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	Issue date	Title	Topic
ML030070208	3 April 2002	Summary Report - Ncrs Initiated Since 03/27/2002
ML030070214	20 March 2002	Summary Report - Ncrs Initiated Since 03/19/2002
ML030070217	6 March 2002	Summary Report - Ncrs Initiated Since 02/27/2002
ML030070220	20 February 2002	Summary Report - Ncrs Initiated Since 02/13/2002
ML030520269	15 February 2003	Follow-up Report, Reference Event #39516
ML030860823	26 March 2003	Attachment Technical Letter Report	Weld Overlay
ML031120705	18 April 2003	Review of 90-day Steam Generator Tube Inservice Inspection Report for a Refueling Outage in 2001
ML031700027	6 June 2003	Submittal of 10-O Report	Boric Acid Power Uprate
ML031890936	10 July 2003	Relaxation of the Order, Exercising Enforcement Discretion, and Extension of the Time to Submit an Answer or Request a Hearing Regarding Order EA-03-038, Fitness-for-Duty Enhancements for Nuclear Security Force Personnel for Brunswick, Crys	Enforcement Discretion
ML032040061	15 July 2003	Unit - Pressure/Temperature Limits Report, Revision 4	Hydrostatic
ML032471632	22 August 2003	Submittal of 10-Q Report	Boric Acid
ML032660252	22 September 2003	Results of Crystal River SDP Phase 2 Notebook Benchmarking Visit	Internal Flooding Probabilistic Risk Assessment Significance Determination Process
ML033520008	3 September 1997	CRC Depletion Calculations for the Rodded Assemblies in Batches 10 and 11 of Crystal River Unit 3	Fuel cladding
ML040960086	29 February 2004	to 0000-0016-6502-SRLR, Supplemental Reload Licensing Report for Brunswick Steam Electric Plant, Unit 1, Reload 14, Cycle 15.	Shutdown Margin Safety Limit Minimum Critical Power Ratio Anticipated operational occurrence Feedwater Controller Failure MELLLA Power Uprate
ML041460246	19 May 2004	Q Report for Period Ending 03/31/2004
ML043430133	30 November 2004	Submital of 10-Q Report
ML050530168	17 February 2005	Background Discussion Material for February 24-25, 2005 NRC Meeting Relating to Replacement for BAW-2374, Revision 1, Evaluation of OTSG Thermal Loads During Hot Leg Loca.	Nondestructive Examination Fuel cladding Operability Assessment
ML050560037	8 February 2005	12-5023272-01, Risk Assessment for Alternate STS End States.	Safe Shutdown Boric Acid Shutdown Margin Ultimate heat sink Mission time Time to boil Probabilistic Risk Assessment Offsite Circuit Manual Operator Action
ML050700408	20 February 2004	EMF-3030(NP), Revision 0, Robinson Nuclear Plant, Realistic Large Break LOCA Analysis, February 2004, Non-Proprietary Version	Loop seal Exclusive Use Affidavit
ML050910212	31 January 2005	0000-0028-0680-SRLR, Revision 0, Supplemental Reload Licensing Report for Brunswick Steam Electric Plant Unit 2 Reload 16 Cycle 17.	Safety Limit Minimum Critical Power Ratio Anticipated operational occurrence Feedwater Controller Failure MELLLA Power Uprate Affidavit
ML051520445	27 May 2005	Significant Adverse Condition Investigation Report	Hot Short Safe Shutdown Unanalyzed Condition Fire Barrier Coatings Exemption Request Continuous fire watch Fire Protection Program Manual Operator Action
ML051590333	31 May 2005	Submittal of 10-Q Report	License Renewal Exemption Request
ML052090202	28 July 2005	Notification of Brunswick Ssdpc IR 05000325-05-07 and 05000324-05-07	Probabilistic Risk Assessment Temporary Modification Maintenance Rule Program
ML052440190	10 August 2005	Attachment E, Crystal River Unit 3 - License Amendment Request #290, Revision 1 Probabilistic Methodology to Determine the Contribution to Main Steam Line Break Leakage Rates for the Once-Through Steam Generator from the Tube End Crack
ML052510504	31 August 2005	Framatome Anp, Inc 77-5069740-NP-00, Shearon Harris Criticality Evaluation.	Exclusive Use Affidavit Water rod
ML053530069	9 May 2005	Operational Safety Review Team (Osart) Mission to Brunswick Nuclear Plant 9-25 May 2005	Safe Shutdown Fitness for Duty Fire Barrier Water Inventory Control Coatings Temporary Modification Aging Management Foreign Material Exclusion Flow Accelerated Corrosion Large early release frequency Stress corrosion cracking Severe Accident Management Guideline License Renewal Earthquake Fire Watch Power change Siren Power Uprate Thermography
ML060810711	22 March 2006	for the Record: Summary of Nrc'S Review of the Recent Security Issues at the Shearon Harris Nuclear Plant	Inattentive
ML061380675	1 December 2005	Report of Independent Auditors
ML061380678	30 September 2005	Financial Highlights
ML061440487	18 May 2006	Submittal of 10-O Report for Quarterly Period Ending March 31, 2006
ML062770227	19 October 2006	Essential Fish Habitat Assessment for License Renewal of Brunswick Steam Electric Plant, Units 1 and 2	License Renewal Biofouling Power Uprate
ML063200168	30 October 2006	G20060793 - Progress Energy Paper Anti-Nuclear Groups Files Petition to Shut Down Harris Plant	Safe Shutdown Fire Barrier Operator Manual Action Hemyc Fire Protection Program Fire Watch
ML063280241	5 October 2006	Shearon Harris, Letter Report NAI-1282-001, Gothic Charging Pump Room Heatup Analysis for Shearon Harris.	GOTHIC
ML071100006	8 December 2006	Operational Safety Review Team (Osart) Mission and Follow-up Visit Report	Safe Shutdown Fitness for Duty Fire Barrier Water Inventory Control Coatings Temporary Modification Aging Management Foreign Material Exclusion Flow Accelerated Corrosion Large early release frequency Stress corrosion cracking Severe Accident Management Guideline License Renewal Earthquake Fire Watch Power change Siren Power Uprate Thermography
ML071270183	4 May 2007	Audit and Review Plan for Plant Aging Managment Programs, Aging Management Reviews, and Time-Limited Aging Analyses for the Harris Nuclear Plant.	Boric Acid Incorporated by reference Aging Management License Renewal Fire Protection Program Backfit Power Uprate
ML071980195	30 July 2007	Environmental Impact Statement Scoping Process Summary Report Shearon Harris Nuclear Power Plant - July 2007	Aging Management License Renewal Environmental Justice Fire Watch
ML072050214	19 July 2007	Afpb Staff Response to NFPA 805 Transition Pilot Plant FAQ 06-0008, Revision 5	Safe Shutdown Fire Barrier Fire Protection Program
ML072070311	30 June 2007	BSEP 07-0067 Enclosure 3; Areva Report ANP-2646(NP), Revision 0, Brunswick, Unit 1, Thermal-Hydraulic Design Report for ATRIUM-10 Fuel Assemblies, Dated June 2007	Anticipated operational occurrence Water rod
ML072070318	30 June 2007	BSEP 07-0067 Enclosure 6; Areva Report ANP-2625(NP), Revision 0, Brunswick, Units 1 and 2 LOCA Break Spectrum Analysis for ATRIUM-10 Fuel, Dated June 2007
ML072180372	31 July 2007	Areva Report ANP-2658(NP), Revision 0, Brunswick Unit 1 Cycle 17 Fuel Cycle Design, Enclosure 3	Shutdown Margin Water rod
ML072420255	30 August 2007	NRC Allegation Report RII-2005-A-0165
ML072700849	31 January 2005	Caldon Experience in Nuclear Feedwater Flow Measurement	Power change
ML072840219	30 September 2007	ANP-2642(NP), Revision 0, Brunswick Nuclear Plant Spent Fuel Storage Pool Criticality Safety Analysis for ATRIUM-10 Fuel.
ML073110381	21 May 2007	Progress Energy Florida, Inc. Proposed Florida Nuclear Site Transmission Planning Study, Final Report, Attachments Dand F Included	Measurement Uncertainty Recapture Affidavit
ML080070531	9 January 2008	Review of the Fire Probabilistic Risk Assessment Model to Support Implementation of National Fire Protection Association (NFPA) Standard NFPA-805	Safe Shutdown Fire Barrier Probabilistic Risk Assessment Multiple Spurious Operation Incorporated by reference Large early release frequency Fire Protection Program
ML082190013	7 August 2008	Monthly Operating Reports Second Quarter 2008	Reserve Station Service Transformer Power change
ML090970246	30 June 2008	Enclosure 7 and 9 to BSEP 09-0034 - ANP-2727(NP), Rev. 0, Brunswick, Unit 2, Cycle 19 Fuel Cycle Design, and Areva Affidavit Re Withholding ANP-2771(P), Rev. 0 from Public Disclosure	Shutdown Margin Exclusive Use Affidavit Water rod
ML090970248	31 July 2008	Enclosure 4 and 6 to BSEP 09-0034 - ANP-2729(NP), Rev. 0, Brunswick, Unit 2, Thermal-Hydraulic Design Report for ATRIUM-10 Fuel Assemblies, and Areva Affidavit Withholding ANP-2727(P), Rev. 0 Form Public Disclosure	Anticipated operational occurrence Exclusive Use Affidavit Water rod
ML091140599	12 August 2008	Attachment B, Off-Site Dose Calculation Manual, Revision 31	Grab sample Offsite Dose Calculation Manual Annual Radioactive Effluent Release Report Annual Radiological Environmental Operating Report Process Control Program
ML092150054	31 May 2009	ANP-2693(NP), Revision 0, Loss of Forced Reactor Coolant Flow Analysis for Harris Nuclear Plant, Unit 1, Enclosure 4 to Serial: HNP-09-068	Fuel cladding Coast down

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