Michael Colomb
Michael Colomb# QUERYecabd9b21fd0e820a14f9a5a925a384f
Michael Colomb# QUERY299475d11b283639b7048dcaa275f769
Michael Colomb OR Michael Colomb
Michael Colomb# QUERY7b0938fe634327524ccef3e1146977a5
Michael Colomb# QUERY259726a3c7eef6288c885a7178f52533
Michael Colomb# QUERY244820e18bf2b287c99335c1a557ca23
False
Michael Colomb# QUERY600bb62cdec9e3bca7c4ea81d1f9984f
True
Michael Colomb# QUERYea8d93abe6e4c24534553889ca4241ff
Michael Colomb# QUERYb4b9062ad13fdacdb7d4ddf321169bd6
Michael Colomb# QUERY0fbb45fad91c524d0e5c9c3002034279
FitzPatrick
Michael Colomb# ERR1dd423a8697e32d6813ecd1a7aae482c
Michael Colomb#Work history: Site Vice President
JAFP-95-0238, Forwards Response to NRC Re Violations Noted in Insp Rept 50-333/95-06 on 950212-0325.Corrective Actions: Review Was Performed of All C02 Heat Detection Sys Surveillance Test Procedures to Identify Addl Procedures
JAFP-95-0122, Responds to NRC Re Violation Noted in Insp Rept 50-333/95-03 on 950123-27.Corrective Actions:Portable Alarming Area Radiation Monitor RM-16 Added to Daily Insp & RP Instrument Procedure RP-INST-103 Being Updated
JAFP-95-0028, Responds to NRC Re Violations Noted in Insp Rept 50-333/94-30 on 941212-16.Corrective Actions:Performance Standards for Good Radiological Work Practices Being Reinforced & Self Identification of Poor Work Ongoing
JAFP-99-0112, Informs of Util Determination That Listed Individuals No Longer Need to Maintain Operating License for Ja FitzPatrick Nuclear Plant.Termination of Listed Licenses,Requested
JAFP-13-0043, Proposed Change to Renewed Facility Operating License Condition 2.T
JAFP-13-0025, Overall Integrated Plan in Response to March 12, 2012, Commission Order to Modify Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)
JAFP-13-0023, Overall Integrated Plan in Response to March 12, 2012 Commission Order Modifying License with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)
JAFP-13-0006, Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 1, Integrated Assessment Approach
JAFP-12-0125, Initial Status Report in Response to March 12,2012 Commission Order Modifying Licenses with Regard to Requirements for Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)
JAFP-12-0124, Initial Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)
JAFP-12-0123, Initial Status Report in Response to March 12,2012, Commission Order to Modify Licenses with Regard to Reliable Hardened Containment Vents (Order Number EA-12-050)
JAFP-12-0095, Response to IE Bulletin 2012-01, Design Vulnerability in Electric Power System
JAFP-12-0072, License Amendment Request - Cyber Security Plan Implementation Schedule Milestones
JAFP-12-0063, Response to NRC Request for Information Per 10CFR50.54(f) Re Flooding Aspects of Recommendations 2.1 and 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident
JAFP-12-0065, 90-Day Response to March 12, 2012 Information Request on Action Plan for Completing Emergency Communication and Staffing Assessments
JAFP-12-0064, Response to NRC Request for Information (RFI) 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 Fukushima Dai-ichi Accident
JAFP-12-0054, Entergy Nuclear Operations, Inc.’S 60-Day Response to the March 12, 2012, Information Request, Action Plan for Completing Emergency Communication and Staffing Assessments
JAFP-12-0032, Response to Request for Additional Information Application for Change to the Current Licensing Basis, Authorizing Use of on Load Tap Changers with the Reserve Station Service Transformers
JAFP-12-0038, Entergy Nuclear Operations, Incorporated - Answer to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)
JAFP-12-0039, Entergy Nuclear Operations, Incorporated - 30 Day Response to March 12, 2012 Information Request
JAFP-12-0036, Entergy Nuclear Operations, Incorporated’S - Answer to March 12, 2012 Commission Order Modifying License with Regard to Requirements for Mitigation Strategies for Beyond-Design Basis External Events (Order Number EA-12-049)
JAFP-12-0002, Withdrawal of Application for Amendment to Modify the Facility Operating License Condition 2.c(3), Fire Protection
JAFP-11-0141, Response to Request for Additional Information for NRC Bulletin 2011-01
BVY 11-070, Technical Specifications Proposed Change No. 295 Supplement 1 - Request for Additional Information
BVY 11-069, Technical Specifications Proposed Change No. 295 Proposed Emergency License Amendment for Single Loop Operation
BVY 11-049, Day Response to NRC Bulletin 2011-01
BVY 11-044, Withdrawal of License Amendment Request
BVY 11-045, Day Response to NRC Bulletin 2011-01
BVY 11-033, License Renewal Safety Evaluation Report Supplement Comments
BVY 11-026, Notification of Revised Regulatory Commitment
BVY 11-042, Technical Specifications Proposed Change No. 293, Supplement 1 Revised Reactor Vessel Pressure-Temperature Limitation Curves
BVY 11-023, Technical Specifications Proposed Change 292, Supplement 2, Response to Request for Additional Information and Revision to Cyber Security Plan
BVY 11-024, Deviation from BWRVIP-25 Inspection Requirements
BVY 11-017, Fitness for Duty Program Performance Report for 2010
BVY 11-011, Technical Specifications Proposed Change 292, Supplement 1 Response to Request for Additional Information on the Cyber Security Plan
BVY 11-015, License Renewal Application Supplemental Information
BVY 11-013, License Renewal Application Supplemental Information
BVY 11-012, License Renewal Application Supplemental Information
BVY 11-007, License Renewal Application Supplemental Information
BVY 11-010, License Renewal Application Supplemental Information
BVY 11-008, Technical Specifications Proposed Change No. 290 Administrative Changes - Supplement 1
BVY 11-001, License Renewal Application Supplemental Information
BVY 10-069, License Renewal Application Annual Update Information
BVY 10-071, Technical Specifications Proposed Change No. 293 Revised Reactor Vessel Pressure-Temperature Limitation Curves
BVY 10-058, License Renewal Application Supplemental Information
BVY 10-059, Technical Specifications Proposed Change No. 294, Elimination of Provisions Allowing HPCI and RCIC Suctions to Be Aligned to the Suppression Pool
BVY 10-057, Closure of Deviation from BWRVIP-130
BVY 10-052, License Renewal Application Supplemental Information
BVY 10-050, License Renewal Application Supplemental Information
BVY 10-045, Technical Specifications Proposed Change No. 289 Suppression Chamber-Drywell Vacuum Breakers and Differential Pressure
BVY 10-039, Supplemental Special Report for Tritium Discovered Onsite
BVY 10-036, Technical Specifications Proposed Change No. 292, License Amendment Withdrawal and Request - Cyber Security Plan
BVY 10-034, Response to Request for Additional Information Regarding Request for Alternative VY-ISI-014
BVY 10-035, RFO-28 Steam Dryer Inspection Results
BVY 10-031, Annual Radiological Environmental Operating Report
BVY 10-030, Radioactive Effluent Release Report
BVY 10-018, Technical Specifications Proposed Change No. 291 Control Rod Actuation Logic System Functional Test
BVY 10-017, Technical Specifications Proposed Change No. 290 Administrative Changes
BVY 10-013, Request for Exemption from Physical Security Requirements - Supplemental Informaiton
BVY 10-008, Decommissioning Funding Assurance Documentation
BVY 10-004, Request for Exemption from Physical Security Requirements
BVY 09-073, License Renewal Application Annual Update
BVY 09-066, 10CFR50.55a(a)(3)(i) Inservice Inspection Program Request VY-ISI-014
BVY 09-068, Technical Specifications Proposed Change No. 288 Scram Discharge Volume Vent and Drain Valves
BVY 09-067, Response to Request for Additional Information Related to Technical Specifications Proposed Change No. 284 Change to Requirements for Inoperable Containment Isolation Valves
BVY 09-063, Technical Specification Proposed Change No. 287 Safety Limit Minimum Critical Power Ratio Change
BVY 09-061, Response to Request for Additional Information on Generic Letter 2008-01
BVY 09-052, Technical Specifications Proposed Change No. 284 Change to Requirements for Inoperable Containment Isolation Valves
BVY 09-051, Technical Specifications Proposed Change No. 285 Revision of High Radiation Area Controls
BVY 09-048, VY Spent Fuel Management Plan - RAI Response
BVY 09-042, Drug and Alcohol Testing Errors
BVY 09-035, Technical Specifications Proposed Change No. 273, Supplement 8, Transmittal of Final Technical Specification Pages
BVY 09-036, 2008 Annual Radiological Environmental Operating Report
BVY 09-029, Technical Specifications Proposed Change No. 283 Change to Requirements for Performing 10 CFR 50, Appendix J, Type a Test
BVY 09-009, Technical Specifications Proposed Change No. 273, Supplement 7 Response to Request for Additional Information
BVY 09-022, Update to Spent Fuel Management Plan
BVY 09-019, License Renewal Application Amendment 38
BVY 09-012, Submittal of Proposed License Amendment for Technical Specifications No. 282, Revision of Drywell Vacuum Breaker Surveillance Requirements
BVY 09-007, Technical Specifications Proposed Change No. 279, Supplement 1, Response to Request for Additional Information
BVY 09-002, Supplemental Response to Generic Letter 2008-01
BVY 09-001, Submittal of Cycle 26 10CFR50.59 Report
BVY 09-006, License Renewal Application Amendment 37
BVY 09-004, CFR 50.46(a)(3)(ii) Annual Report for 2008
BVY 08-090, License Renewal Application Annual Update
BVY 08-085, RFO 27 Steam Dryer Inspection Results
BVY 08-084, Technical Specifications Proposed Change No. 273, Supplement 5, Response to Request for Additional Information
BVY 08-075, Technical Specifications Proposed Change No. 273, Supplement 4, Response to Request for Additional Information Related to Supplement 2
BVY 08-083, Request for Revision to Existing 10 CFR 50 Appendix R Exemption Response to Request for Additional Information
BVY 08-081, Submittal of Revision of Technical Specification Bases Page 29
BVY 08-080, Core Operating Limits Report for Cycle 27
BVY 08-079, Technical Specifications Proposed Change No. 280, Supplement 1 Relocation of Reactor Building Crane Technical Specifications
BVY 08-070, Submittal of Technical Specifications Proposed Change No. 273, Supplement 3, Response to Additional RAI Related to Degraded Grid Protection
NLS2008058, LER 08-S01-00 for Cooper Regarding Temporary Suspension of Security Measures Due to Tornado Warning
NLS2008033, Response to Request for Additional Information for Question I.2 Regarding License Amendment Request to Revise Technical Specifications - Appendix K Measurement Uncertainty Recapture Power Uprate
JAFP-96-0404, Forwards Updated TS Page Changes to Support Issuance of Amend to License DPR-59 Re Extension of Instrumentation & Miscellaneous Surveillance Test Intervals to Accommodate 24 Month Cycles,Per Discussion W/Nrc
05000333/LER-1997-011, Forwards LER 97-011-00 Re Invalid ESF Actuation & Failure to Perform TS Required Acltions While Performing Troubleshooting Activities
05000333/LER-1997-010, Forwards LER 97-010-00 Re Surveillance Testing of Pressure Suppression Chamber.No Commitments Contained in Rept
05000333/LER-1997-013, Forwards LER 97-013-00 Re High Pressure Coolant Injection Sys Which Was Declared Inoperable Due to Instrument Malfunction During Surveillance Testing.No Commitments Made
05000333/LER-1997-008, Forwards LER 97-008-00 Re Inoperability of Both Trains of SGTS Due to Flow Restriction in Discharge Line
05000333/LER-1997-009, Forwards LER 97-009-00 Re Exceeded Quarterly Calibr Frequency for Radwaste Bldg Exhaust Radiation Monitor.No Commitments Contained in Rept
JAFP-98-0195, Responds to NRC Re Violations Noted in Insp Rept 50-333/98-01 on 980222-0419.Corrective Actions:Surveillance Test Procedure ST-39D Revised to Establish Test Methods That Demonstrate Capability of Each SGTS Train
JAFP-98-0193, Monthly Operating Rept for May 1998 for Ja FitzPatrick Nuclear Plant
JAFP-98-0091, Monthly Operating Rept for Feb 1998 for JAFNPP
JAFP-98-0178, Submits Response to RAI Re List of Topics That Were Missed by Individuals Who Were Renewed During Period of 1994 Through Apr 1997
JAFP-98-0168, Monthly Operating Rept for Apr 1998 for Ja FitzPatrick Nuclear Power Plant
JAFP-98-0159, Informs That Medical Personnel Have Determined That No Addl Restriction Needs to Be Placed on J Walkowiak License OP-11261
JAFP-98-0280, Forwards Rev 6 to COLR, for Ja Fitzpatrick Nuclear Power Plant.Rev 6 Supersedes Rev 5 & Updated Thermal Hydraulic Exclusion Region of Core Power/Flow Map
JAFP-98-0274, Forwards Semi-Annual Radioactive Effluent Release Rept for Period of Jan-June 1998. Format Used for Effluent Data Outlined in App B of Reg Guide 1.21,Rev 1.Distribution IAW Reg Guide 10.1,Rev 4
JAFP-98-0264, Monthly Operating Rept for July 1998 for Ja FitzPatrick Nuclear Plant
JAFP-98-0246, Responds to NRC Re Violations Noted in Insp Rept 50-333/98-02 on 980420-0531.Corrective Actions:Prior to Plant Startup from Resulting Forced Outage,All Shift Operators Were Briefed to Use EP as Directed by EOP-3
JAFP-98-0233, Forwards Rept Re Changes & Errors in ECCS Evaluation Models Applicable to Ja FitzPatrick Npp,Per 10CFR50.46(a)(3)(ii) for Period of 970628-980630.There Have Been No Changes or Errors Applicable to Plant
JAFP-98-0219, Provides Info Re Channel Bow That Was Requested in 980528 Telcon W/Nrc,Bwr Owners Group & Several Licensees
JAFP-98-0222, Monthly Operating Rept for June 1998 for Ja FitzPatrick Nuclear Power Plant
JAFP-97-0357, Transmits Written Exams for 971103 Licensing Exam at Plant. Remaining Exam Matls Will Be Forwarded,Per Schedule Agreed Upon by D Florek & Je Morris
JAFP-97-0309, Transmits Proposed Integrated Exam Outline for 971103 Licensing Exam at Plant
JAFP-98-0083, Forwards Form NRC-5 Equivalent Records for All Individuals Monitored at Plant from 970101 to 1231,on Electronic Media. W/O Encl
JAFP-98-0151, Ja FitzPatrick Nuclear Power Plant Annual Radiological Environ Operating Rept for 1997
JAFP-97-0410, Forwards Rev 1 to Ja FitzPatrick Nuclear Power Plant IST Program for Pumps & Valves,Third Interval, Per 10CFR50.55a(f)
JAFP-99-0279, Correction to 980226 Application for Amend to License DPR-59,revising Ref 19 to Assume 90% SBGT Sys Charcoal Efficiency,Instead of 99%.Ref 19 on TS Page 285 Needs to Be Changed from Rev 0 to Rev 1,based on Revised Calculation
JAFP-99-0278, Application for Amend to License DPR-59,providing Rev C to Proposed TS Change Converting Current TSs to Improved Standard Tss.Withdrawal of JPTS-95-004,proposed TS Changes Re Inservice Leak & Hydrostatic Testing Operation,Reflected
JAFP-99-0277, Monthly Operating Rept for Sept 1999 Fpr Ja FitzPatrick Nuclear Power Plant.With
JAFP-98-0135, Provides Addl Clarification Re Proposed Commitments Contained in 961126 & s.Future Changes to Authority Controlled Procedure Will Be Accomplished Using 10CFR50.59 Process
JAFP-98-0137, Provides Rev to 980225 Response to NRC Re NOV from Insp Rept 50-333/97-08 on 971027-1221.Corrective Actions:Performed Root Cause Evaluation
JAFP-97-0341, Monthly Operating Rept for Aug 1997 for Jfnpp
JAFP-97-0326, Submits Info Requested by NRC on 970729 Re Maintenance Rule Insp Planned for Week of 970929
JAFP-98-0128, Monthly Operating Rept for Mar 1998 for Ja FitzPatrick Nuclear Power Plant
JAFP-99-0261, Monthly Operating Rept for Aug 1999 for Jafnpp.With
JAFP-99-0262, Forwards Voluntary Response to Administrative Ltr 99-03, Re Preparation & Scheduling of Operator Licensing Exams. Completed NRC Form 536,containing Info Re Proposed Exam Preparation Schedule & Initial Operator License Exams,Encl
JAFP-99-0258, Forwards Operator License Restriction Change for Tj Pelton, License SOP-10090-3.License Is Requested to Be Reissued with Restriction for Corrective Lenses.Encl Withheld
JAFP-97-0375, Monthly Operating Rept for Sept 1997 for Ja FitzPatrick Nuclear Plant
JAFP-97-0359, Informs That Util Is Revising TS Amend Application Submitted Under to Withdraw Proposed Changes to Sections 3.5.G & 4.5.G & SRs of Sections 4.7.A.5.a & 4.7.D.2.Revised TS & Se,Encl
JAFP-99-0247, Forwards JAFNPP Effluent & Waste Disposal Semi-Annual Rept for 990101-0630, IAW Amend 93,App B,Section 7.3.C of Plant Ts.Format Used for Rept Is Outlined in App B of Reg Guide 1.21,Rev 1.Distribution Is IAW Reg Guide 10.1,Rev 4
JAFP-99-0245, Informs That Two Licensed Operators Have Returned to Site Upon Release for Normal Duties by Physician.R Korthas, License OP-11159,meets ANSI Std 3.4-1983 & R Sarkissian License SOP-10007-3,was Terminated in Mar 1999
JAFP-99-0236, Monthly Operating Rept for July 1999 for Ja FitzPatrick Npp. with
JAFP-97-0303, Forwards Ja FitzPatrick Nuclear Power Plant Effluent & Waste Disposal Semi-Annual Rept,Jan-June 1997. Rept Submitted in Accordance W/Requirements of Amend 93,App B, Section 7.3.C of Ja FitzPatrick Nuclear Power Plant TS
JAFP-97-0297, Monthly Operating Rept for Jul 1997 for Ja FitzPatrick Nuclear Power Plant
JAFP-99-0229, Forwards Three Sets of Corrected Summaries of Changes for Inclusion Into Security Plan for Ja FitzPatrick Nuclear Power Plant,Rev 19 & Security Contingency Plan,Rev 5.Encls Withheld Per 10CFR73.21 & 10CFR2.790)d)(1)
JAFP-99-0228, Forwards Rept Re Changes & Errors in ECCS Evaluation Models, Per 10CFR50.46(a)(3)(ii) for Period from 980701-990630.No Commitments Contained in Submittal
JAFP-99-0208, Provides Clarification of Info Re Proposed Its, & 0601.Table Reconciling Differences,Encl
JAFP-99-0211, Monthly Operating Rept for June 1999 for Ja FitzPatrick Nuclear Power Plant.With
JAFP-99-0092, Monthly Operating Rept for Feb 1999 for Ja FitzPatrick Nuclear Power Plant.With
JAFP-99-0085, Submits in-vessel Visual Insp Summary Rept for RFO 13 for Ja FitzPatrick Nuclear Power Plant.All Relevant Indications Recorded During Insp Were Satisfactorily Dispositioned IAW Util Internal C/A Tracking Sys & Were Found Acceptable
JAFP-99-0071, Forwards Semi-Annual Radioactive Effluent Release Rept for Period of 980701-1231. Format Used for Effluent Data Is Outlined in App B of Reg Guide 1.21,Rev 1.Distribution Is IAW Reg Guide 10.1,Rev 4
JAFP-99-0068, Forwards Form NRC-5 Equivalent Records of All Individuals Monitored at JAFNPP from 980101-1231 on Electronic Media, Per 10CFR20.2206(b) & App a of NRC Reg Guide 8.7, Instruction for Recording & Reporting..
JAFP-99-0171, Forwards Revised Ja FitzPatrick Nuclear Power Plant 1999 FSAR Update. Update Also Includes Changes to Chapter 17, QA Program Which Described in Attachment 1.No Commitments Contained in Ltr
JAFP-99-0073, Submits Annual Rept on SRV Challenges & Failures,Per Plant TS 6.9.A.2.b.No Challenges to SRVs from Automatic Control Circuits or from RCS Pressure Transients,Occurred.Ltr Contains No New Commitments
JAFP-99-0166, Monthly Operating Rept for Apr 1999 for Ja FitzPatrick Nuclear Plant.With
JAFP-99-0160, Forwards 1998 Annual Radiological Environ Operating Rept for Ja FitzPatrick Nuclear Power Plant. Distribution for Rept Is IAW Reg Guide 10.1,Rev 4
JAFP-99-0142, Monthly Operating Rept for Mar 1999 for Ja FitzPatrick Nuclear Power Plant.With
JAFP-99-0129, Submits Comments on Technical Review of Draft Info Notice Describing Unanticipated Reactor Water Draindown at Quad Cities Unit 2,ANO & FitzPatrick
JAFP-99-0127, Forwards Affidavit Signed by Holtec Which Describes Proprietary Nature of Licensing Rept & Addresses Considerations Listed in 10CFR2.790.Attachment 4 in Util Re Design Features Should Be Withheld
JAFP-99-0125, Forwards Rev 5 to JAFNPP Security Contingency Plan,Which Enhances Requirements of 10CFR73.55.Changes Do Not Decrease Effectiveness of Plan.Plan Withheld IAW 10CFR73.21 & 2.790(d)(1)
JAFP-99-0124, Forwards Rev 19 to JAFNPP Security Plan,Which Enhances Requirements of 10CFR73.55.Changes Do Not Decrease Safeguards Effectiveness of Plan.Plan Withheld IAW 10CFR73.21 & 2.790(d)(1)
JAFP-99-0097, Forwards JAFNPP Referenced Simulation Facility Four Year Performance Testing Rept, Containing Description of Performance Testing Completed During Past Four Years & Description of Testing Scheduled During Next Four Years
JAFP-98-0078, Forwards Semi-Annual Radioactive Effluent Release Rept, for July-Dec 1997 & Amend to Table 3B, Solid Waste & Irradiated Fuel Shipments for Semi-Annual Radioactive Effluent Release Rept for Jan-June 1997
JAFP-98-0075, Documents Safety Relief Valve Challenges & Failures for CY97
JAFP-98-0074, Responds to NRC Re Violations Noted in Insp Rept 50-333/97-08 on 971027-1221.Corrective Actions:Operations Manager Has Reviewed Results of Root Cause Evaluation W/ Operations Shift Personnel
JAFP-97-0474, Monthly Operating Rept for Nov 1997 for Ja FitzPatrick Nuclear Power Plant
JAFP-98-0046, Forwards Revised Amend to DPR-59,revising TS Table 3.2-2 & 4.2-2, Core & Containment Cooling Sys Initiation & Control Instrumentation Operability Requirements. W/Revised TS Pages & Safety Evaluation
JAFP-98-0041, Forwards 1997 Personnel Radiation Exposure Summary Rept, for Jfnpp.Total Collective Station Dose Was 89.68 person- Rem.Summary Accounts for 98.43% of Total Dose
JAFP-98-0058, Monthly Operating Rept for Jan 1998 for Ja FitzPatrick Nuclear Power Plant
JAFP-99-0019, Informs of Licensee Intent to Upgrade ERDS at Ja FitzPatrick in Preparation for Year 2000 (Y2K) Readiness,Per GL 98-01. Encl Contains Brief Summary of Proposed Changes to ERDS
JAFP-99-0012, Documents Util Position Re Methodology for LPRM Calibr During Reactor Operation Using Traversing In-core Probe Sys
JAFP-99-0011, Monthly Operating Rept for Dec 1998 for Ja FitzPatrick Nuclear Power Plant.With
JAFP-97-0435, Monthly Operating Rept for Oct 1997 for Ja FitzPatrick Nuclear Power Plant
JAFP-98-0009, Monthly Operating Rept for Dec 1997 for Ja FitzPatrick Nuclear Power Plant
JAFP-97-0500, Notifies Commission of Change in Commitment Made to NRC That Amplified Requirement of TS Amend 148 Which Clarified Use of Terms Demonstrate & Verify Used Throughout TS to Specify Requirements of Various Surveillance Tests
JAFP-97-0325, Forwards Response to Recent Request for Addl Info Pertaining to Proposed TS Amend to Delete Requirements for Plant PORC to Review Fire Protection Program & Implementing Procedures
JAFP-98-0404, Forwards Rev 7 to COLR Cycle 14, Per Requirements of TS Section 6.9.A.4.d.Rev Contains Core Operating Limits Applicable for Next Operating Cycle,Reload 13/cycle 14
JAFP-98-0396, Monthly Operating Rept for Nov 1998 for Ja FitzPatrick Npp. with
JAFP-97-0491, Responds to NRC Re Violations Noted in Insp Rept 50-333/97-07.Corrective Actions:Generated Work Requests, Completed Oil Replacement on Pumps 10P-2A,20P-4 & 20P-8 & Contacted Equipment Manufacturers Re Using Wrong Oil
JAFP-98-0385, Revised Application for Amend to License DPR-59,revising Design Features.Rev 7 to non-proprietary & Proprietary Versions of HI-971661, Licensing Rept for Reracking of Ja FitzPatrick SFP, Encl.Proprietary Info Withheld
JAFP-99-0114, Requests That License OP-11037,for Bs Brooks,Be re-issued Without Restriction for Corrective Lenses.Nrc Form 369,encl. Without Encl
JAFP-97-0251, Submits Response to Violations Noted in in Rept 50-333/97-04 on 970525.Corrective Actions:Individual Decontaminated & interviewed,follow-up Contamination Surveys Performed & Individual Placed on Radiological Hold
JAFP-98-0370, Informs That F Aldrich Is No Longer Employed at Pasn & No Longer Needs to Maintain License.Termination of Senior Reactor Operator License (SOP-11215),is Requested
JAFP-99-0181, Monthly Operating Rept for May 1999 for Jafnpp.With
JAFP-98-0365, Submits Response to NRC Request for Addl Info Re Radiological Controls Insp Exit Meeting for Insp Rept 50-333/98-07.No Commitments Made by Util in Ltr
JAFP-99-0175, Annual Summary of Changes,Tests & Experiments for 1997/1998. with
JAFP-98-0360, Monthly Operating Rept for Oct 1998 for Ja FitzPatrick Nuclear Power Plant.With
JAFP-98-0352, Forwards Addl Info Re Proposed TS Amend Concerning TS Table 3.2-2, Core & Containment Cooling Sys Initiation & Control Instrumentation Operability Requirements. Explanations, Encl
JAFP-98-0353, Forwards Rev 2 to IST Program for Pumps & Valves - Third Interval Plan, for Ja FitzPatrick NPP
JAFP-98-0348, Informs NRC of Completion of Commitment Made in 980330 TS Submittal for Jafnpp.Og Line Isolation LSFT Can Be Extended to 24 Months with Lowered Field Setting Change
JAFP-98-0343, Provides Suppl Info Re Proposed Changes to TS for Slmcpr,In Response to NRC 981019 Verbal Request for Info Re Planned Core Loading for Cycle 14
JAFP-98-0337, Transmits Correction to Administrative Error Contained in Amend to TS Relocating Portions of Section 3/4.6.C from TS, Dtd 980710.Error in No Way Affected Intent of Technical Evaluation & Conclusions Remain Same
JAFP-98-0338, Forwards Response to NRC 980922 RAI Re Licensee Updated Response to GL 96-05.Summary of Util Commitments Are Contained in Attachment 2
JAFP-98-0322, Monthly Operating Rept for Sept 1998 for Ja Fitzpatrick Nuclear Power Plant.With
JAFP-98-0319, Informs That Authority Is Revising Commitment Re Surveillance on Locked Valves at Ja Fitzpatrick Nuclear Power Plant.Changes to Commitments Listed
JAFP-98-0316, Requests NRC Approval of Alternative Plan IAW 10CFR50.55a(a) (3)(i),for Reactor Pressure Vessel Shell Weld Examinations. Ltr Revises Previous Submittal
JAFP-98-0306, Forwards Response to NRC Resulting from ECCS Suction Strainer 980521 Meeting,Per NRC Bulletin 96-003.Addl Encls Contain SEs for RHR & Core Spray Systems Suction Strainer Replacements,Revised Calculation & Commitments
JAFP-98-0293, Forwards MOR for Aug 1998 for Ja FitzPatrick Nuclear Power Plant.Util Requests NRC to Correct Records Re Typo Made in Operating Status Rept for Jul 1998.Net Average Daily Power Level for 980703 Was 801 Mwe
JAFP-98-0292, Forwards Sketch Which Identifies Estimated Accessible & Inaccessible Portions of Plant Reactor Pressure Vessel Shell Welds,Which Can Be Examined Using GE Geris 2000 Exam Equipment.With One Oversize Drawing
JAFP-97-0264, Forwards Summary of Changes & Errors in ECCS Models for Period of 960628-970627,IAW 10CFR50.46(a)(3)(ii)
JAFP-97-0268, Responds to NRC Re Violations Noted in Insp Rept 50-333/97-03.Corrective Actions:Restored Improperly Withdrawn Control Rod to Original Location,Removed CRS & RO from Licensed Responsibilities & Disciplined IAW Policies
JAFP-97-0018, Responds to NRC Re Violations Noted in Insp Rept 50-333/96-07.Corrective Actions:Revoked Contract Supervisor Qualification Certification,Issued Memo Re Expectations of Contract Personnel & Completed Case Study
JAFP-97-0012, Monthly Operating Rept for Dec 1996 for Ja FitzPatrick Nuclear Power Plant
JAFP-96-0449, Submits Updated Pp Re Proposed Changes to TS Amend for Min Critical Power Ratio Safety Limit
JAFP-97-0242, Monthly Operating Rept for June 1997 for Ja FitzPatrick Nuclear Power Plant
JAFP-97-0207, Forwards UFSAR for Ja FitzPatrick Nuclear Plant.Revised Chapter 17 Fulfills Requirement in 10CFR50.54(a) to Submit Update of QA Program Description
JAFP-97-0203, Monthly Operating Rept for May 1997 for Ja FitzPatrick Npp
JAFP-97-0093, Monthly Operating Rept for Feb 1997 for James A. FitzPatrick Nuclear Power Plant
JAFP-97-0184, Informs of Missed Attendance of Licensed Operator Requalification Training That Previously Went Undetected Due to Administrative Error.List of Corrective Actions That Will Prevent Recurrence of Event,Encl
JAFP-97-0178, Monthly Operating Rept for Apr 1997 for Ja FitzPatrick Nuclear Power Plant
JAFP-97-0218, Responds to NRC Re Violations Noted in Insp Rept 50-333/97-02.Corrective Actions:Placed Shutdown Cooling in Service After Resetting Isolation Logic & Refilling & Venting Sys IAW Plant Procedures & Revised Procedure OP-13D
JAFP-97-0202, Annual Summary of Plant Changes,Tests & Experiments for 1996
JAFP-97-0162, New York Power Authority Radiological Environ Operating Rept Jan-Dec 1996 for James a Fitzpatrick Nuclear Power Plant
JAFP-97-0161, Responds to NRC Re Violations Noted in Insp Rept 50-333/97-01.Corrective Actions:Installation of Hose Clamps to Valve Air Actuators Incorporated Into Plants Temporary Mod Control Program
JAFP-97-0126, Monthly Operating Rept for Mar 1997 for JAFNPP
JAFP-97-0098, Forwards NRC Form 5 Equivalent Records for All Individuals Monitored at JAFNPP from 960101-1231,per 10CFR20.2206(b) & App a of NRC Reg Guide 8.7, Instruction for Recording & Reporting Occupational Radiation. W/O Encl
JAFP-97-0090, Forwards Cycle 13 Start-Up Test Rept for Jafnpp,Which Was Submitted IAW Reporting Requirements of Section 6.3.a.1 of Plant TS
JAFP-97-0083, Forwards Response to NRC RAI Re Bulletin 96-002, Movement of Dry Storage Casks Over Spent Fuel,Fuel in Reactor Core or Safety-Related Equipment
JAFP-97-0085, Responds to NRC Re Violations Noted in Insp Rept 50-333/96-08.Corrective Actions:Operating Procedures OP-13 & OP-13B Have Been Revised to Include Precaution Statements Re Potential for Water Hammer & Equipment Damage
JAFP-97-0073, Forwards Semi-Annual Radioactive Effluent Release Rept for Period of 960701-1231 & Rev 4 to Radiological Effluent Controls & Odcm
JAFP-96-0484, Forwards Description of Summary of Changes to Jfnpp Security Plan.Encl Withheld
JAFP-97-0062, Forwards Comments Re Draft NRC Info Notice 97-XX, Potential Failures of GE Magne-Blast Circuit Breaker Subcomponents & Draft Notice
JAFP-97-0067, Documents Safety Relief Valves Challenges & Failures for CY96,per TS 6.9.A2.b & LERs 96-010 & 96-004
JAFP-96-0476, Monthly Operating Rept for Nov 1996 for James A. FitzPatrick Nuclear Power Plant
JAFP-96-0474, Responds to NRC Re Violations Noted in Insp Rept 50-333/96-06.Corrective Action:Training on Procedure Changes Was Conducted with Plant Staff
JAFP-96-0470, Forwards Revised Response to RAI Re Porous Concrete sub-foundation
JAFP-97-0061, Submits Rev to Previous Response to NOV Noted in Insp Rept 50-333/96-07 on 960929-1116.Corrective Actions:Team of Line Personnel Formed to Evaluate Human Performance Related to Events at Site & Develop Improvement Plan
JAFP-97-0063, 1996 Personnel Radiation Exposure Summary Rept
JAFP-96-0450, Submits Response to Request for Addl Info Re Porous Concrete sub-foundation
JAFP-96-0448, Monthly Operating Rept for Oct 1996 for Ja FitzPatrick Nuclear Power Plant
JAFP-96-0439, Submit 180 Day Response to NRC Bulletin 96-003, Potential Plugging of ECC Suction Strainers by Debris in Bwrs
JAFP-97-0028, Responds to NRC Bulletin 95-002 Re ECCS Suction Strainer Insp Results
JAFP-96-0426, Forwards Update TS Page Changes to Support Issuance of TS Amends for Ltrs & 960815
JAFP-96-0378, Forwards Proprietary & Nonproprietary NEDC-32616, Ja FitzPatrick Nuclear Power Plant ATWS Analysis for Recirculation Pump Trip (RPT) Setpoint Changes. GE Signed Affidavit Encl.Proprietary NEDC-32616P Withheld
JAFP-96-0379, Forwards Addl Info Re Proposed Amend to TSs Re Inservice Leak & Hydrostatic Testing Operation,Per NRC Request in Recent Telcons
JAFP-96-0377, Responds to NRC Re Violations Noted in Insp Rept 50-333/96-05.Corrective Actions:Briefed Managers on Tech Spec Requirements Re Overtime Limits & Revised Administrative Procedure AP-11.03, Control of Overtime
JAFP-96-0401, Monthly Operating Rept for Sept 1996 for Jfnpp
JAFP-96-0391, Provides Supplemental Info Re Updated Page Changes for Proposed Change to TS Concerning Power Uprate
JAFP-96-0352, Monthly Operating Rept for Aug 1996 for Ja FitzPatrick Nuclear Power Plant
JAFP-96-0336, Forwards Attachment Ii,Rev 1 to JPN-96-003, Instrumentation & Miscellaneous Sys Se. Changes Made by Rev,Submitted
JAFP-96-0200, Responds to NRC Bulletin 96-002, Movement of Heavy Loads Over Spent Fuel,Over Fuel in Reactor Core or Over Safety-Related Equipment,
JAFP-96-0300, Monthly Operating Rept for Jul 1996 for Ja FitzPatrick Nuclear Power Plant
JAFP-96-0291, Informs of Util Intent to Install Alternate Dhrs at Plant in Advance of Refueling Outage 12,scheduled to Commence in Oct 1996.Info Encl Provides Details of Sys Design & Safety Considerations Pertinent to Sys Installation & Testing
JAFP-96-0275, Monthly Operating Rept for June 1996 for Ja FitzPatrick Nuclear Power Plant
JAFP-96-0240, Monthly Operating Rept for May 1996 for Ja FitzPatrick Nuclear Power Plant
JAFP-96-0226, Forwards Response to Violations Noted in Insp Rept 50-333/96-02.Corrective Actions:Programmatic Assessment Performed on Foreign Matl Exclusion Program
JAFP-96-0224, Responds to NRC Re Violations Noted in Insp Rept 50-333/96-05.Corrective Actions:Project Manager Escorted Off Site & Security Badge Voided,Visitor Access Privileges Rescinded & Evaluation Performed Re Security Records
JAFP-96-0196, Monthly Operating Status Rept for Apr 1996 for Ja FitzPatrick Nuclear Power Plant
JAFP-96-0190, Ja FitzPatrick Nuclear Power Plant,Radiological Environ Operating Rept for 1995
JAFP-96-0168, Annual Summary of Changes,Tests & Experiments for 1995. W/
JAFP-96-0156, Monthly Operating Rept for Mar 1996 for Ja FitzPatrick Nuclear Power Plant
JAFP-96-0113, Monthly Operating Rept for Feb 1996 for Ja FitzPatrick Nuclear Power Plant
JAFP-96-0127, Informs That on 960221,util Identified Urine Blind Test Specimen Positive Result That Had Been Incorrectly Reported as Negative.Util Begun Contract Prerequisites to Convert to Different Health & Human Svcs Certified Testing Lab
JAFP-97-0444, Informs That Attachment 1 to Ltr Should Be Used as Basis for Staff Review of Request for NRC Review & Concurrence of Exception to RG 1.97 Requirements.Attachment Corrects Info Re Incorrect Statement Made in Request
JAFP-99-0168, Forwards Eight Operator License Renewal Applications for Listed Individuals.Without Encls
JAFP-98-0351, Forwards Four Operator License Renewal Application for Listed Individuals.Certification of Medical Exam Is Included as Attachment to Each Application.Without Encl
JAFP-98-0186, Responds to Joint Owners Group (JOG) Program SE on Periodic Verification of MOVs in Response to GL 96-05.Util Plans to Continue Participating in JOG MOV Program as Member of BWROG & Will Implement Elements Noted in Rev 2 to TR NEDC-3271
05000333/LER-1998-006, :on 980708,missed Pressure Testing of Pressure Isolation Valves Was Noted.Caused by Inadequate Implementation of Pressure Testing Requirements.Valves Were Pressure Tested & Test Results Were Adequate
05000333/LER-1999-008-01, :on 990910,HPCI Sys Was Declared Inoperable Due to Apparent Failure of Master Trip Unit (MTU) within HPCI Sys Automatice Isolation Logic.Subject MTU Was Replaced & HPCI Sys Was Returned to Operable Status.With
05000333/LER-1999-007-01, :on 990809,both a & B Division of CS Pump Start Interlock Relays Exceeded Values Required by Ts.Caused by Inappropriate as-left Calibr Tolerance for Time Delay Relays.Relays Were Immediately Recalibr.With
05000333/LER-1999-006-01, :on 990609,LCPI Mode of RHR Sys Was Inoperable. Caused by Loss of Automatic Startup Capability of RHR Pumps. Repaired Defective Fuse Contact & Conducted Equipment Failure Evaluation.With
05000333/LER-1999-005-01, :on 990506,missed Surveillance Test Was Noted. Caused by Inoperable Containment Hydrogen/Oxygen Analyzer. Counseled Personnel Involved & Revised Procedures.With
05000333/LER-1999-002, :on 990113,discovered That Suppression Chamber RB Vacuum Breaker Isolation Valve Differential Pressure Switches Were Out of Tolerance Due to Incorrect Assumption in Calculation.Calibr Pressure Switches.With
05000333/LER-1999-001-01, Forwards LER 99-001-01 Re Incorrect EDG line-up During Fire Placing Plant in Outside Design Basis.Suppl Contains Results of Completed Root Cause Evaluations & Subsequent Corrective Actions Taken.Rept Contains No Commitments
05000333/LER-1998-001, :on 980128,invalid Isolations of Reactor Building Ventilation & Associated Actions,Occurred.Cause Not Determined.Revised Procedure ODSO-34 to Ensure That Prior Independent Reviews of TS Performed
05000333/LER-1997-012, :on 971214,drywall Personnel Airlock Outer Door Seals Local Leak Rate Test Was Not Properly Performed.Caused by Mechanic Installing Incorrect Label.Removed Incorrect Label & Installing Correct Label
05000333/LER-1997-012-01, :on 971214,drywell Personnel Airlock Outer Door Seals Local Leak Rate Test Was Not Properly Performed.Caused by Inattention to Detail on Part of Mechanic Who Installed Label.Removed Incorrect Label
05000333/LER-1998-013, :on 981117,containment Leakage Rate Exceeds Authorized Limits,Was Determined.Caused by Valve Sealing Failure.Failed Valves Repaired & Retested Satisfactorily Prior to Plant Startup
05000333/LER-1998-014, :on 981117,trip of RPS Power Supply & ESF Actuation Occurred.Caused by Relay Failure.Relay Was Replaced & Motor Was Restarted Satisfactorily.With
05000333/LER-1998-012, :on 981104,failure to Meet Primary Containment Leakage Rate Testing Program Requirements Was Noted.Caused by Deficient Test Procedures.Leak Rate Test Procedures Were Revised & Testing Was Completed.With
05000333/LER-1997-006-01, :on 970616,discovered That Instrumentation Isolation Trip Function Surveillance Test Had Not Been Performed at Required Frequency.Caused by Personnel Error. Completed Surveillance Test
05000333/LER-1999-004-01, :on 990403,two Electrical Leads in 09-30 Panel in Relay Room Were Found Unlanded.Caused by Inattention to Detail & Inadequate Process to Ensure Complete Protective Tag.Performed Extent of Condition Walkdowns.With
05000333/LER-1998-011, :on 980929,failure to Meet Drywell Continuous Atmosphere Monitoring Sys TS Surveillance Test Requirements Were Noted.Caused by Deficient Tp.Declared Both Channels of CAM Sys Inoperable.With
05000333/LER-1998-009, :on 980807,error in Exclusion Region of Power Flow Map Was Noted.Caused by Lack of Explicit Procedure on How to Perform Analysis.Revised Vendor Procedure That Is Used to Produce Option 1-D Exclusion Region.With
05000333/LER-1998-010, :on 980813,primary Containment Electrical Penetration Was Noted Inoperable Under Postulated Conditions.Caused by Inadequate Plant Design.Added Second Primary Overcurrent Protective Device.With
05000333/LER-1998-008, :on 980803,automatic Reactor Scram Occurred Due to Low RPV Water Level Following Degradation in Feedwater Flow.Completed Post Transient Evaluation Prior to Startup & Correcting Filling & Venting Procedure
05000333/LER-1998-007, :on 980731,HPCI Was Declared Inoperable Due to DC Ground on B Station Battery Bus.Caused by Inadequate Managerial Methods.Initiated Work Request to Inspect,Clean Meggar & Return Bus to Operable Condition
05000333/LER-1997-004-01, :on 970428,safety Relief Valve Failed to Open During Setpoint Verification Testing.Caused by Presence of Small Screw.Revised Target-Rock 2-Stage SRV Assembly Test Procedures,Reported Per 10CFR21
05000333/LER-1996-010-01, Forwards LER 96-010-01,plant Shut Down Due to Human Error Re Inadvertently Connecting Two Terminals While Calibrating Protective Relay.Revises Rept to Include Corrective Action for Human Performance Deficiencies.W/Status of
05000333/LER-1997-003, :on 970213,identified Potential Overpressurization of Containment Penetrations Due to Thermal Expansion.Caused by Original Plant Design.Completed Operability Determinations IAW GL 91-18
05000333/LER-1996-011-01, :on 961028,both Standby Liquid Control Subsystems Determined Inoperable.Due to Inoperable Pump Discharge Pressure Relief Valves.Slc Sys Pump Discharge Pressure Relief Valve 11SV-39A Was Replaced
05000333/LER-1997-002, :on 970124,shutdown Cooling Isolation Occurred. Caused by Pressure Transient.Placed Shutdown Cooling in Service After Resetting Isolation Logic & Refilling & Venting Sys
05000333/LER-1996-015-01, :on 961218,determined Bypass Flow Path Around Offgas Isolation Valve.Caused by Design Deficiency.Installed Check Valve in Common Drain Line to Prevent Reverse Flow from Steam Jet Air Ejector Discharge
05000333/LER-1996-014, :on 961215,manual Scram Occurred Due to Leak in Main Turbine electro-hydraulic Control Sys.Failed Actuator Seal Was Repaired & Equipment Failure Evaluation of 29BPV-4 Actuator Seal Was Completed
05000333/LER-1996-013-01, :on 961116,reactor Protection & Primary Containment Isolation Sys Actuation on False Low Reactor Water Level Occurred Due to Personnel Error.Instrument Surveillance Procedure Changed
05000333/LER-1996-012-01, :on 961111,primary Containment Accumulative Leakage in Excess of Maximum Allowed by TS Occurred.Caused by Build Up on Valve Seat Areas.Efes Were Completed for Each Failed Valve
05000333/LER-1996-008-01, :on 960906,HPCI Sys Declared Inoperable Due to Failed DC to AC Power Inverter.Failed C11 Capacitor Located in HPCI Inverter 23INV-79 Replaced
05000333/LER-1996-006-01, :on 960511,isolation of Reactor Core Isolation Cooling Sys Occurred.Caused by Failure of Master Trip Unit. Master Trip Unit Replaced W/Vendor Current Model
05000333/LER-1996-009-01, :on 960722,EDG B Failed to Complete Startup Sequence.Caused by Incorrect Installation of Agastat Relays. Calibr & Placed Devices 93-62-1EDGB01,93-62-1EDGB12 & 93-52A-1EDGB01 in Correct Locations
05000333/LER-1996-007-01, :on 960522,sys Isolations & Standby Gas Treatment Initiation Occurred.Caused by False High Radiation Trip Signal.Detector Replaced W/Vendor Current Model
05000333/LER-1996-005-01, :on 960506,error in Safety Limit Minimum Critical Power Ratio (MCPR) Calculation Occurred.Caused by Error in Calculation of Methodology.Administrative Controls Re Operating MCPR Instituted
05000333/LER-1996-002-01, :on 960212,potential Common Mode Failure of Circuit Breakers in Both Safety Divisions Occurred Due to Design or Installation Error.Replaced Contacts in Failed Circuit Breakers
05000333/LER-1996-004-01, :on 960228,multiple SRV Pilot Solenoid Failed Due to Foreign Matls,Vendor Deficiencies & Procedural Errors.Replaced Pilot Solenoid Valve W/Another Rebuilt Assembly
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
JAFP-96-0441, Confirms That Util Will Perform Evaluations for Plant Per GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions
JAFP-13-0056, Entergys 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
05000333/LER-2013-001, Regarding Failed Under Voltage Relay Results in Auto Start of the Emergency Diesel Generators
JAFP-13-0024, Entergy’S Overall Integrated Plan in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents (Order Number EA-12-050)
05000333/LER-2012-008, Regarding Automatic Reactor Shutdown Caused by a Fault in Main Transformer
05000333/LER-2012-007, Regarding Reactor Scram Caused by Main Turbine Emergency Trip Lockout Valve Failure
05000333/LER-2012-006, Loss of Safety Function for RHR Shutdown Cooling Isolation Function Due to Reference Leg Leakage During Maintenance
05000333/LER-2012-005, Regarding Transformer Installation Error Causes Loss of Off-Site Power
05000333/LER-2012-004, Regarding Control Rods Inoperable While Entering Plant Outage
05000333/LER-2012-003, High Pressure Coolant Injection System Inoperable Due to Air in Flow Element Sensing Line
05000333/LER-2012-002, Regarding High Pressure Coolant Injection Pressure Control Valve Failure
JAFP-12-0075, Entergys 120-Day Response to NRC Request for Information (RFI) Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights
05000333/LER-2012-001, Regarding Unit Cooler Fan Motor Contractor Low Voltage Test Failure Results in Loss of Safety Function and Condition Prohibited by the Technical Specifications
JAFP-12-0037, Entergy Nuclear Operations, Incorporated’S Answer to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents (Order Number EA-12-050)
05000333/LER-2010-005-01, Regarding High Pressure Coolant Injection System Declared Inoperable Due to Power Supply Degradation
05000271/LER-2011-001, Inoperability of the High Pressure Coolant Injection System Due to Failure to Follow Procedures
05000271/LER-2010-002, For Vermont Yankee Nuclear Power Station, Regarding Inoperability of Main Steam Safety Relief Valves Due to Degraded Thread Seals
05000271/LER-2010-001, Regarding Automatic Reactor Trip Due to Switchyard Current Transformer Problem
BVY 10-011, Special Report for Tritium Discovered Onsite Vermont Yankee Nuclear Power Station
05000298/LER-2007-007, Re Damaged Lead on Emergency Filter System Fan Motor Results in Loss of Safety Function
05000298/LER-2007-006, Procedural Guidance Leads to Rendering Second Diesel Generator Inoperable
05000298/LER-2007-005, Inadequate Post Fire Procedure Could Have Prevented Achieving Safe Shutdown
05000298/LER-2007-004, Re Manual Reactor Trip Due to Hydraulic Control Unit Valve Bonnet Leak Into Reactor Building
05000298/LER-2007-003, Regarding Incorrectly Installed Fuse Block Resulted in a Condition Prohibited by Technical Specifications
05000298/LER-2007-002, Re Technical Specification Prohibited Operation Due to Safety Relief Valve Test Failure
05000298/LER-2007-001, Regarding High Pressure Coolant Injection Inverter Circuit Failure Results in Loss of Safety Function
JAFP-00-0276, Secy-00-0238-Attachment 5 - Oswego County and New York State Participation in James A. FitzPatricks (Jafs) Emergency Plan
JAFP-00-0270, Secy-00-0238-Attachment 3 - Oswego County and New York State Participation in James A. FitzPatricks (Jafs) Emergency Plan
JAFP-96-0343, Informs That New York Power Authority Has Completed Review of Plant Heavy Load Program to Ensure Compliance W/Clb & Regulatory Guidelines.Results Confirm That Heavy Load Movements Will Continue to Be Performed within CLB
NRC-2012-0068, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events
NRC-2012-0067, Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Effective Immediately) - to All Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status
NRC-2012-0069, Order Modifying Licenses with Regard to Reliable Hardened Containment Vents - to All Operating Boiling Water Reactor Licensees with Mark I and Mark Ii Containments