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LER-1980-122, /01T-0:on 801219,QC Insp of Cable Spreading Room & Control Bldg Sprinkler Hangers Installed in 1978 Revealed Deficiencies Which Jeopardize Seismic Qualification of Sprinkler Sys.Caused by Improper Installation |
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| 3211980122R01 - NRC Website |
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NRC FORM 36G U. S. NUCLEAR REGO' ATORY COMMISSION LICENSEE EVENT REPORT CCNTTYL BLOCK: l I
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8 tra di DOCK ET NUMBER 68 60 EVENT CATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROB ABLE CONSEQUENCES h 10121 10n 12-19-80, at 1300 CST a OC inspection of cable soreadinq room and I
lo 131 I control building sprinkler hangers installed in 1978 revealed deficien _j lo 141 I cies which jeopardize the seismic qualification of the sprinkler sys-1 l
10181 Items.
Unit 2 was in refuel and Unit I was operating at 77% power.
I lo is i I There were no ef fects on public health or safety.
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CAUSE DESCRIPTION AND CORRECTIVE ACTIONS 11 10 I IThe cause of this event is apparently improper installation of hangers l
11 11 1 linstalled under the original fire protection contract.
A 100% OC in-l ii i :i i ispection of hangers in safety-related areas was begun and anchor bolts I
lij,1]are being replaced.
The hangers will be modified prior to Unit 2 start-1 Ii14 I l up.
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C. L. Coqqin, Supt. Plt. Eno. Serv.
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NAVE OF PREPAREH
i LER #:
50-321/1980-122 O
ticensee:
Ceeraia rewer Cemganx Facility Name:
Edwin I.
Hatch Docket #:
50-321 Narrativt Report for LER 50-321/1980-122 Modifications to fire protection sprinkler systems required by IER 50-321/80-02 and 50-366/80-02 were in progress when QA/QC inspections of unmodified portions revealed numerous improper anchor bolt installations.
These fire protection hangers were installed under the original 1978 contract.
The problems discovered in the cable spreading room and control building '
corridor sprinkler systems were of such a nature that could affect the seismic qualification of these systems.
- Based on the preliminary results of the inspections, a
100%
QC inspection of fire protection hangers in. safety-related areas was begun.
All sprinkler zeystems in areas requiring seismic design will be inspected for similar problems and repairs made as necessary to assure the full design factor of safety.
At the time of discovery Unit I was operating at 80% power, and Unit 2 was in cold shutdown for refueling.
Both units are affected due to the cable spreading room being a common area.
An evaluation of the consequences of existing conditions in 1
these systems was performed by the AE.
In the event that a failure of the piping was to occur in the cable spreading room, it was felt that the conduit and cable tray systems in the area should support the pipe and that cable failure of redundant systems in this area is highly improbable.
Damage l
Lo the cable, conduit, and cable tray systems would be minimal for the following reasons:
l 1.
The impact load would be small because the pipe in question does not normally contain water and is small bore pipe most of which is 2 1/2" and less in diameter.
- Also, the maximum distance the pipe should fall is expected to be 1 to 2 feet because of the many obstructions within the cable spreading room.
2.
The accelerations of the-pipe should be small because simultaneous failure of all hangers is unlikely.
Also, it 1
is felt that the pipe will not break, thus providing some self-support from adequate hangers and obstructions.
3.
The conduit and cable tray systems should not collapse due to this additional load because of conservatisms used in the support system design.
Initial analysis assumed that j
cable trays and conduit were filled, and the worst case support loading was examined.
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4.
Cable damage is also unlikely because most of the cables are contained within rigid aluminum conduits or rigid cable trays, many of which have covers.
5.
The low probability of a severe seismic event during the period required for repeirs and the ability to provide additional control functions for cold shutdown equipment through the remote and shutdown panels provide additional safety margin.
Prior to startup of Unit 2 from the present refueling outage all deficiencies within the scope of this finding will be corrected.
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| 05000321/LER-1980-001-01, /01T-0:on 800103,while Performing Maint on RHR LPCI Injection Valve,Clevis Pin Found Missing from Strut on Drywell Penetration Restraint.Caused by Improper Installation.New Clevis Pin Installed | /01T-0:on 800103,while Performing Maint on RHR LPCI Injection Valve,Clevis Pin Found Missing from Strut on Drywell Penetration Restraint.Caused by Improper Installation.New Clevis Pin Installed | | | 05000366/LER-1980-001, Forwards LER 80-001/03L-0 | Forwards LER 80-001/03L-0 | | | 05000366/LER-1980-001-03, /03L-0:on 800102,while Performing Narrow Range Torus Water Level Functional Test & Calibr,Level Transmitter 2T48-N021B Found Out of Tolerance.Caused by Range Drift. Transmitter Recalibr & Returned to Svc | /03L-0:on 800102,while Performing Narrow Range Torus Water Level Functional Test & Calibr,Level Transmitter 2T48-N021B Found Out of Tolerance.Caused by Range Drift. Transmitter Recalibr & Returned to Svc | | | 05000321/LER-1980-001, Forwards LER 80-001/01T-0 | Forwards LER 80-001/01T-0 | | | 05000321/LER-1980-002-03, /03L-0:on 800112,while Performing HNP-1-3655,fan lT46-C001B Would Not Meet Flow Requirements Per Tech Specs. Ten Days Later,While Venting Drywell Per HNP-1-1500,flow Did Not Meet Tech Specs.Equipment Recalibr | /03L-0:on 800112,while Performing HNP-1-3655,fan lT46-C001B Would Not Meet Flow Requirements Per Tech Specs. Ten Days Later,While Venting Drywell Per HNP-1-1500,flow Did Not Meet Tech Specs.Equipment Recalibr | | | 05000321/LER-1980-002, Forwards LER 80-002/03L-0 | Forwards LER 80-002/03L-0 | | | 05000366/LER-1980-002, Forwards LER 80-002/01T-0 | Forwards LER 80-002/01T-0 | | | 05000366/LER-1980-002-01, /01T-0:on 800128,during Cold Shutdown,Ae Notified Util That Single Mode Failure Existed for Torus Gravity Fill Isolation Valve 2G51-F013.Caused by Design Deficiency. Standing Order Issued | /01T-0:on 800128,during Cold Shutdown,Ae Notified Util That Single Mode Failure Existed for Torus Gravity Fill Isolation Valve 2G51-F013.Caused by Design Deficiency. Standing Order Issued | | | 05000366/LER-1980-003, Forwards LER 80-003/03L-0 | Forwards LER 80-003/03L-0 | | | 05000366/LER-1980-003-03, /03L-0:on 800117,while Applying Equalizing Charge to 125/250-volt Dc Station Svc Batteries,Hpci Automatic Flow Control Power Inverter Tripped.Caused by Instrument Drift. Instrument Recalibr Satisfactorily | /03L-0:on 800117,while Applying Equalizing Charge to 125/250-volt Dc Station Svc Batteries,Hpci Automatic Flow Control Power Inverter Tripped.Caused by Instrument Drift. Instrument Recalibr Satisfactorily | | | 05000321/LER-1980-003-03, While Performing RHR Valve Operability Procedure,Outboard Shutdown Cooling Isolation Valve F008 Opened in 25.8-S.Caused by Normal Wear & Human Reaction Time.Valve Operator Adjusted | While Performing RHR Valve Operability Procedure,Outboard Shutdown Cooling Isolation Valve F008 Opened in 25.8-S.Caused by Normal Wear & Human Reaction Time.Valve Operator Adjusted | | | 05000321/LER-1980-003, Forwards Revised LER 80-003/03X-1 | Forwards Revised LER 80-003/03X-1 | | | 05000321/LER-1980-004, Forwards LER 80-004/03L-0 | Forwards LER 80-004/03L-0 | | | 05000321/LER-1980-004-03, /03L-0:on 800106,during Startup Mode,Main Steam Line Inboard Isolation Drain Valve Failed in mid-position. Caused by Failure of Valve Motor Winding.Motor Replaced & Valve Returned to Operable Status | /03L-0:on 800106,during Startup Mode,Main Steam Line Inboard Isolation Drain Valve Failed in mid-position. Caused by Failure of Valve Motor Winding.Motor Replaced & Valve Returned to Operable Status | | | 05000366/LER-1980-004-03, /03L-0:on 800118,during Steady State Power Operation Hydrogen Recombiner Inlet Valve 2T49-F003A Did Not Open.Caused by a Failed Torque Switch.Sys Returned to Operation After Switch Was Replaced | /03L-0:on 800118,during Steady State Power Operation Hydrogen Recombiner Inlet Valve 2T49-F003A Did Not Open.Caused by a Failed Torque Switch.Sys Returned to Operation After Switch Was Replaced | | | 05000366/LER-1980-004, Forwards LER 80-004/03L-0 | Forwards LER 80-004/03L-0 | | | 05000321/LER-1980-005, Forwards LER 80-005/03L-0 | Forwards LER 80-005/03L-0 | | | 05000321/LER-1980-005-03, /03L-0:on 800109,w/reactor Mode Switch in Run Mode,Discovered That Surveillance Procedure HNP-1-3007, Turbine Control Valve Fast Closure,Was Not Performed in Grace Period.Caused by Personnel Error | /03L-0:on 800109,w/reactor Mode Switch in Run Mode,Discovered That Surveillance Procedure HNP-1-3007, Turbine Control Valve Fast Closure,Was Not Performed in Grace Period.Caused by Personnel Error | | | 05000366/LER-1980-005, Forwards LER 80-005/03L-0 | Forwards LER 80-005/03L-0 | | | 05000366/LER-1980-005-03, /03L-0:on 800119,during Power Operation,Tech Specs 4.8.1.1.1.a & 4.8.1.1.2a4 for Electrical Power Sources Were Not Performed within 1-h.Caused by Personnel Misinterpretation of Tech Spec Requirements | /03L-0:on 800119,during Power Operation,Tech Specs 4.8.1.1.1.a & 4.8.1.1.2a4 for Electrical Power Sources Were Not Performed within 1-h.Caused by Personnel Misinterpretation of Tech Spec Requirements | | | 05000321/LER-1980-006-03, /03L-0:on 800113,one Standby Gas Treatment Sys Rendered Inoperable W/Both Units in Power Operation.Unit Not Proven Operable within Required 4-h.Caused by Inability to Prove Filter Train Operable within 4-h | /03L-0:on 800113,one Standby Gas Treatment Sys Rendered Inoperable W/Both Units in Power Operation.Unit Not Proven Operable within Required 4-h.Caused by Inability to Prove Filter Train Operable within 4-h | | | 05000321/LER-1980-006, Forwards LER 80-006/03L-0 | Forwards LER 80-006/03L-0 | | | 05000321/LER-1980-007-03, /03L-0:on 800114,while Testing Standby Svc Water Pump,Pump Would Not Meet Criteria.Caused by Disengagement of Pump First Stage Impeller Lock Collet.Lock Collet Replaced & Pump Reinstalled | /03L-0:on 800114,while Testing Standby Svc Water Pump,Pump Would Not Meet Criteria.Caused by Disengagement of Pump First Stage Impeller Lock Collet.Lock Collet Replaced & Pump Reinstalled | | | 05000321/LER-1980-007, Forwards LER 80-007/03L-0 | Forwards LER 80-007/03L-0 | | | 05000366/LER-1980-007-01, /01T-0:on 800130,while Performing High Drywell Pressure Instrument (Reactor Protection Sys) Functional Test & Calibr,Instruments 2C71-N002A,B & D Exceeded Tech Specs.Caused by Instrument Drift | /01T-0:on 800130,while Performing High Drywell Pressure Instrument (Reactor Protection Sys) Functional Test & Calibr,Instruments 2C71-N002A,B & D Exceeded Tech Specs.Caused by Instrument Drift | | | 05000366/LER-1980-007, Forwards LER 80-007/01T-0 | Forwards LER 80-007/01T-0 | | | 05000366/LER-1980-008-03, While Increasing Reactor Power by Rod Withdrawal,Operator Noticed Rod Select Matrix Backlighted & Rod Sequence Control Sys Not Initiating Rod Blocks Properly.Caused by Design Change | While Increasing Reactor Power by Rod Withdrawal,Operator Noticed Rod Select Matrix Backlighted & Rod Sequence Control Sys Not Initiating Rod Blocks Properly.Caused by Design Change | | | 05000366/LER-1980-008, Forwards LER 80-008/03L-1 | Forwards LER 80-008/03L-1 | | | 05000321/LER-1980-008-03, /03L-0:on 800115,during Steady State Power Operation,Secondary Containment Integrity Violated When Personnel Opened 164-ft Elevation Reactor Bldg & Turbine Bldg Airlock Doors Simultaneously.Procedure Revised | /03L-0:on 800115,during Steady State Power Operation,Secondary Containment Integrity Violated When Personnel Opened 164-ft Elevation Reactor Bldg & Turbine Bldg Airlock Doors Simultaneously.Procedure Revised | | | 05000321/LER-1980-008, Forwards LER 80-008/03L-0 | Forwards LER 80-008/03L-0 | | | 05000366/LER-1980-009-03, /03L-0:on 800130,while Performing Procedure HNP-2-33-3,HPCI Min Flow Valve 2E41-F012 Failed to Close. Caused by Sticking Switch Contacts on Flow Switch 2E41-N006. Switch Contacts Cleaned & Procedure HNP-2-3303 Performed | /03L-0:on 800130,while Performing Procedure HNP-2-33-3,HPCI Min Flow Valve 2E41-F012 Failed to Close. Caused by Sticking Switch Contacts on Flow Switch 2E41-N006. Switch Contacts Cleaned & Procedure HNP-2-3303 Performed | | | 05000321/LER-1980-009-03, /03L-0:on 800118,during Normal Operation,Drywell/ Torus Temp Recorder 1T47-R611 Found Stamping Erratically, Making Drywall & Torus Air Temps & Water Temp Difficult to Ascertain.Caused by Failure of Microswitch.Switch Replace | /03L-0:on 800118,during Normal Operation,Drywell/ Torus Temp Recorder 1T47-R611 Found Stamping Erratically, Making Drywall & Torus Air Temps & Water Temp Difficult to Ascertain.Caused by Failure of Microswitch.Switch Replaced | | | 05000366/LER-1980-009, Forwards LER 80-009/03L-0 | Forwards LER 80-009/03L-0 | | | 05000321/LER-1980-010-03, /03L-0:on 800118,during Normal Operation While Performing Standby Liquid Control Pump Operability Test & Relief Valve Test,Pump a Discharge Relief Valve 1C41-F029A Operated at 1,225 Psig.Caused by Setpoint Drift.Valve Reset | /03L-0:on 800118,during Normal Operation While Performing Standby Liquid Control Pump Operability Test & Relief Valve Test,Pump a Discharge Relief Valve 1C41-F029A Operated at 1,225 Psig.Caused by Setpoint Drift.Valve Reset | | | 05000321/LER-1980-010, Forwards LER 80-010/03L-0 | Forwards LER 80-010/03L-0 | | | 05000366/LER-1980-010, Forwards LER 80-010/03L-0 | Forwards LER 80-010/03L-0 | | | 05000366/LER-1980-010-03, /03L-0:on 800131,during Reactor Startup,At 58% Power,Max Total Peaking Factor Was Calculated at 3.0 Compared to Design Value of 2.38.Caused by Lower than Normal Xenon Distribution During Startup | /03L-0:on 800131,during Reactor Startup,At 58% Power,Max Total Peaking Factor Was Calculated at 3.0 Compared to Design Value of 2.38.Caused by Lower than Normal Xenon Distribution During Startup | | | 05000321/LER-1980-011-03, /03L-0:on 800120,while at Steady State Power, torus-to-drywell Differential Pressure recorder,LT48-R631B Had Low Reading.Cause Not Stated | /03L-0:on 800120,while at Steady State Power, torus-to-drywell Differential Pressure recorder,LT48-R631B Had Low Reading.Cause Not Stated | | | 05000366/LER-1980-011-03, /03L-0:on 800202,while Performing Reactor Core Isolation Cooling Shutdown Flow Test,Power Inverter for Remote Flow Control Loop Found to Be Tripped.Caused by Defective Input Filter Capacitors | /03L-0:on 800202,while Performing Reactor Core Isolation Cooling Shutdown Flow Test,Power Inverter for Remote Flow Control Loop Found to Be Tripped.Caused by Defective Input Filter Capacitors | | | 05000321/LER-1980-011, Forwards LER 80-011/03L-0 | Forwards LER 80-011/03L-0 | | | 05000366/LER-1980-012-03, /03L-0:on 800214,while at Full Power,Rhr & Plant Svc Water Min Flow Line Found to Be Inadequately Supported. Caused by Design Deficiency.Design Change Request & Maint Request Implemented to Add Supports | /03L-0:on 800214,while at Full Power,Rhr & Plant Svc Water Min Flow Line Found to Be Inadequately Supported. Caused by Design Deficiency.Design Change Request & Maint Request Implemented to Add Supports | | | 05000321/LER-1980-012, Forwards LER 80-012/03L-0 | Forwards LER 80-012/03L-0 | | | 05000366/LER-1980-012, Forwards LER 80-012/03L-0 | Forwards LER 80-012/03L-0 | | | 05000321/LER-1980-012-03, /03L-0:on 800122,while Reactor Core Isolation Cooling Sys Was Tagged Out for Maint,Hpci Was Found Inoperable,Requiring Orderly Shutdown.Caused by Leak in Line to HPCI Booster Pump Discharged Pressure Gauge | /03L-0:on 800122,while Reactor Core Isolation Cooling Sys Was Tagged Out for Maint,Hpci Was Found Inoperable,Requiring Orderly Shutdown.Caused by Leak in Line to HPCI Booster Pump Discharged Pressure Gauge | | | 05000321/LER-1980-013, Forwards Updated LER 80-013/03X-1 | Forwards Updated LER 80-013/03X-1 | | | 05000321/LER-1980-013-03, Reactor Recirculation Pump a Tripped Causing Power Reduction.Caused by Electrical Short Circuit Due to Steam Leak in Drywell.Terminal Board Replaced & Tested | Reactor Recirculation Pump a Tripped Causing Power Reduction.Caused by Electrical Short Circuit Due to Steam Leak in Drywell.Terminal Board Replaced & Tested | | | 05000366/LER-1980-013-03, /03L-0:on 800203,while Maint Was Performed on 2082-K002 Static Inverter,Emergency Control Transfer Switch Was Placed in Emergency Position.Reactor Core Isolation Cooling Was Rendered Inoperable.Caused by Personnel Error | /03L-0:on 800203,while Maint Was Performed on 2082-K002 Static Inverter,Emergency Control Transfer Switch Was Placed in Emergency Position.Reactor Core Isolation Cooling Was Rendered Inoperable.Caused by Personnel Error | | | 05000366/LER-1980-013, Forwards LER 80-013/03L-0 | Forwards LER 80-013/03L-0 | | | 05000366/LER-1980-014, Forwards LER 80-014/03L-0 | Forwards LER 80-014/03L-0 | | | 05000366/LER-1980-014-03, /03L-0:on 800204,while Performing HNP-2-3054, Average Power Range Monitor C Failed.Caused by Instrument Drift.Instrument Adjusted Per Procedure & Returned to Svc | /03L-0:on 800204,while Performing HNP-2-3054, Average Power Range Monitor C Failed.Caused by Instrument Drift.Instrument Adjusted Per Procedure & Returned to Svc | |
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