LER-1981-069, Forwards LER 81-069/03L-0.Detailed Event Analysis Encl |
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Nuclear Regulatory Commission b.
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Reference:
Facility Operating License No. OPR-34 Docket No. 50-267
Dear Mr. Seyfrit:
Enclosed please find a copy of Reportable Occurrence Report No. 50-267/81-069, Final, submitted per the requirements of Technical Specification AC 7.5.2(b)2.
- Also, please find enclosed one copy of the Licensee Event Report for Reportable Occurrence Report No. 50-267/81-069.
,ery truly yours,
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Ww Don Warembou Manager, Nuclear Production DW/cls Enclosure cc: Director, MIPC i
8112040449 811123
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PDR ADOCK 05000267 fr 5
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r REPORT DATE: _
November 23, 1981 REPORTABLE OCCURRENCE 81-069 ISSUE 0 OCCURRENCE DATE:
November 4, 1981 Page 1 of 5 FORT ST. VRAIN NUCLEAR GENERATING STATION PUBLIC SERVICE COMPANY OF COLORADO 16805 WELD COUNTY ROAD 19 1/2 PLATTEVILLE, COLORADO 80651-9298 REPORT NO. 50-267/81-069/03-L-0 Final IDENTIFICATION OF OCCURRENCE:
During the period from November 4, 1981, to November 9, 1981, the plant was operated in a degraded mode of LCO 4.2.10 on three occasions.
These events are reportable per Fort St. Vrain Technical Specification AC 7.5.2(b)2.
EVENT
DESCRIPTION
Event 1
.1e Figure 1.
At 0000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> on November 4, 1981, with the average core outlet temperature reaching and exceeding 1200 degrees fah-enheit, the total primary coolant oxidants (the sum of carbon montatete, carbon dioxide, and water) was above 10 parts per mill.on
( ca.-).
Operation continued under these conditions until 0400 hours0.00463 days <br />0.111 hours <br />6.613757e-4 weeks <br />1.522e-4 months <br /> on November 5, 1981. This event constitutes operation in a degraded mode of LCO 4.2.10.
Event 2 See Figure 1.
At 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> on November 5, 1981, with average core outlet temperature greater than 1200 degrees fahrenheit, the total primary coolant oxidants increased above 10 ppm. Operation continued unaer these conditions until 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br /> on November 6, 1981.
This event constitutes operation in a degraded mode of LCO 4.2.10.
Event 3 See Figure 1.
At 1400 hours0.0162 days <br />0.389 hours <br />0.00231 weeks <br />5.327e-4 months <br /> on November 6, 1981, with average core outlet temperature greater than 1200 degrees fahrenheit, the total primary coolant oxidants increased above 10 ppm. Operation continued under these conditions until 0406 hours0.0047 days <br />0.113 hours <br />6.712963e-4 weeks <br />1.54483e-4 months <br /> on Novemuer 9, 1981.
This event constitutes operation in a degraded mode of LCO 4.2.10.
L
REPORTABLE OCCURRENCE 81-069 ISSUE O j
Page 2 of 5 i
CAUSE
l
DESCRIPTION
Event 1 i
See Figure 1.
On November 2, 1981, moisture was inadvertently introduced into the primary coolant system while the reactor was being maintained below 2% power. The primary coolant purification system was utilized tn remove the primary coolant oxidants.
Reactor power was slowly increased as the oxidant concentration trended downward. At 0000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> on November 4, 1981, the average core outlet tamperature reached and exceeded 1200 degrees fahrenheit Jith a total primary coolant oxidant concentration of about 10.7 ppm.
As the average core outlet temperature increased, the total primary coolant oxidants contih.ed to out gas from the core graphite and reached a maximum of 18.3 ppm at 0800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> on November 4, 1981. At 0400 hours0.00463 days <br />0.111 hours <br />6.613757e-4 weeks <br />1.522e-4 months <br /> on November 5, 1981, the primary coolant purification syrtem had reduced the total primary coolanc oxidants below the 10 ppm limit of LCO 4.?,.10.
L Event 2 See Figure 1.
At 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> on November 5, 1981, the total primary 1
coolant oxidants exceeded the 10 ppm limit of LCO 4.2.10.
As reactor i
power was increased from 67.6% at 0000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> to 86.1% at 2400 hours0.0278 days <br />0.667 hours <br />0.00397 weeks <br />9.132e-4 months <br /> on November 5, 1981, the average core outlet temperature increased to j
1391 degrees fahrenheit.
Due to residual moisture in the core, several spikes in the total oxidants' level occurr9d as the core continued to out gas.
The peak levels of 12.1 ppm were reached on f
2200 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.371e-4 months <br />, November 5, 1981, and 0600 hours0.00694 days <br />0.167 hours <br />9.920635e-4 weeks <br />2.283e-4 months <br />, November 6, 1981.
At 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br /> on November 6, 1981, the total primary coolant oxidants fell beluw the 10 ppm limit of LCO 4.2.10.
Event 3 See Figure 1.
As core temperature fluctuation testing (RT-500K) continued with reactor power reaching 100%, the average core outlet
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temperature increased to a maximum of 1428 degrees fahrenheit.
Increases in carbon dioxide and carbon monoxide levels due to out gassing caused total primary coolant exidants to exceed the 1
10 ppm limit of LCO 4.2.10 at 1400 hours0.0162 days <br />0.389 hours <br />0.00231 weeks <br />5.327e-4 months <br /> on November 6', 1981.
This degraded mode of operation continued until 0600 hours0.00694 days <br />0.167 hours <br />9.920635e-4 weeks <br />2.283e-4 months <br /> on November 9, 1981, when the average core outlet temperature fell below the 1200 degree fahrenheit specification of LCO 4.2.10.
During this i
period of operation in a degraded mode, the tetal oxidant concentration reached a maximum of 24.8 ppm at 0600 hours0.00694 days <br />0.167 hours <br />9.920635e-4 weeks <br />2.283e-4 months <br /> on November 7, 1981.
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REPORTABLE OCCURRENCE 81-069 ISSUE 0 Page 3 of 5 CORRECTI'IE ACTION: _
Corrective actions to the degraded mode operations outlined in this occurrence are as follows:
Events 1 and 2 t
The primary coolant purification system was utilized to remove the-primary coolant oxidants; thereby, bringing them below the LCO limit of 10 ppm.
Event 3 The average core outlet temperature dropped below 1200 degrees fahrenheit; thus LCO 4.2.10 no longer applied.
No further corrective action is anticipated or required.
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REPORTABLE OCCURRENCE 81-069 ISSUE O Page 5 of_5 Prepared By:
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Technical Services chnician Reviewed By:
/2d 3//A Charles Fuller Technical Services Engineering Supervisor Reviewed By:
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Edwin D. Hill
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Station Manager Approved By:
Id, Don Warembourg
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Manager, Nuclear Production w-WM-ep-.-ww
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| 05000267/LER-1981-001, Forwards LER 81-001/03L-0.Includes Narrative Description of Event Re High Outlet Temp in Pcrv Cooling Water Sys | Forwards LER 81-001/03L-0.Includes Narrative Description of Event Re High Outlet Temp in Pcrv Cooling Water Sys | | | 05000267/LER-1981-001-03, /03L-0:on 801230,outlet Temp of Loop 2 Pcrv Cooling Water Sys Exceeded Tech Spec Level.Caused by High Setpoint of Cooling Water Temp Controller Following Calibr. Controller Reset & Operators Will Be Reinstructed on Sys | /03L-0:on 801230,outlet Temp of Loop 2 Pcrv Cooling Water Sys Exceeded Tech Spec Level.Caused by High Setpoint of Cooling Water Temp Controller Following Calibr. Controller Reset & Operators Will Be Reinstructed on Sys | | | 05000267/LER-1981-002-03, /03L-0:on 810107,during Normal Operation,Sampling Requirements of SR NR1.1 Found Not Met for Day shift,801225. Caused by Personnel Error.Sampling Resumed on Next Shift & Personnel Reinstructed Re Importance of Requirements | /03L-0:on 810107,during Normal Operation,Sampling Requirements of SR NR1.1 Found Not Met for Day shift,801225. Caused by Personnel Error.Sampling Resumed on Next Shift & Personnel Reinstructed Re Importance of Requirements | | | 05000267/LER-1981-002, Forwards LER 81-002/03L-0 | Forwards LER 81-002/03L-0 | | | 05000267/LER-1981-003-03, /03L-0:on 810106,during Test,One Channel of 1D Helium Circulator Drain Malfunction Found Inoperable.Caused by Blown Switch Module Fuse.Fuse Replaced & Switch Returned to Svc | /03L-0:on 810106,during Test,One Channel of 1D Helium Circulator Drain Malfunction Found Inoperable.Caused by Blown Switch Module Fuse.Fuse Replaced & Switch Returned to Svc | | | 05000267/LER-1981-003, Forwards LER 81-003/03L-0 | Forwards LER 81-003/03L-0 | | | 05000267/LER-1981-004-03, /03L-0:on 810115,high Residual Chlorine Levels Found in Circulating Water Sys Liquid Effluent Sample.Cause Unknown.Subsequent Samples Normal | /03L-0:on 810115,high Residual Chlorine Levels Found in Circulating Water Sys Liquid Effluent Sample.Cause Unknown.Subsequent Samples Normal | | | 05000267/LER-1981-004, Forwards LER 81-004/03L-0 | Forwards LER 81-004/03L-0 | | | 05000267/LER-1981-005, Forwards LER 81-005/03L-0 | Forwards LER 81-005/03L-0 | | | 05000267/LER-1981-005-03, /03L-0:on 810107,during Surveillance Testing,Trip Setting on PDIS-21177 Bearing Water Differential Pressure Switch Found Below Tech Spec Limit.Caused by Instrument Drift.Switch Adjusted & Returned to Svc | /03L-0:on 810107,during Surveillance Testing,Trip Setting on PDIS-21177 Bearing Water Differential Pressure Switch Found Below Tech Spec Limit.Caused by Instrument Drift.Switch Adjusted & Returned to Svc | | | 05000267/LER-1981-006-03, During Annual Testing & Calibr,Six of 12 Helium Circulator Seal Malfunction Pressure Differential Switch Units Tripped Outside Limits.Caused by Dirt Accumulation in Electrical Switches.Switches Replaced | During Annual Testing & Calibr,Six of 12 Helium Circulator Seal Malfunction Pressure Differential Switch Units Tripped Outside Limits.Caused by Dirt Accumulation in Electrical Switches.Switches Replaced | | | 05000267/LER-1981-006, Forwards LER 81-006/03L-0 | Forwards LER 81-006/03L-0 | | | 05000267/LER-1981-007, Forwards LER 81-007/03T-0 | Forwards LER 81-007/03T-0 | | | 05000267/LER-1981-007-03, /03T-0:on 810108,during Pcrv Cooling Water Sys Data Evaluation,Violation of Limiting Conditions of Operation Found Re Loop 2 Inlet & Outlet Average Temp Below Tech Spec Limit.Caused by Insufficient Heat Input | /03T-0:on 810108,during Pcrv Cooling Water Sys Data Evaluation,Violation of Limiting Conditions of Operation Found Re Loop 2 Inlet & Outlet Average Temp Below Tech Spec Limit.Caused by Insufficient Heat Input | | | 05000267/LER-1981-008, Forwards LER 81-008/03L-0 | Forwards LER 81-008/03L-0 | | | 05000267/LER-1981-008-03, /03X-2:on 810120,during Primary Coolant Pressure Scram,Calibr Found Voltage Outputs of Three Pressure Transmitters High.Caused by Instrument Drift.Pressure Transmitters Calibr | /03X-2:on 810120,during Primary Coolant Pressure Scram,Calibr Found Voltage Outputs of Three Pressure Transmitters High.Caused by Instrument Drift.Pressure Transmitters Calibr | | | 05000267/LER-1981-009, Forwards LER 81-009/03L-0.Detailed Event Analysis Submitted | Forwards LER 81-009/03L-0.Detailed Event Analysis Submitted | | | 05000267/LER-1981-009-03, /03L-0:on 810116-0131,plant Operated in Degraded Mode on Five Occasions.Caused by Moisture Outgassing from Core Graphite Due to Increased Power Level.Average Core Outlet Temp Reduced & Purification Sys Removed | /03L-0:on 810116-0131,plant Operated in Degraded Mode on Five Occasions.Caused by Moisture Outgassing from Core Graphite Due to Increased Power Level.Average Core Outlet Temp Reduced & Purification Sys Removed | | | 05000267/LER-1981-010-03, /03L-0:on 810120,five Sample Flow Circuits Found Out of Calibr.Caused by Change of Instrument Characteristics.Calibr Values Revised & Flow Transmitters Recalibr.Alarm Setpoint Functional Test Values Also Changed | /03L-0:on 810120,five Sample Flow Circuits Found Out of Calibr.Caused by Change of Instrument Characteristics.Calibr Values Revised & Flow Transmitters Recalibr.Alarm Setpoint Functional Test Values Also Changed | | | 05000267/LER-1981-010, Forwards LER 81-010/03L-0 | Forwards LER 81-010/03L-0 | | | 05000267/LER-1981-011, Forwards LER 81-011/03L-0 | Forwards LER 81-011/03L-0 | | | 05000267/LER-1981-011-03, /03L-0:on 810121,liquid Nitrogen Storage Tank Level Noted Below Min Required.Caused by Sys Usage & Late Delivery of Liquid Nitrogen.Delivery Restored Tank Levels to Acceptable Values.Second Load Delivered to Top Off Tank | /03L-0:on 810121,liquid Nitrogen Storage Tank Level Noted Below Min Required.Caused by Sys Usage & Late Delivery of Liquid Nitrogen.Delivery Restored Tank Levels to Acceptable Values.Second Load Delivered to Top Off Tank | | | 05000267/LER-1981-012-03, /03L-0:on 810127,six of Twelve Steam Pipe Rupture (Pipe Cavity)Ultrasonic Noise Channels Had Unacceptably Low Response to Known Noise Source During Test.Caused by Microphone &/Or Transmitter Gain Reduced to Stop Tripping | /03L-0:on 810127,six of Twelve Steam Pipe Rupture (Pipe Cavity)Ultrasonic Noise Channels Had Unacceptably Low Response to Known Noise Source During Test.Caused by Microphone &/Or Transmitter Gain Reduced to Stop Tripping | | | 05000267/LER-1981-012, Forwards LER 81-012/03L-0 | Forwards LER 81-012/03L-0 | | | 05000267/LER-1981-013-01, /01T-0:on 810203,following Liquid Waste Release 429,tritium Concentration Exceeded Tech Spec.Caused by Sys Design Inadequacy W/Oil Separator on Liquid Waste Discharge Line.Bypass Installed Around Oil Separator | /01T-0:on 810203,following Liquid Waste Release 429,tritium Concentration Exceeded Tech Spec.Caused by Sys Design Inadequacy W/Oil Separator on Liquid Waste Discharge Line.Bypass Installed Around Oil Separator | | | 05000267/LER-1981-013, Forwards LER 81-013/01T-0.Detailed Event Analysis Submitted | Forwards LER 81-013/01T-0.Detailed Event Analysis Submitted | | | 05000267/LER-1981-014, Forwards LER 81-014/03L-0.Detailed Summary Also Encl | Forwards LER 81-014/03L-0.Detailed Summary Also Encl | | | 05000267/LER-1981-014-03, /03L-0:on 810104,instrument Air Compressors 1C & 1A Out of Svc,Leaving Only Compressor 1B in Svc.Caused by Compressor 1C Tripping on High Discharge Air Temp & Compressor 1A Being Cleared Out for Insp & Repairs | /03L-0:on 810104,instrument Air Compressors 1C & 1A Out of Svc,Leaving Only Compressor 1B in Svc.Caused by Compressor 1C Tripping on High Discharge Air Temp & Compressor 1A Being Cleared Out for Insp & Repairs | | | 05000267/LER-1981-015, Forwards LER 81-015/03L-0.Detailed Event Analysis Encl | Forwards LER 81-015/03L-0.Detailed Event Analysis Encl | | | 05000267/LER-1981-015-03, /03L-0:on 810204-0220,plant Operated in Degraded Mode on Nine Occasions.Causes Include Increased Oxidant Outgassing After Power Increase & Moisture Introduced Into Primary Coolant as Part of Approved Test | /03L-0:on 810204-0220,plant Operated in Degraded Mode on Nine Occasions.Causes Include Increased Oxidant Outgassing After Power Increase & Moisture Introduced Into Primary Coolant as Part of Approved Test | | | 05000267/LER-1981-016-03, During Testing,Three of 12 Helium Circulator Seal Malfunction Pressure Differential Switch Units Tripped Outside Limits.Caused by Dirt Accumulation in Electrical Switches.Switches Replaced | During Testing,Three of 12 Helium Circulator Seal Malfunction Pressure Differential Switch Units Tripped Outside Limits.Caused by Dirt Accumulation in Electrical Switches.Switches Replaced | | | 05000267/LER-1981-016, Forwards LER 81-016/03L-0 | Forwards LER 81-016/03L-0 | | | 05000267/LER-1981-017-03, /03L-0:on 810217,standby Diesel Engine 1B Tripped on High Cooling Water Temp.Caused by Sticking Temp Control Valve.Valve Disassembled,Cleaned & Returned to Svc | /03L-0:on 810217,standby Diesel Engine 1B Tripped on High Cooling Water Temp.Caused by Sticking Temp Control Valve.Valve Disassembled,Cleaned & Returned to Svc | | | 05000267/LER-1981-017, Forwards LER 81-017/03L-0 | Forwards LER 81-017/03L-0 | | | 05000267/LER-1981-018-03, /03L-0:on 810214,sample Flow Alarm Setpoints of Three Dewpoint Moisture Monitors Found Outside Tech Spec. Probably Caused by Previous Misadjustment.Trip Points Readjusted | /03L-0:on 810214,sample Flow Alarm Setpoints of Three Dewpoint Moisture Monitors Found Outside Tech Spec. Probably Caused by Previous Misadjustment.Trip Points Readjusted | | | 05000267/LER-1981-018, Forwards LER 81-018/03L-0.Detailed Event Analysis Encl | Forwards LER 81-018/03L-0.Detailed Event Analysis Encl | | | 05000267/LER-1981-019, Forwards LER 81-019/03L-0.Detailed Event Analysis Encl | Forwards LER 81-019/03L-0.Detailed Event Analysis Encl | | | 05000267/LER-1981-019-03, /03L-0:on 810220,plant Operated in Degraded Mode to Repair Pressure Control Valve PV-21243-1.Caused by Excessive Leakage Through 1/2-inch Masoneilan Pressure Control Valve.Valve Stroke Lengthened.Seat & Stem Replaced | /03L-0:on 810220,plant Operated in Degraded Mode to Repair Pressure Control Valve PV-21243-1.Caused by Excessive Leakage Through 1/2-inch Masoneilan Pressure Control Valve.Valve Stroke Lengthened.Seat & Stem Replaced | | | 05000267/LER-1981-020, Forwards LER 81-020/03L-0.Detailed Event Analysis Encl | Forwards LER 81-020/03L-0.Detailed Event Analysis Encl | | | 05000267/LER-1981-020-03, /03L-0:on 810226,primary Coolant Moisture & Oxidants Exceeded Limits.Caused by Circulator Buffer Sys Upset & Helium Circulator Trip Due to 810223 Reactor Scram. Reactor Power Reduced Until Moisture Level Decreased | /03L-0:on 810226,primary Coolant Moisture & Oxidants Exceeded Limits.Caused by Circulator Buffer Sys Upset & Helium Circulator Trip Due to 810223 Reactor Scram. Reactor Power Reduced Until Moisture Level Decreased | | | 05000267/LER-1981-021, Forwards LER 81-021/03L-0.Detailed Event Analysis Encl | Forwards LER 81-021/03L-0.Detailed Event Analysis Encl | | | 05000267/LER-1981-021-03, /03L-0:on 810302,liquid Nitrogen Storage Tank Level Lower than Tech Spec Requires.Caused by Sys Usage & Unavailable Recondensers.Level Restored W/Two Loads | /03L-0:on 810302,liquid Nitrogen Storage Tank Level Lower than Tech Spec Requires.Caused by Sys Usage & Unavailable Recondensers.Level Restored W/Two Loads | | | 05000267/LER-1981-022, Forwards LER 81-022/03L-0.Detailed Event Analysis Encl | Forwards LER 81-022/03L-0.Detailed Event Analysis Encl | | | 05000267/LER-1981-022-03, /03L-0:on 810310,found That Total Dissolved Solids in Plant Nonradioactive Liquid Waste Effluent Exceeded Tech Specs on 810224.Caused by Restoration of Water Sys Blowdown at High Rate.Blowdown Reduced | /03L-0:on 810310,found That Total Dissolved Solids in Plant Nonradioactive Liquid Waste Effluent Exceeded Tech Specs on 810224.Caused by Restoration of Water Sys Blowdown at High Rate.Blowdown Reduced | | | 05000267/LER-1981-023, Forwards LER 81-023/03L-0.Detailed Event Analysis Encl | Forwards LER 81-023/03L-0.Detailed Event Analysis Encl | | | 05000267/LER-1981-023-03, /03L-0:on 810310,during Release of Reactor Bldg Sump,Sump Pump Effluent Discharge Proportional Sampler Found Inoperable.Caused by Error in Instructions.New Instructions Issued to Assure Sampler Operability | /03L-0:on 810310,during Release of Reactor Bldg Sump,Sump Pump Effluent Discharge Proportional Sampler Found Inoperable.Caused by Error in Instructions.New Instructions Issued to Assure Sampler Operability | | | 05000267/LER-1981-024-03, During Testing,Five of 12 Helium Circulator Seal Malfunction Pressure Differential Switch Units Tripped Outside Limits.Caused by Accumulation of Dirt on Switches.Switches Replaced | During Testing,Five of 12 Helium Circulator Seal Malfunction Pressure Differential Switch Units Tripped Outside Limits.Caused by Accumulation of Dirt on Switches.Switches Replaced | | | 05000267/LER-1981-024, Forwards LER 81-024/03L-0.Detailed Event Analysis Encl | Forwards LER 81-024/03L-0.Detailed Event Analysis Encl | | | 05000267/LER-1981-025, Forwards LER 81-025/03L-0.Detailed Event Analysis Encl | Forwards LER 81-025/03L-0.Detailed Event Analysis Encl | | | 05000267/LER-1981-025-03, /03X-1:on 810317,liquid Nitrogen Storage Tank Level Decreased to Below 650 Gallons.Caused by Loss of Power to Fill Line Isolation Valve.Circuit Breaker Reclosed.Level Reestablished.Bypass Valve Installed Around Converter | /03X-1:on 810317,liquid Nitrogen Storage Tank Level Decreased to Below 650 Gallons.Caused by Loss of Power to Fill Line Isolation Valve.Circuit Breaker Reclosed.Level Reestablished.Bypass Valve Installed Around Converter | |
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