LER-1981-060, /03L-0:on 810702,main Steam Line Isolation Valve Failed Causing Reactor Scram.On 810718,main Steam Line Inboard Isolation Valve Failed to Reopen.Caused by Separation of Steam Disk & Main Disk,Respectively |
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Nf1C FOR'yt 366 U. S. NUCLEAR REGULATORY COMMISSION (7-77 ).
LICENSEE EVENT REPORT CONTROL BLOCK: l l
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8 60 68 DOCKET NUVBER 66 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h l During normal operation with no evolutions in progress, a reactor scram occurred _due,_l o 2 lo l3 ) [ to a failed main steam line isolation valve (MSIV) on "C" main steam line. On 7/18/81l l O l 4 l l while performing routine valve testing of the MSIV's, the "D" main steam line inboard j lOl3l l isolation valve failed to reopen following closure.
Similar events have occurred l
LO 16 I I several times on both units, the last reported in LER 2-81-06.
There are eight MSIV'sl l 0 l 7 l l on each unit, four inboard and four outboard. Neither of these events affected the l
I o 18 l l health and safety of the public.
Technical Specifications 3.6.3, 6.9.1.9h I
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- 7 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h L1 I o i I MSIV F022C had closed due to separation of the valve stem disk from the stem.
MSIV I
i i l F022D would not reopen because the valve main disk had separated from the valve l
Both valves were repaired by utilizing 3 locking pins > 90 apart in the l
l1 l2l l piston.
l stem-stem disk connection and 2 locking pins 90 apart in the main disk-piston l
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[ assembly of each valve.
l 80 7
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% POWER oTHER STATUS IS O RY DISCOVERY DESCRIP TION NA l
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ISSUE D
DESCRIPTION
4 8108100290 810728 68 89
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PDR ADOCK 05000324
) 457-9521 o
S PDR,RER M. J. Pastva, Jr.
PHONE:
o LER ATTACHMENT - R0 #2-81-60 Facility: ESEP Unit No. 2 Event Date: 07/02/81 Investigations into the closures of MSIVs revealed that MSIV B21-F022C failed due to separation of the stem-disk from the stem and MSIV B21-F022D failed due to separation of the main disk from the piston. The separations resulted when threaded connections failed. Inspections of the valve components and a review of the operational history of other MSIV failures reported in previously submitted LER's indicate the separations resulted from an unknown combination of poor thread engagement, poor assembly methods, loose clearances, and relaxation of the pin and seating surfaces. Together, they lead to a loss of preload, unthreading, and/or straight separation.
However, it is suspected that the separation is aggravated by flow instabilities arising from the close connection of pipe run elbows to the inlet of the inboard MSIVs as shown by the predominance of inboard valve failures.
For either type separation, it was determined that the main disk will drop into the body seat as has been found in past MSIV failures. The closing of the main disk will severely reduce main steam line flow through the affected steam line, shifting some of the reduced flow to the other lines and creating a pressure increase in the reactor. This creates a noticeable mismatch between the flows in the affected steam line, the other steam lines, and the feedwater lines due to the side-by-side arrangement of these flow indicators on the. reactor control panel and the range of the indicators. The pressure spike creates a reactor power spike and a reactor level drop due to void collapse. Theso. are obvious to the operator and in cases where the reactor is at a substantial power level, as in the case of the F022C closure, the reactor scrams. When a separation occurs during the performance of PT's which cycle the MSIVs, which happened in the case of the F022D failure to reopen, the operators are monitoring the steam line flows during these tests to verify their satisfactory performance so an abnormal condition is promptly detected. The MSIVs on the affected steam line are then closed in accordance with the requirements of technical specifications. Since the main disk and stem disk will seat after either type of separation, there will be no flow through the affected valve. However, seat leakage may increase through it because of loss of some of the guidance for seating the main disk or stem-disk.
To da h., with the exception of one case, all MSIV failures have been the inboard valves, Indicating a possible link with flow instabilities from the inlet steam line elbow which exists only on the inboard valves. The one case of an outboard valve failure is thought to be due to improper pinning from an earlier disassembly. As a result, a failure is most likely to occur on an inboard MSIV and the probability of the failure of an outboard valve is very small. Since the operation or failure of one MSIV will not affect the other, the outboard MSIV can be counted upon for achieving full isolation in the event the inboard valve suffers a disk separation. The failed valve itself would nearly achieve the desired isolation although the leakage may be greater than before.
The valve vendor performed an evaluation to determine if the increased cicarance found on some of the valve components affected the ability of the MSIVs to J
e perform as required by the GE specifications and as assumed in the accident analyses.
The evaluation determined that code allowable stresses are not exceeded and the valves will function as required; therefore, they still meet the design requirements.
An evaluation by CP&L and the valve vendor of these two failures as well as the other MSIV failures experienced in the past reveals that an MSIV separation on a steam line can be identified and promptly isolated as required by technical specifications and that the MSIVs can be counted on to function properly.
In order to return F022C and F022D to service and ensure their reliable operation, the following actions were or will be taken:
1.
The stem and stem disk threaded connections were matched to ensure proper alignment.
2.
The number of stem to stem disk pins was increased from two to three and the pin engagement, length, and diameter increased.
3.
The number of disk to piston pins was increased from one to two and the pin engagement and length were increased.
4.
Verification and QC checks were added to ensure proper pin engagement.
5.
An evaluation of the failed pieces will be performed.
6.
Both valves were local leak rate tested.
As a result of this event, the remaining MSIVs on Unit No. 2 will be inspected and modified as required during the next refueling outage. The Unit No. 1 MSIVs are presently being inspected and current plans are to complete any required modifications during the current Unit No. 1 outage.
Although it is felt that the changes implemented into the design of the MSIVs will greatly improve their reliability, further investigation into improvements in MSIV design and operation to prevent any future events will continue.
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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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