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LER-1978-040, /03L-0 on 781116:routine Testing Revealed Failure of Heat Tracing Circuit 4C Unit 2 Boron Injection Tank Top Recirculation Return.Caused by Boric Acid Damage to the Heat Tracing Circuit |
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| 2811978040R03 - NRC Website |
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NFIC fORl\\li 366 U. S~ NUCLEAR REGULATORY COMMISSION
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. e LICENSEE EVENT REPORT e ; : *..
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- 75 RePORT CATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES@
!During normal operation, routine testing revealed the failure of heat tracing circuit I (filJ 14c (Panel 11) Unit 112 Boron Injection Tank Top Recirc. return.
This is a degraded lm:J 1mode of ope_ration permitted by T.S. 3.3.B.5 and is reportable as per T.S. 6.6.2.b. (2)]
@I[J 1The health and safety of the general public were not affected.
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CAUSE
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CODE CODE suscooe COMPONENT CODE SUSCOOE 1s IF I@ ~@ -~ I HI Ej A! Tf El Rf@ L:.J@)
9 10 11 12 13 18 19 SEQUENTIAL OCCURRENCE REPORT VALVE SUBCODE LB@
20 t:::\\ LER/RO LVE~T YEAR REPORT No.
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REPORT I 7 j 8 I I I I O I 41 01 1.......-1 I 013 I w 1-1 NUMBER 21 22 23 24 26 27 28 29 30 31 J
80 REVISION NO.
LU 32 COMPONENT TAKEN ACTION ON PLANT METHOD HOURS SUBMITTED FORM :;us.
SUPPLIER ACTION FUTURE EFFeCT SHUT-DOWN
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ATTACHMENT NPR0-4 PRIME<:;OMP.
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MANUFACTURER 33 34 35 36 37 40 41 42 43 j C j _
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- CAUSE DESCRIPTION AND CORRECTIVE ACTIONS @
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~7 o:::::t]J JA review of the heat tracing circuit showed that fail~ was caused by boric acid J
IJ]JJ.,damage of the heat* tracing cirucit.
The corrective action taken was to replace the fJ.:]II !heat tracing tape~.
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FACILITY
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% POWER OTHER STATUS \\.::.::,1 DJI1 l!J(§)' p. 10 10 l@)I NA I
8.' 9 10 12 1'l 44 ACTIVITY CONTENT
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RELEASED OF RELEASE AMOUNT OF ACTIVITY rrm LB 12J@1 NA 1
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9 10 11 44 7
METHOD OF
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DISCOVERY
. DISCOVERY DESCRIPTION ~
L!J@I Electrician* observation 45 46 80 NA
_LOCATION OF RELEASE @
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80 45 80 PERSONNEL EXPOSURES
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NUMBER*
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NUMBER DESCRIPTION6 80 (i]I] ! 0 ! 0 IO I@
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DESCRIPTION
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9 10 80 PUBLICITY Q\\
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78121A01~
T. L. Baucom (804) 357-3184 0
. ~itil OF PREJSA ER PHONE:------------
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. Atta~hment,
Report No:
.Event Date:
Page 1 of 1 Station, Uni~*
50-281 78-039/03L-0 11-15-78
- - Title of Report:
Failure of Loop B Hot Leg Temperature Sensor
.1. Description of Event:
During normal operation it was found that* the "B" loop hot leg temperature sensing element TI-2-422A was drifting low.* This resulted in the inability of TI-2-422A to supply a reliable signal to Channel II Overpower~ Overtemperature Delta-T Protection.
The required degree of redundancy was no.t maintained and this is contrary to Technical Specifications 3.7.B and is reportable per T~ch-nical Specifications 6.6.2.b.(2).
- 2.
- Probable Consequences and Status of;Redundartt*Systems:
. Channel II Overpower - Overtemperature Delta-T Protection was placed in the trip mode.
All other overpower - overtemperature instrumentation remained operable.
Because the required immediate corrective action was taken and the degree of redundancy regained, the health and safety of the general public.were.
not affected.
Cause
This event was caused by a packing leak in-a_RTD 11..oop isolation valv~ (RC-52)
. which sprayed on the Loop B hot leg temperature sensors.
The sensing element insulatio.n resistance decreased causing the output to drift.
- 4.
Immediate Corrective Action
Channel II Overpower - Overtemperature Delta~T Protection was_placed in the trip mod_e.
This restored the required degree of redundancy.
- 5.
Subsequent Corrective Action:
- The insulation :resistance was monitored and when it returned to:its normal range, the instrumentation was calibrated, tested aad returned to service.
6 *. Actions Taken to Prevent Recurrence:
No further corrective action will be required to prevent recurrence.
The packing leak will be rectified during the next outage.
- 7.
Generic Implications:
None
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_..J '(A:tt;_achment, page 1.)
Surry Power Station; Unit 2 Docket No: 50-281 Report No: 78-040/03L~O Event Date: 11-16-78 Low Current on Heat Tracing
- 1. * -_Description of Event:
- 2.
- 3.
With the unit in normal operation at rated power, routine surveillance indicated that heat tracing circuit 4C (Panel 11) was operated at less than the current specified in the surveillance document.
No low temperature alarms were indicated.
Investigation for faulty heat tracing tape was initiated on the affected circuit. Faults were found on circuit 4C (Panel 11) Uriit #2 Boron Injection Tank Top Recirc. Return, and were identified as being the result of boric acid attack on tape *. The tape was. replaced and circuit current verified to be within spec~ of the surveillance document.
This is a degraded mode of operation permitted by T.So 3.3.B.5 and is reportable in accordance with T.S. 6.6.2.b.(2).
Probable Consequences/Status of Redundant Systems:
At all t-imes during the event, the temperature in the piping served by the affected.circuiti was maintained as required.
The redundant circuit was operable.
There were at all times two operable flow paths for boric acid to the reactor. Therefore, the health and safety of the public were not affected.
Cause
The reduc~d currents were due to boric acid damage.to the heat tracing tape on affected circuits.
- 4.
Immediate Corrective Action
The heat tracing tape was replaced.
- 5.
Scheduled Corrective Action:
The problem was corrected immediately and no further action is required.
6.* Action Taken to Prevent Recurrence:
Continuous surveillance is maintained on the heat tracing systems.
No additional action is considered necessary.
- 7.
Generic Implications:
This failure, as with others in the system, is considered random since no specific circuit or panel has exhibited repeated failure *
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Caused When Actuator Cam for Shut Torque Switch Became Wedged Against Torque Switch Hold Down Screw | /03X-1 on 780926:circulating Water Outlet Valve MOV-CW-200D Failed to Close When Operated Electrically. Caused When Actuator Cam for Shut Torque Switch Became Wedged Against Torque Switch Hold Down Screw | | | 05000280/LER-1978-033-03, /03L-0 on 781015:heat Tracing Circuit Failed. Caused by Old Boric Acid Buildup & Penetration of Heat Leakage | /03L-0 on 781015:heat Tracing Circuit Failed. Caused by Old Boric Acid Buildup & Penetration of Heat Leakage | | | 05000281/LER-1978-034-03, /03L-0:on 781006,w/unit at Cold Shutdown,Snubbers 2-RH-HSS-20 & 2-WFPD-HSS-9 Inoperable.Caused by Low Fluid Level.Defective Snubbers Dry Because of Leaking Rod Seals & Mechanical Damage to Seals.Snubbers Replaced | /03L-0:on 781006,w/unit at Cold Shutdown,Snubbers 2-RH-HSS-20 & 2-WFPD-HSS-9 Inoperable.Caused by Low Fluid Level.Defective Snubbers Dry Because of Leaking Rod Seals & Mechanical Damage to Seals.Snubbers Replaced | | | 05000280/LER-1978-034-01, /01X-1 on 781101:noted That 17 Spare Process Piping Penetrations on Unit 1 & 23 on Unit 2 Were Not Capped in Auxiliary Bldg.Caused by Failure to Properly Complete Capping at End of Constr | /01X-1 on 781101:noted That 17 Spare Process Piping Penetrations on Unit 1 & 23 on Unit 2 Were Not Capped in Auxiliary Bldg.Caused by Failure to Properly Complete Capping at End of Constr | | | 05000280/LER-1978-034, Update to LER 78-034/01X-2 on 781101:17 Spare Process Piping Containment Penetrations Were Not Capped.Condition Has Been Overlooked Since Const.Design Change Approved to Weld Caps on Open Ends | Update to LER 78-034/01X-2 on 781101:17 Spare Process Piping Containment Penetrations Were Not Capped.Condition Has Been Overlooked Since Const.Design Change Approved to Weld Caps on Open Ends | | | 05000280/LER-1978-035, Forwards LER 78-035/01T-0 | Forwards LER 78-035/01T-0 | | | 05000281/LER-1978-035-03, /03L-0:on 781007,during Cold Shutdown,Valve Pit Flooded While Draining Circulating Water Box D.Caused by Damage of Valve from Flooding | /03L-0:on 781007,during Cold Shutdown,Valve Pit Flooded While Draining Circulating Water Box D.Caused by Damage of Valve from Flooding | | | 05000280/LER-1978-035-01, /01T-0 on 781109:study of Calibr Techniques Showed That SI Accumulators Indicated Level Would Be Lower than Actual Level.Discovered After Rigorous Review of Factors Affecting Instru | /01T-0 on 781109:study of Calibr Techniques Showed That SI Accumulators Indicated Level Would Be Lower than Actual Level.Discovered After Rigorous Review of Factors Affecting Instru | | | 05000280/LER-1978-036, Forwards LER 78-036/03L-0, 70-037/03L-0 & 78-038/03L-0 | Forwards LER 78-036/03L-0, 70-037/03L-0 & 78-038/03L-0 | | | 05000280/LER-1978-036-03, /03L-0 on 781107:failure of Heat Tracing Circuit 24D,Unit 1,due to Boric Acid Damage.Heat Tracing Tape Replaced | /03L-0 on 781107:failure of Heat Tracing Circuit 24D,Unit 1,due to Boric Acid Damage.Heat Tracing Tape Replaced | | | 05000281/LER-1978-036-03, /03L-0 on 781015:compensatory Surveillance on RCP Cstator & Hearing Temp Had Not Been Performed.Caused by Failure of Operating Personnel to Restore Process Computer Trend Block Following Computer Reinitialization | /03L-0 on 781015:compensatory Surveillance on RCP Cstator & Hearing Temp Had Not Been Performed.Caused by Failure of Operating Personnel to Restore Process Computer Trend Block Following Computer Reinitialization | | | 05000281/LER-1978-036, Forwards LER 78-036/03L-0 | Forwards LER 78-036/03L-0 | | | 05000281/LER-1978-037, Forwards LER 78-037/03L-0 | Forwards LER 78-037/03L-0 | | | 05000280/LER-1978-037-03, /03L-0 on 781107:procedure Deviation Found Re Filling & Venting Reactor Coolant Sys on 770105.Procedure Deviation Was Misrouted to Records Vault W/O Review by Snsoc.Deviation Has Now Been Submitted to Snsoc for Review | /03L-0 on 781107:procedure Deviation Found Re Filling & Venting Reactor Coolant Sys on 770105.Procedure Deviation Was Misrouted to Records Vault W/O Review by Snsoc.Deviation Has Now Been Submitted to Snsoc for Review | | | 05000281/LER-1978-037-03, /03L-0 on 781022:with Unit at Rated Pwr,Panel Indicator for Radiat Monitor RM-213 Monitoring a Steam Generator Blowdown Read 0.Caused by Loose Connector Joining Detector Cable to Electronic Chassis | /03L-0 on 781022:with Unit at Rated Pwr,Panel Indicator for Radiat Monitor RM-213 Monitoring a Steam Generator Blowdown Read 0.Caused by Loose Connector Joining Detector Cable to Electronic Chassis | | | 05000281/LER-1978-038-03, /03X-1 on 781030:boric Acid Flow from Boric Acid Tank to Blender Was Interrupted.Caused by Blockage of Crystallized Boron at Elbow in Line 1-CH-356-152 | /03X-1 on 781030:boric Acid Flow from Boric Acid Tank to Blender Was Interrupted.Caused by Blockage of Crystallized Boron at Elbow in Line 1-CH-356-152 | | | 05000280/LER-1978-038-03, /03X-1 on 781108:review of Operational Data Showed That Quarterly Calibr of Nuclear Power Range Instrumentation Had Not Been Performed Per Schedule,Due to Scheduling Error | /03X-1 on 781108:review of Operational Data Showed That Quarterly Calibr of Nuclear Power Range Instrumentation Had Not Been Performed Per Schedule,Due to Scheduling Error | |
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