal Stage
ML0633103867 November 2006NFPA 805 Trip Report Handout References
HNP-09-014, Calculation HI-971760, Licensing Report for Expanding Storage Capacity in Harris Spent Fuel Pools C and D.22 December 2004Calculation HI-971760, Licensing Report for Expanding Storage Capacity in Harris Spent Fuel Pools C and D.
HNP-04-005, Supplemental Information to the RAI Regarding Generic Letter 96-06, Assurance of Equipment Operability and Containment Integrity During Design-Basis Accident Conditions.19 January 2004Supplemental Information to the RAI Regarding Generic Letter 96-06, Assurance of Equipment Operability and Containment Integrity During Design-Basis Accident Conditions.
ML0217000494 June 2002Joint Appendix Volume II: Pages 542 - 767, Petition to Review a Final Decision of the Nrc. Case Scheduled for Oral Argument September 5, 2002
ML18016A96325 May 1999Forwards Periodic Update to FSAR for Hnp.Amend 49 Is Current Through 981128 (End of RFO 8).Some Changes & Analysis Completed After 981128 Have Also Been Included in Amend
ML20196K8865 April 1999Declaration of Gordon Thompson.* Informs of Participation in Preparation of Orange County Contentions Re Proposed License Amend
ML18017A89328 February 1999Risks & Alternative Options Associated with Spent Fuel Storage at Shearon Harris Nuclear Power Plant.
ML18016A85318 February 1999Non-proprietary Rev 3 to HI-971760, Licensing Rept for Expanding Storage Capacity in Harris SFP 'C' & 'D'.
ML18016A97328 November 1998Changes,Tests & Experiments, for Harris Nuclear Plant.Rept Provides Brief Description of Changes to Facility & Summary & of SE for Each Item That Was Implemented Under 10CFR50.59 Between 970608-981128.With 990527 Ltr
ML18016A52924 August 1998Forwards Revised Response to NRC 971217 Request for Addl Info Re TS Change Request to Allow Use of SG Tube Sleeves Designed by ABB-CE.Next Plant Refueling Outage Currently Scheduled to Commence 981024
ML18016A77126 May 1998Non-proprietary Rev 2 to HI-971760, Licensing Rept for Expanding Storage Capacity in Harris Spent Fuel Pools 'C' & 'D'.
ML18016A34612 March 1998Application for Amend to License NPF-63,deleting TS SR 4.9.12.d.4 Which Requires Verifying That Filter Cooling Bypass Valve for Fhb EES Is Locked in Balanced Position at Least Once Per 18 Months
ML18022B03616 February 1998Responds to RAI on Shearon Harris IPEEE Submittal,Dtd 971215.Rev 0 to C-007, CP&L Harris IPEEE: HCLPF Capacity Calculations for 1X-SAB CST Tank & 1X-SN RWST Tank, Encl
ML18016A41231 December 1997Annual Radioactive Effluent Release Rept for Jan-Dec 1997.
ML18016A2514 December 1997Rept of Changes,Tests & Experiments for Plant for 951213- 970607,per 10CFR50.59(b)(2).Some Changes Implemented After 970607 Are Also Included in Rept
ML18022B01718 April 1997Requests That Approval of Proposed Changes Be Issued Prior to 970430 to Support Installation & Testing of Proposed Mod Prior to Restart from Upcoming Refueling Outage Re EDG Protection During Testing Re 961114 Discovery of Deficiency
ML18022B00127 February 1997Application for Amend to License NPF-63,amending TS 3/4.4.5, Sgs, & Associated Bases,To Add Sleeve Installation as Alternative to Tube Plugging for Repairing Degraded ST Tubes.Trs encl.CEN-630-P,rev 1 Withheld
ML18022A96230 June 1995NPP IPEEE Final Rept.
Information Notice 1995-28, Emplacement of Support Pads for Spent Fuel Dry Storage Installations at Reactor Sites5 June 1995Emplacement of Support Pads for Spent Fuel Dry Storage Installations at Reactor Sites
ML18011A68114 November 1994Rept in Accordance w/10CFR50.59 for Period 930201-940711, Including Harris Plant Refueling Outage
ML18010A97613 October 1992Reactor Containment Bldg Integrated Leakage Rate Test Rept.
ML18010A34026 July 1991Submits Rept Describing Changes to Westinghouse ECCS Evaluation Models as They Apply to Facility for Period from Aug 1990 - May 1991
ML18022A7781 March 1990Rept of 10CFR50.59 Chnages to Procedures &/Or Plant Mods for 1989
ML20011D12430 November 1989Nonproprietary LOFTTR2 Analysis for Steam Generator Tube Rupture W/Revised Operator Action Times for Shearon Harris Nuclear Power Plant.
ML18005B0862 October 1989Forwards Response to NRC 890831 Questions Re Suppl to Cycle 3 Reload Amend Request.Util Currently Performing Addl Steam Generator Tube Rupture Analyses,Based on Revised Operator Action Times Described in Util 890519 Ltr
NRC Generic Letter 1987-1119 June 1987NRC Generic Letter 1987-011: Relaxation in Arbitrary Intermediate Pipe Rupture Requirements
ML18022A47911 December 1986Forwards Addl Responses to ACRS Recommendations Documented in ACRS 840116 Ltr to Chairman Palladino.Control Room Air Ventilation Sys Testing,Westinghouse D-4 Steam Generator Tube Degradation & Documentation of Operations Discussed
ML18022A4443 October 1986Forwards marked-up Amend 37 to Fsar.Justification for Revs to Listed Chapters Also Encl.Revs Do Not Alter Conclusions in SER Through Sser 3 (NUREG-1038).Amend Will Be Formally Reissued in Public Form
ML18004A48825 August 1986Forwards Addl Info Re Util Request for Deviation from NUREG- 0800 Requirements for Manual SSE Hose Stations,Per Request. Redundant Safe Shutdown Equipment Separated by 3 H Rated Barriers Which Are Seismic Class I Structures
ML18019B0653 July 1986Forwards Addl Info Requested in NRC 860512 Ltr Re Testing of Safety & Relief Valves.Info Submitted to Allow Close Out of SER Confirmatory Item 6 & NUREG-0737,Item II.D.1
ML18019B0892 July 1986Petition Requesting Institution of Proceedings Per 10CFR2.206,requiring Util to Respond to Show Cause Order Due to Failure to Meet Required Stds in Areas of Emergency Planning,Plant Safety,Security & Personnel Stress
ML18003B3076 June 1986Responds to Confirmatory Items Identified in Sser 3 (NUREG-1038),Section 3.10.1, Operability Qualification of Mechanical Equipment. Draft Revised List of Active Valves Expected by 860612.Justification for Qualification Encl
ML18019A9764 June 1986Forwards Proposed FSAR Pages,Incorporating Fire Protection Program Per Generic Ltr 86-10.Listed Limiting Conditions of Operation,Action Statements & Surveillance Procedures Will Be Established in Operating Manual to Replace Tech Specs
ML18019A79328 April 1986Rev 1 to Shearon Harris Nuclear Power Plant Crdr Final Summary Rept.
NRC Generic Letter 1986-1024 April 1986NRC Generic Letter 1986-010: Implementation of Fire Protection Requirements
ML18003B24231 March 1986Sqrt Visit Rept, Informal Rept
ML18019A40026 September 1985Forwards Addl Info in Response to SER Confirmatory Item 4 Re Design Documentation of ASME Components.Info Responds to NRC Concerns Identified by 850618 Ltr & Mechanical Engineering Branch Questions 210.80,210.81 & 210.82
ML18003B15319 July 1985Forwards Table Listing Clearances Between Various Bldgs & Max Displacements of Two Adjacent Bldgs,In Response to ACRS Question Re Adequacy of Bldg Clearances During SSE
ML20127J58813 June 1985Responds to Deficiencies & Common Concerns Raised in Chapter 7 of Insp Rept 50-400/84-48 Re Integrated Design Review. Independent Evaluation Team Concluded That Identified Items Resolved & Overall Design Process Adequately Controlled
ML18018B84920 December 1984Forwards Emergency Diesel Generator Equipment & Vols 1-4 of Tdi Diesel Generator Design Review & Quality Revalidation Rept.
ML20100P14617 October 1984Applicant Exhibit A-6,consisting of FSAR Section 9.5.1 & App 9.5A Re Fire Protection Sys (W/Revs of 841010)
ML18018B78610 October 1984Forwards Commitments in Response to SER Open Item 8 Re Qualification of Fire Doors & Revised Tables & Info Concerning Combustible Loading.W/Two Oversize Drawings Encl. Aperture Card Available in PDR
ML20112H52430 September 1984Technical Bases for Eliminating Large Primary Loop Pipe Rupture as Structural Design Basis for Shearon Harris Unit 1
ML20106A41831 August 1984Control of Heavy Loads at Nuclear Power Plants,Shearon Harris Nuclear Power Plants,Units 1 & 2, Draft Technical Evaluation Rept
ML20094H5099 August 1984Testimony of Ga Kanakaris,Rm Parsons & Lf Garner on Eddleman Contention 65 Re Concrete Containment Structure.Related Correspondence
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