Jim Costedio
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Jim Costedio OR Jim Costedio
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SHINE Medical Technologies
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Jim Costedio#Work history: Licensing Manager
NRC-2015-0226, Comment (1) of James Costedio on Behalf of Shine Medical Technologies, Inc. on the Draft Regulatory Issue Summary (Ris), RIS 2015-XX, Review and Submission of Updates to Final Safety Analysis Reports, Emergency Preparedness Documents,
NL-14-140, Withdrawal of December 17, 2012 Coastal Zone Management Act Consistency Certification
NRC 2011-0068, Response to Request for Additional Information Regarding License Amendment 263, Request for Approval of Revised Cyber Security Plan
JAFP-08-0057, Response to Request for Additional Information Regarding Relocation of Pressure and Temperature Curves to the Pressure and Temperature Limits Report
JAFP-08-0034, Application for Amendment to Technical Specifications Regarding Relocation of Pressure and Temperature (P-T) Curves to the Pressure and Temperature Limits Report (PTLR) Consistent with TSTF-419-A
JAFP-08-0011, License Amendment Request Application for Technical Specification Changes Using the Consolidated Line- Item Improvement Process (CLIIP)
CNRO-2008-00003, Entergy Fleet Correspondence Service List; River Bend Station, Grand Gulf Nuclear Station, Arkansas Nuclear One Units 1 and 2, Indian Point Generating Units 1, 2, and 3, Pilgrim Nuclear Power Station, Waterford 3 Steam Electric Stati
JAFP-07-0134, Clarification of Previous Response to Request for Additional Information Regarding the Fourth Inservice Inspection Interval Inspection Program Plan Relief Request RR-6
JAFP-07-0130, License Renewal Application, Amendment 15
JAFP-07-0124, Revision to Application for Technical Specifications (TS) Change Based on TSTF-477, Add Action Statement for Two Inoperable Control Room Air Conditioning Subsystems, Using the Consolidated Line Item Improvement Process (CLIIP)
JAFP-07-0116, Fourth Interval Inservice Testing Program for Pumps and Valves
JAFP-07-0107, Response to Request for Additional Information Regarding Proposed Relief Request PRR-01 for the Fourth Interval In-Service Testing Program
JAFP-07-0108, Comment (3) of Jim Costedio, on Behalf of Entergy Nuclear Operations, Inc. on NUREG-1437 Supplement 31, Draft Generic Environmental Impact Statement for License Renewal of Nuclear Power Plants: Regarding James A. FitzPatrick Nuclear Pow
JAFP-07-0098, Supplement to Application for Amendment to Technical Specifications Regarding Control Room Envelope Habitability, Consistent with TSTF-448 Revision 3
JAFP-07-0100, License Renewal Application, Amendment 13
JAFP-07-0092, Response to Request for Additional Information Regarding Proposed Relief Requests for the James A. FitzPatrick Nuclear Power Plant Fourth Interval In-Service Testing Program
JAFP-07-0091, Application for Technical Specifications Change Based on TSTF-477, Add Action Statement for Two Inoperable Control Room Air Conditioning Subsystems, Using the Consolidated Line Item Improvement Process (CLIIP)
JAFP-07-0079, License Renewal Application, Amendment 12
JAFP-07-0068, Response to May 1, 2007, Notice of Violation (NRC Investigation Report No. 1-2006-014) EA-07-029
JAFP-07-0067, License Renewal Application, Amendment 11
JAFP-07-0059, Response to Generic Letter 2007-01, Inaccessible or Underground Power Cable Failures That Disable Accident Mitigation Systems or Cause Plant Transient.
JAFP-06-0109, License Renewal Application, Amendment 10, RAI Responses
JAFP-07-0050, Proposed Relief Requests for the James A. FitzPatrick Power Plant Fourth Interval In-Service Testing Program
JAFP-07-0019, License Renewal Application, Amendment 9
JAFP-07-0023, Application for Amendment to Technical Specifications 3.10.1. Re Inservice Leak and Hydrostatic Testing Operation, Consistent with TSTF-484
JAFP-07-0021, License Renewal Application, Amendment 6
JAFP-07-0020, Submittal of James A. Fitzpatrick - Inservice Inspection Summary Report 2006 Refuel Outage (Reload 17/Cycle 18)
JAFP-07-0006, Request for Additional Information, Response to Generic Letter 2003-01, Control Room Habitability Response
JAFP-06-0181, License Renewal Application, Amendment 3
JAFP-06-0177, Submittal of License Renewal Application, Amendment 2
JAFP-06-0127, CFR 50.46 Annual Report - Errors in Emergency Core Cooling System (ECCS) Evaluation Models
JAFP-06-0089, Response to Generic Letter 2006-03, Potentially Nonconforming Hemyc and MT Fire Barrier Configurations
JAFP-06-0062, Response to Request for Additional Information Regarding Proposed License Amendment: Changes to the Reactor Vessel Material Surveillance Program
JAFP-06-0057, Response to Generic Letter 2006-02, Grid Reliability and the Impact on Plant Risk and the Operability of Offsite Power
JAFP-06-0016, Proposed License Amendment: Changes to the Reactor Vessel Material Surveillance Program
JAFP-08-0006, Application for Amendment to Technical Specifications Regarding Diesel Fuel Oil, Lube Oil, and Starting Air Consistent with TSTF-501 and Diesel Fuel Oil Testing Program Consistent with TSTF-374
JAFP-07-0088, James A. FitzPatrick, Application for Amendment to Technical Specifications Regarding Control Room Envelope Habitability, Consistent with TSTF-448 Revision 3
05000266/LER-2012-004, Regarding Unit 1 Manual Reactor Trip
05000266/LER-2012-003, Regarding 2B-04 Safeguards 480V Bus De-Energized
05000301/LER-2012-001, Regarding Unit 2 Manual Reactor Trip
05000266/LER-2012-002, Regarding Condition Prohibited by Technical Specification 3.7.5, Auxiliary Feedwater
L-2011-307, Update of Nuclear Regulatory Commission (NRC) Distribution List for Documents Containing Safeguards (Sgi), Official Use Only (Ouo), and Routine Information
JAFP-08-0069, Submittal of NRC Form 536, Operator Licensing Examination Data in Response to Regulatory Issue Summary 2008-16, Preparation and Scheduling of Operator Licensing Examinations
05000333/LER-2007-002, (Jaf) Re Manual Reactor Scram Due to Blocked Circulating Water Intake Screens
05000333/LER-2007-001, Safety Relief Valve Setpoints Outside of Allowable Tolerances
05000333/LER-2006-002, Regarding High Pressure Coolant Injection System (Hpc) Declared Inoperable Due to Turbine Speed Oscillations
05000333/LER-2006-001, Inoperable Reactor Building-To-Suppression Chamber Vacuum Breaker in Excess of Technical Specifications Allowed Out of Service Time
05000333/LER-2005-006, Re Inoperable 115 Kv Line in Excess of Technical Specification Allowed Out of Service Time
05000333/LER-2005-005, Re Automatic Reactor Scram on Low Reactor Vessel Water Level During Reactor Feed Pump Control Reset
JAFP-06-0079, Response to NRC Requests for Additional Information Regarding FitzPatricks Proposed Exemption Request for Hemyc Fire Wrap
NRC 2011-0062, Response to Regulatory Information Summary 2011-08, Preparation and Scheduling of Operator Licensing Examinations
NRC 2012-0076, Response to Request for Additional Information Fall 2011 Unit I (U1 R33) Steam Generator Tube Inspection Report
NRC 2012-0075, Fifth Interval Inservice Inspection Program Plan and Schedule
NRC 2012-0068, Licensee Qualification for Performing Dynamic Rod Worth Measurement Analysis
NRC 2012-0064, Registration of NUHOMS-32PT Casks, WNHOMS-32-033, WNHOMS-32-035, WNHOMS-32-036
NRC 2012-0059, Registration of NUHOMS-32PT Casks, WNHOMS-32.031, WNHOMS-32-032, WNHOMS-32-034
NRC 2012-0057, Response to Regulatory Information Summary 2012-07, Preparation and Scheduling of Operator Licensing Examinations
NRC 2012-0048, 10 CFR 50.59 Summary Report for 2011
NRC 2012-0045, Technical Specification Bases Change Summary
NRC 2012-0044, Technical Requirements Manual Change Summary
NRC 2012-0015, Fall 2011 Unit 1 (U1R33) Steam Generator Tube Inspection Report
NRC 2012-0028, 2011 Annual Monitoring Report, for the Period January 1 Through December 31, 2011
NRC 2012-0031, Annual Report of Individual Monitoring - 2011
NRC 2012-0032, Annual Report of ECCS Evaluation Model Changes
NRC 2012-0014, Filing of Owners Containment Inservice Inspection Summary Report for Refueling Outage U1R33
NRC 2012-0018, Emergency Response Data Svstem (ERDS) Changes
NRC 2012-0012, Fitness for Duty Performance Data
NRC 2011-0100, Transmittal of Core Operating Limits Report, Revision 13
NRC-2011-0077, Emergency Response Data System (ERDS) Changes
NRC 2011-0039, Redacted - Point Beach, Units 1 and 2, Submittal of 2010 Annual Monitoring Report
NRC 2011-0075, Cycle 32 (U2C32) Core Operating Limits Report
NRC 2011-0059, 10 CFR 50.59 Summary Report for 2010
NRC 2011-0060, Technical Requirements Manual Change Summary for January 1, 2010 Through December 31, 2010
NRC 2011-0061, Technical Specification Bases Change Summary for January 1, 2010 Through December 31, 2010
NRC 2011-0055, Units I and 2, Transmittal of Core Operating Limits and Pressure and Temperature Limits Reports
NRC 2011-0050, Emergency Core Cooling System Evaluation Model Changes
NRC 2011-0047, Annual Report of Individual Monitoring - 2010
NRC 2011-0035, Cycle 32 (U2C32) Core Operating Limits Report
NRC 2011-0024, Submittal of 2010 Fitness for Duty Performance Data
NRC 2010-0196, Spent Fuel Storage Five-Year Inspection Report Ventilated Spent Fuel Storage Cask WVSC-24-01 Certificate of Compliance 1007
NRC 2010-0155, License Qualification for Performing Safety Analysis Generic Letter 83-11, Supplement 1
NRC 2010-0090, Technical Specification Bases Change Summary for January 1, 2009 Through December 31, 2009
NRC 2010-0091, Technical Requirements Manual Change Summary
NRC 2010-0092, ECCS Evaluation Model Changes
NRC 2010-0066, Annual Report of Individual Monitoring - 2009
NRC 2010-0048, Submittal of Revisions of Physical Security Plan and Supporting Appendices Justification of Changes
NRC 2010-0041, Cycle 33 (U1C33) Core Operating Limits Report
NRC 2009-0112, Cycle 31 (U2C31) Core Operating Limits Report
NRC 2009-0100, Annual Report of Changes to, and Errors Discovered in, Emergency Core Cooling System (ECCS) Evaluation Model Changes
NRC 2009-0067, 10 CFR 50.59 Summary Report for 2008
NRC 2009-0079, Submittal of Registration of NUHOMS-32PT Casks WNHOMS-32-26, WNHOMS-32-27, WNHOMS-32-28, WNHOMS-32-29, and WNHOMS-32-30
NRC 2009-0059, Response to Request for Additional Information GSI-I91/GL 2004-02 Potential Lmpact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors
NRC 2008-0063, Technical Requirements Manual Change Summary
NRC 2009-0062, Technical Specification Bases Change Summary
NRC 2009-0046, Annual Monitoring Report, Appendix 1 Through End
NRC-2009-0046, Annual Monitoring Report, Cover Letter Through Part D, Groundwater Monitoring
NRC 2009-0041, Fall 2008 Unit 1 (U1R31), Steam Generator Tube Inspection Report
NRC 2009-0052, Submittal of Cycle 32 (U1C32) Core Operating Limit Report
NRC 2009-0048, Submittal of Annual Individual Monitoring Report for Cy 2008
NRC 2009-0034, Revision to Security Plan
NRC 2009-0012, Response to Request for Additional Information Spring 2008 Unit 2 (U2R29) Steam Generator Tube Inspection Report
JAFP-08-0042, Transmittal of Annual Radiological Environmental Operating Report
JAFP-08-0038, Inservice Inspection Program Relief Requests Third Ten-year Interval Closeout
JAFP-08-0037, J. A. FitzPatrick - Annual Radiological Effluent Release Report for the Period of January 1, 2007 Through December 31, 2007
NRC 2011-0045, Point Beach Nuclear Plant, Units 1 and 2 - 2010 Annual Fatigue Results Supplemental Response
NRC 2010-0029, Point Beach, Units 1 & 2, Submittal of Fitness for Duty Performance Data for Period Ending December 31, 2009
NRC 2009-0096, Point Beach, Unit 1 - Response to Request for Additional Information Re Fall 2008 Unit 1 (U1R31) Steam Generator Tube Inspection Report
JAFP-07-0104, NRC Form 536, Operator Licensing Examination Data
JAFP-07-0102, Response to Request for Additional Information Regarding the James A. FitzPatrick Nuclear Power Plant Fourth Inservice Inspection Interval Inspection Program Plan Relief Request RR-6
JAFP-07-0090, Core Operating Limits Report, Revision 23
JAFP-06-0180, Core Operating Limits Report, Revision 22
JAFP-06-0143, NRC Form 536, Operator Licensing Examination Data
JAFP-06-0120, Groundwater Protection Baseline Information
JAFP-06-0085, Revision to Response for Additional Information Regarding Request for Approval of Relief Request No. 39, Implementation of BWRVIP Guidelines in Lieu of ASME Section XI Code Requirements on Reactor Vessel Internals and Components Inspect
05000333/LER-1997-010-01, :on 971021,determined That Surveillance Testing of Primary Containment Pressure Chamber,Drywell Vacuum Breakers Coincident W/Loca.Caused by Inadequate Procedures Reviews.Procedures Revised
05000333/LER-1996-003-01, :on 960222,plant Shutdown Due to Degraded Control Rod Scram Times & Manual Scram.Caused by Leak in Main Turbine EHC Sys.C/A:Bypass Valves Replaced
05000333/LER-1995-011-01, :on 950531,leakage of Primary Containment Isolation Valves Was Exceeded.Caused by 02-2AOV-39 & 02- 2AOV-40 Experiencing Repeated Difficulty in Passing Llrt. Flushed Seat on Inboard Isolation Valve
NRC-2009-0025, And Revision 51 to Emergency Plan and Emergency Plan Manual
NRC 2012-0038, ECCS 30-Day Report for the Thermal Conductivity Degradation Impact on Large Break Loss of Coolant Accident Analyses with ASTRUM
NRC 2012-0019, Filing of Owners Class 1, 2, and 3 Inservice Inspection Summary Report for Point Beach Nuclear Plant Refueling Outage U1R33
NRC 2011-0084, Filing of Owners Inservice Inspection Summary Report for Refueling Outage U2R31
NRC 2010-0096, Filing of Owners Inservice Inspection Summary Report Refueling Outage U1R32
NRC 2010-0028, Filing of Owners Inservice Inspection Summary Report for Refueling Outage U2R30
NRC 2009-0083, Response to Regulatory Information Summary 2009-11, Preparation and Scheduling of Operator Licensing Examinations
NRC 2010-0115, Response to Regulatory Information Summary 2010-08, Preparation and Scheduling of Operator Licensing Examinations
JAFP-06-0166, Revision to the 2002 Annual Radioactive Effluent Release Report
NRC 2010-0094, Filing of Owners Inservice Inspection Summary Report for Refueling Outage U1R32