LER-1981-018, /03L-0:on 810701,Channel I (PI-474) of a Steam Generator Steam Line Pressure Indicated High Compared to Two Redundant Channels.Caused by Throttled Root Isolation Valve MSV-14.Valve Reopened |
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- -e-NRC F oRM M6.
U. S. NUCLE AR REGULATORY COMMISSION 0 77)
LICENSEE EVENT REPORT CONTROL BLOCX: l l
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8 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 7S REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h I o 12 I lon July 1,1981, with the unit at 93% power, the Control Operator observed that Channell lT[5] lI (PI-474) of "A" Steam Generator Steam Line Pressure was indicating high compared to l l o 14 j lits two redundant channels. Channel I was declared inoperable at 1128 hours0.0131 days <br />0.313 hours <br />0.00187 weeks <br />4.29204e-4 months <br />. The l
lo is] l Channel I bistables were tripped to maintain the minimu:: degree of redundancy. However) g Ithe apparent inoperability of Channel I, prior to tripping its bistables, resulted in l g l exceeding the minimum degree of redundancy required by Technical Specification Table l
lOIsl 13.5-3 which is reportable pursuant to 6.9.2.b.2.
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40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h l i l o l lThe Channel I deviation was caused by a throttled root isolation valve (MSV-14) on l
[the instrument sensing line. MSV-14 was opened, and Channel I was declared operable l
3 i jat 1440 hours0.0167 days <br />0.4 hours <br />0.00238 weeks <br />5.4792e-4 months <br />. Operating personnel have been cautioned as to the importance of l
, 7 l insuring that instrument sensing line root isolation valves are fully open, and all l
3 3 employees have been reminded that no valve operation is to be done by unauthorized or I i l 41 juntrained personnel.
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DISCOVERY DESCRIPTION [J j@ l O l 9 l 3 l@l N/A l
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SUPPLEMENTAL INFORMATION FOR LICENSEE EVENT REPORT 81-018 1.
Cause Description and Analysis At approximately 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br /> en July 1, 1981, with the unit at 93%
power, the Control Operator observed that Channel I (PI-474) of "A" Steam Generator Steam Line Pressure was indicating high compared to its two redundant channels. These Steam Line Pressure Channels supply signals for sensing high differential steam pressure between the steam generator line and the steam header which provide steam line break protection. At 1128 hours0.0131 days <br />0.313 hours <br />0.00187 weeks <br />4.29204e-4 months <br />, Channel I was declared in-operable and its bistables tripped using Operating Work Permit (OWP)
RP-ll.
Instrumentation and Control personnel verified that the problem was not in the Channel I electronics.
It was suspected the problem was due to sludge blocking the instrument sensing line. When flush-ing the sensing line failed, an operator proceeded to close the root isolation valve (MSV-14) so the line could be disconnected and back-flushed. The operator discovered MSV-14 to be throttled.
This throttled position of MSV-14 caused the steam line pressure signal to be dampened and reduced the ability of Channel I to respond to short duration steam line pressure changes. This created the channel deviation observed by the Control Operator. MSV-14 was opened and Channel I (PI-474) returned within the deviation limits of its two redundant channels. An investigation was conducted to determine how valve MSV-14 could have been misplaced into the throttled position.
The most recent valve lineup documentation was reviewed and the operator who made the lineup was questioned as to the last known posi-tion of the valve. The operator stated that on June 9, 1981, when the valve w s last checked, it was in the fully opened position. A review of past maintenance records indicates that no work has been done on the valve since June 9, 1981.
In addition, a review of' operating conditions at the valve indicate that local vibrations are not of sufficient magnitude to cause the valve position to change.
Therefore, although the operator stated positively that the MSV-14 valve had been fully opened, operator error cannot be ruled out as the most probable cause for this event.
Channel I was checked for proper signal levels and declared operable at 1440 hours0.0167 days <br />0.4 hours <br />0.00238 weeks <br />5.4792e-4 months <br /> in accordance with OWP RP-ll.
Throughout this event, the other two. redundant channels of "A" Steam Generator Steam Line Pressure were operational. This provided the necessary indication and safety signals.
There was no threat to the public health and safety. However, the apparent inoperability of Channel I prior to tripping its bistables resulted in exceeding the minimum degree of redundancy required by Technical Specification Table 3.5-3 which is reportable pursuant to 6.9.2.b.2.
2.
Corrective Action
The immediate corrective action was to fully open MSV-14.
This restored Channel I to within the deviation limits. The instrument sensing was flushed as an added precaution.
3.
Corrective Action To Prevent Recurrence 1
3 This event appears to be the result of either mis-operation or not' assuring the valve was in its fully open position. Therefore, Operating personr.el have been cautioned as to the importance of assuring that instrument sensing line root valves, which are required 7
to be open, are fully opened. Also, Operating personnel will review this LER for its lessons to be learned.
In addition, all plant personnel will be reminded by August 15, 1981, that no valve opera-i tion is to be done by unauthorized or not properly trained personnel.
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| 05000261/LER-1981-001, Updated LER 81-001/01T-1:on 810109,turbine Runback & Automatic Rod Withdrawal Block Protection Defeated W/Power Range Channel N41 Being Out of Svc.Caused by Improper Rod Drop Analysis.Administrative Controls Revised | Updated LER 81-001/01T-1:on 810109,turbine Runback & Automatic Rod Withdrawal Block Protection Defeated W/Power Range Channel N41 Being Out of Svc.Caused by Improper Rod Drop Analysis.Administrative Controls Revised | | | 05000261/LER-1981-002, Updated LER 81-002/01T-2:on 810113,review of Svc Water Sys Revealed Potential Unmonitored Release Path on Svc Water Return Lines from Containment for Hydrogen Vent Header Motor Coolers.Caused by Design Error.Sys Will Be Modifie | Updated LER 81-002/01T-2:on 810113,review of Svc Water Sys Revealed Potential Unmonitored Release Path on Svc Water Return Lines from Containment for Hydrogen Vent Header Motor Coolers.Caused by Design Error.Sys Will Be Modified | | | 05000261/LER-1981-002-01, /01T-3:on 810113,review of Svc Water Sys Revealed Potential Unmonitored Release Path to Environ.Caused by Lack of Radiation Monitoring on Svc Water Return Lines from Containment.Discharge Lines Modified | /01T-3:on 810113,review of Svc Water Sys Revealed Potential Unmonitored Release Path to Environ.Caused by Lack of Radiation Monitoring on Svc Water Return Lines from Containment.Discharge Lines Modified | | | 05000261/LER-1981-004, Forwards Updated LER 81-004/03L-1 | Forwards Updated LER 81-004/03L-1 | | | 05000261/LER-1981-004-03, Primary Coolant Sys Leak Found.Caused by Sample Cooler Tube Bundle Leakage Due to Normal Wear.Bundle Replaced.Review of Maint Records Revealed No Generic Problems | Primary Coolant Sys Leak Found.Caused by Sample Cooler Tube Bundle Leakage Due to Normal Wear.Bundle Replaced.Review of Maint Records Revealed No Generic Problems | | | 05000261/LER-1981-006-01, /01T-0:on 820715,motor Cooler Leak Found in Containment Fan Cooler HVH-2.HVH-2 Shut Down & Svc Water to Unit Isolated.Caused by Corrosion/Erosion of Cooler Tubing. 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| 05000261/LER-1981-015-03, /03L-0:on 810525,computer Box FM-475 Found to Be Out of Acceptable Tolerances & Several Checkpoints Showed Erratic Readings During Loop a Steam Flow Channel Investigation.Caused by Two Worn Electronic Components | /03L-0:on 810525,computer Box FM-475 Found to Be Out of Acceptable Tolerances & Several Checkpoints Showed Erratic Readings During Loop a Steam Flow Channel Investigation.Caused by Two Worn Electronic Components | | | 05000261/LER-1981-016, Forwards LER 81-016/03L-0 | Forwards LER 81-016/03L-0 | | | 05000261/LER-1981-016-03, /03L-0:on 810611,during Startup,Motor Driven Auxiliary Feedwater Pump a Tripped Due to Low Discharge Pressure While Feeding Steam Generators.Event Reoccurred on 810716.Caused by Backleakage Through Discharge Valve AFW-40 | /03L-0:on 810611,during Startup,Motor Driven Auxiliary Feedwater Pump a Tripped Due to Low Discharge Pressure While Feeding Steam Generators.Event Reoccurred on 810716.Caused by Backleakage Through Discharge 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81-020/03L-0 | | | 05000261/LER-1981-021, Forwards LER 81-021/01T-0 | Forwards LER 81-021/01T-0 | | | 05000261/LER-1981-021-01, /01T-0:on 810925,w/unit at 50% Power,Group 2 Control Bank D Control Rods Were Inoperable & Reactor Shutdown Commenced.Caused by Faulty Input/Output Amplifier Printed Circuit Card in Control Rod Logic Cabinet | /01T-0:on 810925,w/unit at 50% Power,Group 2 Control Bank D Control Rods Were Inoperable & Reactor Shutdown Commenced.Caused by Faulty Input/Output Amplifier Printed Circuit Card in Control Rod Logic Cabinet | | | 05000261/LER-1981-022, Forwards LER 81-022/03L-0 | Forwards LER 81-022/03L-0 | | | 05000261/LER-1981-022-03, /03L-0:on 811015,w/unit at 50% Power,Lower than Normal Temp Indication Noted on Strip Chart Recorder for Valves on Discharge Line of Boron Injection Tank.Caused by Broken Wire Splice in Heat Tracing Circuit 70 | /03L-0:on 811015,w/unit at 50% Power,Lower than Normal Temp Indication Noted on Strip Chart Recorder for Valves on Discharge 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Procedure Revised & Motor Replaced | | | 05000261/LER-1981-032, Forwards LER 81-032/03L-0 | Forwards LER 81-032/03L-0 | | | 05000261/LER-1981-033, Forwards LER 81-033/01T-0 | Forwards LER 81-033/01T-0 | | | 05000261/LER-1981-033-01, /01T-0:on 811228,error in Tech Spec Heatup & Cooldown Curves Found to Be Not Reported to Nrc.Caused by Administrative Reporting Failure & Errors in Calculation. Info Will Be Reported as Tech Spec Change by 820131 | /01T-0:on 811228,error in Tech Spec Heatup & Cooldown Curves Found to Be Not Reported to Nrc.Caused by Administrative Reporting Failure & Errors in Calculation. Info Will Be Reported as Tech Spec Change by 820131 | | | 05000261/LER-1981-034-03, /03L-0:on 811211,loop 2 Steamline Pressure Channel Indicated Higher than Other Channels.Caused by Frozen Sensing Lines in Pressure Transmitter & Failure to Return Freeze Protection Circuit to Svc After Maint | /03L-0:on 811211,loop 2 Steamline Pressure Channel Indicated Higher than Other Channels.Caused by Frozen Sensing Lines in Pressure Transmitter & Failure to Return Freeze Protection Circuit to Svc After Maint | | | 05000261/LER-1981-034, Forwards LER 81-034/03L-0 | Forwards LER 81-034/03L-0 | |
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