LER-1979-016, /01T-0 on 790521:punch Gap of Pcrv Rupture Disc M-11702 Found Out of Tolerance W/Vendor Specs.Caused by Undocumented Change of Punch Gap Specs.Tolerances Returned to Original Specs |
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| 2671979016R01 - NRC Website |
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'S REPCRT CATE 80 EVENT DESCRIPTION AND PACBABLE CONSEQUENCES h a
2 l During refueling shutdown, shile performin g routine surveillance testing on PCRV rup-I o
3 lture disc, 11-11702, the punch gap was found to be out of tolerance specified by canu-l l f acturer which could have prevented relief valve frem fulfilling the functional re-I 0
A l quirements of the sys tem as required by Technical Specification AC 7.5.2(a) 5.
Rupturel o
s 3 i,3 ! l disc 11-11701 was also recoved and tested and was also out of tolerance.
No over-i o;7 l pressurization of the PCRV occurred.
This had no affect on plant operation.
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o l The oroblem occurred because of an undocumented chance o? ounch eso soecifications.
I iii l This resulted in some documents showing the original tolerances and others the re-I
, l vised tolerances.
Because of deficiency in documentation at. this time tolerances werel l returned to the original specifications and the punch gaos modified to.085 inches.
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REPORT DATE:
June 1, 19 79 REPOKIABLE OCCURRENCE 79-16 ISSUE O OCCURRENCE DATE:
May 21, 1979 Page 1 of 4 EDRT ST. VRAIN NUCLEAR GENERATING STATION PUBLIC SERVICE COMPANY OF COLORADO P. O. BOX 361 PLAITEVILLE, COLORADO 80651 RP. PORT No. 50- 26 7/ 79-16/01-T-0 Final IDENTIFICATION OF OCCURRENCE :
On iby 21,1979, while the reactor was shutdown and depressurized for refueling, surveillance tes ting and preventive maintenance was being performed on the PCRV relief valve sys tem.
The cutting edge for the rupture discs was found out of tolerance, which could have prevented either relief valve from fulfilling the functional requirements of the system.
Since the reactor has been operated at power during the surveillance interval, this is reportable per Fort St. Vrain Technical Specifica tion AC 7. 5.2(a)5.
EVENT DES CRIPTION :
Whil.e the reactor was shutdown and depressurized for refueling the low set rup-ture disc, 1911702, was removed from service for a scheduled surveillance bench test.
See Figure 1.
During this tes t the punch gap, ([l, was found out of tolerance.
The cutting edge, ([), was farther from the rupture disc, (}),
than allowed by manuf acturer's specifications.
Since the low set rupture disc punch gap was out of tolerance, the high set rupture disc, M-11701, was also removed and bench tested. Its punch gap, 0 6
, was also out of tolerance with
(]l), being farther from the rupture disc,The punch gap toleran the cutting edge, by manufacturer's specification.
ments are listed below.
Punch Cao Allowed
- Actual Low Set Rupture Disc Fhil702 0.065/0.085 in.
0.111 in.
High Set Rupture Dise M-11701 0.065/0.085 in.
0.105 in.
- Per Ametek/Calmec Operation and Maintenance Manual PS-239 for M-11701 and M-11702 (Calmec Part Number 2002-503).
The manufacturer's representative was contacted and indicated that because of the large size and movement of these discs the punch would have probably cut the disc in both cases.
2285 086
REPORTABLE OCCURRENCE 79-16 ISSUE O Page 2 of 4
CAUSE
DESCRIPTION:
During initial installation and testing, and subsequent surveillance testing of these rupture discs, the punch gap was checked per approved procedures.
How-ever, during the initial installation and testing some confusion resulted over the correct punch gap tolerances.
Some of the procedures were changed from the original 0.065 to 0.085 inch punch gap to allow a 0.100 to 0.120 inch punch gap.
This was apparently done on a verbal authorizacion of the technical representa-tive present as no authorizing documentation can be found.
These undocumented limits were still present on some of the approved procedures.
The problem was dis covered when the engineer supervising the surveillance this year used a pro-cedure having the original tolerances as listed in the manual.
Because the manufacturer has gone out of business and all records are in storage, it would be extremely difficult to document the higher specifications at this time.
Th erefo re, the punch gaps have been decreased to a maximum of 0.085 inches.
CORRECTIVE ACTION:
The punch has been cachined to produce a punch gap of 0.085 inches on both M-11701 and FF11702.
The procedures concerning these rupture discs have been reviewed and the correct specifications for the punch gap verified.
Since there is no mechanism for the punch gap measurement to change in service, no further corrective action is anticipated.
2285 087
REPORTABLE OCCURRENCE 79-16 ISSUE O Page 2 of 4
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REPORTABLE OCCURRENCE 79-16 ISSUE O Page 4 of 4 Prepared by:
>M Asa B. Reed '
Technical Services Technician
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Frank M. Mathie Operations Manager Approved by: uk ' 'd i h f
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Don Warerbourg f/
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Manager, Nuclear Product' ion 2285 089
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| 05000267/LER-1979-001, Forwards LER 79-001/03L-0 | Forwards LER 79-001/03L-0 | | | 05000267/LER-1979-001-03, /03L-0 on 790102:total Primary Coolant Oxidant Concentration Exceeded 10 Vol Ppm While Core Average Outlet Temp Was Greater than 1200 F.Caused by Low Temp Absorber Heatup,Releasing Oxidant to Primary Coolant | /03L-0 on 790102:total Primary Coolant Oxidant Concentration Exceeded 10 Vol Ppm While Core Average Outlet Temp Was Greater than 1200 F.Caused by Low Temp Absorber Heatup,Releasing Oxidant to Primary Coolant | | | 05000267/LER-1979-002, Forwards LER 79-002/03L-0 | Forwards LER 79-002/03L-0 | | | 05000267/LER-1979-002-03, /03L-0 on 790127:operation in Degraded Mode Resulted from Repairs to Seat of Buffer Helium Purge Valve. Bypass of Buffer Helium Dryer Caused by Leakage Past Valve Seat Insert of Velan Model P-33876-N/78R Valve | /03L-0 on 790127:operation in Degraded Mode Resulted from Repairs to Seat of Buffer Helium Purge Valve. Bypass of Buffer Helium Dryer Caused by Leakage Past Valve Seat Insert of Velan Model P-33876-N/78R Valve | | | 05000267/LER-1979-004-03, /03L-0 on 790203:during Normal Operation,Cooling Tower Blowdown Exceeded Limit But Was Not Reported.Caused by Incorrect Completion of Surveillance Forms.Forms Changed & Personnel Instructed | /03L-0 on 790203:during Normal Operation,Cooling Tower Blowdown Exceeded Limit But Was Not Reported.Caused by Incorrect Completion of Surveillance Forms.Forms Changed & Personnel Instructed | | | 05000267/LER-1979-004, Forwards LER 79-004/03L-0 | Forwards LER 79-004/03L-0 | | | 05000267/LER-1979-005-03, /03L-0 on 790209:during Semiannual Loss of Outside Electrical Power Test,Output Circuit Breaker Did Not Close.Cause Unknown.Breaker Replaced W/Equivalent Spare | /03L-0 on 790209:during Semiannual Loss of Outside Electrical Power Test,Output Circuit Breaker Did Not Close.Cause Unknown.Breaker Replaced W/Equivalent Spare | | | 05000267/LER-1979-005, Forwards LER 79-005/03L-0 | Forwards LER 79-005/03L-0 | | | 05000267/LER-1979-013, Forwards RO 50-267/79-13/03-L-O & LER 79-013/03L-0 | Forwards RO 50-267/79-13/03-L-O & LER 79-013/03L-0 | | | 05000267/LER-1979-013-03, /03L-0 on 790412:during Test of Snubbers Many Found Inoperable Due to Unacceptable Lockup & Bleed Characteristics.Caused by Setpoint Drift,Dirty Oil & Clogged Valves.All Snubbers Repaired & Adjusted | /03L-0 on 790412:during Test of Snubbers Many Found Inoperable Due to Unacceptable Lockup & Bleed Characteristics.Caused by Setpoint Drift,Dirty Oil & Clogged Valves.All Snubbers Repaired & Adjusted | | | 05000267/LER-1979-015, Forwards LER 79-015/03L-0 | Forwards LER 79-015/03L-0 | | | 05000267/LER-1979-015-03, /03L-0 on 790507:during Routine Surveillance Testing,Setpoint of Pcrv Rupture Disc M-11702 Found to Be 826 Psig.Caused by Calibr Drift.Disc Recalbr | /03L-0 on 790507:during Routine Surveillance Testing,Setpoint of Pcrv Rupture Disc M-11702 Found to Be 826 Psig.Caused by Calibr Drift.Disc Recalbr | | | 05000267/LER-1979-016, Forwards LER 79-016/01T-0 | Forwards LER 79-016/01T-0 | | | 05000267/LER-1979-016-01, /01T-0 on 790521:punch Gap of Pcrv Rupture Disc M-11702 Found Out of Tolerance W/Vendor Specs.Caused by Undocumented Change of Punch Gap Specs.Tolerances Returned to Original Specs | /01T-0 on 790521:punch Gap of Pcrv Rupture Disc M-11702 Found Out of Tolerance W/Vendor Specs.Caused by Undocumented Change of Punch Gap Specs.Tolerances Returned to Original Specs | | | 05000267/LER-1979-017, Forwards LER 79-017/01T-0 | Forwards LER 79-017/01T-0 | | | 05000267/LER-1979-017-01, /01T-0 on 790626:fault Current Trip Occurred, Causing Reactor Scram & Interrupted Reactor Cooling.Caused by Water Spray in Switchgear,Resulting in Short Circuit Due to Voltage Perturbation | /01T-0 on 790626:fault Current Trip Occurred, Causing Reactor Scram & Interrupted Reactor Cooling.Caused by Water Spray in Switchgear,Resulting in Short Circuit Due to Voltage Perturbation | | | 05000267/LER-1979-018, Forwards LER 79-018/03L-0 | Forwards LER 79-018/03L-0 | | | 05000267/LER-1979-018-03, /03L-0 on 790630:one motor-operated Butterfly Valve Found Inoperable by Remote Manual Control.Cause Is Unknown.Cause & Corrective Action to Be Reported in Future Suppl | /03L-0 on 790630:one motor-operated Butterfly Valve Found Inoperable by Remote Manual Control.Cause Is Unknown.Cause & Corrective Action to Be Reported in Future Suppl | | | 05000267/LER-1979-019-03, /03L-0 on 790711:during Normal Operation,Weekly Functional Test of Area Radiation Monitors Not Performed for 1 Wk.Caused by Misfiling of Card for Surveillance Test. Computer Readout Will Be Used as Cross Check on Card Sys | /03L-0 on 790711:during Normal Operation,Weekly Functional Test of Area Radiation Monitors Not Performed for 1 Wk.Caused by Misfiling of Card for Surveillance Test. Computer Readout Will Be Used as Cross Check on Card Sys | | | 05000267/LER-1979-020-03, /03L-0 on 790717:during Normal Plant Operation, Engine Failed to Start.Caused by Failure of Emergency Diesel Temp Switch C.Switch Replaced | /03L-0 on 790717:during Normal Plant Operation, Engine Failed to Start.Caused by Failure of Emergency Diesel Temp Switch C.Switch Replaced | | | 05000267/LER-1979-021-03, /03L-1 on 790720:during Review of Surveillance Tests,Discovered That Halon Fire Suppression Sys Surveillance Test for Second Quarter Not Performed.Caused by Inadequate Control & Direction Re Refueling Work Load | /03L-1 on 790720:during Review of Surveillance Tests,Discovered That Halon Fire Suppression Sys Surveillance Test for Second Quarter Not Performed.Caused by Inadequate Control & Direction Re Refueling Work Load | | | 05000267/LER-1979-021, Forwards LER 79-021/03L-0 | Forwards LER 79-021/03L-0 | | | 05000267/LER-1979-022-03, /03L-0 on 790720:lack of Aquatic Macroinvertebrate Sample Collection.Caused by Oversight of Field Sampling Personnel Employed by Contract Agent.Agent Indicated Program Was Resumed & Will Continue Biweekly | /03L-0 on 790720:lack of Aquatic Macroinvertebrate Sample Collection.Caused by Oversight of Field Sampling Personnel Employed by Contract Agent.Agent Indicated Program Was Resumed & Will Continue Biweekly | | | 05000267/LER-1979-023-03, /03L-0 on 790727:while Performing Normal Surveillance,Fixed Feedwater Low Flow Switch Found Inoperable. Caused by Component Failure from Normal Wear. Module Was Repaired,Reinstalled & Retested Satisfactorily | /03L-0 on 790727:while Performing Normal Surveillance,Fixed Feedwater Low Flow Switch Found Inoperable. Caused by Component Failure from Normal Wear. Module Was Repaired,Reinstalled & Retested Satisfactorily | | | 05000267/LER-1979-024, Forwards LER 79-024/03L-0 | Forwards LER 79-024/03L-0 | | | 05000267/LER-1979-024-03, /03L-0:on 790804,on Three Occasions Between 790804-16,total Primary Coolant Oxidants Exceeded 10 Ppm W/Core Average Outlet Temp Greater than 1,200 F.Caused by Dryer Bypass Resulting in Water Ingress to Core | /03L-0:on 790804,on Three Occasions Between 790804-16,total Primary Coolant Oxidants Exceeded 10 Ppm W/Core Average Outlet Temp Greater than 1,200 F.Caused by Dryer Bypass Resulting in Water Ingress to Core | | | 05000267/LER-1979-025-03, /03X-0:on 790806,during Steady State Operation at 45% Thermal Power,Emergency Diesel Generator a Found in Degraded Mode, & B Engine Also Declutched.Caused by Relay Failure Due to Normal End of Life.Relay Replaced | /03X-0:on 790806,during Steady State Operation at 45% Thermal Power,Emergency Diesel Generator a Found in Degraded Mode, & B Engine Also Declutched.Caused by Relay Failure Due to Normal End of Life.Relay Replaced | | | 05000267/LER-1979-026-03, /03L-0:on 790807,bearing Water Makeup Pump P-2105 Removed from Svc to Perform Line Repair W/Reactor at 65% Power.Caused by Hole in Recirculation Line of Pump,Requiring Removal from Svc.Line Repaired.Pump Returned to Svc | /03L-0:on 790807,bearing Water Makeup Pump P-2105 Removed from Svc to Perform Line Repair W/Reactor at 65% Power.Caused by Hole in Recirculation Line of Pump,Requiring Removal from Svc.Line Repaired.Pump Returned to Svc | | | 05000267/LER-1979-027-01, /01T-0:on 790817,noted That Recent Pipe Hanger Installation Power Operated Relief Valve Cooling Water Lines Would Have Prevented Proper Installation of Pipe Spools. Caused by Pipe Ends Changing Alignment | /01T-0:on 790817,noted That Recent Pipe Hanger Installation Power Operated Relief Valve Cooling Water Lines Would Have Prevented Proper Installation of Pipe Spools. Caused by Pipe Ends Changing Alignment | | | 05000267/LER-1979-028-01, Plant Personnel Inadvertently Grounded Instrument Panel I-36,blowing Panel Fuses & Causing Voltage Perturbation on Bus 2.Caused by Personnel Error.Ground Corrected | Plant Personnel Inadvertently Grounded Instrument Panel I-36,blowing Panel Fuses & Causing Voltage Perturbation on Bus 2.Caused by Personnel Error.Ground Corrected | | | 05000267/LER-1979-029-03, /03L-0:on 790819,during Plant Startup,B Instrument Air Compressor Became Inoperable.Caused by Failure of Discharge Feather Valve.All Discharge Valves on Compressor Replaced & C Air Compressor Returned to Svc | /03L-0:on 790819,during Plant Startup,B Instrument Air Compressor Became Inoperable.Caused by Failure of Discharge Feather Valve.All Discharge Valves on Compressor Replaced & C Air Compressor Returned to Svc | | | 05000267/LER-1979-029, Forwards LER 79-029/03L-0 | Forwards LER 79-029/03L-0 | | | 05000267/LER-1979-030, Forwards LER 79-030/03L-0 | Forwards LER 79-030/03L-0 | | | 05000267/LER-1979-030-03, /03L-0:on 790821,primary Coolant Oxidants Exceeded Limiting Condition for Operation.Caused by Offline Helium Dryer Drying Out Operations & Extended Regeneration Period. Core Outlet Temps Reduced Whenever Oxidant Limits Excee | /03L-0:on 790821,primary Coolant Oxidants Exceeded Limiting Condition for Operation.Caused by Offline Helium Dryer Drying Out Operations & Extended Regeneration Period. Core Outlet Temps Reduced Whenever Oxidant Limits Exceeded | | | 05000267/LER-1979-031-03, /03L-0:on 790821 & 0830,plant Operated W/Reactor Dewpoint Outside Tech Spec Limits.Caused by Helium Dryer Bypass,Due to Faulty Time Delay Relay.No Cause for 790821 Event.Relay Replaced & Tested | /03L-0:on 790821 & 0830,plant Operated W/Reactor Dewpoint Outside Tech Spec Limits.Caused by Helium Dryer Bypass,Due to Faulty Time Delay Relay.No Cause for 790821 Event.Relay Replaced & Tested | | | 05000267/LER-1979-031, Forwards LER 79-031/03L-0 | Forwards LER 79-031/03L-0 | | | 05000267/LER-1979-032, Forwards LER 79-032/03X-1 | Forwards LER 79-032/03X-1 | | | 05000267/LER-1979-032-03, During Testing,Four of 12 Helium Circulator Seal Malfunction Pressure Differential Switch Units Would Not Trip.Caused by Dirt Accumulation in Electrical Switches.Switches Replaced | During Testing,Four of 12 Helium Circulator Seal Malfunction Pressure Differential Switch Units Would Not Trip.Caused by Dirt Accumulation in Electrical Switches.Switches Replaced | | | 05000267/LER-1979-033, Forwards LER 79-033/03L-0 | Forwards LER 79-033/03L-0 | | | 05000267/LER-1979-033-03, /03L-0:on 790828,unauthorized Release Made from 1A Gas Waste Surge Tank.Caused by Wrong Valve Lineup.Valve Checkoff Sheets Revised to Require Operator Initials for Each Valve.Personnel Admonished | /03L-0:on 790828,unauthorized Release Made from 1A Gas Waste Surge Tank.Caused by Wrong Valve Lineup.Valve Checkoff Sheets Revised to Require Operator Initials for Each Valve.Personnel Admonished | | | 05000267/LER-1979-034-03, /03L-0:on 790830,while Operating at 36% Thermal Power,Emergency Diesel Generator Day Tanks Did Not Have 500 Gallons of Fuel Oil as Required Per Tech Specs.Caused by Inoperable High Level Switch Which Controls Pump Operations | /03L-0:on 790830,while Operating at 36% Thermal Power,Emergency Diesel Generator Day Tanks Did Not Have 500 Gallons of Fuel Oil as Required Per Tech Specs.Caused by Inoperable High Level Switch Which Controls Pump Operations | | | 05000267/LER-1979-034, Forwards LER 79-034/03L-0 | Forwards LER 79-034/03L-0 | | | 05000267/LER-1979-035-01, /01X-1:on 790831,field Audit & Preliminary Engineering Analysis of Random Sample of as-built safety-related Piping Drawings Showed Several Hangers W/Inconsistencies.Caused by Design Inconsistencies | /01X-1:on 790831,field Audit & Preliminary Engineering Analysis of Random Sample of as-built safety-related Piping Drawings Showed Several Hangers W/Inconsistencies.Caused by Design Inconsistencies | | | 05000267/LER-1979-036-03, /03L-0:on 790910,cold Reheat Snubber CRS-262 Inoperable W/Reactor in Shutdown Condition.Caused by Missing Pin That Kept Snubber from Being Properly Attached to Pipe. New Pin Fabricated & Installed.Snubber Returned to Svc | /03L-0:on 790910,cold Reheat Snubber CRS-262 Inoperable W/Reactor in Shutdown Condition.Caused by Missing Pin That Kept Snubber from Being Properly Attached to Pipe. New Pin Fabricated & Installed.Snubber Returned to Svc | | | 05000267/LER-1979-037, Forwards LER 79-037/03L-0 | Forwards LER 79-037/03L-0 | | | 05000267/LER-1979-037-03, /03L-0:on 790919,during Normal Operation,Liquid Radwaste Release Was Made in Noncompliance W/Limiting Conditions for Operation.Caused by Operator Failure to Reset Flow Switch to New Required Flow Rate.Operators Admonished | /03L-0:on 790919,during Normal Operation,Liquid Radwaste Release Was Made in Noncompliance W/Limiting Conditions for Operation.Caused by Operator Failure to Reset Flow Switch to New Required Flow Rate.Operators Admonished | | | 05000267/LER-1979-038-03, /03L-0:on 790921,analytical Sys Primary Coolant Moisture Monitor ME-9307 Became Inoperable W/Reactor at Less than 2% Power.Caused by Burned Out Thermal Electric Heater/Cooler & Two Faulty Relays.Head & Relays Replaced | /03L-0:on 790921,analytical Sys Primary Coolant Moisture Monitor ME-9307 Became Inoperable W/Reactor at Less than 2% Power.Caused by Burned Out Thermal Electric Heater/Cooler & Two Faulty Relays.Head & Relays Replaced | | | 05000267/LER-1979-038, Forwards LER 79-038/03L-0 | Forwards LER 79-038/03L-0 | | | 05000267/LER-1979-039-03, /03L-0:on 790924,authorized Liquid Waste Release Was Made,Requiring Raising Setpoints on Liquid Waste Activity Monitors Above Normal.Caused by Failure to Return Monitors to Normal Setpoints Prior to Starting Release | /03L-0:on 790924,authorized Liquid Waste Release Was Made,Requiring Raising Setpoints on Liquid Waste Activity Monitors Above Normal.Caused by Failure to Return Monitors to Normal Setpoints Prior to Starting Release | | | 05000267/LER-1979-040-03, Ler 79-040/03L-0:on 791001,two Snubbers Required During Power Operation Found Inoperable.Caused by Oil Reservoir Leak in HRS-194 & Loose Lock Nut on HOS-29.Reservoir Refilled & Lock Nut Tightened | Ler 79-040/03L-0:on 791001,two Snubbers Required During Power Operation Found Inoperable.Caused by Oil Reservoir Leak in HRS-194 & Loose Lock Nut on HOS-29.Reservoir Refilled & Lock Nut Tightened | |
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