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LER-1981-031, /01T-0:on 810415,notified by Scsi That Wall C130-39 in Plant Control Bldg Had Local Stress Exceeding Design Allowables.Caused by More Conservative Stress Criteria in Ieb 80-11 than in Original Design |
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| 3211981031R01 - NRC Website |
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60 68 DOCKET NUMOER 60 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h l0 l 2 l lon 4-15-81, with Unit 1 in the refueling mode and the Unit 2 reactor in l i o i3, inormal power operation at 740 MWe, the plant was notified by SCSI that I
l wall C130-39 in the Plant Hatch Control Building has a local stress l
o 4 lOlsiIwhich exceeds design allowables during a postulated OBE and/or DBE. Thisl 10 Ic I loverstress con'dition was determined in the process of responding to l
l 0 l 7 l lIEB 80-11.
This is a repetitive occurrence - see LER 50-321/1980-115.
I iogi;There were no effects on public health or safety due to this event.
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33 34 35 36 31 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS 27 i,,og;The acceptance criteria for allowable stresses during a postulated i
i,,,,jearthquake utilized in the response to IEB 80-11 are more conservative i
- than the criteria utilized in the original design of the wall.
The wall i
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.g LER #:. 50-321/1981-031
< Licensee:
Georgia Power Company T
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Docket #:- 50-321
' Facility-Name:
Edwin'I.' Hatch m
. Narrative Report' for LER-50-321/1981-031
+
On 4-15-81, with Unit 1 in'. the refueling --mode; and Unit.2 -in normal steady state-operation at 740 MWe,.the ' plant-was
~.
notified by SCSI that wall C130-39 in the Plant ^ Hatch Control Building requires a minor modification - to lower the calculated stresscs et one localized section of the wall to within design allowables during a
postulated DBE and/or OBE.
SCSI had performed a
reanalysis of wall-C130-39 in response to-a
~
Bechtel letter indicating that additional evaluation should be performed on certain.
concrete-masonry walls which were analyzed in the 180-day response. to IEB 80-11.-
This is a repetitive occurrence - see LER 50-321/1980-115.-
.There were no effects on public health or safety due to this event.
The acceptance criteria for design allowable stresses during a postulated earthquake used in the 180-day response to IEB pd 80-11 are more conservative than the design criteria : utilized -
in the original design of concrete masonry - walls.
The new-acceptance criteria caused wall C130-39 to have a calculated stress which slightly exc'eeded design allowables.-
Wall' C130-39 will be modified to relieve the overstress condition when materials are available.
The concrete masonry walls at Plant Hatch are reinforced vertically and horizontally.
Horizontal extra-heavy Durowall reinforcing is provided in the ' mortar' joint at every block course.
Vertical reinforcing is provided at l'4" or.
2'3" centers (maximum spacing) for solidly filled and partially filled walls, respectively.
The walls are tied mechanically to the supporting columns 'or
- walls, and to the floor supporting the walls by dovetail stone
- anchors, expansion anchors, and reinforcing dowels.
The reinforcing will serve to distribute wall loads and " hold" the wall together in the event an carthquake should occur.
This would tend to ensure that blocks will not be indiscrimin,ately tossed
- about, even though local cracking might occur.
The floor response spectrum for the floor located above the wall was used in the analysis as a conservatism.
O 4
Although v211 'C130-39 in the Plant. Hatch Control Building shows local stress above the code allowables during an OBE
(),
and/or Dub, it is unlikely that the wall will totally coJ1 apse and render safety related equipment or systems ' inoperable.
The following considerations were used to substantiate this conclusion:
1.-
The overstress condition identified is a
localized condition only.
2.
The overstress condition is based on code allowables not-material yield' stresses or ultimate stresses.
3.
As local yiciding takes place the wall will -lose _ some. of its ability to carry load at the point of local yielding,_
and the stresses will be distributed to adjacent elements via the reinforcing and ma:.onry thus spreading-out' the loads.
4.
If local cracking develops in the masonry ~during an earthquake the wall loses its ability to transmit stresses across the
' discontinuity at the crack; therefore, damping is. increased and earthquake forces are not as readily transmitted throughout the wall.
5.
Maximum wall displacements identified from our seismic analyses are less than
.02" for the wall.
This small displacement should not degrade ' the integrity of safety related equipment in the event of an earthquake.
Local points of attachment to the wall were checked to verify-that no local failures would occur during an earthquake.
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modes of failure at local attachments were investigated, and no overstresses were identified when compared with code allowables.
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| 05000366/LER-1981-001-03, /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 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 | | | 05000366/LER-1981-001, Forwards LER 81-001/03L-0.Detailed Event Analysis Encl | Forwards LER 81-001/03L-0.Detailed Event Analysis Encl | | | 05000321/LER-1981-001, Forwards LER 81-001/01T-0 | Forwards LER 81-001/01T-0 | | | 05000321/LER-1981-001-01, /01T-0:on 801228,HPCI Steam Line Pressure Switches 1E41-N001a,c,d Actuated Outside Tech Specs.Caused by Switch Setpoint Drift.Switches Recalibr | /01T-0:on 801228,HPCI Steam Line Pressure Switches 1E41-N001a,c,d Actuated Outside Tech Specs.Caused by Switch Setpoint Drift.Switches Recalibr | | | 05000366/LER-1981-002, Forwards LER 81-002/03L-0 | Forwards LER 81-002/03L-0 | | | 05000366/LER-1981-002-03, /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 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 | | | 05000321/LER-1981-002, Forwards LER 81-002/03L-0 | Forwards LER 81-002/03L-0 | | | 05000321/LER-1981-002-03, /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 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 | | | 05000366/LER-1981-003-03, /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 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 | | | 05000321/LER-1981-003-03, /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 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 | | | 05000366/LER-1981-003, Forwards LER 81-003/03L-0 | Forwards LER 81-003/03L-0 | | | 05000321/LER-1981-003, Forwards LER 81-003/03L-0 | Forwards LER 81-003/03L-0 | | | 05000366/LER-1981-004, Forwards LER 81-004/03L-0 | Forwards LER 81-004/03L-0 | | | 05000366/LER-1981-004-03, /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 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 | | | 05000321/LER-1981-004, Forwards LER 81-004/03L-0 | Forwards LER 81-004/03L-0 | | | 05000321/LER-1981-004-03, /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 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 | | | 05000366/LER-1981-005-01, /01T-0:on 810126,reactor Pressure Vessel Core Spray Loops Discovered Inoperable.Caused by Procedure HNP-2-1230 Being Performed,Closing Manual Injection Valves 2E21-F007A & B.Valves Reopened & Procedure Changed | /01T-0:on 810126,reactor Pressure Vessel Core Spray Loops Discovered Inoperable.Caused by Procedure HNP-2-1230 Being Performed,Closing Manual Injection Valves 2E21-F007A & B.Valves Reopened & Procedure Changed | | | 05000366/LER-1981-005, Forwards LER 81-005/01T-0 | Forwards LER 81-005/01T-0 | | | 05000321/LER-1981-005-03, /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 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 | | | 05000321/LER-1981-005, Forwards LER 81-005/03L-0 | Forwards LER 81-005/03L-0 | | | 05000366/LER-1981-006, Forwards LER 81-006/03L-0 | Forwards LER 81-006/03L-0 | | | 05000366/LER-1981-006-03, /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 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 | | | 05000321/LER-1981-006, Forwards LER 81-006/03L-0 | Forwards LER 81-006/03L-0 | | | 05000321/LER-1981-006-03, /03L-0:on 810119,standby Liquid Control Pump a Discharge Relief Valve 1C41-F029A Operated Outside Tech Spec.Caused by Setpoint Drift.Valve Reset | /03L-0:on 810119,standby Liquid Control Pump a Discharge Relief Valve 1C41-F029A Operated Outside Tech Spec.Caused by Setpoint Drift.Valve Reset | | | 05000321/LER-1981-007, Forwards LER 81-007/03L-0 | Forwards LER 81-007/03L-0 | | | 05000321/LER-1981-007-03, /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. 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05000321/LER-1981-008, Forwards LER 81-008/03L-0 | Forwards LER 81-008/03L-0 | | | 05000366/LER-1981-008, Forwards LER 81-008/03L-0 | Forwards LER 81-008/03L-0 | | | 05000366/LER-1981-008-03, /03L-0:on 810119,pressure Switches Were Found Out of Tolerance.Caused by Setpoint Drift.Pressure Switches Recalibr & Returned to Svc | /03L-0:on 810119,pressure Switches Were Found Out of Tolerance.Caused by Setpoint Drift.Pressure Switches Recalibr & Returned to Svc | | | 05000366/LER-1981-009-03, /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 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 | | | 05000366/LER-1981-009, Forwards LER 81-009/03L-0 | Forwards LER 81-009/03L-0 | | | 05000321/LER-1981-009-03, /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 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 | | | 05000321/LER-1981-009, Forwards LER 81-009/03L-0 | Forwards LER 81-009/03L-0 | | | 05000366/LER-1981-010, Forwards LER 81-010/03L-0 | Forwards LER 81-010/03L-0 | | | 05000366/LER-1981-010-03, /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 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 | | | 05000321/LER-1981-010, Forwards LER 81-010/01T-0 | Forwards LER 81-010/01T-0 | | | 05000321/LER-1981-010-01, /01T-0:on 810211,AE Reported That Diesel Generator 1A,1C,2A,2B & 1B Outlet Svc Water Piping & Associated Seismic Supports Exceeded Tech Spec.Caused by Design Omission.Design Mods Made | /01T-0:on 810211,AE Reported That Diesel Generator 1A,1C,2A,2B & 1B Outlet Svc Water Piping & Associated Seismic Supports Exceeded Tech Spec.Caused by Design Omission.Design Mods Made | | | 05000321/LER-1981-011-03, /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 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 | | | 05000321/LER-1981-011, Forwards LER 81-011/03L-0 | Forwards LER 81-011/03L-0 | | | 05000366/LER-1981-011-03, /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 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 | | | 05000366/LER-1981-011, Forwards LER 81-011/03L-0 | Forwards LER 81-011/03L-0 | | | 05000321/LER-1981-012-03, /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 | /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 | | | 05000321/LER-1981-012, Forwards LER 81-012/03L-0 | Forwards LER 81-012/03L-0 | | | 05000366/LER-1981-012-02, /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 | /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 | | | 05000366/LER-1981-012, Forwards LER 81-012/02L-0 | Forwards LER 81-012/02L-0 | | | 05000366/LER-1981-013, Forwards LER 81-013/03L-0 | Forwards LER 81-013/03L-0 | | | 05000321/LER-1981-013-03, /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 | /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 | |
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