LER-1979-141, /01X-1:on 791106,sys Operation Review Revealed Design Deficiencies in Engineered Safety Feature Equipment. Deficiencies Could Result in Less Conservative Operation than Assumed in Fsar.Cause Unknown |
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U. S. NUCLEAR REGULATORY C N
NRC FORM 366 (7 77)
LICENSEE EVENT REPORT CONTROL BLOCK: l l
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EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h o
2 l During a review of system operation, it was discovered that do< f on doffeloncfoc e n.1 A I [O l3 ) [ result in ESF equipment operating less conservatively than assuned in the F9AR.
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systems returning to non-safety mode following reset nf F9F nnA tino l
lolsl l delay start systems not going to completion following reset of ESF.
SV. HV. RS and W l lo is l Isystems are affected. The safety of the public was not affected.
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i o lThe exact cause for the nonconservative operation of these ESF Systems is unknown [this time, however, a design deficiency by the architect eneineer is cusnected.
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l problem is being evaluated to determine the corrective actions required.
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% pot.E R OTHER STATUS IS O RY DISCOVERY DESCRIPTION l1 l5 l [H Jg l 0 l 0 l 0 l@l NA l
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7 8 9 10 NAME OF PREPARER V D.
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Updated Report Virginia Electric and Power Company North Anna Power Station #1
Attachment:
Page 1 of 2 Docket No. 50-338 Report No. LER 79-141/01X-1
Description of Event
On November 6,1979, during a review of system operation following a review of system performance during a recent unit trip and subsequent safety injection, it was discovered that the control room air-operated dampers which isolate the control room from outside air on an SI signal return to their non-safety mode when the SI signal is reset.
This is contrary to FSAR comment 7.4 which states that two actions are required to return ESF equipment to a non-safety mode.
Specifically, it is accom-plished by resetting the appropriate actuation signal and subsequently operating the control switch for the device.
A review was immediately initiated to determine if any other deficiencies existed.
The following is a list of potential design deficiencies that were discovered.
The following systems return to their non-safety mode following reset of an ESF signal:
Control Room Habitability System (HV)
Supply Air Damper A0D-HV-160-1 Exhaust Air Damper A0D-HV-161-1 Dampers reopen af ter the SI signal is reset.
Safeguards Area Ventilation System (HV)
Exhaus t Air Dampers A0D-HV-128-1,2,-3,-4 Filter Bank Dampers A0D-HV-107A-1,A-2,A-3,A-4,B-1,B-2,B-3,B-4 Dampers re-position to bypass filters af ter Containment Depressurization Actuation (CDA) signal is reset.
Containment Ventilation System (HV)
Containment Recirculation Cooler Fan, 1-HV-F-1 A,-B Control Rod Drive Cooling Fan, 1-HV-F-37 A, B, C, D, E, F Fans restart af ter CDA signal is reset.
Service Water System (SW)
Supply to Air Cooling Coils, MOV-SW-110A,B,-114A,B Supply to Air Cooling Coils, TV-SW-101 A,B Valves reopen to provide service water to the containment air coolers af ter CDA signal is reset.
This occurs only when the control switch for cooling had previously been placed in the service water position.
Normal cooling of the recirculation air coolers is with chilled water.
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Updated Report Attachment: Page 2 of 2 Secondary Vents System (SV)
Air Ejector Air Discharge Valve TV-SV102-1 Air Ejector Air Discharge Valve TV-SV103 With a Hi-Hi radiation signal present, valves reopen to divert air to the containment after Phase A Containment Isolation signal is reset.
The following systems do not go to completion if the CDA signal is reset prior to expiration of the starting time delay relay:
Recirculation Spray System (RS)
Outside Recirculation Spray Pump, 1-RS-P-2 A, B Inside Recirculation Spray Pump, 1-RS-P-1A,B Service Water System (SW)
RS Heat Exchanger Radiation Monitoring Sample Pumps, 1-SW-P-5,6,7,8 Probable Consequences of Occurrence The reset capability of ESF signals is required to permit action in the post accident period. With the present design, the protective actions of the af fected systems could be prevented or cancelled once the associated actuation signal is reset which is in noncompliance with IEEE Standards.
The health and safety of the general public were not af fected by this event.
Unit 2 systems have the same reset design and are similarly af fected.
Cause of Occurrence The cause of these discrepancies is not known at this time.
- However, it appears that they may have resulted from a possible design deficiency by Stone and Webster.
Immediate Corrective Action
The problem is being evaluated by Engineering Services to determine what corrective actions are required.
Scheduled Corrective Action The reset circuitry for tha affected ESF equipment will be modified or redesigned, as required.
Actions Taken to Prevent Recurr?nce No further actions are required.
1541 228
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| 05000338/LER-1979-001-01, /01T-0 on 790115:non-conservatism Identified in Calculations Performed in Monitoring Axial Power Distribution Fj(Z).Caused by Omission of Sys & Procedures Used to Monitor Fj(Z) | /01T-0 on 790115:non-conservatism Identified in Calculations Performed in Monitoring Axial Power Distribution Fj(Z).Caused by Omission of Sys & Procedures Used to Monitor Fj(Z) | | | 05000338/LER-1979-001, Forwards LER 79-001/01T-0 | Forwards LER 79-001/01T-0 | | | 05000338/LER-1979-002, Forwards LER 79-002/03L-0 & 79-003/03L-0 | Forwards LER 79-002/03L-0 & 79-003/03L-0 | | | 05000338/LER-1979-002-03, /03L-0 on 790101:during Normal Operation,Pump 1-RM-P-159A Tripped on Overload.Containment Particulate Sample Flow Was Lost,Rendering Inoperable 1 Reactor Coolant Leak Detection Sys,Due to Deficient Federal 1206LLT Bearing | /03L-0 on 790101:during Normal Operation,Pump 1-RM-P-159A Tripped on Overload.Containment Particulate Sample Flow Was Lost,Rendering Inoperable 1 Reactor Coolant Leak Detection Sys,Due to Deficient Federal 1206LLT Bearing | | | 05000338/LER-1979-003-03, /03L-0 on 790102:during Periodic Test,Noted That Containment Isolation Valve TV-SV-102-1 Would Not Shut Fully.Cause Undetermined | /03L-0 on 790102:during Periodic Test,Noted That Containment Isolation Valve TV-SV-102-1 Would Not Shut Fully.Cause Undetermined | | | 05000338/LER-1979-004-03, /03L-0 on 790108:during 1-PT-36-1(A) Found That Steam Generator 3 Hi Hi Level Test Panel Was Faulty, Preventing Test of This Channel.Caused by Faulty Universal Logic Card on Test Panel | /03L-0 on 790108:during 1-PT-36-1(A) Found That Steam Generator 3 Hi Hi Level Test Panel Was Faulty, Preventing Test of This Channel.Caused by Faulty Universal Logic Card on Test Panel | | | 05000338/LER-1979-005-01, /01T-0 on 790129:mufflers for Emergency Diesel Generators Not Seismically Supported Nor Missile Protected as Required by Fsar.Caused by Const Error | /01T-0 on 790129:mufflers for Emergency Diesel Generators Not Seismically Supported Nor Missile Protected as Required by Fsar.Caused by Const Error | | | 05000338/LER-1979-005, Forwards LER 79-005/01T-0 & 79-008/01T-0 | Forwards LER 79-005/01T-0 & 79-008/01T-0 | | | 05000338/LER-1979-006-03, /03L-0 on 790111:damaged Wiper Seal Found on Hydraulic Suppressor 1-FW-HSS-233.Caused by Poppet Valves Which Control Lock Up Rate Being Improperly Set.Suppressor Replaced W/Operable Spare Suppressor.No Danger to Public | /03L-0 on 790111:damaged Wiper Seal Found on Hydraulic Suppressor 1-FW-HSS-233.Caused by Poppet Valves Which Control Lock Up Rate Being Improperly Set.Suppressor Replaced W/Operable Spare Suppressor.No Danger to Public | | | 05000338/LER-1979-006, Forwards LER 79-006/03L-0 | Forwards LER 79-006/03L-0 | | | 05000338/LER-1979-007-03, /03L-0 on 781116:during Normal Operation,Fire Door S54-5 Between Unit 1 Emergency Switchgear Room & Cable Vault Was Sprung & Would Not Make a Tight Seal,Evidently Due to Attempt to Free It While Stuck | /03L-0 on 781116:during Normal Operation,Fire Door S54-5 Between Unit 1 Emergency Switchgear Room & Cable Vault Was Sprung & Would Not Make a Tight Seal,Evidently Due to Attempt to Free It While Stuck | | | 05000338/LER-1979-008-01, /01T-0 on 790129:design Flow of 37 Gpm to Charging Pump Coolers Could Not Be Met.Caused by 2 Inch Carbon Steel Piping & Charging Pump Skid Piping Being Too Large to Allow Adequate Flow | /01T-0 on 790129:design Flow of 37 Gpm to Charging Pump Coolers Could Not Be Met.Caused by 2 Inch Carbon Steel Piping & Charging Pump Skid Piping Being Too Large to Allow Adequate Flow | | | 05000338/LER-1979-009, Forwards LER 79-009/03L-0 | Forwards LER 79-009/03L-0 | | | 05000338/LER-1979-009-03, /03L-0 on 790212:during Normal Operation,Snubber Support for C Steam Generator Atmosphere Discharge Line Found Damaged.Caused by Use of Support as Anchor for Chain Fall.Support Replaced | /03L-0 on 790212:during Normal Operation,Snubber Support for C Steam Generator Atmosphere Discharge Line Found Damaged.Caused by Use of Support as Anchor for Chain Fall.Support Replaced | | | 05000338/LER-1979-010-03, /03L-0 on 790127: During Calibr of Containment Particulate Monitor RMS159 in Mode 1, Instrument Read Low for Known Radiation Level. Caused by Detector High Voltage Setting Being Set Too Low | /03L-0 on 790127: During Calibr of Containment Particulate Monitor RMS159 in Mode 1, Instrument Read Low for Known Radiation Level. Caused by Detector High Voltage Setting Being Set Too Low | | | 05000338/LER-1979-011, Forwards LER 79-011/03L-0 | Forwards LER 79-011/03L-0 | | | 05000338/LER-1979-011-03, /03L-0 on 790126:fire Door SS54-9 Was Nonfunctional.Caused by Removal of Latch from Door by Person or Persons Unknown | /03L-0 on 790126:fire Door SS54-9 Was Nonfunctional.Caused by Removal of Latch from Door by Person or Persons Unknown | | | 05000338/LER-1979-012-03, /03L-0 on 790127: Unidentified Primary Coolant Leakage Greater than 5 Gpm Noted. Caused by Blown Packing on Residual Heat Removal Isolation Valve MOV-1700 & Packing Leak on Pressurizer Spray Valve PCV-1455A | /03L-0 on 790127: Unidentified Primary Coolant Leakage Greater than 5 Gpm Noted. Caused by Blown Packing on Residual Heat Removal Isolation Valve MOV-1700 & Packing Leak on Pressurizer Spray Valve PCV-1455A | | | 05000338/LER-1979-013-03, /03L-0 on 790214:during Normal Operation,Fire Door S71-7 Between Auxiliary Bldg & Health Physics Found non- Functional.Caused by Bent Phaser on Left Door.Phaser Taped Out of Way & New Phaser Installed | /03L-0 on 790214:during Normal Operation,Fire Door S71-7 Between Auxiliary Bldg & Health Physics Found non- Functional.Caused by Bent Phaser on Left Door.Phaser Taped Out of Way & New Phaser Installed | | | 05000338/LER-1979-014-03, /03L-0 on 790202:pressurizer Level Indicator Indicated High Over Allowable Range.Caused by Voltage Drift in Associated Level Transmitter.Appropriate Channel Placed in Trip Condition & Transmitter Recalibr | /03L-0 on 790202:pressurizer Level Indicator Indicated High Over Allowable Range.Caused by Voltage Drift in Associated Level Transmitter.Appropriate Channel Placed in Trip Condition & Transmitter Recalibr | | | 05000338/LER-1979-014, Forwards LER 79-014/03L-0 | Forwards LER 79-014/03L-0 | | | 05000338/LER-1979-015-03, /03L-0 on 790204:rod F08 Indicators in Disagreement.Caused by Voltage Drift in Signal Conditioning Card.Card Recalibrated & Functional Checks Performed Satisfactorily | /03L-0 on 790204:rod F08 Indicators in Disagreement.Caused by Voltage Drift in Signal Conditioning Card.Card Recalibrated & Functional Checks Performed Satisfactorily | | | 05000338/LER-1979-015, Forwards LER 79-015/03L-0 | Forwards LER 79-015/03L-0 | | | 05000338/LER-1979-016, Forwards LER 79-016/03L-0 | Forwards LER 79-016/03L-0 | | | 05000338/LER-1979-016-03, /03L-0 on 790213:main Steam trip,TV-MS-111A,valve Opened to Only 75% Capacity.Caused by Improperly Positioned Needle Valve Which Supplied Air to Valve Actuator.Valve Repositioned & Operation Restored | /03L-0 on 790213:main Steam trip,TV-MS-111A,valve Opened to Only 75% Capacity.Caused by Improperly Positioned Needle Valve Which Supplied Air to Valve Actuator.Valve Repositioned & Operation Restored | | | 05000338/LER-1979-017, Forwards LER 79-017/01T-0 | Forwards LER 79-017/01T-0 | | | 05000338/LER-1979-017-01, /01T-0 on 790212:during Axial Power Distribution Monitoring Sys Failure on 790206,FQ Survey Computer Program Could Not Monitor Axial Power Distribution.Caused by Incorrect Power Inputs from Process Computer | /01T-0 on 790212:during Axial Power Distribution Monitoring Sys Failure on 790206,FQ Survey Computer Program Could Not Monitor Axial Power Distribution.Caused by Incorrect Power Inputs from Process Computer | | | 05000338/LER-1979-018-03, /03L-0 on 790214:during Mode 1 Operation at 98% Power,Main Steam Trip Valve 1-TV-MS-111B Leaked Excessively & Was Isolated for Repair.Caused by Deteriorated Internal Gasket.Valve Isolated & Gasket Replaced | /03L-0 on 790214:during Mode 1 Operation at 98% Power,Main Steam Trip Valve 1-TV-MS-111B Leaked Excessively & Was Isolated for Repair.Caused by Deteriorated Internal Gasket.Valve Isolated & Gasket Replaced | | | 05000338/LER-1979-019-03, /03L-0 on 790216:during Surveillance,Emergency Diesel Generator 1H Did Not Reach 900 Revolutions Per Minute in Required 10-s.Probable Cause Was Low Ambient Air Temp. Conditions of First Start Were Not Reproducible | /03L-0 on 790216:during Surveillance,Emergency Diesel Generator 1H Did Not Reach 900 Revolutions Per Minute in Required 10-s.Probable Cause Was Low Ambient Air Temp. Conditions of First Start Were Not Reproducible | | | 05000338/LER-1979-020-03, /03L-0 on 790131:fire Door S54-9 Was Found to Be non-functional.Caused by Recently Installed Electric Door Strike Slipping Out of Adjustment | /03L-0 on 790131:fire Door S54-9 Was Found to Be non-functional.Caused by Recently Installed Electric Door Strike Slipping Out of Adjustment | | | 05000338/LER-1979-020, Forwards LER 79-020/03L-0 | Forwards LER 79-020/03L-0 | | | 05000338/LER-1979-021-99, /99T-0 on 790212:meterological Air Temp Change in Temp Indication Was Observed to Be off-scale Low.Caused by Faulty Resistance Temp Detector.Temp Element Replaced | /99T-0 on 790212:meterological Air Temp Change in Temp Indication Was Observed to Be off-scale Low.Caused by Faulty Resistance Temp Detector.Temp Element Replaced | | | 05000338/LER-1979-021, Forwards LER 79-021/99T-0 | Forwards LER 79-021/99T-0 | | | 05000338/LER-1979-022-03, /03L-0 on 790227:power Supply to Post DBA H Recombiner Deenergized Rendering Recombiner Inoperable for 4-h.Caused by Deenergizing of Motor Control Center to Perform Voltage Measurements | /03L-0 on 790227:power Supply to Post DBA H Recombiner Deenergized Rendering Recombiner Inoperable for 4-h.Caused by Deenergizing of Motor Control Center to Perform Voltage Measurements | | | 05000338/LER-1979-023, Forwards LER 79-023/03L-0,79-025/03L-0 & 79-031/03L-0 | Forwards LER 79-023/03L-0,79-025/03L-0 & 79-031/03L-0 | | | 05000338/LER-1979-023-03, /03L-0 on 790303:disagreement Noted Between Group & Individual Indication for Rod D-10.Caused by Voltage Drift in Conditioning Card.Calibr & Functional Checks Were Performed | /03L-0 on 790303:disagreement Noted Between Group & Individual Indication for Rod D-10.Caused by Voltage Drift in Conditioning Card.Calibr & Functional Checks Were Performed | | | 05000338/LER-1979-024, Forwards LER 79-024/43X-1 | Forwards LER 79-024/43X-1 | | | 05000338/LER-1979-024-43, /43X-1:on 790228,radwaste Release Occurred Unexpectedly During Pumping of Unit 2 Containment Sump Via Temporary Pump to Storm Drain Sys.Caused by Pressure Relief Valve Leaks in Units 1 & 2 Purge Headers | /43X-1:on 790228,radwaste Release Occurred Unexpectedly During Pumping of Unit 2 Containment Sump Via Temporary Pump to Storm Drain Sys.Caused by Pressure Relief Valve Leaks in Units 1 & 2 Purge Headers | | | 05000338/LER-1979-025-03, /03L-0 on 790228:power Range Channel N42 Placed in Tripped Condition.Caused to Allow Replacement of Erratic Delta Flux Indicator.Indicator Replaced & Power Range Detector Returned to Svc | /03L-0 on 790228:power Range Channel N42 Placed in Tripped Condition.Caused to Allow Replacement of Erratic Delta Flux Indicator.Indicator Replaced & Power Range Detector Returned to Svc | | | 05000338/LER-1979-026-03, /03L-0 on 790306:RHR Discharge Valve Opened Accidentally Causing Loop C Accumulator Level to Drop Below Min Volume Required.Caused by Accidental Operation of MOV-1720B.Valve Closed & Loop Accumulator Level Restored | /03L-0 on 790306:RHR Discharge Valve Opened Accidentally Causing Loop C Accumulator Level to Drop Below Min Volume Required.Caused by Accidental Operation of MOV-1720B.Valve Closed & Loop Accumulator Level Restored | | | 05000338/LER-1979-027-03, /03L-0 on 790225:axial Flux Difference Deviated Greater than 5% from Target.Caused by Xenon Transient Occurring During Startup Operation.Corrected by Boration by Reactor Operator | /03L-0 on 790225:axial Flux Difference Deviated Greater than 5% from Target.Caused by Xenon Transient Occurring During Startup Operation.Corrected by Boration by Reactor Operator | | | 05000338/LER-1979-027, Forwards LER 79-027/03L-0 | Forwards LER 79-027/03L-0 | | | 05000338/LER-1979-028-03, /03L-0 on 790225:greater than 12-step Disagreement Noted Among Rod Position Indication,Computer Position Indication & Demand Signal Indication for Rod 9.Caused by Voltage Drift in Signal Conditioning Card | /03L-0 on 790225:greater than 12-step Disagreement Noted Among Rod Position Indication,Computer Position Indication & Demand Signal Indication for Rod 9.Caused by Voltage Drift in Signal Conditioning Card | | | 05000338/LER-1979-030-03, /03X-1 on 790308:nonconservative Gain Setting on delta-flux Signal Feeding Overpower Delta T Protection Circuitry Observed.Caused by Improper Setting of delta-flux Gain.Signal Recalibr | /03X-1 on 790308:nonconservative Gain Setting on delta-flux Signal Feeding Overpower Delta T Protection Circuitry Observed.Caused by Improper Setting of delta-flux Gain.Signal Recalibr | | | 05000245/LER-1979-030-03, /03L-0 on 790308:calibr Procedure Revealed Nonconservative Gain Setting on delta-flux Signal Feeding Overpower Delta T Protection Circuitry.Caused by Improper Setting of delta-flux Gain.Signal Recalibrated | /03L-0 on 790308:calibr Procedure Revealed Nonconservative Gain Setting on delta-flux Signal Feeding Overpower Delta T Protection Circuitry.Caused by Improper Setting of delta-flux Gain.Signal Recalibrated | | | 05000338/LER-1979-031-03, /03L-0 on 790302:surveillances of Engineered Safety Feature Pumps Not Performed within Interval.Caused by Personnel Error Due to Long Period from Preoperational Tests to Operation.Surveillances Will Be Performed | /03L-0 on 790302:surveillances of Engineered Safety Feature Pumps Not Performed within Interval.Caused by Personnel Error Due to Long Period from Preoperational Tests to Operation.Surveillances Will Be Performed | | | 05000338/LER-1979-032-03, /03L-0 on 790312:containment Vacuum Pump Suction Valve TV-CV150A Would Not Remain Closed When Operated from Control Room.Caused by Relay Sticking in Energized Position.Relay Repaired & Tested Satisfactorily | /03L-0 on 790312:containment Vacuum Pump Suction Valve TV-CV150A Would Not Remain Closed When Operated from Control Room.Caused by Relay Sticking in Energized Position.Relay Repaired & Tested Satisfactorily | | | 05000338/LER-1979-032, Forwards LER 79-032/03L-0 | Forwards LER 79-032/03L-0 | | | 05000338/LER-1979-033, Forwards LER 79-033/03L-0,79-036/03L-0,79-037/03L-0 & 79-038/03L-0 | Forwards LER 79-033/03L-0,79-036/03L-0,79-037/03L-0 & 79-038/03L-0 | | | 05000338/LER-1979-033-03, /03L-0 on 790321: C Steam Generator Narrow Range Level Indicator LI-1496 Gave Readings w/20% Disagreement W/Two Other Channels.Caused by Steam Leak in One Sensing Line Isolation Valve | /03L-0 on 790321: C Steam Generator Narrow Range Level Indicator LI-1496 Gave Readings w/20% Disagreement W/Two Other Channels.Caused by Steam Leak in One Sensing Line Isolation Valve | |
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