LER-1981-032, /03L-0:on 810419,heat Exchanger,Model Ceu,Size 52-8-144,baffle Plate Was Discovered to Be Bowed.Caused by Excessive Differential Pressure Across Baffle Plate from Accumulation of Shells in Heat Exchanger.Plate Reinstalled |
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60 Gl DOCKET.NUMSER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h l [TITl l During a special inspection of 1B RHR heat exchaneer. as conunitted to in LER' 2-80-30. I (gl it was discovered that the heat exchanger, Model No. CEU, Size 52-8-144." baffle plate I l
@ l was partially bowed in the center at the bottom siere it fits into a eroove of the ITTTI I channel cover. As a result of this event, an inspection of the Unit No. 2 RHR heat I
l o Is l I exchangces was conducted which is being reported in LER 2-81-49.
This event did not I l o 171 l affect the health or safety of the public.
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35 36 37 40 41 42 43 44 47 33 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h 1 o I Excessive differential oressure across the baffle nlate resultine from an accumula-1 1 1 l
tion of shells in the heat exchanoer enused the ninte to how and narefn11v cannenea I l
from attachment welds on each side of the plate. The heat exchanger tubes are I
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reinstalled to return the heat exchanger to operability.
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LER ATTACHMENT - RO #1-E -32
- - Facility: BSEP Unit No. 1 Event Date: 4-19-81 During the inspection of IB RHR heat exchanger, it was found that the heat exchanger baffle plate was displaced approximately 9" at the bottom, which created a service water flow path from the inlet to the outlet, bypassing the tubes. The purpose of the plate is ~ t<i separate RHRSW. entering.the heat exchanger from RHRSW 1eaving'after-it has passed through the heat exchanger U-tubes. From the -inspection and an engineering evaluation of the plate failure,'
it was concluded that the failure occurred due to the failure of ;,lete attachment welds to within 8 - 10" of the heat ' exchanger tube sheet which' resulted from excessive differential pressure across the plate. The cause o.f the excessive differential pressure has been attributed to a blockage of the heat exchanger tube by shells (approximately 95Y, oyster) which accuciulated'in the heat exchanger when shells on the walls of the main service water piping became dislodged. The shall buildup apparently resulted from the service water chlorination system being out of service for an extended period.
4 l-During the repair of the IB RHR heat exchanger, a loss of cooling was" experienced immediately following the starting of a second. RHR service water pump on the 1A RHR heat exchanger., In establishing an alternate shutdown cooling line sp, it was decided to reject from the vessel with the RHR system through the fuel pool coolers and to the condensate storage tank (CST). To i
return water to the vessel, the Core Spray system would take a suction from the CST and provide makeup to the vessel at a throttled flow.of approximately 5000' gpm for level control. This lineup was later modified to delete the Core Spray system and the CST and return water to the vessel using the RHR system. Vessel temperature never reached 170*F. Using the Control Rod Drive system for vessel ~
l return was considered, however, it was felt that the low flow rate of this system would not provide sufficient cooling and mixing to maintain reactor temoarature below a desirable level.
To restore a normal shutdown cooling lineup as expeditiously as possible, temporary repairs were performed on the 1A heat exchanger and it was restored to service while permanent repairs were still in progress on the IB heat exchanger.
The baffle plate on the 1A heat exchanger was also found to be displaced at the bottom.
I An evaluation of the 1A heat exchanger baffle failure concluded that baffle displacement also occurred as a result of shell buildup. When the second RHRSW pur, was started, increased flow through the heat exchanger caused an excessive d__ferential pressure that displaced the baffle plate approyimately 9".
Permanent repairs for the la heat exchanger will follow the completion of work and the return to service of the IB heat exchanger.
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LER ATTACHMENT - RO #1-81-32 Facility: BSEP Unit No.1 Event Date: 4-19-81 o
A program is being pursued to monitor safety-related heat exchanger performance.
It will consist of using available temperature, flow and differential pressure instrumentation to determine the heat transfer rates and flow rates. This will help predict baffle plate degradation.
In order to prevent future similar occurrences, plant procedures will be revised to ensure the RHRSW system header is vented once per week and prior to opuration of the system. In addition, the heat exchanger tubes and service water piping will be cleaned to remove shell buildup. A design review of the divider plate will be performed to assure its adequacy.
These actions, along with the resumption of the service water chlorination program, will help eliminate future organism shell growth.
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| 05000325/LER-1981-001, Forwards LER 81-001/01T-0 | Forwards LER 81-001/01T-0 | | | 05000325/LER-1981-001-01, /01T-0:on 810103,feed Pump Tripped on High Vessel Level Due to safety-relief Valve B21-F013G,Model 67F,lift. Caused by High Second Stage & Pilot Leakage in Valve.Pilot Valve Temporarily Replaced Until Next Scheduled Outage | /01T-0:on 810103,feed Pump Tripped on High Vessel Level Due to safety-relief Valve B21-F013G,Model 67F,lift. Caused by High Second Stage & Pilot Leakage in Valve.Pilot Valve Temporarily Replaced Until Next Scheduled Outage | | | 05000324/LER-1981-001, Forwards LER 81-001/03L-0 | Forwards LER 81-001/03L-0 | | | 05000324/LER-1981-001-03, /03L-0:on 810129,during Surveillance Testing, HPCI Sys Initiation Reactor Level Switch Actuated at Simulated Level Above Tech Spec.Caused by Components Slipping Due to Loose Set Screws on Actuator Pointers | /03L-0:on 810129,during Surveillance Testing, HPCI Sys Initiation Reactor Level Switch Actuated at Simulated Level Above Tech Spec.Caused by Components Slipping Due to Loose Set Screws on Actuator Pointers | | | 05000325/LER-1981-002-03, /03L-0:on 810114 & 0212,reactor Protection Sys Logic relays,C71-K3D & K3E,did Not de-energize When MSIV 1-B21-F028B Was Closed.Caused by Sticking Valve Position Limit Switch Actuator Arm Cam.Switch Replaced | /03L-0:on 810114 & 0212,reactor Protection Sys Logic relays,C71-K3D & K3E,did Not de-energize When MSIV 1-B21-F028B Was Closed.Caused by Sticking Valve Position Limit Switch Actuator Arm Cam.Switch Replaced | | | 05000325/LER-1981-002, Forwards LER 81-002/03L-0 | Forwards LER 81-002/03L-0 | | | 05000324/LER-1981-002-03, /03L-0:on 810104,vacuum Breaker X-18A Had Dual open-close Position Indication While in Open Position. Probably Caused by Problem W/Vacuum Breaker Position Limit Switches.Problem Will Be Resolved During Next Outage | /03L-0:on 810104,vacuum Breaker X-18A Had Dual open-close Position Indication While in Open Position. Probably Caused by Problem W/Vacuum Breaker Position Limit Switches.Problem Will Be Resolved During Next Outage | | | 05000324/LER-1981-002, Forwards LER 81-002/03L-0 | Forwards LER 81-002/03L-0 | | | 05000324/LER-1981-003-03, /03L-0:on 810108,suppression Pool Level Exceeded Specs.Caused by Valve Operator Torque Switch Out of Adjustment Allowing Leakage Into Suppression Pool.Switch Repaired | /03L-0:on 810108,suppression Pool Level Exceeded Specs.Caused by Valve Operator Torque Switch Out of Adjustment Allowing Leakage Into Suppression Pool.Switch Repaired | | | 05000324/LER-1981-003, Forwards LER 81-003/03L-0 | Forwards LER 81-003/03L-0 | | | 05000325/LER-1981-003-03, /03L-0:control Rod 26-35 on 810103,18-51 on 810113,38-31 & 22-15 on 810114 Showed Inaccurate Position Indications.Caused by Buffer Card Failure on 26-35;defective Reed Switches in Others.Card Replaced,Switches Repaired | /03L-0:control Rod 26-35 on 810103,18-51 on 810113,38-31 & 22-15 on 810114 Showed Inaccurate Position Indications.Caused by Buffer Card Failure on 26-35;defective Reed Switches in Others.Card Replaced,Switches Repaired | | | 05000325/LER-1981-003, Forwards LER 81-003/03L-0 | Forwards LER 81-003/03L-0 | | | 05000324/LER-1981-004, Forwards LER 81-004/03L-0 | Forwards LER 81-004/03L-0 | | | 05000324/LER-1981-004-03, /03L-0:on 810110,during Startup,Intermediate Range Monitor a Did Not Respond to Changes in Input Signal.Monitor C Indicated Downscale When on Range 7.On 810111 Monitor E Indicated Downscale While Monitor C Still Inoperable | /03L-0:on 810110,during Startup,Intermediate Range Monitor a Did Not Respond to Changes in Input Signal.Monitor C Indicated Downscale When on Range 7.On 810111 Monitor E Indicated Downscale While Monitor C Still Inoperable | | | 05000325/LER-1981-004, Forwards LER 81-004/03L-0 | Forwards LER 81-004/03L-0 | | | 05000325/LER-1981-004-03, /03L-0:on 810118,during Control Rod Operability Check,Pt 14.1,rod 26-07 Would Not Select.Caused by Loose Solder Joint in Rod Select Switch Due to Frequent Use of Switch.New Solder Joint Made | /03L-0:on 810118,during Control Rod Operability Check,Pt 14.1,rod 26-07 Would Not Select.Caused by Loose Solder Joint in Rod Select Switch Due to Frequent Use of Switch.New Solder Joint Made | | | 05000325/LER-1981-005, Forwards LER 81-005/03L-0 | Forwards LER 81-005/03L-0 | | | 05000325/LER-1981-005-03, /03L-0:on 810101,during Normal Surveillance, Discovered Secondary Containment 20 Ft Elevation Inner Air Lock Door Inoperable Due to Missing Gasket Sealing Matl. Caused by High Personnel Traffic.Gasket Replaced | /03L-0:on 810101,during Normal Surveillance, Discovered Secondary Containment 20 Ft Elevation Inner Air Lock Door Inoperable Due to Missing Gasket Sealing Matl. Caused by High Personnel Traffic.Gasket Replaced | | | 05000324/LER-1981-005-03, /03L-0:on 810113,during Normal Surveillance, Secondary Containment 20-ft Elevation Outer Air Lock Personnel Door Found Not Sealing.Caused by Heavy Personnel Traffic Through Door.Gasket Repaired | /03L-0:on 810113,during Normal Surveillance, Secondary Containment 20-ft Elevation Outer Air Lock Personnel Door Found Not Sealing.Caused by Heavy Personnel Traffic Through Door.Gasket Repaired | | | 05000324/LER-1981-005, Forwards LER 81-005/03L-0 | Forwards LER 81-005/03L-0 | | | 05000324/LER-1981-006-03, /03L-0:on 810115,when Main Steam Line Isolation Valve F028C Reopened During Test P.T.1.3.1P-2,main Steam Line C Indicated Min Flow.Cause Undetermined.Investigation Will Be Performed During Future Outage | /03L-0:on 810115,when Main Steam Line Isolation Valve F028C Reopened During Test P.T.1.3.1P-2,main Steam Line C Indicated Min Flow.Cause Undetermined.Investigation Will Be Performed During Future Outage | | | 05000324/LER-1981-006, Forwards LER 81-006/03L-0 | Forwards LER 81-006/03L-0 | | | 05000325/LER-1981-006, Forwards LER 81-006/03L-0 | Forwards LER 81-006/03L-0 | | | 05000325/LER-1981-006-03, /03L-0:on 810101,containment Atmospheric Monitor, 1-CAC-ATH-1259-2 Found Out of Calibr.Caused by Instrument Drift.Monitor Recalibr & Returned to Svc | /03L-0:on 810101,containment Atmospheric Monitor, 1-CAC-ATH-1259-2 Found Out of Calibr.Caused by Instrument Drift.Monitor Recalibr & Returned to Svc | | | 05000324/LER-1981-007, Forwards LER 81-007/03L-0 | Forwards LER 81-007/03L-0 | | | 05000325/LER-1981-007-03, /03L-0:on 810220,observed 2-inch Discrepancy Between Level Indicators of Suppression Pool Level Transmitters 1-CAC-LT-2601 & 2602.Caused by Insufficient Venting of 2602 Transmitter High Side Sensing Line | /03L-0:on 810220,observed 2-inch Discrepancy Between Level Indicators of Suppression Pool Level Transmitters 1-CAC-LT-2601 & 2602.Caused by Insufficient Venting of 2602 Transmitter High Side Sensing Line | | | 05000325/LER-1981-007, Forwards LER 81-007/03L-0 | Forwards LER 81-007/03L-0 | | | 05000324/LER-1981-007-03, /03L-0:on 810115,Group 1 Isolation Signal Received on Reactor Protection Sys Trip Channel B.Caused by Failure of Relay Coil,Model P/N 12HFAS1A49F Due to Insulation Breakdown.Coil Replaced | /03L-0:on 810115,Group 1 Isolation Signal Received on Reactor Protection Sys Trip Channel B.Caused by Failure of Relay Coil,Model P/N 12HFAS1A49F Due to Insulation Breakdown.Coil Replaced | | | 05000325/LER-1981-008-03, /03L-0:on 810106,while Performing Primary Containment Leak Rate Testing of Personnel Airlock Doors, Discovered That Drywell Exterior Airlock Door Leakage Rate Exceeded Limits.Caused by Tubing Fitting Lodged in Door | /03L-0:on 810106,while Performing Primary Containment Leak Rate Testing of Personnel Airlock Doors, Discovered That Drywell Exterior Airlock Door Leakage Rate Exceeded Limits.Caused by Tubing Fitting Lodged in Door | | | 05000325/LER-1981-008, Forwards LER 81-008/03L-0 | Forwards LER 81-008/03L-0 | | | 05000324/LER-1981-009-04, /04T-0:on 810128,radwaste Sys Liquid Effluent Discharge High Range Indicator/Recorder Found to Have Recorded Release Rate Less than Actual,Causing Tech Spec Limit to Be Exceeded.Caused by Loose Mechanical Linkage | /04T-0:on 810128,radwaste Sys Liquid Effluent Discharge High Range Indicator/Recorder Found to Have Recorded Release Rate Less than Actual,Causing Tech Spec Limit to Be Exceeded.Caused by Loose Mechanical Linkage | | | 05000325/LER-1981-009, Forwards LER 81-009/03L-0 | Forwards LER 81-009/03L-0 | | | 05000325/LER-1981-009-03, /03L-0:on 810115,sys Oil Cooler Inlet Isolation Valve 1-E51-F046 Would Not Open from RTGB Resulting in Reactor Core Isolation Cooling Inoperability.Caused by Incorrect Motor Control Ctr Key Lock Switch Position | /03L-0:on 810115,sys Oil Cooler Inlet Isolation Valve 1-E51-F046 Would Not Open from RTGB Resulting in Reactor Core Isolation Cooling Inoperability.Caused by Incorrect Motor Control Ctr Key Lock Switch Position | | | 05000324/LER-1981-009, Forwards LER 81-009/04T-0 | Forwards LER 81-009/04T-0 | | | 05000325/LER-1981-010, Forwards LER 81-010/03L-0 | Forwards LER 81-010/03L-0 | | | 05000325/LER-1981-010-03, /03L-0:on 810120,upon Auto Initiation After Reactor Scram,Rcic Turbine Failed to Accelerate to Idle Speed,Making RCIC Inoperable.Caused by Dirty Contacts in Turbine Steam Inlet Supply Valve 1-E51-F045.Contacts Cleaned | /03L-0:on 810120,upon Auto Initiation After Reactor Scram,Rcic Turbine Failed to Accelerate to Idle Speed,Making RCIC Inoperable.Caused by Dirty Contacts in Turbine Steam Inlet Supply Valve 1-E51-F045.Contacts Cleaned | | | 05000324/LER-1981-010, Forwards LER 81-010/03L-0 | Forwards LER 81-010/03L-0 | | | 05000324/LER-1981-010-03, /03L-0:on 810120,RHR Svc Water Subsys a Suction valve,2-SW-V101,would Not Open Fully.Caused by Two Hex Nuts on Input Shaft of Valve Motor Operator,Model H3BC-SMB-00, Freezing to Shaft.Nuts & Shaft Reworked & Lubricated | /03L-0:on 810120,RHR Svc Water Subsys a Suction valve,2-SW-V101,would Not Open Fully.Caused by Two Hex Nuts on Input Shaft of Valve Motor Operator,Model H3BC-SMB-00, Freezing to Shaft.Nuts & Shaft Reworked & Lubricated | | | 05000324/LER-1981-011-03, /03L-0:on 810120 & 0123,actual Pool Level Determined in Excess of Upper Tech Spec Limit.Caused by Improper Calibr Data & Calibr Procedure Inadequacy.Procedure Revision Underway & Indicators Correctly Calibr | /03L-0:on 810120 & 0123,actual Pool Level Determined in Excess of Upper Tech Spec Limit.Caused by Improper Calibr Data & Calibr Procedure Inadequacy.Procedure Revision Underway & Indicators Correctly Calibr | | | 05000324/LER-1981-011, Forewards LER 81-011/03L-0 | Forewards LER 81-011/03L-0 | | | 05000325/LER-1981-011-03, /03L-0:on 810121,during Routine Shutdown Operation,Seat Leakage Discovered on Reactor Recirculation Sample Inboard Isolation Valve 1-B32-F019.Cause Unknown. Valve Will Be Inspected & Repaired During Next Outage | /03L-0:on 810121,during Routine Shutdown Operation,Seat Leakage Discovered on Reactor Recirculation Sample Inboard Isolation Valve 1-B32-F019.Cause Unknown. Valve Will Be Inspected & Repaired During Next Outage | | | 05000325/LER-1981-011, Forwards LER 81-011/03L-0 | Forwards LER 81-011/03L-0 | | | 05000324/LER-1981-012-03, /03L-0:on 810320,wiring Deficiency Associated W/ Actuation Switch Discovered That Prevented Switch Operation. Caused by Improper Writing of Field Revision to Plant Mods Requiring Installation of Switches | /03L-0:on 810320,wiring Deficiency Associated W/ Actuation Switch Discovered That Prevented Switch Operation. Caused by Improper Writing of Field Revision to Plant Mods Requiring Installation of Switches | | | 05000325/LER-1981-012-03, /03L-0:on 810122,rod 26-35 Did Not Have Position Indication at Position 03 & Rod 34-35 Did Not Have Position Indication at Position 02.Caused by Defective Rod Position Indication Reed Switches.Corrective Maint Will Be Comple | /03L-0:on 810122,rod 26-35 Did Not Have Position Indication at Position 03 & Rod 34-35 Did Not Have Position Indication at Position 02.Caused by Defective Rod Position Indication Reed Switches.Corrective Maint Will Be Completed | | | 05000325/LER-1981-012, Forwards LER 81-012/03L-0 | Forwards LER 81-012/03L-0 | | | 05000324/LER-1981-012, Forwards LER 81-012/03L-0 | Forwards LER 81-012/03L-0 | | | 05000324/LER-1981-013-03, /03L-0:on 810119,HPCI Sys Component Test Tp 9.3.a Could Not Be Completed.Caused by Failed Motor on CST Suction Valve F004.Motor Sent to Svc Contractor to Be Repaired | /03L-0:on 810119,HPCI Sys Component Test Tp 9.3.a Could Not Be Completed.Caused by Failed Motor on CST Suction Valve F004.Motor Sent to Svc Contractor to Be Repaired | | | 05000324/LER-1981-013, Forwards LER 81-013/03L-0 | Forwards LER 81-013/03L-0 | | | 05000325/LER-1981-013, Forwards LER 81-013/03L-0 | Forwards LER 81-013/03L-0 | | | 05000325/LER-1981-013-03, /03L-0:on 810122,rod Worth Minimizer Sys Rod Blocks Were Received W/Proper Adherence to Control Rod Pattern Pull Sheet.Caused by Inadequate Procedures.Rods Pulled to Correct Position | /03L-0:on 810122,rod Worth Minimizer Sys Rod Blocks Were Received W/Proper Adherence to Control Rod Pattern Pull Sheet.Caused by Inadequate Procedures.Rods Pulled to Correct Position | |
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