LER-1980-037, During Mode 1 Operation, Safety Injection Tanks (SIT) C & D Were Found to Have Boron Concentrations of 1711 Ppm & 1620 Ppm.Probably Caused by Dilution of SIT Makeup Path by Reactor Coolant |
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A Ci Revised Report - Previous Report Date 6/17/80 NRC F ORM 366 U. S. NUCLE AR REGULATORY COMMISS60N (7 77)
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74 76 HFPoRT DATE 80 EVENT DESCRIPTION AND PROBA8LE CONSEQUENCES h i o 12 i f Durina Mode 1 operation, Safety In.iection Tanks (SIT) "C"
& "D" were i
i found to have boron concentrations of 1711 ppm and 1620 ppm boron con-1 io i3 i go i. i i centration, which is below the 1731 ppm boron concentration as per i
inisii T.S. 3.5.1.c.
The SIT "A"
& "B" boron concentrations were verified to i
io gi i be at acceptable levels.
Prompt reportable per T.S.6.9.1.8.b due to i
,,,,, i simul taneous out of spec SIT's.
No similar occurrences.
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33 40 41 42 43 44 43 CAUSE OESCRiPTION AND CORREC(IVE ACTIONS h Cause of occurrence is believed to be dilution of the SIT makeup path by,
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Reportable Occurrence Report No. 50-368/80-037 2.
Report Date:
3.
' Occurrence Date: 6/3/80 4
Facility: Arkansas Nuclear One - Unit II Russellville, Arkansas 5.
Identification of Occurrence:
Operation of the Emergency Core Cooling System with the Safe +y Injection Tanks (SIT) operability less conservative than tk least conservative aspect of the limiting condition for operation defined in T.S. 3.5.1.c.
6.
Conditions Prior to Occurrence:
Steady-State Power X
Reactor Power _ 2815 Knth 4
Hot Standby Net Output
=925 Kwe Cold Shutdown Percent of Full Power 100
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Refueling Shutdown Load Changes During Routine Power Operation Rcutine Startup Operation i
Routine Shutdown i
Operation Other (specify) i
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l Description of Occurrence:
l Two SIT's boron concentration simultaneously out of specification for less than one hour.
During routine sampling of the SIT's, it was discovered that SIT "C" and "D" had boron concentrations less than 173:
m boron specified r
(
in T.S. 3.5.1.c.
SIT "A" and "B" boron concentrations were verified to be greater than 1731 ppm boron.
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Reportable Occurrence Report No.
8.
Designation of Apparent Cause of Occurrence:
l 3esign Procedure Maniufactu.e Unusual Service Condition Including Environmental Insta11at: ion /
Construction Component Failure (See Failure Data)
Operator Other (specify)
Boration path dilution Based on local sampling tests, a portion of the SIT fill path may be diluted (from the RWT concentration) by reactor coolant during extend.
Shutdown Cooling System operation. With such dilution occurring during the snall makeup operations, the SIT boron concentration is decreased.
9.
Analysis of Occurrence:
The SIT's renuire periodic makeup to maintain T.S. required levels due to volume contraction during unit cooldowns and volume reductions dur ir,g ncrmal operation.
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Reportable Occurrence Report No.
10.
Corrective Action
2 The SIT fill path and fill method is being evaluated to ensure undiluted boration. Boron stratification in the SIT is also being studied.
SIT "C" and "D" were returned to the Tech Spec required boron concentrations utilizing the feed-and-bleed method.
1 11.
Failure Data:
There have been no similar occurrences.
t 11.
Failure Data:
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| 05000368/LER-1980-001-03, /03L-0:on 800107,during Mode 1 Operation, Containment Isolation Valve 25V-5876-2 Failed to Close After Taking Samples from Safety Injection Tanks for Boron Analysis.Caused by Faulty Valve Position Indication | /03L-0:on 800107,during Mode 1 Operation, Containment Isolation Valve 25V-5876-2 Failed to Close After Taking Samples from Safety Injection Tanks for Boron Analysis.Caused by Faulty Valve Position Indication | | | 05000313/LER-1980-001-03, /03L-0:on 800114,while Performing Surveillance Test,Hydrogen Purge Supply Isolation Valve CV-7444 Failed to Close.Caused by Oxidation on Torque Switch Contacts, Resulting in High Resistance to Closure.Contacts Cleaned | /03L-0:on 800114,while Performing Surveillance Test,Hydrogen Purge Supply Isolation Valve CV-7444 Failed to Close.Caused by Oxidation on Torque Switch Contacts, Resulting in High Resistance to Closure.Contacts Cleaned | | | 05000368/LER-1980-002-03, /03L-0:on 800110,during Mode 1 Operation,Core Protection Calculator C Failed,Resulting in DNBR & Linear Power Density Trips in Channel C Primary Power Sys.Cause Undetermined.Sys Restarted During Failure Analysis | /03L-0:on 800110,during Mode 1 Operation,Core Protection Calculator C Failed,Resulting in DNBR & Linear Power Density Trips in Channel C Primary Power Sys.Cause Undetermined.Sys Restarted During Failure Analysis | | | 05000313/LER-1980-002-03, /03L-0:on 800114,while Performing Surveillance Test,Hydrogen Purge Supply Isolation Valve CV-7448 Failed to Close.Caused by Oxidation on Torque Switch Contacts.Contacts Cleaned | /03L-0:on 800114,while Performing Surveillance Test,Hydrogen Purge Supply Isolation Valve CV-7448 Failed to Close.Caused by Oxidation on Torque Switch Contacts.Contacts Cleaned | | | 05000313/LER-1980-003-01, /01T-0:on 800121,while at Cold Shutdown,Boron Buildups Identified on Loop B of Reactor Bldg Spray & Piping.Buildups Verified to Be Cracks in heat-affected Zone of Schedule 10 Pipe to Fitting Welds | /01T-0:on 800121,while at Cold Shutdown,Boron Buildups Identified on Loop B of Reactor Bldg Spray & Piping.Buildups Verified to Be Cracks in heat-affected Zone of Schedule 10 Pipe to Fitting Welds | | | 05000313/LER-1980-003, Forwards LER 80-003/01T-0 | Forwards LER 80-003/01T-0 | | | 05000368/LER-1980-003-03, /03L-0:on 800120,during Mode 3 Operation, Emergency Feedwater Flow Control Valve Failed to Close on Demand.Caused by Lack of Hydraulic Pressure | /03L-0:on 800120,during Mode 3 Operation, Emergency Feedwater Flow Control Valve Failed to Close on Demand.Caused by Lack of Hydraulic Pressure | | | 05000368/LER-1980-004-03, /03L-0:on 800107,during Mode 1 Operation,Core Protection Calculator B Failed.Channel B DNBR & Linear Power Density Trips Were Bypassed Placing Reactor Trip Logic in two-out-of-three Trip Sequence.Cause Unknown | /03L-0:on 800107,during Mode 1 Operation,Core Protection Calculator B Failed.Channel B DNBR & Linear Power Density Trips Were Bypassed Placing Reactor Trip Logic in two-out-of-three Trip Sequence.Cause Unknown | | | 05000313/LER-1980-004-03, /03L-0:on 800205,during Operational Test for Leak Rates,Reactor Bldg Ventilation Penetrations V1 & V2 Found Leaking in Excess of Tech Specs.Caused by Maladjusted Valve Seats.Valves Readjusted & Retested | /03L-0:on 800205,during Operational Test for Leak Rates,Reactor Bldg Ventilation Penetrations V1 & V2 Found Leaking in Excess of Tech Specs.Caused by Maladjusted Valve Seats.Valves Readjusted & Retested | | | 05000313/LER-1980-004, Forwards LER 80-004/03L-0 | Forwards LER 80-004/03L-0 | | | 05000368/LER-1980-005, Forwards Revised LER 80-005/03X-1 | Forwards Revised LER 80-005/03X-1 | | | 05000368/LER-1980-005-03, /03L-0:on 800123,during Steady State Mode 1 Operation,Reactor Coolant Leakage Calculation Indicated Approx 3.6 Gpm Unidentified Leakage.Caused by Packing on Pressurized Spray Valves Leaking Excessively | /03L-0:on 800123,during Steady State Mode 1 Operation,Reactor Coolant Leakage Calculation Indicated Approx 3.6 Gpm Unidentified Leakage.Caused by Packing on Pressurized Spray Valves Leaking Excessively | | | 05000313/LER-1980-005, Forwards LER 80-005/03L-0 | Forwards LER 80-005/03L-0 | | | 05000313/LER-1980-005-03, /03L-0:on 800306,during Scheduled Surveillance Test of P7-A,CV-2617 Valve Failed to Close Remote Electrically.Caused by Valve Binding in Closed Position. Valve Stem Repacked & Proper Operation Verified | /03L-0:on 800306,during Scheduled Surveillance Test of P7-A,CV-2617 Valve Failed to Close Remote Electrically.Caused by Valve Binding in Closed Position. Valve Stem Repacked & Proper Operation Verified | | | 05000313/LER-1980-006, Forwards LER 80-006/04L-0 | Forwards LER 80-006/04L-0 | | | 05000368/LER-1980-006-03, /03L-0:on 800123,during Mode 1 Operation,Core Protection Calculator B Failed,Generating DNBR & Linear Power Density Trips in Primary Power Sys.Cause Undetermined. Channel Restarted & Declared Operable | /03L-0:on 800123,during Mode 1 Operation,Core Protection Calculator B Failed,Generating DNBR & Linear Power Density Trips in Primary Power Sys.Cause Undetermined. Channel Restarted & Declared Operable | | | 05000313/LER-1980-006-04, /04L-0:on 800318,average Gross Release Rate for Jan-Mar 1980 Found to Be 4.3% of Max Permissible Concentration,Exceeding Tech Specs.Major Portion Caused by Reactor Bldg Purge in Jan | /04L-0:on 800318,average Gross Release Rate for Jan-Mar 1980 Found to Be 4.3% of Max Permissible Concentration,Exceeding Tech Specs.Major Portion Caused by Reactor Bldg Purge in Jan | | | 05000313/LER-1980-007, Forwards LER 80-007/01T-0 | Forwards LER 80-007/01T-0 | | | 05000313/LER-1980-007-99, Vendor Notified of Discrepancy Between Decay Heat Pump Specs & Parts Supplied. Potential Failure Feared.Tests & Performance History Indicate No Reliability Problems | Vendor Notified of Discrepancy Between Decay Heat Pump Specs & Parts Supplied. Potential Failure Feared.Tests & Performance History Indicate No Reliability Problems | | | 05000313/LER-1980-007-01, /01T-0:on 800314,B&W Advised That Mating Wear Rings on Double Suction Pump Could Cause Pump Failure During Accident Conditions.Caused by Failure to Document Design Revision on Pump Design Drawings | /01T-0:on 800314,B&W Advised That Mating Wear Rings on Double Suction Pump Could Cause Pump Failure During Accident Conditions.Caused by Failure to Document Design Revision on Pump Design Drawings | | | 05000368/LER-1980-007-03, /03L-0:on 800124,during Mode 1 Operation,Sodium Hydroxide Tank Level Found to Be 93% of Indicated Level. Following Calibr,Level Found to Be Below Tech Spec Limits. Cause Not Stated.Tank Levels Returned to Operable Limits | /03L-0:on 800124,during Mode 1 Operation,Sodium Hydroxide Tank Level Found to Be 93% of Indicated Level. Following Calibr,Level Found to Be Below Tech Spec Limits. Cause Not Stated.Tank Levels Returned to Operable Limits | | | 05000313/LER-1980-008-03, /03L-0:on 800324,while Performing Surveillance Test,Bypass Flow Was Observed to Be Zero Due to Failure of CV-2126 in Closed Position.Caused by Blown Control Fuse.Fuse Replaced & Valve Proved Operable | /03L-0:on 800324,while Performing Surveillance Test,Bypass Flow Was Observed to Be Zero Due to Failure of CV-2126 in Closed Position.Caused by Blown Control Fuse.Fuse Replaced & Valve Proved Operable | | | 05000368/LER-1980-008-03, /03L-0:on 800128,during Mode 1 Operation,Core Protection Calculator B Failed.Cause Not Determined.Core Protection Calculator B Restored & Functionally Tested | /03L-0:on 800128,during Mode 1 Operation,Core Protection Calculator B Failed.Cause Not Determined.Core Protection Calculator B Restored & Functionally Tested | | | 05000313/LER-1980-008, Forwards LER 80-008/03L-0 | Forwards LER 80-008/03L-0 | | | 05000313/LER-1980-009-03, /03L-0:on 800328,while Performing Surveillance Test,Lead Hydrogen Purge Supply fan,VSF-30A Tripped on Overload.Caused by Check Valve HPA-5 Being Stuck,Due to Corrosion from Seal Water Leaking Onto Valve | /03L-0:on 800328,while Performing Surveillance Test,Lead Hydrogen Purge Supply fan,VSF-30A Tripped on Overload.Caused by Check Valve HPA-5 Being Stuck,Due to Corrosion from Seal Water Leaking Onto Valve | | | 05000313/LER-1980-009, Forwards LER 80-009/03L-0 | Forwards LER 80-009/03L-0 | | | 05000368/LER-1980-009, Forwards LER 80-009/03L-0 | Forwards LER 80-009/03L-0 | | | 05000368/LER-1980-009-03, /03L-0:on 800129,during Mode 3 Operation Following Reactor Trip from 100% power,I-131 Value of 1.67 Uci Was Observed.Caused by Expected Spike Following Reactor Trip.No Corrective Actions Necessary | /03L-0:on 800129,during Mode 3 Operation Following Reactor Trip from 100% power,I-131 Value of 1.67 Uci Was Observed.Caused by Expected Spike Following Reactor Trip.No Corrective Actions Necessary | | | 05000368/LER-1980-010-03, /03L-0:on 800212,during Mode 5 Operation, Discovered That Tech Spec 24-month Local Leak Rate Surveillance Requirements Had Not Been Performed.Caused by Confusion Over 24-month Surveillance Interval | /03L-0:on 800212,during Mode 5 Operation, Discovered That Tech Spec 24-month Local Leak Rate Surveillance Requirements Had Not Been Performed.Caused by Confusion Over 24-month Surveillance Interval | | | 05000313/LER-1980-010-03, /03L-0:on 800307,sys Reviews Per IE Bulletin 79-14 Found Hangers Inoperable.Cause Not Stated.Hangers Repaired & Mods Made by Revision to DCP 80-D-1207.List of Hangers Encl | /03L-0:on 800307,sys Reviews Per IE Bulletin 79-14 Found Hangers Inoperable.Cause Not Stated.Hangers Repaired & Mods Made by Revision to DCP 80-D-1207.List of Hangers Encl | | | 05000313/LER-1980-010, Forwards LER 80-010/03L-0 | Forwards LER 80-010/03L-0 | | | 05000313/LER-1980-011, Forwards LER 80-011/03L-0 | Forwards LER 80-011/03L-0 | | | 05000313/LER-1980-011-03, /03L-0:on 800401,based on Sys Review Per IE Bulletin 79-14,certain Hangers Declared Inoperable.Cause Not Stated.Hangers Repaired or Modified within Required Time Limit on Affected Svc Water & Main Steam Sys | /03L-0:on 800401,based on Sys Review Per IE Bulletin 79-14,certain Hangers Declared Inoperable.Cause Not Stated.Hangers Repaired or Modified within Required Time Limit on Affected Svc Water & Main Steam Sys | | | 05000368/LER-1980-011-03, /03L-0:on 800214,during Mode 5 Operation,While Performing Local Leak Rate Test,Five Containment Penetration Leak Rates Exceeded Tech Specs.Caused by Corrosion Buildup on Seating Surface or Valves Needing Adjustment | /03L-0:on 800214,during Mode 5 Operation,While Performing Local Leak Rate Test,Five Containment Penetration Leak Rates Exceeded Tech Specs.Caused by Corrosion Buildup on Seating Surface or Valves Needing Adjustment | | | 05000368/LER-1980-012, Forwards Updated LER 80-012/03X-2 | Forwards Updated LER 80-012/03X-2 | | | 05000313/LER-1980-012, Forwards LER 80-012/03L-0 | Forwards LER 80-012/03L-0 | | | 05000313/LER-1980-012-03, /03L:on 800406,while Performing Monthly Inservice Valve Stroke Test,Emergency Feedwater Supply valves,CV2667 & CV2617,failed to Fully Open.Caused by Binding Due to Loose Bolts Securing Actuator | /03L:on 800406,while Performing Monthly Inservice Valve Stroke Test,Emergency Feedwater Supply valves,CV2667 & CV2617,failed to Fully Open.Caused by Binding Due to Loose Bolts Securing Actuator | | | 05000368/LER-1980-012-03, /03L-0:on 800222,during Mode 5 Operation,While Performing Surveillance Tests on Diesel Generator 1,unit Became Inoperable.Caused by Broken Generator Rotor Shaft in Area of Motor End Bearing Housing.Analyzing Exact Cause | /03L-0:on 800222,during Mode 5 Operation,While Performing Surveillance Tests on Diesel Generator 1,unit Became Inoperable.Caused by Broken Generator Rotor Shaft in Area of Motor End Bearing Housing.Analyzing Exact Cause | | | 05000313/LER-1980-013, Forwards LER 80-013/03L-0 | Forwards LER 80-013/03L-0 | | | 05000368/LER-1980-013-03, /03L-0:on 800229,during Mode 5 Operation,Reactor Cooling Sys Chloride Concentration Found to Be Approx 0.5 Ppm,Violating Tech Specs.Probably Caused by Batch Contaminated During Maint on Safety Injection Check Valve | /03L-0:on 800229,during Mode 5 Operation,Reactor Cooling Sys Chloride Concentration Found to Be Approx 0.5 Ppm,Violating Tech Specs.Probably Caused by Batch Contaminated During Maint on Safety Injection Check Valve | | | 05000368/LER-1980-013, Forwards LER 80-013/03L-0 | Forwards LER 80-013/03L-0 | | | 05000313/LER-1980-013-03, /03L-0:on 800407,during Reactor Trip of Offsite Power,High Pressure Injection Was Manually Initiated & CV-1227 High Pressure Injection Valve,Loop B Failed to Open on Demand.Caused by Stuck Engaging Lever | /03L-0:on 800407,during Reactor Trip of Offsite Power,High Pressure Injection Was Manually Initiated & CV-1227 High Pressure Injection Valve,Loop B Failed to Open on Demand.Caused by Stuck Engaging Lever | | | 05000368/LER-1980-014-03, /03L-0:on 800313,during Mode 5 Operation,Local Leak Rate Testing at Containment Penetration 2V2 Revealed Excessive Leak Rate Between Valve Actuation & Heatup Processes.Caused by Partially Open Inside Isolation Valve | /03L-0:on 800313,during Mode 5 Operation,Local Leak Rate Testing at Containment Penetration 2V2 Revealed Excessive Leak Rate Between Valve Actuation & Heatup Processes.Caused by Partially Open Inside Isolation Valve | | | 05000368/LER-1980-014, Forwards LER 80-014/03L-0 | Forwards LER 80-014/03L-0 | | | 05000313/LER-1980-014, Forwards LER 80-014/03L-0 | Forwards LER 80-014/03L-0 | | | 05000313/LER-1980-014-03, /03X-1:on 800415,fire & Smoke Detector Testing Not Completed within Surveillance Interval Due to High Radiation Level.Detectors Tested at Cold Shutdown.Tech Spec 4.19 Revised | /03X-1:on 800415,fire & Smoke Detector Testing Not Completed within Surveillance Interval Due to High Radiation Level.Detectors Tested at Cold Shutdown.Tech Spec 4.19 Revised | | | 05000368/LER-1980-015, Forward LER 80-015/99X-0 | Forward LER 80-015/99X-0 | | | 05000368/LER-1980-015-99, /99X-0:on 800129,during Recovery from Planned Transient,Rcs Depressurized to Min of 1,350 Psia.Caused by Pressurizer Spray Valve 2CV-4651 & Steam Dump & Bypass Valve 2CV-0301 Not Fully Closing on Demand.Valves Modified | /99X-0:on 800129,during Recovery from Planned Transient,Rcs Depressurized to Min of 1,350 Psia.Caused by Pressurizer Spray Valve 2CV-4651 & Steam Dump & Bypass Valve 2CV-0301 Not Fully Closing on Demand.Valves Modified | | | 05000313/LER-1980-015, Forwards LER 80-015/01T-0 | Forwards LER 80-015/01T-0 | | | 05000313/LER-1980-015-01, /01T-0:on 800510,changes in Seal Pressure & Makeup Tank Level Occurred During Steady State Power Operation. Caused by Rx Coolant Pump Seal C.Seal Cartridge Rebuilt & Seal Failure Being Investigated | /01T-0:on 800510,changes in Seal Pressure & Makeup Tank Level Occurred During Steady State Power Operation. Caused by Rx Coolant Pump Seal C.Seal Cartridge Rebuilt & Seal Failure Being Investigated | |
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