05000312/LER-1981-052, Forwards LER 81-052/03L-0.Detailed Event Analysis Submittted

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Forwards LER 81-052/03L-0.Detailed Event Analysis Submittted
Person / Time
ML20032D359
Site:	Rancho Seco
Issue date:	10/26/1981
From:	Mattimoe J SACRAMENTO MUNICIPAL UTILITY DISTRICT
To:	Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML20032D360	List: 05000312/LER-1981-052, Forwards LER 81-052/03L-0.Detailed Event Analysis Submittted 05000312/LER-1981-052-03, /03L-0:on 811005,nuclear Svc Raw Water Pump B (P-472B)tripped W/O Alarms or Target Drops.Cause Not Found. Pump Restarted & Quarterly Surveillance Test Run W/O Problems
References
NUDOCS 8111130691
Download: ML20032D359 (2)
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LER-1981-052, Forwards LER 81-052/03L-0.Detailed Event Analysis Submittted

Event date:
Report date:
3121981052R00 - NRC Website
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text

Licensee Event Report

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		Reporting criterion
05000312/LER-1981-003-03, /03L-0:on 810203,during Reactor Bldg Spray Sys Loop B Sfas Test,Reactor Bldg Spray Pump B Started Late. Caused by Incorrect Setting on Model 62B Agastat Timer. Timer Reset	/03L-0:on 810203,during Reactor Bldg Spray Sys Loop B Sfas Test,Reactor Bldg Spray Pump B Started Late. Caused by Incorrect Setting on Model 62B Agastat Timer. Timer Reset
05000312/LER-1981-003, Forwards LER 81-003/03L-0	Forwards LER 81-003/03L-0
05000312/LER-1981-004, Forwards LER 81-004/03L-0	Forwards LER 81-004/03L-0
05000312/LER-1981-004-03, /03L-0:on 810202,component Cooling Water Isolation Valve Failed to Close During Surveillance Procedure 205.07C, Isolation Valve Surveillance test,SFV-46204.Caused by Water in Air Line of Valve Actuator.Water Drained	/03L-0:on 810202,component Cooling Water Isolation Valve Failed to Close During Surveillance Procedure 205.07C, Isolation Valve Surveillance test,SFV-46204.Caused by Water in Air Line of Valve Actuator.Water Drained
05000312/LER-1981-005, Forwards LER 81-005/04L-0	Forwards LER 81-005/04L-0
05000312/LER-1981-005-04, /04L-0:on 810125,plant Liquid Effluent Ph Exceeded 8.5 Limit Established by Tech Spec App B,Section 2.4.Caused by Slightly out-of-tolerance Setpoint.Diversion Setpoint Was Reset.Alarm Setpoint Will Be Lowered	/04L-0:on 810125,plant Liquid Effluent Ph Exceeded 8.5 Limit Established by Tech Spec App B,Section 2.4.Caused by Slightly out-of-tolerance Setpoint.Diversion Setpoint Was Reset.Alarm Setpoint Will Be Lowered
05000312/LER-1981-006, Forwards LER 81-006/03L-0	Forwards LER 81-006/03L-0
05000312/LER-1981-006-03, /03L-0:on 810206,one of Two Pressurizer Code Safety valves,PSV-21506,lifted Above Setpoint Level Per Tech Specs During Bench Test.Possibly Caused by Seat Leakage During Test & Limited Capacity of Bench Tester	/03L-0:on 810206,one of Two Pressurizer Code Safety valves,PSV-21506,lifted Above Setpoint Level Per Tech Specs During Bench Test.Possibly Caused by Seat Leakage During Test & Limited Capacity of Bench Tester
05000312/LER-1981-007-01, /01T-0:on 810210,info Received That Certain safety-related Instrument Errors Exceed Those Assumed in FSAR Analysis.Possibly Caused by String Error Discrepancies. Applicability of Methodology Used in Rept Being Reviewed	/01T-0:on 810210,info Received That Certain safety-related Instrument Errors Exceed Those Assumed in FSAR Analysis.Possibly Caused by String Error Discrepancies. Applicability of Methodology Used in Rept Being Reviewed
05000312/LER-1981-007, Forwards LER 81-007/01T-0	Forwards LER 81-007/01T-0
05000312/LER-1981-008, Forwards LER 81-008/01T-0	Forwards LER 81-008/01T-0
05000312/LER-1981-008-01, /01T-0:on 810218,breaker Did Not Trip During Preventative Maint on Breaker 3A09,RBS Pump P-291A.Caused by Loose Wire on Pigtail of Trip Coil Due to Use of 14-16 Awg Lug on 20 Awg Wire.All Lugs on Pigtail Leads to Be Replaced	/01T-0:on 810218,breaker Did Not Trip During Preventative Maint on Breaker 3A09,RBS Pump P-291A.Caused by Loose Wire on Pigtail of Trip Coil Due to Use of 14-16 Awg Lug on 20 Awg Wire.All Lugs on Pigtail Leads to Be Replaced
05000312/LER-1981-009, Forwards LER 81-009/03L-0	Forwards LER 81-009/03L-0
05000312/LER-1981-009-03, /03L-0:on 810217,during Testing of Mod to Diesel Generator Room Vent Fans,Breaker 52-3B17 Tripped Free. Cause Undetermined.Breaker Replaced W/Class 1 Breaker & Returned to Svc	/03L-0:on 810217,during Testing of Mod to Diesel Generator Room Vent Fans,Breaker 52-3B17 Tripped Free. Cause Undetermined.Breaker Replaced W/Class 1 Breaker & Returned to Svc
05000312/LER-1981-010, Forwards LER 81-010/01T-0	Forwards LER 81-010/01T-0
05000312/LER-1981-010-01, /01T-0:on 810225,A/E,performing Analysis for IE Bulletin 79-14,informed of Potential Piping Stress Problem on Decay Heat Removal Sys A,Line 26120-10.Caused Not Stated. Sys Use Restricted to Temps & Pressures Below Design Lim	/01T-0:on 810225,A/E,performing Analysis for IE Bulletin 79-14,informed of Potential Piping Stress Problem on Decay Heat Removal Sys A,Line 26120-10.Caused Not Stated. Sys Use Restricted to Temps & Pressures Below Design Limits
05000312/LER-1981-011, Forwards LER 81-011/03L-0.Detailed Event Analysis Submitted	Forwards LER 81-011/03L-0.Detailed Event Analysis Submitted
05000312/LER-1981-011-03, /03L-0:on 810217,reactor Bldg Sump/Decay Heat Removal Sys Flow Path Obstructed.Caused by Installation of Blank Test Flanges on Suction Lines.Flanges Removed & Test Procedure Revised	/03L-0:on 810217,reactor Bldg Sump/Decay Heat Removal Sys Flow Path Obstructed.Caused by Installation of Blank Test Flanges on Suction Lines.Flanges Removed & Test Procedure Revised
05000312/LER-1981-012-01, /01T-0:on 810303,as-found Setpoints for High Reactor Bldg Pressure Trip Were Noted Exceeding Tech Spec. Caused by Instrument Drift.Switches Reset & Setpoints Revised	/01T-0:on 810303,as-found Setpoints for High Reactor Bldg Pressure Trip Were Noted Exceeding Tech Spec. Caused by Instrument Drift.Switches Reset & Setpoints Revised
05000312/LER-1981-012, Forwards LER 81-012/01T-0.Detailed Event Analysis Submitted	Forwards LER 81-012/01T-0.Detailed Event Analysis Submitted
05000312/LER-1981-013-03, /03L-0:on 810223,inner Door of Reactor Bldg Personnel Hatch Failed to Close Completely.Caused by Misinterpretation of Tech Specs.Written Interpretation to Be Distributed	/03L-0:on 810223,inner Door of Reactor Bldg Personnel Hatch Failed to Close Completely.Caused by Misinterpretation of Tech Specs.Written Interpretation to Be Distributed
05000312/LER-1981-013, Forwards LER 81-013/03L-0	Forwards LER 81-013/03L-0
05000312/LER-1981-014, Forwards LER 81-014/03L-0.Detailed Event Analysis Encl	Forwards LER 81-014/03L-0.Detailed Event Analysis Encl
05000312/LER-1981-014-03, /03L-0:on 810306,unacceptable Leak Rate Obtained During Local Component Leak Rate Test on Reactor Bldg Penetration 34.Caused by Motor Pinion Gear Key Backed Out of Keyway & Sheared Off.Set Screw Added to Operator Key	/03L-0:on 810306,unacceptable Leak Rate Obtained During Local Component Leak Rate Test on Reactor Bldg Penetration 34.Caused by Motor Pinion Gear Key Backed Out of Keyway & Sheared Off.Set Screw Added to Operator Key
05000312/LER-1981-015, Forwards LER 81-015/04T-0.Event Analysis Submitted	Forwards LER 81-015/04T-0.Event Analysis Submitted
05000312/LER-1981-015-04, /04T-0:on 810214,review of Feb 1981 Effluent Charts Showed Tech Spec for Plant Effluent Ph Was Exceeded. Caused by Effluent Diversion Setpoint Being Slightly out-of-tolerance.Setpoints Lowered	/04T-0:on 810214,review of Feb 1981 Effluent Charts Showed Tech Spec for Plant Effluent Ph Was Exceeded. Caused by Effluent Diversion Setpoint Being Slightly out-of-tolerance.Setpoints Lowered
05000312/LER-1981-016-03, Degradation of Lube Oil Cooling Capacity on HPI Pump B Found.Caused by Excessive Corrosion of Cooler Heads.Coolers Cleaned & One Epoxy Coated.After Satisfactory Performance Two Others Coated	Degradation of Lube Oil Cooling Capacity on HPI Pump B Found.Caused by Excessive Corrosion of Cooler Heads.Coolers Cleaned & One Epoxy Coated.After Satisfactory Performance Two Others Coated
05000312/LER-1981-016-01, /01T-0:on 810312,during Maint Insp of Lube Oil Cooler for HPI Pump B Discovered Substantial Corrosion Products Causing Degradation in Cooling Capacity.Caused by Excessive Corrosion of Cooler Heads	/01T-0:on 810312,during Maint Insp of Lube Oil Cooler for HPI Pump B Discovered Substantial Corrosion Products Causing Degradation in Cooling Capacity.Caused by Excessive Corrosion of Cooler Heads
05000312/LER-1981-016, Forwards LER 81-016/01T-0	Forwards LER 81-016/01T-0
05000312/LER-1981-017, Forwards LER 81-017/03L-0 & Submits Detailed Event Analysis	Forwards LER 81-017/03L-0 & Submits Detailed Event Analysis
05000312/LER-1981-017-03, /03L-0:on 810316,unistrut Cable Tray Support H-80 Found 3 Ft Out of Position & Not Fastened W/Anchor Bolts. Probably Caused by Relocation to Facilitate Movement of Equipment.Support Relocated & Fastened	/03L-0:on 810316,unistrut Cable Tray Support H-80 Found 3 Ft Out of Position & Not Fastened W/Anchor Bolts. Probably Caused by Relocation to Facilitate Movement of Equipment.Support Relocated & Fastened
05000312/LER-1981-018, Forwards LER 81-018/04T-0	Forwards LER 81-018/04T-0
05000312/LER-1981-018-04, /04T-0:on 810317,chlorine Concentration Exceeded Tech Specs Limit.Caused by Lower Flow Rate in One of Two Plant Sewage Sys Sump Pumps,Allowing Excess Hypochlorite Injection.Injection Rate Has Been Decreased	/04T-0:on 810317,chlorine Concentration Exceeded Tech Specs Limit.Caused by Lower Flow Rate in One of Two Plant Sewage Sys Sump Pumps,Allowing Excess Hypochlorite Injection.Injection Rate Has Been Decreased
05000312/LER-1981-019, Forwards LER 81-019/03L-0 & Submits Detailed Event Analysis	Forwards LER 81-019/03L-0 & Submits Detailed Event Analysis
05000312/LER-1981-019-03, /03L-0:on 810316,obstruction in Suction of Atmosphere Radiation Monitor R15001B Discovered.Caused by Plastic Cap from Bottle of Industrial Leak Detection Fluid. Bottle Cap Removed from Sample Line Suction	/03L-0:on 810316,obstruction in Suction of Atmosphere Radiation Monitor R15001B Discovered.Caused by Plastic Cap from Bottle of Industrial Leak Detection Fluid. Bottle Cap Removed from Sample Line Suction
05000312/LER-1981-020, Forwards LER 81-020/04T-0 & Submits Detailed Event Analysis	Forwards LER 81-020/04T-0 & Submits Detailed Event Analysis
05000312/LER-1981-020-04, /04T-0:on 810326,liquid Effluent Ph Exceeded 8.5 Tech Spec Limit for Approx 15 Minutes.Caused by Retention Basin Being Released Prior to Increasing Dilution Water Flow.Effluent Ph Instrumentation Calibr & Monitored	/04T-0:on 810326,liquid Effluent Ph Exceeded 8.5 Tech Spec Limit for Approx 15 Minutes.Caused by Retention Basin Being Released Prior to Increasing Dilution Water Flow.Effluent Ph Instrumentation Calibr & Monitored
05000312/LER-1981-021, Forwards LER 81-021/03T-0.Detailed Event Analysis Also Submitted	Forwards LER 81-021/03T-0.Detailed Event Analysis Also Submitted
05000312/LER-1981-021-03, /03T-0:on 810402,BWST Valve SFV-25003 Failed to Open Electrically Due to Rounded Off Dogs on Worm Shaft Clutch Gear.Caused by Manual Operation of Valve.Worm Components Replaced.Design Changes Are Being Processed	/03T-0:on 810402,BWST Valve SFV-25003 Failed to Open Electrically Due to Rounded Off Dogs on Worm Shaft Clutch Gear.Caused by Manual Operation of Valve.Worm Components Replaced.Design Changes Are Being Processed
05000312/LER-1981-022-03, /03L-0:on 810416,safety Sys Hydraulic Snubbers SS-16,SS-17 & 71(MS-20522-SW2) Were Found Low on Fluid Level.Cause Not Stated.Assemblies Reworked	/03L-0:on 810416,safety Sys Hydraulic Snubbers SS-16,SS-17 & 71(MS-20522-SW2) Were Found Low on Fluid Level.Cause Not Stated.Assemblies Reworked
05000312/LER-1981-022, Forwards LER 81-022/03L-0.Detailed Event Analysis Also Submitted	Forwards LER 81-022/03L-0.Detailed Event Analysis Also Submitted
05000312/LER-1981-023, Forwards LER 81-023/04T-0.Detailed Event Analysis Also Submitted	Forwards LER 81-023/04T-0.Detailed Event Analysis Also Submitted
05000312/LER-1981-023-04, /04T-0:on 810408,plant Liquid Effluent Ph Was Found to Have Dropped Below Tech Spec Limit.Probably Caused by Stagnant,Low Ph Water in Drain Line Due to Gravity Drain of Basin	/04T-0:on 810408,plant Liquid Effluent Ph Was Found to Have Dropped Below Tech Spec Limit.Probably Caused by Stagnant,Low Ph Water in Drain Line Due to Gravity Drain of Basin
05000312/LER-1981-024, Forwards LER 81-024/03T-0.Detailed Event Analysis Encl	Forwards LER 81-024/03T-0.Detailed Event Analysis Encl
05000312/LER-1981-024-03, /03T-0:on 810419,approx 4,000 Gallons of Reactor Coolant Was Inadvertently Transferred from RCS to Reactor Bldg Emergency Pump.Caused by Personnel Error.Rcs Was Refilled & Revented	/03T-0:on 810419,approx 4,000 Gallons of Reactor Coolant Was Inadvertently Transferred from RCS to Reactor Bldg Emergency Pump.Caused by Personnel Error.Rcs Was Refilled & Revented
05000312/LER-1981-025, Forwards LER 81-025/03T-0.Detailed Event Analysis Also Submitted	Forwards LER 81-025/03T-0.Detailed Event Analysis Also Submitted
05000312/LER-1981-025-03, /03T-0:on 810420 & 0506,pressurizer Liquid Sample Valve Failed to Operate.Caused by Stripped Drive Sleeve Bevel Gear.Operator Removed & Replaced.Valve Tested & Stroked	/03T-0:on 810420 & 0506,pressurizer Liquid Sample Valve Failed to Operate.Caused by Stripped Drive Sleeve Bevel Gear.Operator Removed & Replaced.Valve Tested & Stroked
05000312/LER-1981-026-01, /01T-0:on 810516,alert Indication Shown on Condenser Air Ejector Radiation Monitor Followed by High Alarm.Caused by Tube Leakage Due to through-wall Crack.Tubes Stabilized & Plugged	/01T-0:on 810516,alert Indication Shown on Condenser Air Ejector Radiation Monitor Followed by High Alarm.Caused by Tube Leakage Due to through-wall Crack.Tubes Stabilized & Plugged
05000312/LER-1981-026, Forwards LER 81-026/01T-0 & Submits Detailed Event Analysis	Forwards LER 81-026/01T-0 & Submits Detailed Event Analysis
05000312/LER-1981-027, Forwards LER 81-027/03L-0.Detailed Event Analysis Also Submitted	Forwards LER 81-027/03L-0.Detailed Event Analysis Also Submitted
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