LER-1979-020, /01T-0 on 781107:during Controlled Steam Lift, Discovered Warn Ring Lockpin Had Broken on Four Occasions. Caused by Lockpin Fragility.Lockpins Replaced W/Ones of Stronger Design |
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NRC FORM 366 U. S. NUCLE AR REGUL ATORY COMMISSION (7 77)
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- - 4 63 EVENT DATE 74 75 Mf'OH1 CATE 80 EVFNT DESCRIPTION AND PROBAOLE CONSEQUENCES h i During testing of the Main Steam line code safety valves, executing a i
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2PSV1002 lockpin broke on 11/7/78 and; l11/20/78.
2PSV1052 lockpin broke twice on 11/21/78. The relieving n
s Icapacity of the remaining safety valves exceeded that required for safe O g, l operation, as dictated by T.S. Table 3 7.1.
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Reportable Occurrence Report No. 50-368/79-020 2.
Report Date: 03/22/79 3.
Occurrence Date: 11/7/78 4
Facility:
Arkansas Nuclear One - Unit Two Russellville, Arkansas 72801 5.
Identification of Occurrence:
Performance of Main Steam Line Code Safety Valves that required remedial action and corrective measures to prevent operation in a manner less conservative than that assumed in the accident analysis in the SAR or T.S. bases.
Occurrence is reportable per T.S.6.9.1.8(i).
6.
Coiditions Prior to Occurrence:
Steady-State Power Reactor Power 0
MWth Hot Standby X
Net Output 0
MWe Cold Shutdown Percent of Full Power 0
Refueling Shutdown Load Changes During Routine Power Operation Routine Startup Operation Routine Shutdown Operation Other (specify) 7.
Description of Occurrence:
The Main Steam Line C cde Safety Valves were being treated by increasing the Main Steam pressure to the valve lift setpoint, thus verifying proper adjustment and blowback.
On four separate occasions, it..was discovered that the warn ring lockpin had broken.
On 11/7/78 and 11/20/78, the lockpin broke on 2PSV1002.
The lockpin in 2PSV1052 broke twice on 11/21/78.
Reportabic Occurrence Report No.
50-368/79-020 8.
Designation of Apparent Cause of Occurrence:
Design X
Procedure bbnufacture Unusual Service Condition Including Environmental Installation /
Const ruction Component Failure (See Failure Data)
Operator Other (specify)
Failure was determined to be a result of the lockpin's fragility.
9.
Analysis of Occurrence:
The lockpin function is to maintain the warn ring adjustment. With the lockpin broken, the relief setpoint for each valve could not be
- 1s sured.
The failure occurred during Mode 3 operation, prior to initial criticality. The relieving capacity of the remaining safety valves always exceeded that required for safe operation, as dictated by T.S. Table 3.7.-l.
w Reportable Occurrence Report So. 50-368/79-020 10.
Corrective Action
Upon discovery of the failure, the lechpin was replaced with one of similar design until 11/21/78. At the end of testing, 2?SV1052, 2?SV1055 and 2?SV1056 vere gagged because lockpins had been used for replacements in other valves.
On 11/28/78, the Icekpins were replaced in all of the Main Steas Line Code Safety Valves with one of a stronger and cere reliable design (see Sketch 1).
11.
Failure Data:
Other occurrences involving the Main Stea= Safety Valves are 50-368/79-019 and 50-368/78-010; however, they are not similar.
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| 05000368/LER-1979-001-03, /03L-0 on 790102:refueling Water Tank Level Indicator Failed High.Caused by Frozen Transmitter Sensing Line.Line Was Thawed & Returned to Operable Status within 20-h | /03L-0 on 790102:refueling Water Tank Level Indicator Failed High.Caused by Frozen Transmitter Sensing Line.Line Was Thawed & Returned to Operable Status within 20-h | | | 05000313/LER-1979-001, Forwards LER 79-001/03L-0 | Forwards LER 79-001/03L-0 | | | 05000313/LER-1979-001-03, /03L-0 on 790112:during Mode 5 Operation,Purge Supply Flow from VSF-30B Would Not Meet Surveillance Requirements.Caused by Supply Filter VFA-20B Collapsing from Water Restricting Air Flow.Filter Changed | /03L-0 on 790112:during Mode 5 Operation,Purge Supply Flow from VSF-30B Would Not Meet Surveillance Requirements.Caused by Supply Filter VFA-20B Collapsing from Water Restricting Air Flow.Filter Changed | | | 05000313/LER-1979-002-01, /01T-0 on 790205:during Startup,Nuclear Instrumentation Was Not Calibr as Required by Tech Spec 4.1, Table 4.1-1.Caused by Personnel Error.Occurrence Discussed W/Shift | /01T-0 on 790205:during Startup,Nuclear Instrumentation Was Not Calibr as Required by Tech Spec 4.1, Table 4.1-1.Caused by Personnel Error.Occurrence Discussed W/Shift | | | 05000313/LER-1979-002, Forwards LER 79-002/01T-0 | Forwards LER 79-002/01T-0 | | | 05000368/LER-1979-002-03, /03L-0 on 790103:refueling Water Level Transmitter Refroze.Caused by Frozen Transmitter Sensing Line.Addl Insulation & Heat Lamps Added to Sensing Lines & Transmitter Cabinets | /03L-0 on 790103:refueling Water Level Transmitter Refroze.Caused by Frozen Transmitter Sensing Line.Addl Insulation & Heat Lamps Added to Sensing Lines & Transmitter Cabinets | | | 05000313/LER-1979-003-01, /01T-0 on 790425:leak Discovered in Heat Affected Zone of 1 Inch Drainline Socket Weld in B Decay Heat Discharge Cross Connect to a Loop.Caused by Vibration Fatigue.Outer Drainline Isolation Valves Replaced | /01T-0 on 790425:leak Discovered in Heat Affected Zone of 1 Inch Drainline Socket Weld in B Decay Heat Discharge Cross Connect to a Loop.Caused by Vibration Fatigue.Outer Drainline Isolation Valves Replaced | | | 05000368/LER-1979-004-03, /03L-0 on 790107:during Power Escalation Testing, Both Control Element Assembly Clusters Declared Inoperable. Caused by Weak Reed Switch Position Transmitter Power Supply | /03L-0 on 790107:during Power Escalation Testing, Both Control Element Assembly Clusters Declared Inoperable. Caused by Weak Reed Switch Position Transmitter Power Supply | | | 05000313/LER-1979-004-03, /03L-0 on 790424:reactor Bldg Spray Pump Unresponsive to Engineered Safeguards Signal.Caused by Incorrect Agastat Time Relay Setting.Relay Adjusted | /03L-0 on 790424:reactor Bldg Spray Pump Unresponsive to Engineered Safeguards Signal.Caused by Incorrect Agastat Time Relay Setting.Relay Adjusted | | | 05000313/LER-1979-004, Forwards LER 79-004/03L-0 | Forwards LER 79-004/03L-0 | | | 05000368/LER-1979-005-03, /03L-0 on 790109:during Power Escalation Testing, Bistable Primary Power System 6 C Failed,Rendering C Pressurizer Low Pressure Trip Inoperable | /03L-0 on 790109:during Power Escalation Testing, Bistable Primary Power System 6 C Failed,Rendering C Pressurizer Low Pressure Trip Inoperable | | | 05000313/LER-1979-005-03, /03L-0 on 790524:during Leak Rate Testing, Penetration V-1 Leaked in Excess of 50,000 Cubic Cm/Minute. Caused by Buildup of Boric Acid Crystals on Valve Seating Surfaces.Repairs Made & Penetrations Retested | /03L-0 on 790524:during Leak Rate Testing, Penetration V-1 Leaked in Excess of 50,000 Cubic Cm/Minute. Caused by Buildup of Boric Acid Crystals on Valve Seating Surfaces.Repairs Made & Penetrations Retested | | | 05000313/LER-1979-005, Forwards LER 79-005/03L-0 | Forwards LER 79-005/03L-0 | | | 05000368/LER-1979-006-03, /03L-0 on 790109:during Power Escalation Testing, B Core Protection Computer Declared Inoperable When Low Pressurizer Pressure Trips Received.Investigation Showed Ground Fault Relays Fall Out on Low Bus Voltage | /03L-0 on 790109:during Power Escalation Testing, B Core Protection Computer Declared Inoperable When Low Pressurizer Pressure Trips Received.Investigation Showed Ground Fault Relays Fall Out on Low Bus Voltage | | | 05000368/LER-1979-006, Forwards Revised LER 79-006/03X-1 | Forwards Revised LER 79-006/03X-1 | | | 05000313/LER-1979-006-01, /01T-0 on 790607:vendor Notified Util of Possibility That Turbocharger Thrust Bearing Could Be Damaged Under Certain Repeat Start Operating Modes. Procedures Modifided & Improved Lube Oil Sys Being Designed | /01T-0 on 790607:vendor Notified Util of Possibility That Turbocharger Thrust Bearing Could Be Damaged Under Certain Repeat Start Operating Modes. Procedures Modifided & Improved Lube Oil Sys Being Designed | | | 05000313/LER-1979-006, Forwards LER 79-006/01T-0 | Forwards LER 79-006/01T-0 | | | 05000368/LER-1979-007, Forwards LER 79-007/03L-0 & LER 79-009/03L-0 | Forwards LER 79-007/03L-0 & LER 79-009/03L-0 | | | 05000368/LER-1979-007-03, /03L-0 on 790113:during Power Escalation Test, Control Element Assembly Position as Received by Core Protection Computer B Was Incorrect.Caused by Bad Multiplexer Card,Which Was Replaced | /03L-0 on 790113:during Power Escalation Test, Control Element Assembly Position as Received by Core Protection Computer B Was Incorrect.Caused by Bad Multiplexer Card,Which Was Replaced | | | 05000313/LER-1979-007, Forwards LER 79-007/03L-0 | Forwards LER 79-007/03L-0 | | | 05000313/LER-1979-007-03, /03L-0 on 790616:during Heatup,Emergency Feedwater Pump Automatically Started W/Inadvertent Actuation.Caused by Valve Lineup Error.Outboard Pump Bearing Found to Be Hot Due to Faulty Installation.Maint Procedure Revised | /03L-0 on 790616:during Heatup,Emergency Feedwater Pump Automatically Started W/Inadvertent Actuation.Caused by Valve Lineup Error.Outboard Pump Bearing Found to Be Hot Due to Faulty Installation.Maint Procedure Revised | | | 05000313/LER-1979-008, Forwards LER 79-008/03L-0 | Forwards LER 79-008/03L-0 | | | 05000368/LER-1979-008-03, /03L-0 on 790114:during Power Ascension Testing, Refueling Water Tank Level transmitter,2LT-5639-3,sensing Line Froze Due to Temporary Heat Lamp Burnout | /03L-0 on 790114:during Power Ascension Testing, Refueling Water Tank Level transmitter,2LT-5639-3,sensing Line Froze Due to Temporary Heat Lamp Burnout | | | 05000313/LER-1979-008-03, /03L-0 on 790621:emergency Feed Actuation Received When once-through Steam Generator a Startup Level Transmitter Selection Was Shifted.Caused by Overspeed Trips Due to Water in Steam Supply Line | /03L-0 on 790621:emergency Feed Actuation Received When once-through Steam Generator a Startup Level Transmitter Selection Was Shifted.Caused by Overspeed Trips Due to Water in Steam Supply Line | | | 05000368/LER-1979-009-03, /03L-0 on 790121:during Power Escalation Testing, Reactor Protection Sys Channel C Trip Path Solid State Relay Failed,Opening Reactor Trip Path Circuit Breakers 3 & 7.Relay Was Replaced;Within 4-h Circuit Breakers Closed | /03L-0 on 790121:during Power Escalation Testing, Reactor Protection Sys Channel C Trip Path Solid State Relay Failed,Opening Reactor Trip Path Circuit Breakers 3 & 7.Relay Was Replaced;Within 4-h Circuit Breakers Closed | | | 05000313/LER-1979-009, Forwards LER 79-009/03L-0 & 79-010/01T-0 | Forwards LER 79-009/03L-0 & 79-010/01T-0 | | | 05000313/LER-1979-009-03, /03L-0 on 790628:during Power Operation Reactor Bldg Hydrogen Purge Fan VSF-30A Tripped After 90 Minutes of 10-h Run.Caused by Overcurrent.Fan Restarted Using Less Sealing Water | /03L-0 on 790628:during Power Operation Reactor Bldg Hydrogen Purge Fan VSF-30A Tripped After 90 Minutes of 10-h Run.Caused by Overcurrent.Fan Restarted Using Less Sealing Water | | | 05000313/LER-1979-010, Forwards Updated LER 79-010/01X-1 | Forwards Updated LER 79-010/01X-1 | | | 05000313/LER-1979-010-01, /01T-0 on 790714:design of Main Steamline Restraints Did Not Consider Steam Hammer Transient Forces. Review Performed.Overstressed Area Will Be Modified | /01T-0 on 790714:design of Main Steamline Restraints Did Not Consider Steam Hammer Transient Forces. Review Performed.Overstressed Area Will Be Modified | | | 05000368/LER-1979-010-03, /03L-0 on 790124:pump Discharge valve,2CV-5667-2, Stroked Fully Open But Immediately Reclosed.Caused by sodium-hydroxide Tank Low Level Alarm & Indication Circuit Being Out of Alignment | /03L-0 on 790124:pump Discharge valve,2CV-5667-2, Stroked Fully Open But Immediately Reclosed.Caused by sodium-hydroxide Tank Low Level Alarm & Indication Circuit Being Out of Alignment | | | 05000368/LER-1979-011-03, /03L-0 on 790125:during Power Escalation,Channel B Core Protection Computer Failed,Resulting in Departure from Nucleate Boiling Ratio & Linear Power Density Trips. Caused by Movement of Temporary Cables Connected to B | /03L-0 on 790125:during Power Escalation,Channel B Core Protection Computer Failed,Resulting in Departure from Nucleate Boiling Ratio & Linear Power Density Trips. Caused by Movement of Temporary Cables Connected to B | | | 05000368/LER-1979-011, Forwards LER 79-011/03L-0 | Forwards LER 79-011/03L-0 | | | 05000313/LER-1979-011, Forwards LER 79-011/01T-O | Forwards LER 79-011/01T-O | | | 05000313/LER-1979-011-01, /01T-0 on 790809:during NRC Performance Appraisal Team Interview,Discovered That Pressurizer Safety Relief Valve PSV-1002 Was Not Properly Tested in Mar 1978.Valve Retested 790812 W/No Adjustments Required | /01T-0 on 790809:during NRC Performance Appraisal Team Interview,Discovered That Pressurizer Safety Relief Valve PSV-1002 Was Not Properly Tested in Mar 1978.Valve Retested 790812 W/No Adjustments Required | | | 05000313/LER-1979-012, Forwards LER 79-012/03L-1 | Forwards LER 79-012/03L-1 | | | 05000313/LER-1979-012-03, Leak Rate Testing of Reactor Bldg Purge Valves at Penetration V-1 Indicated Leak Rate in Excess of Tech Spec Limits.Caused by Maladjusted Valve Seat Shims.Leak Rate Test Performed | Leak Rate Testing of Reactor Bldg Purge Valves at Penetration V-1 Indicated Leak Rate in Excess of Tech Spec Limits.Caused by Maladjusted Valve Seat Shims.Leak Rate Test Performed | | | 05000368/LER-1979-012-03, /03L-0 on 790127:core Protection Computer Channel B Failed,Resulting in Trips.Caused by Analog High Level Amplifier Card Improperly Seating in Connector.Card Reseated & Functional Test Conducted | /03L-0 on 790127:core Protection Computer Channel B Failed,Resulting in Trips.Caused by Analog High Level Amplifier Card Improperly Seating in Connector.Card Reseated & Functional Test Conducted | | | 05000313/LER-1979-013-03, /03L-0:on 790808,decay Heat Boron Concentration Was Not Monitored During Prescribed Interval & Inservice Decay Heat Loop Was Switched W/O Switching Sample Lineup. Caused by Communications Breakdown Between Depts | /03L-0:on 790808,decay Heat Boron Concentration Was Not Monitored During Prescribed Interval & Inservice Decay Heat Loop Was Switched W/O Switching Sample Lineup. Caused by Communications Breakdown Between Depts | | | 05000313/LER-1979-013, Forwards LER 79-013/03L-0 | Forwards LER 79-013/03L-0 | | | 05000368/LER-1979-013-03, /03L-0 on 790127:control Element Assembly Cluster (Ceac) Deviation Alarms Received.Caused by Disturbance of Ceac Cable Connections | /03L-0 on 790127:control Element Assembly Cluster (Ceac) Deviation Alarms Received.Caused by Disturbance of Ceac Cable Connections | | | 05000313/LER-1979-014, Forwards LER 79-014/99X-0 | Forwards LER 79-014/99X-0 | | | 05000313/LER-1979-014-99, /99X-0:on 790813,w/75% Reactor Power,Switchyard Relay 21Z1 Failed,Causing Turbine Trip.Caused by Lug Failure on Terminal Leads to Turbine Lockout Relay 286-T.Failed Lug Replaced,Terminals Tightened & Turbine Interlocks Teste | /99X-0:on 790813,w/75% Reactor Power,Switchyard Relay 21Z1 Failed,Causing Turbine Trip.Caused by Lug Failure on Terminal Leads to Turbine Lockout Relay 286-T.Failed Lug Replaced,Terminals Tightened & Turbine Interlocks Tested | | | 05000368/LER-1979-014-03, /03-0 on 790127:plant Protection Sys C Containment Bldg Pressure Transmitter 2PT-5603-3N Failed, Causing Hi & Hi-Hi Containment Pressure Trips.Caused by Loose Output Connection,Which Was Subsequently Reconnected | /03-0 on 790127:plant Protection Sys C Containment Bldg Pressure Transmitter 2PT-5603-3N Failed, Causing Hi & Hi-Hi Containment Pressure Trips.Caused by Loose Output Connection,Which Was Subsequently Reconnected | | | 05000368/LER-1979-015-03, /03L-0 on 790128:failure of Core Protection Computer D & C,Resulting in Respective Channel Trips;One Caused by Tripped Power Supply & Other Appears non-repetitive.Both Channels Were Successfully Restarted | /03L-0 on 790128:failure of Core Protection Computer D & C,Resulting in Respective Channel Trips;One Caused by Tripped Power Supply & Other Appears non-repetitive.Both Channels Were Successfully Restarted | | | 05000313/LER-1979-015-99, /99X-0:on 790817,as Result of Analysis of Seismic Category I Pipe supports,37 Restraints Were Identified to Have Safety Factor of Less than Two.Supports Modified | /99X-0:on 790817,as Result of Analysis of Seismic Category I Pipe supports,37 Restraints Were Identified to Have Safety Factor of Less than Two.Supports Modified | | | 05000368/LER-1979-015, Forwards LER 79-015/03L-0 | Forwards LER 79-015/03L-0 | | | 05000368/LER-1979-016-03, /03L-0 on 790130:during Power Escalation Testing, Mode 1 Operation,Safety Injection Tank D Pressure Dropped Below Tech Spec Limit.Caused by Excessive Leakage Due to Oversized Valve Body.Seal Ring Replaced W/Oversized Ring | /03L-0 on 790130:during Power Escalation Testing, Mode 1 Operation,Safety Injection Tank D Pressure Dropped Below Tech Spec Limit.Caused by Excessive Leakage Due to Oversized Valve Body.Seal Ring Replaced W/Oversized Ring | | | 05000313/LER-1979-016, Forwards Updated LER 79-016/03X-1 | Forwards Updated LER 79-016/03X-1 | | | 05000313/LER-1979-016-03, /03L-0:on 790827,diesel Generator 2 Tripped on Low Oil Pressure,Rendering Generator Inoperable.Caused by Leak Allowing Water to Enter Oil Sys,Causing High Crankcase Pressure.Oil Cooler Replaced | /03L-0:on 790827,diesel Generator 2 Tripped on Low Oil Pressure,Rendering Generator Inoperable.Caused by Leak Allowing Water to Enter Oil Sys,Causing High Crankcase Pressure.Oil Cooler Replaced | | | 05000368/LER-1979-016, Forwards LER 79-016/03L-0 | Forwards LER 79-016/03L-0 | |
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