Similar Documents at Salem |
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LER-1979-048, /01T-0 on 790709:during Normal Maint Operations, Significant Wear Marks Found on Tubes Adjacent to Tube Lane Blocking Devices.Caused by Movement of Blocking Devices. Steam Adjacent to Blocking Devices Were Plugged |
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| 2721979048R01 - NRC Website |
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Report Number:
Report Date:
Occurrence Date:
7.48/0lT 7/20/79 7/9/79 Salem Generating Station Public Service Electric & Gas Company Hancocks Bridge, New Jersey 08038 IDENTIFICATION OF OCCURRENCE:
Degradation of Stearn Generator Tubes CONDITIONS PRIOR TO*OCCURRENCE:
Operational Mode 6 DESCRIPTION OF OCCURRENCE:
Six inch handholes in the lower section of each steam generator were removed during scheduled outage maintenance to perforrn sludge lancing.
Wear marks on several tubes adjacent to tube lane blocking devices on Nos. 11, 13 and 14 Steam Generators were sighted and investigated.
The largest wear marks were approximately l" long and 3/16" wide; most marks were somewhat smaller.
No significant wear marks were' visible upon ~nspection of the No. 12 steam generator by PSE&G and Westinghouse officials.
This is documented on Deficiency Report No. MD-584.
DESIGNATION OF APPARENT CAUSE OF OCCURRENCE:
Wear marks are attributed to movement of the tube lane blocking devices against adjacent tubes during steam generator operation.
Water flowing around.the blocking devices and possible improper installation by construction personnel prior to startup operation caused them to loosen with the passage of time and vibrate against the tubes.
ANALYSI~ OF OCCURRENCE:
Salem Unit N<?* 1 Technical Specification, Section 3.4.5 addresses the operability of the steam generators during normal operation and stipulates a plugging requirement for all tubes with imperfections exceeding the plugging limit of 40% of the tube nominal wall thick-ness.
By plugging a.11 inspected steam generator tubes which showed visual or eddy current degradation, the structural integrity of that portion of the Reactor Coolant System*has been maintained.
LER 79-48/0lT CORRECTIVE ACTION:
Eddy current testing was performed on a total of 30 tubes adjacent to the tube lane blocking devices in Nos. 11, 13 and 14 Steam Gen-erators.
Testing revealed that six tube ends in five tubes showed degradation greater than 40% of the nominal wall thickness.
Consequently, it was decided to perform explosive plugging on both ends 9f the 30 tubes adjacent to tube lane blocking devices in Nos. *11, 13 and 14 steam generators.
After completion of the plugging, photornapping was used to document the results.
The tube lane blocking devices were reinstalled by station maintenance personnel under direct supervision of the vendor.
FAILURE DATA:
Eddy current results greater than 40% nominal wall thickness:
Steam Generator No.
Location Tube No.
% Defect Depth 11 Inlet (Manway Side) 1-94-Tl
> 50 11 Inlet (Manway Side) l-91-T4 48 11 Outlet (Manway Side) l-91-T4.
63 11 Outlet (.Manway Side) l-92-T3 41 13 Inlet (Manway Side) l-92-T3 50 14 Inlet (Nozzle Side) l-3-T3 45 Prepared by __
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- T NUMBER 63 69 EVE"lT DATE 74 7o R!:?ORT OATE Sll EVENT DESCRIPTION AND PROBABLE CONSEQUENCES@
I During normal maintenance operations, significant wear marks on steaiu tubes adjacent to tube lane blocking devices were found on #11,~13 & *14 Steam Generators.
If T/S 3.4.5 plugging requirements are not followed for tubes with degraded wall thickness, the structural inteority of the!
((TI] I RCS will not be assured within acceptable limits.
This is the first [ill] I occurrence of this type.
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CAUSE
CAUSE COM?.
VALVE CODE CODE SUBCODE COMPONENT CODE SUB CC DE suacoD:
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CODE TYPE NC.
REPORT I 7 I 9 I L=1 I o I 4 I s I I/I Ioli I LLl L=1 LiLl NUMBER 21 22 23 24 26 27 23 29 JO 31 32 30 ACTION FUTURE EFi'ECT SHUTDOWN Q.
ATIACHM!:NT "1?AD-4 TAKEN ACTION ON PLANT METr;oD HOURS ~ SUBMITTED FORM ~us.
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.!7 [II)) Wear marks were caused bv movement of tube lane blocking devices which QIO loosen up with the passage of time and vibrate against adiacent stea.1"[1.
ITJJJ 1tubes.due*to water flow during S/G operation.
Steam tubes adjacent to
[!))] blocking devices in #11, #13 & #14 S/G's have been plugged.
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DISCOVERY DISCOVERY DESCRIPTION-~
W@I Discovered during sludae lancina in§!:Ctl.
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| 05000272/LER-1979-001-03, /03L-0 on 790102:during Normal Operation,The No 12 Containment Fan Coil Unit Shifted to Slow Speed,But No Indication of Svc Water Flow Was Noted.Caused by Burned Out Coil in Solenoid SV-624,supplying Control Air for 12SW223 | /03L-0 on 790102:during Normal Operation,The No 12 Containment Fan Coil Unit Shifted to Slow Speed,But No Indication of Svc Water Flow Was Noted.Caused by Burned Out Coil in Solenoid SV-624,supplying Control Air for 12SW223 | | | 05000272/LER-1979-001, Supplemental LER 79-001/03X-1:on 790102,during Normal Operations,Containment Fan Coil 12 Shifted to Slow Speed. Operator Noticed No Indication of Svc Waterflow.Caused by Burned Out Coil in Solenoid Valve SV-624.Coil Replaced | Supplemental LER 79-001/03X-1:on 790102,during Normal Operations,Containment Fan Coil 12 Shifted to Slow Speed. Operator Noticed No Indication of Svc Waterflow.Caused by Burned Out Coil in Solenoid Valve SV-624.Coil Replaced | | | 05000272/LER-1979-002-03, /03L-0 on 790103:excessive Leak Rate in W1 100 Air Lock Noted.Doors Were Reworked & Airlock Returned to Operation.Seals Failed Due to Split at Vulcanized Seam. Door Seals Were Replaced | /03L-0 on 790103:excessive Leak Rate in W1 100 Air Lock Noted.Doors Were Reworked & Airlock Returned to Operation.Seals Failed Due to Split at Vulcanized Seam. Door Seals Were Replaced | | | 05000272/LER-1979-002, Forwards LER 79-002/03L-0 | Forwards LER 79-002/03L-0 | | | 05000272/LER-1979-003, Forwards LER 79-003/03L-0 | Forwards LER 79-003/03L-0 | | | 05000272/LER-1979-003-03, /03L-0 on 790103:containment Pressure Exceeded Tech Spec Max.Caused by Isolation of Pressure/Vacuum Relief System for Rework of 1CV6 | /03L-0 on 790103:containment Pressure Exceeded Tech Spec Max.Caused by Isolation of Pressure/Vacuum Relief System for Rework of 1CV6 | | | 05000272/LER-1979-004, Forwards Updated LER 79-004/03X-1 | Forwards Updated LER 79-004/03X-1 | | | 05000272/LER-1979-004-03, /03L-0 on 790103:Loop 4 Channel IV Was 100 Psi Too High.Caused by Steam Pressure Transmitter Being Frozen by an Outside Air Damper Directing Cold Air Onto the Sensing Lines | /03L-0 on 790103:Loop 4 Channel IV Was 100 Psi Too High.Caused by Steam Pressure Transmitter Being Frozen by an Outside Air Damper Directing Cold Air Onto the Sensing Lines | | | 05000272/LER-1979-005-03, /03L-0 on 790104:during Normal Operations,Position Indication for Rod 2D5 Began Oscillating.Rod Position within 12 Steps of Bank D.Caused Traced to Rod Indication Coil Stack on Reactor.Repairs Planned for Next Reactor Outage | /03L-0 on 790104:during Normal Operations,Position Indication for Rod 2D5 Began Oscillating.Rod Position within 12 Steps of Bank D.Caused Traced to Rod Indication Coil Stack on Reactor.Repairs Planned for Next Reactor Outage | | | 05000272/LER-1979-005, Supplemental LER 79-05L/03X-1:on 790104,during Normal Operation,Individual Rod Position Indication for Rod 2D5 Began Oscillating.Cause Could Not Be Identified.Connectors Checked & RPI Coil Stack Replaced | Supplemental LER 79-05L/03X-1:on 790104,during Normal Operation,Individual Rod Position Indication for Rod 2D5 Began Oscillating.Cause Could Not Be Identified.Connectors Checked & RPI Coil Stack Replaced | | | 05000272/LER-1979-006-03, /03L-0 on 790102:inservice Insp Data Packages Not Being Reviewed.Cause Was Lack of Administrative Control to Correlate Responsibilities of Two Station Depts.Dept Review Procedures Have Been Rewritten | /03L-0 on 790102:inservice Insp Data Packages Not Being Reviewed.Cause Was Lack of Administrative Control to Correlate Responsibilities of Two Station Depts.Dept Review Procedures Have Been Rewritten | | | 05000272/LER-1979-006, Forwards LER 79-006/03L-0 | Forwards LER 79-006/03L-0 | | | 05000272/LER-1979-007, Forwards LER 79-007/03L-0 | Forwards LER 79-007/03L-0 | | | 05000272/LER-1979-007-03, /03L-0 on 790126:while Performing Channel Check of Pressurizer Level,Channel II Found 5% Lower than Others. Caused by Instrument Drift Resulting in Zero Shift in Transmitter Output | /03L-0 on 790126:while Performing Channel Check of Pressurizer Level,Channel II Found 5% Lower than Others. Caused by Instrument Drift Resulting in Zero Shift in Transmitter Output | | | 05000272/LER-1979-008-03, /03L-0 on 790111:during Normal Operation While Refilling Boric Acid Storage Tanks,Operator Added Improper Batch of Acid to Tanks & Pumped Concentrates Tank to Storage Tanks.Caused by Personnel Error | /03L-0 on 790111:during Normal Operation While Refilling Boric Acid Storage Tanks,Operator Added Improper Batch of Acid to Tanks & Pumped Concentrates Tank to Storage Tanks.Caused by Personnel Error | | | 05000272/LER-1979-008, Forwards LER 79-008/03L-0 | Forwards LER 79-008/03L-0 | | | 05000272/LER-1979-009-03, /03L-0 on 790112:No 13 Auxiliary Bldg Exhaust Fan Removed from Svc to Replace Motor.Caused by Worn Keyway in Drive Motor Shaft | /03L-0 on 790112:No 13 Auxiliary Bldg Exhaust Fan Removed from Svc to Replace Motor.Caused by Worn Keyway in Drive Motor Shaft | | | 05000272/LER-1979-009, Forwards LER 79-009/03L-0 | Forwards LER 79-009/03L-0 | | | 05000272/LER-1979-011, Forwards LER 79-011/01X-2 | Forwards LER 79-011/01X-2 | | | 05000272/LER-1979-011-01, /01X-2 on 790116:RMS Channel Which Had Alarmed & Cleared Had Been Reset at Control Console But Not at RMS Panel.Caused by Procedure Inadequacy.Procedure Changed Initiated to Clarify Functions | /01X-2 on 790116:RMS Channel Which Had Alarmed & Cleared Had Been Reset at Control Console But Not at RMS Panel.Caused by Procedure Inadequacy.Procedure Changed Initiated to Clarify Functions | | | 05000272/LER-1979-012, Forwards LER 79-012/03L-0 | Forwards LER 79-012/03L-0 | | | 05000272/LER-1979-012-03, /03L-0 on 790115:No 11 Steam Generator Steam Flow Channel II Failed Low.No Cause Found.Operator Took Manual Control & re-established Steam Generator Level.Channel Indication Normalized within 10 Minutes | /03L-0 on 790115:No 11 Steam Generator Steam Flow Channel II Failed Low.No Cause Found.Operator Took Manual Control & re-established Steam Generator Level.Channel Indication Normalized within 10 Minutes | | | 05000272/LER-1979-013-04, /04L on 790102:non-radioactive Waste Effluent Total Suspended Solids Exceeded Tech Specs.Caused by Abnormally High Number of Demineralized Regenerations Supporting Initial Flushes for Startup Preparation | /04L on 790102:non-radioactive Waste Effluent Total Suspended Solids Exceeded Tech Specs.Caused by Abnormally High Number of Demineralized Regenerations Supporting Initial Flushes for Startup Preparation | | | 05000272/LER-1979-013, Supplemental LER 79-013/04X-1:on 790102,during Preparation of Annual Nonradioactive Environ Operating Rept,Average 1978 Suspended Solids Concentrate in Discharge Exceeded Limit. Caused by Abnormally High Demineralizer Regenerat | Supplemental LER 79-013/04X-1:on 790102,during Preparation of Annual Nonradioactive Environ Operating Rept,Average 1978 Suspended Solids Concentrate in Discharge Exceeded Limit. Caused by Abnormally High Demineralizer Regenerations | | | 05000272/LER-1979-014-03, /03L-0 on 790220:during Normal Operation,Radiation Monitoring Sys Channel 1R 12B Alarms Found Not Operating. Channel Later Returned to Svc & Operated Properly.Caused by Unknown Factor | /03L-0 on 790220:during Normal Operation,Radiation Monitoring Sys Channel 1R 12B Alarms Found Not Operating. Channel Later Returned to Svc & Operated Properly.Caused by Unknown Factor | | | 05000272/LER-1979-014, Forwards LER 79-014/03L-0 | Forwards LER 79-014/03L-0 | | | 05000272/LER-1979-015, Forwards LER 79-015/03L-0 | Forwards LER 79-015/03L-0 | | | 05000272/LER-1979-015-03, /03L-0 on 790212:during Normal Operation,Noted Required Surveillance to Be Performed Every 78-h Had Not Been Done on 790210 When Scheduled.Caused by Personnel Error.Entry Made in Log Instructing Supervisor | /03L-0 on 790212:during Normal Operation,Noted Required Surveillance to Be Performed Every 78-h Had Not Been Done on 790210 When Scheduled.Caused by Personnel Error.Entry Made in Log Instructing Supervisor | | | 05000272/LER-1979-016, Forwards LER 79-016/03L-0 | Forwards LER 79-016/03L-0 | | | 05000272/LER-1979-016-03, /03L-0 on 790220:control Operator Observed Zero Svc Water Flow Through Unit.Caused by Burned Out Coil in Solenoid Valve.Coil Replaced | /03L-0 on 790220:control Operator Observed Zero Svc Water Flow Through Unit.Caused by Burned Out Coil in Solenoid Valve.Coil Replaced | | | 05000272/LER-1979-017, Forwards LER 79-017/03L-0 | Forwards LER 79-017/03L-0 | | | 05000272/LER-1979-017-03, /03L-0 on 790219:gross Activity Surveillance of Coolant Sys & Steam Generators Was Not Performed.Caused by Personnel Error in Not Returning Gas Bottles to Storage.New Bottle Storage Pad Will Be Built | /03L-0 on 790219:gross Activity Surveillance of Coolant Sys & Steam Generators Was Not Performed.Caused by Personnel Error in Not Returning Gas Bottles to Storage.New Bottle Storage Pad Will Be Built | | | 05000272/LER-1979-018, Forwards LER 79-018/03L-0 | Forwards LER 79-018/03L-0 | | | 05000272/LER-1979-018-03, /03L-0 on 790223:auxiliary Feedwater Pump Breaker Cubicle Was Hot.Caused by Burned Out Closing Spring Charging Motor.Motor & Breaker Replaced | /03L-0 on 790223:auxiliary Feedwater Pump Breaker Cubicle Was Hot.Caused by Burned Out Closing Spring Charging Motor.Motor & Breaker Replaced | | | 05000272/LER-1979-020-03, /03L-0 on 790225:pressurizer Level Channel II Was Declared Inoperable.Caused by non-linearity of Strain Gauge in Level Sensor Transmitter.Strain Gauge Replaced Along W/ Zero & Span Potentiometers.Transmitter Recalibrated | /03L-0 on 790225:pressurizer Level Channel II Was Declared Inoperable.Caused by non-linearity of Strain Gauge in Level Sensor Transmitter.Strain Gauge Replaced Along W/ Zero & Span Potentiometers.Transmitter Recalibrated | | | 05000272/LER-1979-021, Forwards LER 79-021/03L-0 | Forwards LER 79-021/03L-0 | | | 05000272/LER-1979-021-03, /03L-0 on 790302:overhead Annuciators in Control Room Alarmed,Indicating Power Range Nuclear Instrumentation Channel Failure.Caused by Failure of N41 Channel High Voltage Power Supply.Failed Power Supply Replaced | /03L-0 on 790302:overhead Annuciators in Control Room Alarmed,Indicating Power Range Nuclear Instrumentation Channel Failure.Caused by Failure of N41 Channel High Voltage Power Supply.Failed Power Supply Replaced | | | 05000272/LER-1979-022-03, /03L-0 on 790221:during Normal Operations,While Conducting Routine Insp,Nrc Inspector Found Missed Tech Spec Surveillance Reading.Caused by Personnel Error.Surveillance Posted on Plant Status Board | /03L-0 on 790221:during Normal Operations,While Conducting Routine Insp,Nrc Inspector Found Missed Tech Spec Surveillance Reading.Caused by Personnel Error.Surveillance Posted on Plant Status Board | | | 05000272/LER-1979-022, Forwards LER 79-022/03L-0 | Forwards LER 79-022/03L-0 | | | 05000272/LER-1979-024, Forwards LER 79-024/03L-0 | Forwards LER 79-024/03L-0 | | | 05000272/LER-1979-024-03, /03L-0 on 790313:air Particulate Monitor Was Declared Inoperable.Caused by Failing Motor Bearings Which Led Filter Paper Drive to Slow & Activate Failed Filter Alarm.Motor Was Cleaned & Bearing Replaced | /03L-0 on 790313:air Particulate Monitor Was Declared Inoperable.Caused by Failing Motor Bearings Which Led Filter Paper Drive to Slow & Activate Failed Filter Alarm.Motor Was Cleaned & Bearing Replaced | | | 05000272/LER-1979-025, Forwards LER 79-025/03L-0 | Forwards LER 79-025/03L-0 | | | 05000272/LER-1979-025-03, /03L-0 on 790315:during Normal Operation on 790302,retest Not Performed After 790302 Maint on Chilled Water Pump 11.Caused by Personnel Error.Procedure Reviewed & Rewritten | /03L-0 on 790315:during Normal Operation on 790302,retest Not Performed After 790302 Maint on Chilled Water Pump 11.Caused by Personnel Error.Procedure Reviewed & Rewritten | | | 05000272/LER-1979-026, Forwards LER 79-026/03L-0 | Forwards LER 79-026/03L-0 | | | 05000272/LER-1979-026-03, /03L-0 on 790318:No 13 Reactor Coolant Loop Protection Channel III Inoperable.Caused by Faulty Channel Summator Module.Summator Was Replaced | /03L-0 on 790318:No 13 Reactor Coolant Loop Protection Channel III Inoperable.Caused by Faulty Channel Summator Module.Summator Was Replaced | | | 05000272/LER-1979-027-01, /01X-1 on 790325:while Providing Backup Protection to Hope Creek,Facility Fresh Water Tanks Were Below Tech Spec Required Levels.Caused by Poor Communications Between Facilities.Water Level Restored | /01X-1 on 790325:while Providing Backup Protection to Hope Creek,Facility Fresh Water Tanks Were Below Tech Spec Required Levels.Caused by Poor Communications Between Facilities.Water Level Restored | | | 05000272/LER-1979-027, Forwards LER 79-027/01X-1 | Forwards LER 79-027/01X-1 | | | 05000272/LER-1979-028, Has Been Voided | Has Been Voided | | | 05000272/LER-1979-029-03, /03L-0 on 790320:during Channel Functional Test High Voltage Was Found to Be Low.Caused by Breakdown of Diode in High Voltage Power Supply.Diode Was Replaced & Channel Functional Was Completed | /03L-0 on 790320:during Channel Functional Test High Voltage Was Found to Be Low.Caused by Breakdown of Diode in High Voltage Power Supply.Diode Was Replaced & Channel Functional Was Completed | | | 05000272/LER-1979-029, Forwards LER 79-029/03L-0 | Forwards LER 79-029/03L-0 | |
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