LER-1980-007, Forwards LER 80-007/01T-0 |
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l PHILADELPHIA ELECTRIC COMPANY 2301 MARKET STREET P.O. BOX 8699 PHILADELPHIA. PA.19101 azisieai4ooo March 6, 1980 Hr. Boyse H.
Grier, Director Office of Inspection and Enforcement Region I US Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406
Dear Mr. Grier:
SUBJECT:
L i c e_n s e e _Ev_e n t Report Narrative Description The following occurrence was reported to Mr. Greenman, US Nuclear Regulatory Commission, Region I,
Office of Inspection and Enforcement on February 21, 1980.
Reference:
Docket No. 50-278 Report No.;
LER 3-80-7/IT Report Date:
March 6, 1980 Occurrence Date:
February 21, 1980 Facility:
Peach Bottom Atomic Power Station RD 1, Delta, PA 17314 Technical Specifications Reference:
Technical Specifications 6.9.2.a.(6) states in part
" Personnel arror or procedural inadequacy which prevents or could prevent, by itself, the fulfillment of the functional requirements of systems required to cope with a c c id e :i t s analyzed in the SAR" shall be reported.
Description of the Event a)
During a routine inspection of plant equipment, the back up seismically qualified, bottled nitrogen supply to five containment ventilation valves was found valved out of service.
The valves, however, were being supplied from the normal instrument air supply and therefore, the boot seals were inflated and containment integrity was maintained.
The normal instrument air supply is not seismically qualified. /9002 5
///
8003180 g
Mr. Bo y c e 11. Grior Page 2 LER 3-80-7/1T b)
When the first seismic back up bottle supply was found closed, an investigation into the cause and an inspection of all containment ventilation valves was inacdiately initiated.
Additionally, a blocking error was al"9 identified.
At approximately 3:20 a.m.
on 2/20/ts, ventilation valve A0-3512 was blocked for modification work.
The. operator applying the blocking permit incorrectly valved out the disc seal air supply to A0-3511 as well as A0-3512.
At the time the inspection was made, the disc seal pressure on these valves was 15 psig and 55 osig.
Normal seal pressure is greater than 75 psig.
The inspection of all other Unit 2 & 3 containment ventilation valves did not identify any other deficiencies.
Consequences of the Event:
a)
If a seismic event occurred which resulted in failure of.the instrument air system, the five valves involved could have permitted containment leakage after some time interval if corrective action was not taken.
If a seismic event had occur ed, the valves would have remained sealed for about 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> based on testing of a set of these valves.
If the disc seal pressure decayed to about 62 psig, an indicating light in the control room would indicate a deflated disc seal for four of the five valves involved.
(Pressure switch installation on ene fifth valve was not completed at chts date).
The required once per shift panel check by the operator would have identified the condition of four of the five valves and the seismic air supply would have been re-established prior to loss of containment integrity.
This occurrence could have resulted in loss of containment integrity following a postulated seismic event only if j
additional operator errors had occurred and if j
administrative controls were not adhered to.
i i
i b)
Leak tests performed to determine seal capability of A0-3511 I
and A0-3512 at the disc seal pressure existing wnen the I
blocking error was found indicated leakage well below the i j' acceptable level.
This occurrence could have resulted in loss of containment integrity if the disc seal pressure decayed without notice.
I t
Cause of the Event
a)
Investigation has shown that the back up, seismically qualified, bottled nitrogen supplies to the five containment ventilation valves have been valved out of service since December 23, 1979.
The containment ventilation valves are being modified to qualify them for operation during seismic l~
event.
Some of the valves have been modified, and some have not.
Those valves which are not modified have a seismically qualified nitrogen bottle supply to the valve disc seal which is manually actuated follo4ing the positioning of the valve in the closed position.
It order to ouen these i
Mr. Boyco H.
Grior Page 3 LER 3-80-7/lT 1
unmodified valves, an operator must valve out this bottle supply to the disc seal prior to operating the valve from the control room.
The same nitrogen bottles have a different purpose on the modified valves, and the nitrogen bottles on these five modified valves were valved out of service in-the mistaken belief that the bottles were no longer needed.
b)
The blocking error was caused by a lack of equipment identification and inadequate operator training.
Corrective Actionsi When the first seismic air suppif was found valved out, an inspection of all containment ventilation valves was immediately initiated.
This inspection identified four other bottled supplies which were valved out of service, along with the blocking error.
All problems were corrected immediately.
l The operators were instructed as to the status of all containment I
ventilation valves.
Tags were hung on all air supply valves, both seismic back-up and normal, indicating the normal valve position.
Applicable procedures and check-off lists have been revised to include the position of valves associated with the containment ventilation valves.
The bottle pressure round sheet has been converted to a surveillance test to ensure that the seismic back up supply is functional.
Previous Similar Occurrence:
I LER 2-80-1/IT Very truly yours,
/E'Y Qft
'A.
Coone Su erinten nt Generation Division - Nuclear Attachment l
cc:
Director, NRC - Office of Inspection and Enforcement Mr. Norman M.
Haller, NRC - Office of Hanagement &
li Program Analysis I
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| 05000278/LER-1980-001-03, /03L-0:on 800106,during Surveillance Tests,Main Steam Line Radiation Monitor D Failed to Actuate hi-hi Trip to Initiate Channel B one-half Scram & Group 1 Isolation. Cause Unknown.Monitor Replaced | /03L-0:on 800106,during Surveillance Tests,Main Steam Line Radiation Monitor D Failed to Actuate hi-hi Trip to Initiate Channel B one-half Scram & Group 1 Isolation. Cause Unknown.Monitor Replaced | | | 05000277/LER-1980-001-01, /01T-0:on 800103,w/Unit 2 at Power & Drywell Being Deinerted in Preparation for Planned Outage,Drywell Ventilation Isolation Valves AO-2521A & AO-2521B Discovered Fully Open.Caused by Lack of Procedural Control | /01T-0:on 800103,w/Unit 2 at Power & Drywell Being Deinerted in Preparation for Planned Outage,Drywell Ventilation Isolation Valves AO-2521A & AO-2521B Discovered Fully Open.Caused by Lack of Procedural Control | | | 05000277/LER-1980-001, Forwards LER 80-001/01T-0 | Forwards LER 80-001/01T-0 | | | 05000278/LER-1980-002-03, /03L-0:on 800118,while at Power During Insertion of Tip Probe 5 Into Core,Tip Probe Inshield Light Came On. Probe Could Be Inserted,But Not Withdrawn.Caused by Tip Inshield Limit Switch Being Out of Calibr | /03L-0:on 800118,while at Power During Insertion of Tip Probe 5 Into Core,Tip Probe Inshield Light Came On. Probe Could Be Inserted,But Not Withdrawn.Caused by Tip Inshield Limit Switch Being Out of Calibr | | | 05000277/LER-1980-002-01, /01T-0:on 800110,during Leak Testing of Automatic Depressurization Sys safety-related Instrument Air Supply Piping,Identified Hard Seated Check Valves That Showed Leakage in Reverse Direction.Cause Not Stated | /01T-0:on 800110,during Leak Testing of Automatic Depressurization Sys safety-related Instrument Air Supply Piping,Identified Hard Seated Check Valves That Showed Leakage in Reverse Direction.Cause Not Stated | | | 05000277/LER-1980-002, Forwards LER 80-002/01T-0 | Forwards LER 80-002/01T-0 | | | 05000278/LER-1980-003-03, /03L-0:on 800303,while Performing Surveillance tests,MO-3-10-25A LPCI on A,Loop Failed to Open & RHR Pump Would Not Start.Caused by Galled Walworth 24-inch Gate, Pressure Seal Bonnet.Valve Repaired & Leak Tested | /03L-0:on 800303,while Performing Surveillance tests,MO-3-10-25A LPCI on A,Loop Failed to Open & RHR Pump Would Not Start.Caused by Galled Walworth 24-inch Gate, Pressure Seal Bonnet.Valve Repaired & Leak Tested | | | 05000277/LER-1980-004-03, /03L-0:on 800123,while Performing Routine Rod Block Monitor Surveillance,Channel B Flow Biased Rod Setpoints on Rod Block Monitor Found Out of Spec by Approx 11%.Caused by Diode Failure in Analog Circuit | /03L-0:on 800123,while Performing Routine Rod Block Monitor Surveillance,Channel B Flow Biased Rod Setpoints on Rod Block Monitor Found Out of Spec by Approx 11%.Caused by Diode Failure in Analog Circuit | | | 05000278/LER-1980-004, Forwards LER 80-004/03L-0 | Forwards LER 80-004/03L-0 | | | 05000278/LER-1980-004-03, /03L-0:on 800205 During Plant Startup,Reactor Water Conductivity Increased & Exceeded Tech Spec Limits. Caused by Resin Injection.Reactor Was Shut Down & Primary Coolant Chemistry Brought within Tech Spec Limits | /03L-0:on 800205 During Plant Startup,Reactor Water Conductivity Increased & Exceeded Tech Spec Limits. Caused by Resin Injection.Reactor Was Shut Down & Primary Coolant Chemistry Brought within Tech Spec Limits | | | 05000277/LER-1980-005-03, /03L-0:on 800126,while at Power Operation, Surveillance Testing of Diesel Driven Fire Pump Revealed Flow Less than Tech Specs.Caused by Slippage of Throttle Cable Governor,Resulting in Setpoint Drift | /03L-0:on 800126,while at Power Operation, Surveillance Testing of Diesel Driven Fire Pump Revealed Flow Less than Tech Specs.Caused by Slippage of Throttle Cable Governor,Resulting in Setpoint Drift | | | 05000278/LER-1980-005-03, /03L-0:on 800207,during Surveillance Test,Setpoint of DPIS 3-13-84,reactor Core Isolation Cooling Turbine Steam Supply High Flow Sensor Found to Be 10 Inches of Water Greater than Tech Spec.Caused by Setpoint Drift | /03L-0:on 800207,during Surveillance Test,Setpoint of DPIS 3-13-84,reactor Core Isolation Cooling Turbine Steam Supply High Flow Sensor Found to Be 10 Inches of Water Greater than Tech Spec.Caused by Setpoint Drift | | | 05000277/LER-1980-006-03, /03L-0:on 800305,w/both Units at Full Power,One of Two Offsite Power Sources Tripped Due to Loss of Transformer Cooling Fans.Exact Cause Unknown.Cooling Fans Restored,Blown Fuse Replaced & Transformer Tested | /03L-0:on 800305,w/both Units at Full Power,One of Two Offsite Power Sources Tripped Due to Loss of Transformer Cooling Fans.Exact Cause Unknown.Cooling Fans Restored,Blown Fuse Replaced & Transformer Tested | | | 05000278/LER-1980-006-03, /03L-0:on 800213,while at Power,Reactor Core Isolation Cooling Automatic Control from Control Room Found Inoperable.Caused by Logic Circuit Board Failure in Pump Discharge Flow Controller.Defective Controller Replaced | /03L-0:on 800213,while at Power,Reactor Core Isolation Cooling Automatic Control from Control Room Found Inoperable.Caused by Logic Circuit Board Failure in Pump Discharge Flow Controller.Defective Controller Replaced | | | 05000278/LER-1980-007, Forwards LER 80-007/01T-0 | Forwards LER 80-007/01T-0 | | | 05000278/LER-1980-007-01, /01T-0:on 800221,during Routine Plant Equipment Insp,Seismically Qualified Backup Nitrogen Bottle Supplies to Five Containment Ventilation Valves Found Out of Svc. Caused by Lack of Operator Info & Equipment Identification | /01T-0:on 800221,during Routine Plant Equipment Insp,Seismically Qualified Backup Nitrogen Bottle Supplies to Five Containment Ventilation Valves Found Out of Svc. Caused by Lack of Operator Info & Equipment Identification | | | 05000277/LER-1980-007-03, /03L-0:on 800306,while Performing Routine Surveillance Test,Pressure Switch Ps 2-2-134C Setpoint Found Less than 1% Outside of Tech Spec Limit.Caused by Setpoint Drift.Switch Recalibr | /03L-0:on 800306,while Performing Routine Surveillance Test,Pressure Switch Ps 2-2-134C Setpoint Found Less than 1% Outside of Tech Spec Limit.Caused by Setpoint Drift.Switch Recalibr | | | 05000277/LER-1980-008, Forwards LER 80-008/01T-0 | Forwards LER 80-008/01T-0 | | | 05000277/LER-1980-008-01, /01T-0:on 800417,while Performing Insp Requested by IE Bulletin 79-01B,discovered That Safety Factor Was Less than Acceptable.Caused by Refined Calculation.Unit 3 Isolation Valves Closed.Mods Will Be Made | /01T-0:on 800417,while Performing Insp Requested by IE Bulletin 79-01B,discovered That Safety Factor Was Less than Acceptable.Caused by Refined Calculation.Unit 3 Isolation Valves Closed.Mods Will Be Made | | | 05000278/LER-1980-008-01, /01T-0:on 800305,while at power,E334 Load Ctr Was Shed Automatically Due to Loss of Site Startup Source,But Failed to Recover Automatically.Caused by Agastat Time Delay relay,Model7012PC,not Picking Up on Restoration | /01T-0:on 800305,while at power,E334 Load Ctr Was Shed Automatically Due to Loss of Site Startup Source,But Failed to Recover Automatically.Caused by Agastat Time Delay relay,Model7012PC,not Picking Up on Restoration | | | 05000278/LER-1980-008, Forwards LER 80-008/01T-0 | Forwards LER 80-008/01T-0 | | | 05000277/LER-1980-009-01, /01T-0:on 800502,irradiated Fuel Bundle Moved in Spent Fuel Pool for Lead Test Assembly Insp.Caused by Procedure Deficiency Which Adequately Specified Conditions Under Which Penetration Boots Could Be Removed | /01T-0:on 800502,irradiated Fuel Bundle Moved in Spent Fuel Pool for Lead Test Assembly Insp.Caused by Procedure Deficiency Which Adequately Specified Conditions Under Which Penetration Boots Could Be Removed | | | 05000278/LER-1980-009-03, /03L-0:on 800414,during Normal Operation,Shift Personnel Verified Reported Leak at Suction Piping Header one-inch Drain Line Connection on D RHR Pump.Caused by Fatigue Failure of Pipe.Pump Suction Line Repaired | /03L-0:on 800414,during Normal Operation,Shift Personnel Verified Reported Leak at Suction Piping Header one-inch Drain Line Connection on D RHR Pump.Caused by Fatigue Failure of Pipe.Pump Suction Line Repaired | | | 05000277/LER-1980-009, Forwards LER 80-009/01T-0 | Forwards LER 80-009/01T-0 | | | 05000278/LER-1980-010-03, /03L-0:on 800421,while Performing Surveillance Test,Lpci Injection valve,MO-3-10-25B,failed to Open.Caused by Lack of Guide Clearance Between Valve Disc & Valve Guide. Valve Was Repaired & Stroked Satisfactorily | /03L-0:on 800421,while Performing Surveillance Test,Lpci Injection valve,MO-3-10-25B,failed to Open.Caused by Lack of Guide Clearance Between Valve Disc & Valve Guide. Valve Was Repaired & Stroked Satisfactorily | | | 05000277/LER-1980-010-01, /01T-0:on 800603,w/unit at Power,Leak Developed in A1 Section of Condenser.Caused by Lack of Proper Procedure During Shutdown Condition Allowing Hotwell Level to Rise. Condenser Tubes to Be Decontaminated | /01T-0:on 800603,w/unit at Power,Leak Developed in A1 Section of Condenser.Caused by Lack of Proper Procedure During Shutdown Condition Allowing Hotwell Level to Rise. Condenser Tubes to Be Decontaminated | | | 05000277/LER-1980-010, Forwards LER 80-010/01T-0 | Forwards LER 80-010/01T-0 | | | 05000278/LER-1980-011-03, /03L-0:on 800516,during Power Operation,Instrument Surveillance Test Revealed Setpoint for Pressure Switch 3-2-128B at 33 Psi Above Tech Spec.Caused by Barksdale Model PIH-M8555-V Pressure Switch Setpoint Drift | /03L-0:on 800516,during Power Operation,Instrument Surveillance Test Revealed Setpoint for Pressure Switch 3-2-128B at 33 Psi Above Tech Spec.Caused by Barksdale Model PIH-M8555-V Pressure Switch Setpoint Drift | | | 05000277/LER-1980-011-01, /01T-0:on 800714,during Training on Sys,Diesel Generator Cardox Sys Vapor Pilot Valve Found Closed. Cause Not Found.Valve Immediately Locked Open.Valve Also Added to Sys Checkoff & Locked Valve Lists | /01T-0:on 800714,during Training on Sys,Diesel Generator Cardox Sys Vapor Pilot Valve Found Closed. Cause Not Found.Valve Immediately Locked Open.Valve Also Added to Sys Checkoff & Locked Valve Lists | | | 05000277/LER-1980-011, Forwards LER 80-011/01T-0 | Forwards LER 80-011/01T-0 | | | 05000277/LER-1980-012, Forwards LER 80-012/01T-0 | Forwards LER 80-012/01T-0 | | | 05000277/LER-1980-012-01, /01T-0:on 800721,during Operational Hydro,Scram Discharge Vol Vent & Drain Valves Failed to Operate. Investigation Indicated at Least One Vent & Drain Solenoid & Both Backup Scram Solenoids Failed | /01T-0:on 800721,during Operational Hydro,Scram Discharge Vol Vent & Drain Valves Failed to Operate. Investigation Indicated at Least One Vent & Drain Solenoid & Both Backup Scram Solenoids Failed | | | 05000278/LER-1980-012-03, /03L-0:on 800520,during Full Power Operation, Routine Testing Revealed Pressure Switch 5121B Setpoint at 700 Psi Above Tech Spec.Caused by Personnel Error.Setpoint Adjusted.Technician Instructed | /03L-0:on 800520,during Full Power Operation, Routine Testing Revealed Pressure Switch 5121B Setpoint at 700 Psi Above Tech Spec.Caused by Personnel Error.Setpoint Adjusted.Technician Instructed | | | 05000278/LER-1980-013-03, /03L-0:on 800605,during Surveillance Test,Pressure Switch Ps 3 5 12C Found 0.3 Psig Above Tech Spec Limit. Caused by Setpoint Drift.Switch Recalibr,Tested & Returned to Svc | /03L-0:on 800605,during Surveillance Test,Pressure Switch Ps 3 5 12C Found 0.3 Psig Above Tech Spec Limit. Caused by Setpoint Drift.Switch Recalibr,Tested & Returned to Svc | | | 05000277/LER-1980-013-03, /03L-0:on 800801,during Refueling Outage, Surveillance Leak Test Results Exceeded Tech Spec Limits Due to Leakage Failure of Eight Msivs.Caused by Improper Seat Contact Due to Damage to Seats,Plugs & Guides | /03L-0:on 800801,during Refueling Outage, Surveillance Leak Test Results Exceeded Tech Spec Limits Due to Leakage Failure of Eight Msivs.Caused by Improper Seat Contact Due to Damage to Seats,Plugs & Guides | | | 05000278/LER-1980-014-03, /03L-0:on 800608,while Performing ST 6.9,valve Mo 3-10-26B Failed to Close After Stroked Open.Caused by Mechanical Problem in Valve.Mo 3-10-26B to Be Disassembled & Repaired | /03L-0:on 800608,while Performing ST 6.9,valve Mo 3-10-26B Failed to Close After Stroked Open.Caused by Mechanical Problem in Valve.Mo 3-10-26B to Be Disassembled & Repaired | | | 05000277/LER-1980-014, Forwards LER 80-014/04T-0 | Forwards LER 80-014/04T-0 | | | 05000277/LER-1980-014-04, /04T-0:on 800808,oil Sheen Observed on Conowingo Pond,Near Berm That Separates Pond from Cooling Towers. Caused by Oil Overflow Due to Incorrect Level Gauge Reading in Diesel Storage Tank a During Oil Delivery.Gauge Recalibr | /04T-0:on 800808,oil Sheen Observed on Conowingo Pond,Near Berm That Separates Pond from Cooling Towers. Caused by Oil Overflow Due to Incorrect Level Gauge Reading in Diesel Storage Tank a During Oil Delivery.Gauge Recalibr | | | 05000277/LER-1980-015-03, /03X-1:on 800904,during Surveillance Testing at Full Power,Reactor Core Isolation Cooling Outboard Steam Supply Isolation Valve MO-2-13-16 Failed to Close.Caused by Improperly Functioning Switch on Limitorque Operator | /03X-1:on 800904,during Surveillance Testing at Full Power,Reactor Core Isolation Cooling Outboard Steam Supply Isolation Valve MO-2-13-16 Failed to Close.Caused by Improperly Functioning Switch on Limitorque Operator | | | 05000278/LER-1980-015-03, /03L-0:on 800707,during Full Power operation,3A Refuel Floor Exhaust Rad Monitor Found Drifting Downscale. Cause Has Not Been Determined.New Gm Tube & Electronic Circuitry Installed | /03L-0:on 800707,during Full Power operation,3A Refuel Floor Exhaust Rad Monitor Found Drifting Downscale. Cause Has Not Been Determined.New Gm Tube & Electronic Circuitry Installed | | | 05000278/LER-1980-016-01, /01T-0:on 800717,reanalysis by Bechtel of as-built Piping Determined That Stresses on Snubber 3-10-GB-S-44 Exceeded Operability Criteria.Caused by Inadequate Design Due to as-built Condition & Seismic Analysis Info Variance | /01T-0:on 800717,reanalysis by Bechtel of as-built Piping Determined That Stresses on Snubber 3-10-GB-S-44 Exceeded Operability Criteria.Caused by Inadequate Design Due to as-built Condition & Seismic Analysis Info Variance | | | 05000278/LER-1980-016, Forwards LER 80-016/01T-0 | Forwards LER 80-016/01T-0 | | | 05000277/LER-1980-016-03, /03L-0:on 800909,during Surveillance Testing W/Unit at Full Power,Eccs a Channel Logic Relay Failed to Function Properly W/Simulated Low Reactor Pressure.Caused by Dirty Contacts on GE Type Hfa Relay.Contacts Cleaned | /03L-0:on 800909,during Surveillance Testing W/Unit at Full Power,Eccs a Channel Logic Relay Failed to Function Properly W/Simulated Low Reactor Pressure.Caused by Dirty Contacts on GE Type Hfa Relay.Contacts Cleaned | | | 05000277/LER-1980-017-03, /03L-0:on 800906,during Surveillance Test at Full Power,Rhr B Subsystem Pump Room Cooler Failed to Start Automatically.Caused by Improper Adjustment of Cell Switch on Pump Breaker.Breaker Replaced & Test Completed | /03L-0:on 800906,during Surveillance Test at Full Power,Rhr B Subsystem Pump Room Cooler Failed to Start Automatically.Caused by Improper Adjustment of Cell Switch on Pump Breaker.Breaker Replaced & Test Completed | | | 05000278/LER-1980-017-03, /03L-0:on 800802,during Surveillance Test on PCIS Normally Open Valves,Drywell 2-inch Valve AO-3509 Failed to Close.Caused by Tight Packing on Valve.Packing & Proper Operation Verified | /03L-0:on 800802,during Surveillance Test on PCIS Normally Open Valves,Drywell 2-inch Valve AO-3509 Failed to Close.Caused by Tight Packing on Valve.Packing & Proper Operation Verified | | | 05000277/LER-1980-018-03, /03L-0:on 800918,HPCI Turbine Steam Line High Flow Trip Instrument Revealed That Setpoint Was 5 Inches Above Tech Spec Limit.Caused by Setpoint Drift of Instrument. Instrument Recalibr | /03L-0:on 800918,HPCI Turbine Steam Line High Flow Trip Instrument Revealed That Setpoint Was 5 Inches Above Tech Spec Limit.Caused by Setpoint Drift of Instrument. Instrument Recalibr | | | 05000278/LER-1980-018-03, /03L-0:on 800802,during Surveillance Test on PCIS Normally Open Valves W/Unit at Full Power,Reactor Water Cleanup Sys Return Isolation Valve MO-3-12-68 Failed to Close Using Control Switch.Cause Not Determined | /03L-0:on 800802,during Surveillance Test on PCIS Normally Open Valves W/Unit at Full Power,Reactor Water Cleanup Sys Return Isolation Valve MO-3-12-68 Failed to Close Using Control Switch.Cause Not Determined | | | 05000277/LER-1980-019-03, /03L-0:on 800906,during Surveillance Testing, Primary Containment Air Sample Flow Discovered Lost.Caused by Short in Coil of Demo Type Solenoid Valve Which Blew Fuse Common to All Seven Valves.Coil Replaced | /03L-0:on 800906,during Surveillance Testing, Primary Containment Air Sample Flow Discovered Lost.Caused by Short in Coil of Demo Type Solenoid Valve Which Blew Fuse Common to All Seven Valves.Coil Replaced | | | 05000278/LER-1980-019-03, /03L-0:on 800806,while Performing Surveillance Test on RHR Sys W/Unit at power,MO-3-10-25A LPCI Injection Valve Failed to Open.Caused by Multiple Full Penetration Cracks on Drive Sleeve of Type SMB-4 Limitorque Operator | /03L-0:on 800806,while Performing Surveillance Test on RHR Sys W/Unit at power,MO-3-10-25A LPCI Injection Valve Failed to Open.Caused by Multiple Full Penetration Cracks on Drive Sleeve of Type SMB-4 Limitorque Operator | | | 05000278/LER-1980-020-03, /03L-0:on 800815,while Performing Leak Test, Containment Ventilation Valve AO-3521B Was Found Leaking Excessively.Caused by Valve T-ring Inflating Before Closure.Air Valves Adjusted & Valve Tested | /03L-0:on 800815,while Performing Leak Test, Containment Ventilation Valve AO-3521B Was Found Leaking Excessively.Caused by Valve T-ring Inflating Before Closure.Air Valves Adjusted & Valve Tested | |
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