LER-1979-019, /03L-0 on 781031:w/both Reactor Coolant Loops & Associated Steam Generators in Operation,One or More Main Steam Line Safety Valves Were Inoperable.Caused by Safety Valve Gagging.W/Chronological Log Describing Incidents |
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| 3681979019R03 - NRC Website |
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NRC FORM 366 U. S. NUCLE AR REGULATORY COMMISSION (7 77)
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2 i With both Reactor Coolant loops and associated Steam Generators in l
0 3 1 operation, one or more t'.ain Steam line code Safety Valves were inoperablp I driny Mode 1. 2. or 7 contrary to T.S.3.7.1.1.
Valve inoperability andj O
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O 1 %e Fafety Va17es were carred due to excessive leakage, with the l
)i ii j i excettion of the three gagged on 11/21/78.
No more tha.n three Safety i
, i Valves were ever inoperable on either Steam Generator and the Linear Power High Trip Setpoint was always 5 405, meeting requirenents of 3
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ATTACHMENT LER 50-368/79-019 MAIN STEAM SAFETY VALVE GAGGING CHRONOLOGICAL LOG DATE TIME
DESCRIPTION
10/31/78 2205 2PSV1052, 2PSV1056 gagged due to leakage, Mode 3 operation.
11/ 1/78 2015 2PSV1052 ungagged; no leakage, valve seated properly follow-ing system heatup.
11/ 2/78 2050 2PSVIO02 gagged due to leakage.
11/ 3/78 2230 2PSV1052 gagged due to leakage.
11/ 8/78 1733 2PSV1052 ungagged for test, remained ungagged, 11/11/78 2135 To Mode 4 or 5 operation, Mode 3 operation with safety valves inoperable for 263.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.
11/16/78 2PSV1002 replaced guide ring and worn rings.
2PSV1052 replaced worn rings.
2PSV1056 adjusted control and worn rings.
11/19/78 2010 To Mode 3 operation; 2PSV1056, 2PSV1002 inoperable.
11/21/78 0830 2PSV1052 gagged due to leakage.
11/21/78 2115 2PSV1055, 2PSV1052, 2PSV1056 remained gagged due to testing, no lockpins on worn ring.
11/28/78 New lockpins installed on all valves.
2PSV1002, 2PSV1055, 2PSV1056 ungagged.
2PSV1052 remained gagged due to gauled worn ring.
12/ 2/78 2353 To Mode 4 or 5 operation, Mode 3 operation with safety valves inoperable _ for 315.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />.
12/ 5/78 1455 To Mode 3, 2,1 or Reactor Critical 0260 F (Initial Criti-cality) operation; 2PSV1052 inoperable.
12/17/78 1000 2PSV1002 gagged due to leakage.
12/20/78 2057 To Mode 4 operation, Mode 3, 2 or 1 operation with safety valves inoperable for 366.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />.
12/22/78 0320 To Mode 3, 2 or 1 operation; 2PSV1002, 2P'V1052 inoperable.
12/22/78 0900 2PSV1056 gagged due to leakage.
12/23/78 1410 To Mode 4 or 5 operation, Mode 3, 2 or 1 operation with safety valves inoperable for 34.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
12/25/78 2147 To Mode 3, 2 or 1 operation; 2PSV1002, 2PSV1052, 2PSV1056 inoperable.
12/27/78 0700 2PSV1053 gagged due to leakage.
12/30/78 1250 2PSV1056 ungagged, no leakage.
2PSV1054 gagged due to leakage.
2/ 1/79 0106 To Mode 4 or 5 operation. Mode 3, 2 or 1 operation with safety
.ves inoperable for 890.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
Total hours to date, 1870.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
2PSV1002, 2PSV1052, 2PSV1053, 2PSV1054 repaired during present outage. All valves modified with new stem guide and realignment of seating surfaces to alleviate the problem of premature leakage.
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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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