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LER-1981-088, /03L-0:on 810811 & 18,oil Leaks Discovered on HPCI Oil Sys.Caused by Ruptured Diaphragm on Diaphragm Control Valve.Diaphragm Replaced |
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| 3211981088R03 - NRC Website |
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NRC FORM 36G U.S. NUCLEAR REGULATORY COMMISSION (777)
LICENSEF EVENT REPORT CONTROL BLOCK: l l
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8 60 63 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DAT E 80 EVENT OESCRIPTION AND PROBABLE CONSEQUENCES h 10 # 21 pn 8-11-81, with Hatch 1 pcrforming Rx. S/U and on 8-18-81. with the uniti iO i3i iat steady state 91.77. thermal power oil le'aks were discovered on the HPCII iai.,i pil system.
This is reportable under Tech Spec 6.9.1.9.b. As per Tech 1
10 i s t fPec 3. 5.D RCIC, ADS, CSS, and LPCI were operable and no significant l
l0 lei pvents occurred.
This is a non-repetitive event and there were no l
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31 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h Ii 10 l 1 These oil leaks were due to a rut >tured diaphraem on the Robt. Shaw Dia-1 Ii ii i I phragm Control Valve.
The diaphraem was reolaced each time with ones I
,,i,iinot meeting original design specifications.
Close monitoring will con
'I i,,3i ltinue until Terry Turbine suoplies a diaphragm meeting original desinn I
tigiispecifications.
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50-321/1981-088 Licensee:
Georgia Power Company-Facility-Name:
Edwin I. Hatch 4
Docket #:
50-321
Narrative
Report for LER 50-321/1981-088 On 12 - 81, the Unit 1 HPCI, Robert Shaw diaphragm control valve (Model VC-210) supplied by General
- Electric, was installed to solve a. previous HPCI inoperability problem (Ref:
LER 50-321/1981-068).
It was unknown at the time that the diaphragm supplied with the valve was made - of a material not meeting original design spec.
The new valve along with its diaphragm was installed and HPCI was proven operable following this event.
On 7-21'-81, with Unit 1 at steady state 95.7% thermal power, procedure HNP-1-6011 "HPCI Leakage Inspection" was being-performed.
During this insp ect i.on, the ' diaphragm in the HPCI Robert Shaw diaphragm control valve.
ruptured and
'the inspection was stopped.
HPCI was declared inoperabic per Tech Spec 3.5.D.2 and RCIC,
- ADS, CSS, and LPCI were operable.
There were no effects upon public health and safety due to this event.
Upon inspection of the diaphragm, it was observed that the diaphragm was deformed, thereby leading plant personnel to believe the wrong size diaphragm rather than a
non-coil compatable diaphragm was installed in the G.E.
- Supplied, Robert Shaw diaphragm control valve.
A replacement diaphragm t
was obtained through Robert Shaw for the model VC-210 Control Valve, and it was unknown at the time that the diaphragm.was non-oil compatable and therefore had a reduced lifetime.
The diaphragm was installed and HPCI was proven operable.
On 8-11-81, with Unit 1 in Rx startup at 0% thermal power, the operators noticed that the "HPCI Oil Tank - Level High/ Low" annunciator was activated and 'upon investigation, it was discovered that the HPCI oil tank was emptied due to
'a ruptured diaphragm in the Robert Shaw diaphragm control valve.
The LPCI system was declared inoperable per Tech Spec section 3.5.D, RCIC, ADS, CSS, and LPCI were operable.
No significant event occurred.
~ Upon examination of the diaphragm, it was found to be in the same deformed shape as the one previously removed.
It was then realized that the diaphragns obtained from Robert Shaw were non-oil compatable.
An attempt to obtain an oil compatable diaphragm f rom G.E.
and Terry Turbine was made~but proved unsuccessful due to the unavailability of a replacement diaphragms capable of meeting original design specifications.
Site personnel felt that using the Robert Shaw diaphragms with the reduce.d lifetime could be used if the diaphragm was replaced on a bi-weekly basis, until replacement diaphragm capable of meeting the original design spec. was available.
The diaphragm was replaced and HPCI was proven operabic.
On 8-18-81, at 9:45 EDT and with Unit 1 at steady state 91.7%
thermal power, the monthly test of "HPCI Pump Operability" (HNP-1-3303) was being performed.
As per procedure "HPCI Leakage Inspection" (HNP-1-6011) it was found that the Robert Shaw diaphragm in the Robert Shaw Control Valve had ruptured.
The HPCI system was declared inoperable and per Tech Spec Section 3.5.D.2 RCIC, ADS, CSS, and LPCI were operable.
No significant event occurred.
The diaphragm for the control valve was replaced with a Terry Turbine Supplied diaphragm different from the one previously installed, but capable of 100 cycles.
Close monitoring of the number of cycles placed on the diaphragm is in progress until a replacement meeting the 1000 cycle condition is availabic.
This is a non-repetitive event and there were no ef fects upon public health and safety due to this event.
There is no impact on Unit 2 HPCI since it has the 1000 cycle diaphragm installed.
This is currently being evaluated as a potential 10CFR21.
The 1000 cycle diaphragm will be installed in Unit 1 HPCI following receipt.
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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. Personnel Reinstructed | /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 | | | 05000366/LER-1981-007-03, /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 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 | | | 05000366/LER-1981-007, Forwards LER 81-007/03L-0 | Forwards LER 81-007/03L-0 | | | 05000321/LER-1981-008-03, /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 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 | | | 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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