LER-1979-048, Forwards LER 79-048/03L-0 |
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| 2771979048R00 - NRC Website |
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PHILADELPHI A ELECTRIC COM PANY 2301 M ARKET STREET P.O. BOX 8699 PHILADELPHI A. PA.19101 (215)8414000 November 29, 1979 Mr. Boyce H.
Grier, Director Office of Inspection and Enf orcement Region I United States Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406
Dear Mr. Grier:
SUBJECT:
License Event Report Narrative Description
Reference:
Docket No. 50-277 Report No:
LER 2-79-48/3L Report Date:
November 29, 1979 Occurrence Date:
October 30, 1979 Facility:
Peach Bottom Atomic Power Station RD.
1, Delta, PA 17314 Technical Specification Reference:
This occurrence is rep ortable under Technical Specifications 3.8.C.7.a and 3.8.C.8.
Technical Specification 3.8.C.7.a states "During release of gaseous wastes the following conditions shall be met: monitors for gross gas activity, iodine and particulate sampler shall be op e r a b le.
Technical Specification 3.8.C.8 states "One reactor building exhaust vent and one plant stack monitoring system shall be operable and the off-gas radiation monitors shall be operable or operating whenever s team p ressure is available to the air ejectors.
If these requirements are not satisfied, a normal orderly shutdown shall be initiated within one h ou r, and the reactor shall be in the hot shutdown condition within 10 hourk in the case of the stack monitor or 10 days in the case of the building vent monitor."
Description of the Event:
With Unit 2 at power and Unit 3 off for refueling, at approximately 4:45 pm on 10/30/79 during relamping of the main 1542 158 7 912120j3eF[$
Mr. Boyce H.
Grier Page 2 off-gas stack observation li gh t s, it was discovered that the main stack isokinetic sample line was broken.
The defective sample line was removed from scrvice and a temporary isokinetic probe and samp le line was placed in service within 35 minutes after the
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discovery.
The damaged sample line was t e mp o ra rily repaired and returned to service within two h ou rs after the event and permanent repairs were performed the next day (10/31/79).
No unit power reduction was required per Tech. Spec. 3 8.c.8 because the temporary sample line was in service in less than one hour after the event.
Before returning to service, the permanent sample line was velocity cleaned using compressed air.
When the system was placed in service, a significant decrease in sample vacuum was noted which indicates a partial restriction had existed.
It is believed that the restriction reduced the indicated release rate of short lived particulate.
Consequences of Event After permanent repairs were made to the s a mp le line, the indicated nobic gas release rate increased by a factor of approximately 2.1.
Based on a review of the is ot op ic gamma analysis done on the holdup pipe samples during the past six months which showed normally lower readings than the calculated release rate from the noble gas radiation monitors, and based on the conservatism in the noble gas radiation monitor calculation, it is believed that a correction factor need not be applied to ca lcu la t e d noble gas releases during the period between the estimated f ailu re date and the date of repair.
The iodine (131) and particulate (h a lf lives less than eight days) indicated release rate increased by a factor of about six after repairs were made.
It is believed that a portion of the increase resulted from the cleaning of the sample line.
- However, since the release rates before and after the repair were so very low (a b ou t 0.00055 % of Tech Spec.
instantaneous limit), it is extremely difficult to determine whether the change in release rate was due to sample line problems or to fluctuations in the release rate.
Using a correction factor of six, the h i gh es t instantaneous release rate during the last six months would have been only 0.02 % of Tech spec limit.
Applying the factor of six results in an insignificant ch an ge in the quarterly Tech Spec release limit.
Cause o _f_
Ev e n t Upon inspection of the s a mp le line failure it appeared that the line had been crimped at a "U" clamp support bracket.
It is believed that the failure resulted from subsequent fatigue from expansion, contraction, and wind loading.
In retrospect, after reviewing the main stack radiation recorder t ra ces, it appears that the f ailure may have occurred on 1542 159
Mr. Boyce II. Grier Page 3 September 14, 1979, during a violent thunderstorm.
After the storm, the monitor experienced low s amp le flow.
After the correct flow was established, monitor readings dropped by a factor of two.
An investigation revealed no apparent problems and the monitor continued to respond to varying plant conditions, therefore it was believed to be operating correctly.
Even with a broken sample line, the monitor received a diluted but representative sample of stack gas which was contained by the insulation and heating tracing.
Corrective Action
Within 35 minutes of the discovery of the failure, a t emp ora ry isokinetic probe and sample line was placed into service in accordance with Special Procedure No. 298 which permitted normal operation of main stack radiation monitors with t e mp ora ry lodine and particulate sampling.
T e mp o ra ry repairs were c omp le t e d and normal operation resumed on the main stack radiation monitoring system within two h ours of the event.
The next day, 10/31/79, the s a mp le line was permanently repaired.
Before returning to service, the permanent sample line was velocity cleaned using compressed air.
After the system was placed int o s ervice, a significant decrease in sample vacuum was noted which indicates there had been a partial restriction in the line.
An air test at 40 psig was successfully performed to prove the integrity of the sample line.
The sample line was checked at each of the support brackets for crimping and breakage and no evidence of damage was found.
In addition, once a week during the normal filter change, a dif f erential p ressure test is now performed to prove the integrity of the sample line.
Philadelphia Electric Company's Engineering Department is reviewing the f ailu re to determine if additional corrective action is required.
1542 160
Mr. B oy ce H.
Grier Page 4 The iodine and particulate release rates will be increased by a factor of six f rom Sep tembe r 14, 1979 to October 30, 1979 in the s e mi -a n n u a l report to c on s e r va t ive ly account for releases during this period.
Because of"the c on s e r va t i ve calculation method used f or noble gas releases no correction is anticipated.
Very truly yours,
' fl( ( <
M.
J.
Cooney SIfperintendent Generation Division - Nuclear At ta ch me n t cc:
Director, NRC - Office of Inspection and Enforcement Mr. Norman M.
Haller, NRC Office of Management &
Program Analysis 1542 161
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| 05000277/LER-1979-001, Forwards LER 79-001/01T-0 | Forwards LER 79-001/01T-0 | | | 05000277/LER-1979-001-01, /01T-0 on 790104:design Errors in Cable Designations Were Identified.Ten Cables Found to Be Designated Nonsafeguard.Caused by Improper Designation of Cables During Design Phase.New Cable Routing Completed | /01T-0 on 790104:design Errors in Cable Designations Were Identified.Ten Cables Found to Be Designated Nonsafeguard.Caused by Improper Designation of Cables During Design Phase.New Cable Routing Completed | | | 05000278/LER-1979-001-03, /03L-0 on 790111:discovered That Recorded hi-hi Trip Valve for Steam Line Radiation Monitor Was 50 man-rem/h Greater than Tech Spec Limit & No Corrective Action Taken. Caused by Procedural Deficiency | /03L-0 on 790111:discovered That Recorded hi-hi Trip Valve for Steam Line Radiation Monitor Was 50 man-rem/h Greater than Tech Spec Limit & No Corrective Action Taken. Caused by Procedural Deficiency | | | 05000277/LER-1979-002-01, /01T-0 on 790108:cable Spreading Room Cardox Sys Disabled W/O Firewatch Present.Absence Due to Failure of Personnel to Notify Shift Supervisor Upon Work Completion | /01T-0 on 790108:cable Spreading Room Cardox Sys Disabled W/O Firewatch Present.Absence Due to Failure of Personnel to Notify Shift Supervisor Upon Work Completion | | | 05000277/LER-1979-002, Forwards LER 79-002/01T-0 | Forwards LER 79-002/01T-0 | | | 05000278/LER-1979-002-01, /01T-0 on 790108:roof Vent Stack Instantaneous Gas Release Rate Above Tech Spec Limit Due to Valve Operator Failure,Causing Loss of Inservice RHR Loop,Rise in Coolant Temp & Gaseous Release Via Core Isolation Cooling Valves | /01T-0 on 790108:roof Vent Stack Instantaneous Gas Release Rate Above Tech Spec Limit Due to Valve Operator Failure,Causing Loss of Inservice RHR Loop,Rise in Coolant Temp & Gaseous Release Via Core Isolation Cooling Valves | | | 05000278/LER-1979-002, Forwards LER 79-002/01T-0 | Forwards LER 79-002/01T-0 | | | 05000277/LER-1979-003-03, /03L-0 on 790109:2A Offgas Radiation Monitor Failed Downscale.Dirt on Contacts of Trip Test/Zero Calibr Switch Caused Input Key to Remain Deenergized Upon Release of Switch.Contacts Were Cleaned & Monitor Returned to Svc | /03L-0 on 790109:2A Offgas Radiation Monitor Failed Downscale.Dirt on Contacts of Trip Test/Zero Calibr Switch Caused Input Key to Remain Deenergized Upon Release of Switch.Contacts Were Cleaned & Monitor Returned to Svc | | | 05000278/LER-1979-003-03, /03L-0 on 790111:during Unit Shutdown for Maint an Instrument Shutoff Valve to Pressure Switch Found Closed Due to Personnel Error.Unit Operated 9 Days W/Instrument Out of Svc.Appropriate Disciplinary Action Taken | /03L-0 on 790111:during Unit Shutdown for Maint an Instrument Shutoff Valve to Pressure Switch Found Closed Due to Personnel Error.Unit Operated 9 Days W/Instrument Out of Svc.Appropriate Disciplinary Action Taken | | | 05000277/LER-1979-004-03, /04L-0 on 790112:during Surveillance Test of Cable Spreading Room Smoke Detector,Annunciator Could Not Be Reset Because It Was Not Properly Reset Previously.Detector Lead Disconnected to Reset Annunciator | /04L-0 on 790112:during Surveillance Test of Cable Spreading Room Smoke Detector,Annunciator Could Not Be Reset Because It Was Not Properly Reset Previously.Detector Lead Disconnected to Reset Annunciator | | | 05000278/LER-1979-004-03, /03L-0 on 790117:during Surveillance Test,Setpoint of PS-3-14-44D Found to Be Greater than Tech Spec Max.Caused by Setpoint Drift on static-o-ring Model 5N-AA3 Pressure Switch.Instrument Recalibrated | /03L-0 on 790117:during Surveillance Test,Setpoint of PS-3-14-44D Found to Be Greater than Tech Spec Max.Caused by Setpoint Drift on static-o-ring Model 5N-AA3 Pressure Switch.Instrument Recalibrated | | | 05000277/LER-1979-005-03, /03L-0 on 790118:at Power,Routine Surveillance Test Revealed Setpoint of DPIS-2-14-43B Was Below Tech Spec Min.Caused by Instrument DPIS-2-14-43B Being Out of Calibr Due to Setpoint Drift | /03L-0 on 790118:at Power,Routine Surveillance Test Revealed Setpoint of DPIS-2-14-43B Was Below Tech Spec Min.Caused by Instrument DPIS-2-14-43B Being Out of Calibr Due to Setpoint Drift | | | 05000278/LER-1979-005-03, /03L-0 on 790208:setpoint of Reactor Core Isolation Cooling Turbine Steam Supply Flow Sensor Was Above Tech Specs Max.Caused by Setpoint Drift on Barton Model 288 Differential Pressure Switch.Switch Recalibrated | /03L-0 on 790208:setpoint of Reactor Core Isolation Cooling Turbine Steam Supply Flow Sensor Was Above Tech Specs Max.Caused by Setpoint Drift on Barton Model 288 Differential Pressure Switch.Switch Recalibrated | | | 05000277/LER-1979-006-01, /01T-0 on 790130:recirculation Motor Generator Set Room Fire Detection Sys (Smoke Detectors) Disabled for Mod Work & Not Restored When Work Completed.Caused by Personnel Error.Sys Restored to Svc Upon Discovery | /01T-0 on 790130:recirculation Motor Generator Set Room Fire Detection Sys (Smoke Detectors) Disabled for Mod Work & Not Restored When Work Completed.Caused by Personnel Error.Sys Restored to Svc Upon Discovery | | | 05000277/LER-1979-006, Forwards LER 79-006/01T-0 | Forwards LER 79-006/01T-0 | | | 05000278/LER-1979-006-03, /03L-1 on 790212:at Power & During Surveillance Test,Setpoint of B Core Spray Pump Start Timer Was Less than Tech Spec Min.Caused by Setpoint Drift on GE Model CR-2820 Time Delay Relay.Relay Readjusted & Tested | /03L-1 on 790212:at Power & During Surveillance Test,Setpoint of B Core Spray Pump Start Timer Was Less than Tech Spec Min.Caused by Setpoint Drift on GE Model CR-2820 Time Delay Relay.Relay Readjusted & Tested | | | 05000278/LER-1979-007-03, /03L-0 on 790212:during Surveillance,Setpoint of a Logic Automatic Depressurization Sys Time Delay Relay Was Greater than Tech Spec Limit.Caused by Setpoint Drift on GE Model CR-2820 Time Delay.Relay Readjusted & Tested | /03L-0 on 790212:during Surveillance,Setpoint of a Logic Automatic Depressurization Sys Time Delay Relay Was Greater than Tech Spec Limit.Caused by Setpoint Drift on GE Model CR-2820 Time Delay.Relay Readjusted & Tested | | | 05000277/LER-1979-008-03, /03L-0 on 790225:fuses Were Blown in Control Circuit of Main Steam Relief Valve RV-71L.Replacements Blew Immediately.Caused by Failed Solenoid & Short Circuit.Leads to Solenoid Lifted;Fuses & Solenoid Replaced | /03L-0 on 790225:fuses Were Blown in Control Circuit of Main Steam Relief Valve RV-71L.Replacements Blew Immediately.Caused by Failed Solenoid & Short Circuit.Leads to Solenoid Lifted;Fuses & Solenoid Replaced | | | 05000277/LER-1979-008, Forwards LER 79-008/01T-0 | Forwards LER 79-008/01T-0 | | | 05000277/LER-1979-008-01, /01T-0 on 790219:steady State Power Level Exceeded License Limit by Less than 2% for About 6-h.Caused by Error Calculating Scanned Feedwater Flow.Power Reduced to License Limit | /01T-0 on 790219:steady State Power Level Exceeded License Limit by Less than 2% for About 6-h.Caused by Error Calculating Scanned Feedwater Flow.Power Reduced to License Limit | | | 05000277/LER-1979-009-03, /03L-0 on 790213:fire Alarm Sys Malfunctioned, Causing Audible Signal to Alarm W/O Coding.Caused by Mechanical Binding of Cam in Alarm Box.Binding Problem Corrected & Sys Returned to Svc | /03L-0 on 790213:fire Alarm Sys Malfunctioned, Causing Audible Signal to Alarm W/O Coding.Caused by Mechanical Binding of Cam in Alarm Box.Binding Problem Corrected & Sys Returned to Svc | | | 05000278/LER-1979-009-03, /03L-0 on 790307:calculated Torus Water Level Did Not Provide Proper Torus Water Vol Per Tech Spec.Caused by Failure to See Pressure Differential Between Drywell & Torus Holds Level in Downcomers Was Below Torus Level | /03L-0 on 790307:calculated Torus Water Level Did Not Provide Proper Torus Water Vol Per Tech Spec.Caused by Failure to See Pressure Differential Between Drywell & Torus Holds Level in Downcomers Was Below Torus Level | | | 05000277/LER-1979-010-01, /01T-0 on 790226:power & Control Cables Associated W/Recirculation Pump Discharge Valves & Bypass Valves Were Found Routed in non-safeguard Cable Trays.Caused by Improperly Designated Cables During Design Phase | /01T-0 on 790226:power & Control Cables Associated W/Recirculation Pump Discharge Valves & Bypass Valves Were Found Routed in non-safeguard Cable Trays.Caused by Improperly Designated Cables During Design Phase | | | 05000277/LER-1979-010, Forwards LER 79-010/01T-0 | Forwards LER 79-010/01T-0 | | | 05000278/LER-1979-011-01, /01T-0 on 790323:during Routine Insp of Drywell & Torus Ventilation Valves,Inflatable Disc Seals Were Found Depressurized.Caused by Procedural Deficiency Following Mod to Drywell & Torus Vent Valves.Procedures Revised | /01T-0 on 790323:during Routine Insp of Drywell & Torus Ventilation Valves,Inflatable Disc Seals Were Found Depressurized.Caused by Procedural Deficiency Following Mod to Drywell & Torus Vent Valves.Procedures Revised | | | 05000278/LER-1979-011, Forwards LER 79-011/01T-0 | Forwards LER 79-011/01T-0 | | | 05000277/LER-1979-011-01, /01T-0 on 790302:engineering Review Determined Certain Containment Isolation Valves Incapable of Closing Against LOCA Pressure.Caused by Design Oversight.Future Mod to Expand Valve Open Alarm to Include Seal Low Pressure | /01T-0 on 790302:engineering Review Determined Certain Containment Isolation Valves Incapable of Closing Against LOCA Pressure.Caused by Design Oversight.Future Mod to Expand Valve Open Alarm to Include Seal Low Pressure | | | 05000277/LER-1979-011, Forwards LER 79-011/01T-0 | Forwards LER 79-011/01T-0 | | | 05000278/LER-1979-013-01, /01T-0 on 790613:main Steam Relief Valve RV3-2-71L Lifted,Causing Torus Water Vol to Exceed Tech Spec Limit by 2.6%.Reactor Manually Scrammed.Valve Replaced & Sent to Wiley Lab to Determine Cause for Failure | /01T-0 on 790613:main Steam Relief Valve RV3-2-71L Lifted,Causing Torus Water Vol to Exceed Tech Spec Limit by 2.6%.Reactor Manually Scrammed.Valve Replaced & Sent to Wiley Lab to Determine Cause for Failure | | | 05000278/LER-1979-013, Forwards LER 79-013/01T-0 | Forwards LER 79-013/01T-0 | | | 05000278/LER-1979-014, /O3L-0 on 790522:offsite Source Breaker SU25 Tripped on Low Air Pressure.Caused by Short Circuit in Light Socket & Dirty Contacts on Voltage Relay.Relay Contacts Cleaned & Socket Removed Pending Replacement | /O3L-0 on 790522:offsite Source Breaker SU25 Tripped on Low Air Pressure.Caused by Short Circuit in Light Socket & Dirty Contacts on Voltage Relay.Relay Contacts Cleaned & Socket Removed Pending Replacement | | | 05000277/LER-1979-014-03, /03L-0 on 790327:trip Setpoint Drift of Drywell High Pressure Switch Was Beyond Tech Spec Limit.Caused by Static-O-Ring Model 12N-AA4 Being Out of Calibr Due to Setpoint Drift.It Was Recalibrated & Returned to Svc | /03L-0 on 790327:trip Setpoint Drift of Drywell High Pressure Switch Was Beyond Tech Spec Limit.Caused by Static-O-Ring Model 12N-AA4 Being Out of Calibr Due to Setpoint Drift.It Was Recalibrated & Returned to Svc | | | 05000278/LER-1979-015, /O3L-0 on 790523:automatic Depressurization Sys a Auto Blowdown Timer Trip Setting Found 13-s Less than Tech Spec Min.Caused by Setpoint Drift of Time Delay Relay.Relay Readjusted,Tested & Returned to Svc | /O3L-0 on 790523:automatic Depressurization Sys a Auto Blowdown Timer Trip Setting Found 13-s Less than Tech Spec Min.Caused by Setpoint Drift of Time Delay Relay.Relay Readjusted,Tested & Returned to Svc | | | 05000278/LER-1979-016-03, /03L-0 on 790628:while at Power,Routine Surveillance Test Revealed Setpoint of Switch 2 Was Below Tech Spec Min.Caused by Barton Model 288 Instrument Out of Calibr from Drift.Instrument Recalibr | /03L-0 on 790628:while at Power,Routine Surveillance Test Revealed Setpoint of Switch 2 Was Below Tech Spec Min.Caused by Barton Model 288 Instrument Out of Calibr from Drift.Instrument Recalibr | | | 05000278/LER-1979-017-31, /03L-0 on 790615:while Reactor Subcritical,D Main Steam Line Radiation Monitor Hi-Hi Trip Failed.Caused by Dirty Trip Relay or Dirty Test Switch Contacts. Condition Corrected by Repeated Testing | /03L-0 on 790615:while Reactor Subcritical,D Main Steam Line Radiation Monitor Hi-Hi Trip Failed.Caused by Dirty Trip Relay or Dirty Test Switch Contacts. Condition Corrected by Repeated Testing | | | 05000278/LER-1979-017, Discusses LER 79-017/03L-0.While Reactor Subcritical & Less than 212 F,Main Steam Line D Radiation Monitor Hi-Hi Trip Failed.Caused by Dirty Trip Relay or Dirty Test Switch Contacts.Repeated Testing Corrected Condition | Discusses LER 79-017/03L-0.While Reactor Subcritical & Less than 212 F,Main Steam Line D Radiation Monitor Hi-Hi Trip Failed.Caused by Dirty Trip Relay or Dirty Test Switch Contacts.Repeated Testing Corrected Condition | | | 05000278/LER-1979-018-03, /03L-0 on 790630:during Surveillance Testing, Reactor Water Sample Line Isolation Valve Failed to Close. Caused by Lack of Valve Operator Spring Tension.Valve Operator Spring Tension Was Increased | /03L-0 on 790630:during Surveillance Testing, Reactor Water Sample Line Isolation Valve Failed to Close. Caused by Lack of Valve Operator Spring Tension.Valve Operator Spring Tension Was Increased | | | 05000277/LER-1979-019-03, /03L-0 on 790501:during Surveillance Testing of Normally Open Primary Containment Isolation Valves,Four Oxygen Analyzer Sys Isolation Valves Failed to Close.Caused by Binding of Pistons in Valve Bodies.Valve Parts Rebuilt | /03L-0 on 790501:during Surveillance Testing of Normally Open Primary Containment Isolation Valves,Four Oxygen Analyzer Sys Isolation Valves Failed to Close.Caused by Binding of Pistons in Valve Bodies.Valve Parts Rebuilt | | | 05000278/LER-1979-019-01, /01T-0 on 790621:during Seismic Support Insp Program, Reactor Core Isolation Cooling Piping Anchor Discovered to Have Two Bolts That Could Not Be Torqued. Caused by Improper Installation of Bolt Shells | /01T-0 on 790621:during Seismic Support Insp Program, Reactor Core Isolation Cooling Piping Anchor Discovered to Have Two Bolts That Could Not Be Torqued. Caused by Improper Installation of Bolt Shells | | | 05000278/LER-1979-019, Forwards LER 79-019/01T-0 | Forwards LER 79-019/01T-0 | | | 05000277/LER-1979-020-03, /03L-0 on 790503:solution Temp in Standby Liquid Control Sys Found to Be 2 F Less than Tech Spec Requirement for Existing Boron Concentration.Caused by Incorrect Acceptable Temp Controller Setpoint Range | /03L-0 on 790503:solution Temp in Standby Liquid Control Sys Found to Be 2 F Less than Tech Spec Requirement for Existing Boron Concentration.Caused by Incorrect Acceptable Temp Controller Setpoint Range | | | 05000278/LER-1979-020-01, /01T-0 on 790621:radioactive Release Rate at Main Stack During Plant Startup Exceeded Tech Specs.Caused by Deficiency in Procedure for Depressurization Following Shutdown.Investigation Underway to Improve Procedure | /01T-0 on 790621:radioactive Release Rate at Main Stack During Plant Startup Exceeded Tech Specs.Caused by Deficiency in Procedure for Depressurization Following Shutdown.Investigation Underway to Improve Procedure | | | 05000278/LER-1979-020, Forwards LER 79-020/01T-0 | Forwards LER 79-020/01T-0 | | | 05000278/LER-1979-021-03, /03X-1:on 790630,during Surveillance Testing,Main Steam Sample Line Inboard Isolation Valve Failed to Close. Probably Caused by Valve Packing Binding or Solenoid Valve Sticking While Valve Was at High Temp | /03X-1:on 790630,during Surveillance Testing,Main Steam Sample Line Inboard Isolation Valve Failed to Close. Probably Caused by Valve Packing Binding or Solenoid Valve Sticking While Valve Was at High Temp | | | 05000277/LER-1979-022-03, /03L-0 on 790513:fire Hose Nozzles Were Missing from Two Hose Stations in Turbine Bldg.Cause Not Noted. Nozzles Replaced & Wrench Tightened to Inhibit Removal | /03L-0 on 790513:fire Hose Nozzles Were Missing from Two Hose Stations in Turbine Bldg.Cause Not Noted. Nozzles Replaced & Wrench Tightened to Inhibit Removal | | | 05000278/LER-1979-022-03, /03L-0 on 790719:annunciator Sys II Drywell Pressure Permits Containment Spray Alarmed During Routine Startup.Caused by Failure of Diaphragm on PS-3-10-119D. Switch Repaired,Tested & Returned to Svc within Five Days | /03L-0 on 790719:annunciator Sys II Drywell Pressure Permits Containment Spray Alarmed During Routine Startup.Caused by Failure of Diaphragm on PS-3-10-119D. Switch Repaired,Tested & Returned to Svc within Five Days | | | 05000277/LER-1979-023-01, /01T-0 on 790724:insp Program Performed in Response to IE Bulletin 79-02 Identified Two Anchors in One Support Which Failed to Torque Test Properly.Caused by Improper Installation.Anchors Replaced | /01T-0 on 790724:insp Program Performed in Response to IE Bulletin 79-02 Identified Two Anchors in One Support Which Failed to Torque Test Properly.Caused by Improper Installation.Anchors Replaced | | | 05000277/LER-1979-023, Forwards LER 79-023/01T-0 | Forwards LER 79-023/01T-0 | | | 05000277/LER-1979-023-04, /04T-0 on 790515:routine Ph Analysis of Sewage Plant Effluent Identified Ph of 5.8 Which Exceeded Tech Specs.Caused by Air Blower Failure Which Allowed Dissolved Oxygen to Drop to 0 & Aeration Tank to Become Anaerobic | /04T-0 on 790515:routine Ph Analysis of Sewage Plant Effluent Identified Ph of 5.8 Which Exceeded Tech Specs.Caused by Air Blower Failure Which Allowed Dissolved Oxygen to Drop to 0 & Aeration Tank to Become Anaerobic | | | 05000277/LER-1979-024, Forwards LER 79-024/01T-0 | Forwards LER 79-024/01T-0 | |
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