HL-5758, Forwards Response to NRC 990129 RAI Re GL 96-05 Program at Ei Hatch Nuclear Plant
HL-5777, Notifies NRC That Exam Coverage for One Weld Exceeded Criteria for Plant.Reasons for Exam Coverage Being Less than Initially Estimated as Listed
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HL-5785, Forwards New Relief Requests RR-V-16 for Third 10-yr Interval Inservice Testing Program for Ei Hatch Nuclear Plant.Relief Request Was Developed to Propose Alternate Schedule for Replacement of HPCI Rupture Disks
HL-5763, Informs That Util Is Changing Responsibility for Periodic Concerns Program Review,Per Insp Repts 50-321/95-12 & 50-366/95-12.Reviews Will Now Be Performed Under Direction of Vice President & Corporate Counsel
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HL-5790, Responds to NRC RAI Re GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants
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HL-5796, Forwards Response to NRC 990331 Request for Supplemental Info Re SNC Earlier GL 95-07 Responses.Gl 95-07 Evaluation Sheets for Units 1 & 2 RHR Torus Spray Isolation Valves Are Encl
HL-5804, Informs NRC That on or After 991018,SNOC Plans to Begin Storing Spent Fuel in Ei Hatch ISFSI IAW General License Issued,Per 10CFR72.210
HL-5801, Forwards New Relief Requests for Third 10-Yr Interval ISI Program for Ei Hatch Nuclear Plant.New Relief Requests RR-25 & RR-26 Were Developed to Propose Alternate Repair Techniques IAW ASME Code N-562 & N-561,respectively
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HL-5807, Estimates That Seventeen (17) Submittals Will Be Made During Fy 2000 & Two (2) Submittals Will Be Made During Fy 2001,in Response to Administative Ltr 99-02, Operating Reactor Licensing Action Estimates
HL-5810, Forwards Rev 17B to Ei Hatch FSAR & Rev 14B to Fire Hazards Analysis & Fire Protection Program, for Plant.Encls Reflect Changes Made Since Previous Submittal.With Instructions
HL-5808, Forwards Ei Hatch Nuclear Plant,Unit 1 Extended Power Uprate Startup Test Rept for Cycle 19. Rept Summarizes Startup Testing Performed on Unit 1 Following Implementation of Extended Uprate During Eighteenth Refueling Outage
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HL-5814, Forwards New Relief Requests for Third 10-year Interval Inservice Insp Program for Ei Hatch Nuclear Plant.New Relief Requests Were Developed to Propose Alternate Insps & to Allow Use of ASME Code Cases N-605,N-508-1,N-323-1 & N-528
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HL-5824, Requests Exemption from Expedited Implementation Requirements of Paragraph 10CFR50.55a(g)(6)(ii)(B) as Applicable to Containment General Visual Exams of Subsection Iwe,Table IWE-2500-1,Category E-A,Item E1.11
HL-5788, Forwards Owner Activity Repts,Form OAR-1 for Ei Hatch Nuclear Plant for First Period of Third 10-yr Interval ISI Program.Repts Are for Unit 2 Refueling Outages 13 & 14
HL-5827, Forwards Fitness for Duty Performance Data for six-month Reporting period,Jan-June 1999,as Required by 10CFR26.71(d)
HL-5825, Forwards Response to Informal NRC RAI Re Proposed Emergency Actions Levels Associated with Independent Spent Fuel Storage Operations
HL-5837, Informs That Recent Evaluation of Inservice Testing Program Activities Has Resulted in Requirement for Snoc to Revise Two Existing Requests for Relief,Withdraw One Request for Relief & Revise One Existing Cold SD Justification
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HL-5839, Forwards Three New & One Revised Relief Requests for Third 10-year Interval ISI Program for Plant,Developed to Clarify Documentation Requirements,To Propose Alternate Exam Requirements IAW ASME Code Cases N-598 & N-573
HL-5708, Provides Updated Response to RAI for GL 96-06, Waterhammer in Containment Coolers
HL-5710, Requests Approval of Alternative Reactor Vessel Weld Exam for Ehnp,Unit 1,per 10CFR50.55a(g)(6)(ii)(A)(5) for Permanently Excluding Exam of RPV Circumferential Shell Welds
HL-5712, Forwards Ehnp Intake Structure License Rept, to Provide Example of Technical Content & Level of Detail Planned for Application for License Renewal,For NRC Review
HL-5725, Informs That SNC Intends to Examine Approx Dozen Weld Overlays During Unit 1 Spring 1999 Outage That to Date Have Not Been Examined Three Times Since Weld Overlay Was Supplied
HL-5728, Requests That RPV Shell Weld Ultrasonic Exams Be Performed Using Techniques & Procedures,Iaw ASME Section Xi,App Viii, 1992 Edition,1993 Addendum,In Lieu of ASME Section XI,1989 Edition Exam Techniques & Procedures
HL-5729, Submits Proposed Rev to Plant QA Program as Described in Chapter 17 of Unit 2 Fsar,Per 10CFR50.54(a)(3).Rev Would Relocate to Controlled Document Other than Fsar,Units 1 & 2 Lists of SR SSC Comprising Items Covered Under QA Program
HL-5733, Forwards Rev 17A to Ei Hatch FSAR & Rev 14A to Fire Hazards Analysis & Fire Protection Program, for Plant.Encl Reflects Changes Made Since Previous Submittal.With Instructions
HL-5737, Forwards Part of Table (Table 1) Util Provided in 980728 Response to RAI for GL 92-01,Rev 1,Suppl 1,reflecting Lower Shell Axial Welds Identified as C-4-A Through C-4-C & Lower Intermediate Axial Welds Identified as C-3-A Through C-3-C
HL-5735, Provides NRC with Update Status of Progress Util Is Making Toward Development of Product That Was Originally Identified in to NRC
HL-5751, Forwards Change to Hatch EP for Review & Approval,Per Requirements of 10CFR50,App E,Section Iv.B.Bases for Proposed EALs & Statements of Agreement from State & Local Governmental Authorities
HL-5756, Submits Summary Rept of Present Level & Source of Onsite Property Damage Insurance Coverage for Ei Hatch Nuclear Plant,Units 1 & 2
HL-5757, Informs That SNC Withdraws SNC Proposed Rev to Plant Hatch QA Program Submitted 990127
HL-5753, Submits Response to Five Criteria Described in NUREG/CR-6396 Section 3.3.2.Attachment Contains Relief Request RR-P-14, Which Has Been Revised & Enhanced to Include Addl Info to Justify Proposed Alternative
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HL-5754, Forwards Ei Hatch Nuclear Plant Unit 2 Extended Power Uprate Startup Test Rept for Cycle 15, IAW Regulatory Commitments.Testing Identified No Major Problems.Startup Testing for Unit 1 Is Scheduled for Spring 1999 RFO
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HL-5750, Forwards Status of Decommissining Funding,Per Requirements 10CFR50.75(f)(1),on Behalf of Licensed Owners of Ei Hatch Nuclear Plant
HL-5758, Forwards Response to NRC 990129 RAI Re GL 96-05 Program at Ei Hatch Nuclear Plant
HL-5777, Notifies NRC That Exam Coverage for One Weld Exceeded Criteria for Plant.Reasons for Exam Coverage Being Less than Initially Estimated as Listed
HL-5785, Forwards New Relief Requests RR-V-16 for Third 10-yr Interval Inservice Testing Program for Ei Hatch Nuclear Plant.Relief Request Was Developed to Propose Alternate Schedule for Replacement of HPCI Rupture Disks
HL-5763, Informs That Util Is Changing Responsibility for Periodic Concerns Program Review,Per Insp Repts 50-321/95-12 & 50-366/95-12.Reviews Will Now Be Performed Under Direction of Vice President & Corporate Counsel
HL-5790, Responds to NRC RAI Re GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants
HL-5801, Forwards New Relief Requests for Third 10-Yr Interval ISI Program for Ei Hatch Nuclear Plant.New Relief Requests RR-25 & RR-26 Were Developed to Propose Alternate Repair Techniques IAW ASME Code N-562 & N-561,respectively
HL-5804, Informs NRC That on or After 991018,SNOC Plans to Begin Storing Spent Fuel in Ei Hatch ISFSI IAW General License Issued,Per 10CFR72.210
HL-5796, Forwards Response to NRC 990331 Request for Supplemental Info Re SNC Earlier GL 95-07 Responses.Gl 95-07 Evaluation Sheets for Units 1 & 2 RHR Torus Spray Isolation Valves Are Encl
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HL-5807, Estimates That Seventeen (17) Submittals Will Be Made During Fy 2000 & Two (2) Submittals Will Be Made During Fy 2001,in Response to Administative Ltr 99-02, Operating Reactor Licensing Action Estimates
HL-5808, Forwards Ei Hatch Nuclear Plant,Unit 1 Extended Power Uprate Startup Test Rept for Cycle 19. Rept Summarizes Startup Testing Performed on Unit 1 Following Implementation of Extended Uprate During Eighteenth Refueling Outage
HL-5810, Forwards Rev 17B to Ei Hatch FSAR & Rev 14B to Fire Hazards Analysis & Fire Protection Program, for Plant.Encls Reflect Changes Made Since Previous Submittal.With Instructions
HL-5814, Forwards New Relief Requests for Third 10-year Interval Inservice Insp Program for Ei Hatch Nuclear Plant.New Relief Requests Were Developed to Propose Alternate Insps & to Allow Use of ASME Code Cases N-605,N-508-1,N-323-1 & N-528
HL-5824, Requests Exemption from Expedited Implementation Requirements of Paragraph 10CFR50.55a(g)(6)(ii)(B) as Applicable to Containment General Visual Exams of Subsection Iwe,Table IWE-2500-1,Category E-A,Item E1.11
HL-5788, Forwards Owner Activity Repts,Form OAR-1 for Ei Hatch Nuclear Plant for First Period of Third 10-yr Interval ISI Program.Repts Are for Unit 2 Refueling Outages 13 & 14
HL-5827, Forwards Fitness for Duty Performance Data for six-month Reporting period,Jan-June 1999,as Required by 10CFR26.71(d)
HL-5825, Forwards Response to Informal NRC RAI Re Proposed Emergency Actions Levels Associated with Independent Spent Fuel Storage Operations
HL-5837, Informs That Recent Evaluation of Inservice Testing Program Activities Has Resulted in Requirement for Snoc to Revise Two Existing Requests for Relief,Withdraw One Request for Relief & Revise One Existing Cold SD Justification
HL-5839, Forwards Three New & One Revised Relief Requests for Third 10-year Interval ISI Program for Plant,Developed to Clarify Documentation Requirements,To Propose Alternate Exam Requirements IAW ASME Code Cases N-598 & N-573
ELV-01131, Provides Feedback on NRC Pilot Project Involving Electronic Distribution of NRC Generic Communications.Sys Found to Be Most Useful Re Generic Ltrs & Bulletins Where Timely Receipt Critical
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HL-1003, Responds to Generic Ltr 89-19 Re Safety Implementation of Control Sys in LWR Nuclear Power Plants,Per 890920 Request & Understands That NRC Has Agreed to Extend Response Deadline Until 900504
HL-1043, Responds to NRC Bulletin 90-002 Re Loss of Thermal Margin Caused by Channel Box Bow.Procedure Rev Currently in Validation Process at Plant Placing Cautionary Note in Procedure for Channeling Bundles
HL-1056, Forwards Results of 900411,13 & 16 Telcons & Provides Addl Info & Justification Requested by NRC Re Insp of IGSCC Susceptible Welds,Per Generic Ltr 88-01 & Rev 2 to NUREG-0313.Proposed Weld Overlay Designs Also Encl
HL-1053, Provides Response to Generic Ltr 89-19, Safety Implication of Control Sys in LWR Nuclear Power Plants. Plant Procedures Address Possibility of Vessel Overfill Events & Training Alert Operators to Potential Overfills
HL-1082, Forwards Response to NRC Re Violations Noted in Insp Repts 50-321/90-07 & 50-366/90-07.Encl Withheld (Ref 10CFR73.21)
HL-1019, Submits Certification That Operator Licensing Simulation Facility Located at Plant Meets NRC Requirements
HL-1125, Forwards Rev 0 to Core Operating Limits Rept for Operating Cycle 13, Per Amend 168 to License DPR-57
HL-1158, Forwards Rev 0 to SIR-90-039, Flaw Evaluation & Weld Overlay Designs for Ei Hatch Unit 1 Spring 1990 Refueling Outage. Rept Details IGSCC Exam Results,Weld Overlay Design & Evaluation of Weld Shrinkage Stresses
HL-1035, Forwards Nuclear Decommissioning Funding Plan for Plant,Per 10CFR50.75(b) & 33(k).Reasonable Assurance That NRC Prescribed Min Funding Will Be Available to Decommission Each Unit on Current Expiration Date Exists
HL-1215, Informs of Implementation of Amend 169 to Facility Tech Specs
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HL-1245, Forwards Fitness for Duty Performance Data for First Six Month Reporting Period,Per 10CFR26.71d
HL-1250, Forwards Post-Refueling Outage Startup Test Rept,Unit 1 Cycle 13, Per Tech Spec 6.9.1.1.Rept Presents Static & Dynamic Functional Core Tests Performed During Startup from Spring 1990 Maint/Refueling Outage
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HL-1183, Forwards Owners Data Rept for Inservice Insp Ei Hatch Nuclear Plant Unit 1 Feb-June 1990
HL-1237, Requests Permission to Use Facility Reactor Bldg Crane to Move Large Shipping Casks,Per Tech Spec 3.10.F.1 & 4.10.F.1
HL-1278, Responds to NRC Re Violations Noted in Insp Repts 50-321/90-15 & 50-366/90-15.Corrective Actions: Mispositioned Valves 1E21-F025B & 1E21-F027B Placed in Correct Positions & Technicians Disciplined
HL-1176, Forwards Updated Listing of Outstanding Licensing Requests for Plant,Tabulated Chronologically by Util Submittal Date
PLANT E. I. HATCH Licensee Event Report Docket No. 50-321 United States Nuclear Regulatory Commission Office of Inspection and Enforcement Region II Suite 3100 101 Marietta Street Atlanta, Georgia 30303 O
ATTENTION: Mr. James P. O'Reilly Pursuant to Section 6.9.1.8.i of Hatch Unit I Technical Specifications, please find attached Reportable Occurrence Report No. 50-321/1981-001.
/03L-0:on 810102,during Refueling,Drywell Isolation Valve 2T48/F209 Found Leaking When LLRT Performed on Drywell to Torus Dp Sys.Caused by Scratches on Valve Seat Due to Valve Closing on Debris
/03L-0:on 810106,reactor Core Isolation Cooling Steamline Pressure Switches 2E51-NO19A & C Were Found to Actuate Below Tech Spec Limits.Caused by Setpoint Drift. Switches Recalibr
/03L-0:on 810101,more than 5 Gpm Leaked Into Drywell W/Reactor at 401 Mwe.Caused by Mechanical Seal Leaking Water from Reactor Recirculation pump,1B31-C001A. Seal Replaced
/03L-0:on 810130,HPCI Governor Valve Stuck Open. Caused by Lift Rod Being Bent & Galled Due to Interference Between Lift Rod Fork Connector & Valve Lever.Damaged Rod Replaced,Upper Guide Bushing Honed & Fork Modified
/03L-0:on 810223,core Max Fraction of Limiting Power Density Found to Be Greater than Frtp During Startup. Caused by Time Delays for Adjusting Rods,Running Transient Incore Probe Scans & Processing Time for Computer
/03L-0:on 810106,w/unit in Steady State Power Operation,Qa Audit Showed That Temporary Procedure Change HNP-818 Was Not Approved by Plant Manager within 14 Days of Implementation.Caused by Deletion of Requirement
/03L-0:on 810122,nozzle Loads Found Exceeding Vendor Allowables for Reactor Core Isolation Cooling Steam Turbine During Reanalysis of Piping & Hangers Per IE Bulletin 79-14.Caused by Ae Error in Sys Design
/03L-0:on 810113,during Steady State Operation, Drywell Temp Recorder IT47-R612 Found to Be Inoperative. Caused by Misalignment of Cam Follower Contact W/Main Programming Cam.Follower Adjusted to Maintain Contact W/Cam
/03L-0:on 810123,standby Gas Treatment Sys Filter train,2T46-D001A,removed Less Halogenated Hydrocarbon Refrigerant Gas than Required by Tech Specs During Testing by Vendor.Caused by Defective Charcoal in Filter Bed
/03L-0:on 810203 & 19,unit 1 Cable Spread Room Sprinkler Sys Was Inoperable for Period Greater than 14 Days & Special Repts Were Not Issued.Caused by Personnel Error. Personnel Reinstructed
/03L-0:on 810126,discovered That on 810124 & 25 Reactor Coolant Sampled from Wrong Sample Line.Caused by Lack of Communication Among Personnel Who Collect & Analyze Reactor Coolant.Personnel Instructed & Coolant Sampled
/03L-0:on 810216,in Normal Operations at 309 Mwt, 1E51-N012A,B,C & D Actuated at 10.2,11.3,11.2 & 10.7 Psig, Respectively.Caused by Switch Setpoint Drift.Barksdale Switches Recalibr
/03L-0:on 810206,nitrogen Storage Tank Inventory Went Below 2000 Gallon Tech Spec Requirement.Caused by Supplier Delaying Shipment.Shipment Received.Supplier Instructed Not to Delay Shipments
/03L-0:on 810212,reactor Coolant Not Analyzed Once Per 24-h as Required by Tech Spec.Caused by Reactor Vessel Hydro During Time Period When Next Conductivity Measurement Was to Be Taken
/03L-0:on 810222,reactor Core Isolation Cooling Auto Flow Controller Did Not Control Turbine Properly While in Auto Position During Quickstart Test.Caused by Loose Ribbon Connector on Flow Control M-4 Station
/03L-0:on 810214,liquid Radwaste Sample Tank, WSTB1,discharged Prior to Analysis,Contrary to Ets.Caused by Technician Error in Collecting Unit 2 Radwaste Sample in Prelabeled Unit 1 WSTB-1 Bottle
/03L-0:on 810204,nonrated Window Discovered in 3-h Rated Fire Wall.Caused by Design,Mfg & Const/Installation Error.Direct Conversion Reactor Study 81-48 Submitted & Fire Watch Established
/03L-0:on 810228,turbine Failed to Trip on Overspeed.Caused by Dried Lubrication Around Overspeed Tripping Mechanisms Causing Binding.Mechanism Disassembled, Cleaned,Relubricated & Reassembled
/02L-0:on 810224,during Surveillance Testing, Standby Liquid Control Pump B Failed to Start,Losing Squibb Valve B Continuity.Caused by Failure of Control Fuse in Circuit Breaker.Fuse Replaced
/03L-0:on 810228,HPCI Sys Was Declared Inoperable When Oil Line Near Rear Bearing Broke.Caused by Person Stepping on Oil Line & Turbine Vibration Finishing Separation.Line Repaired