LER-1979-015, /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 |
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REPORT DATE:
June 6, 1979 REPORTABLE OCCURRENCE 79-15 ISSUE O OCCURRENCE DATE:
May 7, 1979 Page 1 of 3 FORT ST. VRAIN NU"I, EAR GENERATING STATION PUBLIC SERVICE COMPANY OF COLORADO P. O. BOX 361 PLATTEVILLE, COLORADO 80651 REPORT No. 50-267/ 79-15 /03-L-0
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2 Final IDENTIFICATION OF OCCURRENCE:
During a routine surveillance calibratian check performed on May 5,1979, the
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setpoint of the PCRV rupture disc assembly M-11702 was found to be 826 psig.
Since this setpoint is higher than the 812 psig + 1% allowable by Fort St.
Vrain Technical Specification LSSS 3.3.2(c), it is being reported per Fort S t.
Vrain Technical Specification AC 7.5.2(b)l.
EVENT
DESCRIPTION
With the reactor shutdown and depressurized for refueling, low set rupture disc, M-11702, was removed from service for a scheduled surveillance calibra-tion bench test.
The "as found" pressure setpoint was 826 psig. The accep-tance criterion of LSSS 3.3.2(c) requires the set pressure to be 812 psig +
1% (804 psig to 820 psig).
Refer to Figure 1.
Before the test gas pressure is applied the cutter, 1
is removed and a s ville washers, ($)pecial ring is installed to limit the travel of the Bel e-These washers snap over when the set pressure is reached.
Ad ustment of the set pressure is made by positioning of the threaded ring, 3
When the set pressure is reached, the diaphragm and washers travel ew thousandths of an inch, which produces an audible " thump".
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CAUSE
DESCRIPTION:
The rupture disc being out of tolerance was caused by calibration drif t over the two years it had been in service since its last calibration surveillance.
CORRECTIVE ACTION:
The rupture disc was calibrated to 812 psig and returned to service.
No further corrective action is anticipated or required.
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NRC FORM 366 U. S. NUCLEAR REGULATORY COMMISSION (7 77)' *
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8 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATd 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES O'o l During refueling shutdown, while performing routine surveillance testing of PCRV rup-l o
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- ture disc M-ll702 its setpoint was found to be 826 psig.
This is outside the 812 l
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g sig + 1% allowed by Fort St. Vrain Technical Specification LSSS 3.3.2(c) and is p
g being reported per Fort St. Vrain Technical Specification AC 7.5.2(b)l.
The reactor ;
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47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h i io Cause of the problem was calibration drif t.
The ructure disc was calibrated to the y
proper setpoint and returned to service. No further corrective action anticipated or 1 l required.
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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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