LER-1982-012, /01T-0:on 820831,clearance Found Denoting Inoperability of safety-related Heat Tracing Circuit Associated W/Boric Acid Flow Path to Chemical & Vol Control Sys Blender.Caused by Personnel Error.Circuit Repaired |
| Event date: |
|
|---|
| Report date: |
|
|---|
| 2511982012R01 - NRC Website |
|
text
.
t NaC PCA M 364 U. $. NUCLE AR AECULATORY COMMIS$10N (7-778 LICENSEE EVENT REPORT contact st0C4: i l
l l 1
'l s@
I intEAsE *a:NT Ca Tyre ALL necui AEo iNPomuAtioN; I
lo t :1 i FIL I T I Pls 14 l@'l0 l o l l o l o l 01 O' 0 1_lO 1 0l@ 4 1111 1 1 1 1 l@l l l@
A 8 UC&%541 CQat
.!C145& rewus4A 11
- 6 6.C1%54 Tvet J3 63 CA T $4 CCN'T lo!il E'"c,ILl@l015l0l01012I511 @l 018t*3 I ll 812 l@l O! 9 l 114 I 8 l 21@
F 5
63 61 00C44T huus e n 68 da SvtNT OATE 84 75 AIPORTDATI 30 EVENT DESCAiPTIOas Aho PRCSA8LE CONSECUENCES h go,:ilDuring a routine review of outstanding clearances, Operations found a l
ITTTI I clearance denoting inoperability of a safety-related heat-tracing-circuit t
, associated with the boric ' acid flow path to the CVCS blender. The actual i
iois,i boric acid flow path was not blocked. An alternate flow path to the I
g ; reactor from the RWST was also available. The health and safety of the (TTTI I Public was not affected. This is reportable pursuant to TS 6.9.2.a.2.
I i o, s,1 Shutdown was initiated 'nd in pronress until repair completion.
I 7
5 4 50 E
CO E 5 8CC f C3..O.NENT CCCE tue of 3
g IC19l 1 Plc l @ LA_j @ LXJ @ lHlEIA I T I EIR !@ Lz_l@ L2J @
7 9
30 ft
$2 10
- 5 69 23 313.s f N TI A L CC;6aefNc3 ms sent 48b'58 3as gga,ag tvtqTvtan mE omT ho, C004 TTPt N C.
@s,57,;a 18121 1 1011121 1/l
! Oll !
IT l L-J [0J a
f
,_2 n 22 23 24 26
- P 05 25 00
- t 3
g[.sh,gY LBJ@LxJ@"CN PLANTLB_J@
LAl@
- 1. Ol 0 ! O ! 3 I LvJ@
ti_J@
Ui]@
l Cl 31312 l@
A N
AC CN stet =
saoung 3 3 e som g.
va s&C aim
- 3 04 35 3e 38
'O 43 42 4J 44 41 CAUSE CESCRIPTION AND CORRECTIVE ACitONS h t i t a l lThe inoperable circuit was found on 8/23 /82 with the cables. comecHne-the
,,,,,, thermostats to their power supply cut.
Plant documentation was not updated,e i. !3, ] according to procedure. af ter a plant chance which rnade this circuit safety I tii:1!vn13ena Thin ncconnend fnr tho an1ny e n nt n corrective action.
The I
, circuit was repaired and the documentation is being updated.
p r
i 9 ao ITA
'nPOwf4 CTut A STATUS D5 AV 3r$Covimv ogsCa6rrion Ii i s l [yj@ l 110 0 l@l NA l
l A l@ Operator observation
!i t s I W @e e.o'2;ivt
',Criviry C
Auov=ron.Criviry @ l tocariC= e, =s-rass @
.itense ascease l NA LzJO!
NA
.....,.~/.n,:sLi
,,,C...T>o= @
v.,
I' I r ! 10 ! O ! O!@Lz_l@l NA I
..sc~~.'J.~,.7,es
- Ca. tic ~@
uuver.
li l a i 10101 0}@l NA l
r 3 3
- )
12 30 M',',*01f;':"',','C,'*@
5*
l #9i [z_Jgl NA l
a na 1:ici ig @$E:..,,.:~ @
- 53. gs
^^C'8 EON'Y l
n
! II'!lltiIliI I a >
sa <*
as P. L. Pace Pw3NE:(305) 552-3654 N A*.T OF poEP A A ER 820921o A9(,
s R EPORTABLE OCCUR RENCE 251-82-012 LICENSEE EVENT REPORT TURKEY POINT UNIT 4 Page two Additional Event Description and Probable Consequences In routinely reviewing outstanding clearances, the Plant Supervisor-Nuclear (NPS) found a clearance denoting inoperability of a heat tracing circuit (Ckt. No. 57 A & B) associated with the boric acid flow path to the CVCS blender. This circuit had been out of service for at least several days. While this heat tracing circuit was not designated as safety-related on the Control Room listing of heat tracing circuits, the NPS desired more specific information on the circuit. To this end, the NPS researched the heat tracing circuit drawings and found that a plant change / modification (PC/M 78-13) had changed the circuit function so that it provided heat tracing for a portion of the common piping from the Boric Acid Transfer Pumps to the CVCS blending station and the charging pump suction. The actual boric acid flow path was not blocked. An alternate flow path to the reactor directly from the RWST was available. The health and safety of the public was not affected. Similar occurrences were reported as LER 251-81-017, LER 251-78-001, LER 251-77-12 and AO 251-74-08. The fact that a safety related heat tracing circuit was inoperable for more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> is contrary to TS 3.6.d.3 and thus is reportable pursuant to TS 6.9.2.a.2.
Additional Cause Description and Corrective Actions During a routine preventive maintenance (PM) exercise, Electrical Department personnel noticed that the temperature readirgs associated with circuit 57 A & B had been steadily decreasing. A plant work order was generated (PWO 4212) on August 17,1982 to investigate the problem. Circuit 57 was designated as a spare circuit on the N.O. log sheets. On August 23,1982, Electrical Maintenance discovered that both conduits (trains A & B) connecting the thermostat of circuit 57 to their power supplies were cut and a 6-8 f t. section of conduit removed. The heat tracing and lagging associated with circuit 57 were found intact, only the power supply lines were found disturbed. A non-safety-related clearance was issued at this time for personnel safety reasons since this circuit was designated as a " spare circuit". No attempts to repair the circuit were made at that time pending an investigation of who cut it and why.
l Further investigation revealed that originally the section of pipe from the Boric Acid Transfer Pumps to the CVCS blender were heat-traced with only two circuits (Ckts. 23 and 24), but due to line blockage in the past (see LER 251-78-001), a PC/M (78-13) was implemented on November 17,1978 to cover this section of pipe with seven circuits (Ckts.
23,24,56,57,93,94 and 95). Although PC/M 78-13 listed the affected drawings and procedures to be updated, including the N.O. log sheet (#6 " Critical Heat Tracing Circuits"), all of these changes had not been made. Consequently, the information i
available in the Control Room (including OP 2504.1," Heat Tracing System - Periodic Test" and OP 2500.I, " Heat Tracing System - Normal Operation") had not been updated to reflect the changes made by PC/M 78-13.
Upon discovering the Technical Specification violation mentioned above, the NPS immediately initiated action to shutdown the unit in accordance with applicable operating procedures and proceeded to have the heat tracing circuit repaired. The circuit was repaired within three (3) hours and the unit was subsequently returned to full power operation. The work to replace the missing conduits was completed on September 3,1982.
i o
R EPORTABLE OCCURRENCE 251-82-012 LICENSEE EVENT REPORT TURKEY POINT UNIT 4 Page three The root cause is believed to be personnel error in cutting the wires and removing conduit.
without prior notification or approval. A significant factor on the delay to take corrective action can be attributed to the fact that appropriate plant documents were not updated af ter a plant change by the responsible department in accordance with Administrative Procedure 190.15," Plant Changes and Modifications". Several procedure changes have since been made to prevent recurrence of this situation. The reason for the disconnected conduits and the responsible person (s) could not be determined. An investigation is still in progress by both plant maintenance personnel and construction personnel to determine the reason for the circuit interruption and to identify the responsible individual (s). Pending the outcome of this investigation, a LER update will be issued. The listing denoting safety-related heat tracing circuits was expeditiously updated and made available to the operators on September 3,1982. An in-depth review of this listing, which confirmed the September 3 update, was completed on September 10, 1982.
The appropriate documents, drawings and procedures are presently being updated to reflect existing plant conditions.
|
|---|
|
|
| | | Reporting criterion |
|---|
| 05000250/LER-1982-001, Forwards LER 82-001/03L-0 | Forwards LER 82-001/03L-0 | | | 05000250/LER-1982-001-03, /03L-0:on 820103,fire Watch Patrol Failed to Inspect Inoperable Zone for 3-h Per Tech Spec Requirements.Caused by Misunderstanding by Contractor Personnel Re Agreement to Maintain Insps During Holidays | /03L-0:on 820103,fire Watch Patrol Failed to Inspect Inoperable Zone for 3-h Per Tech Spec Requirements.Caused by Misunderstanding by Contractor Personnel Re Agreement to Maintain Insps During Holidays | | | 05000251/LER-1982-001, Forwards LER 82-001/01T-0 | Forwards LER 82-001/01T-0 | | | 05000251/LER-1982-001-01, /01T-0:on 820105,D Motor Control Ctr Tripped Due to Phase to Phase Fault Associated W/Bus.Caused by Entrance of Metal Fish Tape Through Unused Conduit.Motor Control Ctr re-energized.Unused Conduit Capped | /01T-0:on 820105,D Motor Control Ctr Tripped Due to Phase to Phase Fault Associated W/Bus.Caused by Entrance of Metal Fish Tape Through Unused Conduit.Motor Control Ctr re-energized.Unused Conduit Capped | | | 05000250/LER-1982-002, Forwards LER 82-002/03L-0 | Forwards LER 82-002/03L-0 | | | 05000250/LER-1982-002-03, /03L-0:on 820216,while Performing Periodic Test of Fire Pumps,West Pump Failed to Automatically Start at Min Accepted Starting Pressure.Caused by Trip Switch & Gauge Being Out of Calibr.Recalibr Performed & Pump Tested | /03L-0:on 820216,while Performing Periodic Test of Fire Pumps,West Pump Failed to Automatically Start at Min Accepted Starting Pressure.Caused by Trip Switch & Gauge Being Out of Calibr.Recalibr Performed & Pump Tested | | | 05000251/LER-1982-002, Forwards LER 82-002/01T-0 | Forwards LER 82-002/01T-0 | | | 05000250/LER-1982-003, Forwards LER 82-003/03L-0 | Forwards LER 82-003/03L-0 | | | 05000251/LER-1982-003-01, /01T-0:on 820331,deficiency Involving Supports Associated W/Component Cooling Water Sys Found.Max Stress Would Exceed Acceptance Criteria on Supports.Cause Not Stated.Mod Implemented to Support Piping | /01T-0:on 820331,deficiency Involving Supports Associated W/Component Cooling Water Sys Found.Max Stress Would Exceed Acceptance Criteria on Supports.Cause Not Stated.Mod Implemented to Support Piping | | | 05000251/LER-1982-003, Forwards LER 82-003/01T-0 | Forwards LER 82-003/01T-0 | | | 05000250/LER-1982-003-03, /03L-0:on 820301,while Performing Hot Functional Test,High Point Vent in Normal Charging Line to RCS Loop a Cold Leg Found W/Cracked Weld.Stress from Line Vibration Suspected.Crack Repaired by Plugging Vent Line | /03L-0:on 820301,while Performing Hot Functional Test,High Point Vent in Normal Charging Line to RCS Loop a Cold Leg Found W/Cracked Weld.Stress from Line Vibration Suspected.Crack Repaired by Plugging Vent Line | | | 05000250/LER-1982-004, Forwards LER 82-004/03L-0 | Forwards LER 82-004/03L-0 | | | 05000251/LER-1982-004, Forwards LER 82-004/01T-0 | Forwards LER 82-004/01T-0 | | | 05000250/LER-1982-004-03, /03L-0:on 820517,during Routine Reactor Startup, Augmented Surveillance of Hot Channel Factors Not Maintained as Required.Caused by Computer Taken Out of Svc During Surveillance Sequence.Personnel Reinstructed | /03L-0:on 820517,during Routine Reactor Startup, Augmented Surveillance of Hot Channel Factors Not Maintained as Required.Caused by Computer Taken Out of Svc During Surveillance Sequence.Personnel Reinstructed | | | 05000251/LER-1982-004-01, /01T-0:on 820408,while Operating at Full Power, Routine Sample Analysis Found Boron Concentration in Boron Injection Tank Lower than Tech Specs.Caused by Boric Acid Obstructing Flow Path.Line Flushed W/Steam | /01T-0:on 820408,while Operating at Full Power, Routine Sample Analysis Found Boron Concentration in Boron Injection Tank Lower than Tech Specs.Caused by Boric Acid Obstructing Flow Path.Line Flushed W/Steam | | | 05000251/LER-1982-005, Forwards LER 82-005/03L-0 | Forwards LER 82-005/03L-0 | | | 05000251/LER-1982-005-03, /03L-0:on 820414,when Attempting to Fill Condensate Storage Tank After Low Level Alarm,Level Fell Below Acceptable Limit.Caused by Open Manual Valve DWDS-001 Allowing Flow to Demineralized Water Storage Tank | /03L-0:on 820414,when Attempting to Fill Condensate Storage Tank After Low Level Alarm,Level Fell Below Acceptable Limit.Caused by Open Manual Valve DWDS-001 Allowing Flow to Demineralized Water Storage Tank | | | 05000250/LER-1982-005-03, /03L-0:on 820519,during Routine Startup,Augmented Surveillance of Hot Channel Factors Not Initiated When Threshold Power (98%) Was Passed.Caused by Procedural Error.Procedure Change Initiated | /03L-0:on 820519,during Routine Startup,Augmented Surveillance of Hot Channel Factors Not Initiated When Threshold Power (98%) Was Passed.Caused by Procedural Error.Procedure Change Initiated | | | 05000250/LER-1982-005, Forwards LER 82-005/03L-0 | Forwards LER 82-005/03L-0 | | | 05000251/LER-1982-006, Forwards LER 82-006/01T-0 | Forwards LER 82-006/01T-0 | | | 05000250/LER-1982-006, Forwards LER 82-006/03L-0 | Forwards LER 82-006/03L-0 | | | 05000251/LER-1982-006-01, /01T-0:on 820509,boron Concentration Found Lower than Min Allowable Concentration During Routine Chemical Analysis of Boron Injection Tank Sample.Caused by Plugging of Normal Recirculation Supply Line | /01T-0:on 820509,boron Concentration Found Lower than Min Allowable Concentration During Routine Chemical Analysis of Boron Injection Tank Sample.Caused by Plugging of Normal Recirculation Supply Line | | | 05000250/LER-1982-006-03, /03L-0:on 820527,diesel Generator a Tripped at 2,500 Kw.Caused by Malfunctioning Relief Valve in Fuel Oil Supply.Valve Replaced & Generator Retested | /03L-0:on 820527,diesel Generator a Tripped at 2,500 Kw.Caused by Malfunctioning Relief Valve in Fuel Oil Supply.Valve Replaced & Generator Retested | | | 05000250/LER-1982-007-03, /03L-0:on 820529,while Performing Containment Leak Insp,Broken Hangers & Broken Snubber Discovered on 3C Steam Generator Blowdown Lines.Caused by Hydraulic Shock to Blowdown Lines | /03L-0:on 820529,while Performing Containment Leak Insp,Broken Hangers & Broken Snubber Discovered on 3C Steam Generator Blowdown Lines.Caused by Hydraulic Shock to Blowdown Lines | | | 05000251/LER-1982-007, Forwards LER 82-007/01T-0 | Forwards LER 82-007/01T-0 | | | 05000251/LER-1982-007-01, /01T-0:on 820522,while Boron Injection Tank Recirculating W/Boric Acid Storage Tank C,Low Boron Concentration Found in Both Tanks.Caused by MOV-4-867B Being Open One Turn.Valve Manually Closed | /01T-0:on 820522,while Boron Injection Tank Recirculating W/Boric Acid Storage Tank C,Low Boron Concentration Found in Both Tanks.Caused by MOV-4-867B Being Open One Turn.Valve Manually Closed | | | 05000250/LER-1982-007, Forwards LER 82-007/03L-0 | Forwards LER 82-007/03L-0 | | | 05000250/LER-1982-008-03, /03L-0:on 820609,3A High Head Safety Injection Pump Failed to Start from Manual Operation of Normal Control Switch.Cause Not Determined.Breaker Control Panel Fuses Replaced & Breaker Racked Out & Backed in | /03L-0:on 820609,3A High Head Safety Injection Pump Failed to Start from Manual Operation of Normal Control Switch.Cause Not Determined.Breaker Control Panel Fuses Replaced & Breaker Racked Out & Backed in | | | 05000251/LER-1982-008-03, /03L-0:on 820608,disc Stud Nut on Main Feedwater Check Valve CV-4-2900 Found Missing.Caused by Failure of Nut Locking Device.New Locking Device Installed | /03L-0:on 820608,disc Stud Nut on Main Feedwater Check Valve CV-4-2900 Found Missing.Caused by Failure of Nut Locking Device.New Locking Device Installed | | | 05000251/LER-1982-008, Forwards LER 82-008/03L-0 | Forwards LER 82-008/03L-0 | | | 05000250/LER-1982-008, Forwards LER 82-008/03L-0 | Forwards LER 82-008/03L-0 | | | 05000250/LER-1982-009-03, /03L-0:on 820617,tritium Activity Weekly Sampling Tests Not Performed.Caused by Out of Svc Liquid Scintillation Machine.Samples Counted on 820621.Normal Levels Recorded | /03L-0:on 820617,tritium Activity Weekly Sampling Tests Not Performed.Caused by Out of Svc Liquid Scintillation Machine.Samples Counted on 820621.Normal Levels Recorded | | | 05000251/LER-1982-009-03, /03L-0:on 820623,biweekly Testing for Tave & Delta T Protection Channel Was Completed 2 Days After Latest Date Allowable.Caused by Computation Using Completion Date for Previous Test.Channel Test Completed 820625 | /03L-0:on 820623,biweekly Testing for Tave & Delta T Protection Channel Was Completed 2 Days After Latest Date Allowable.Caused by Computation Using Completion Date for Previous Test.Channel Test Completed 820625 | | | 05000250/LER-1982-009, Forwards LER 82-009/03L-0 | Forwards LER 82-009/03L-0 | | | 05000251/LER-1982-009, Forwards LER 82-009/03L-0 | Forwards LER 82-009/03L-0 | | | 05000250/LER-1982-010-03, /03L-0:on 820617,nonfunctional Vertical Pipe Support Discovered on Suction Line of 3A Component Cooling Water Pump.Caused by Cracking of Grout Under Plate,Resulting in Loss of Contact W/Ground.Support Regrouted | /03L-0:on 820617,nonfunctional Vertical Pipe Support Discovered on Suction Line of 3A Component Cooling Water Pump.Caused by Cracking of Grout Under Plate,Resulting in Loss of Contact W/Ground.Support Regrouted | | | 05000250/LER-1982-010, Forwards LER 82-010/03L-0 | Forwards LER 82-010/03L-0 | | | 05000251/LER-1982-010-03, /03L-0:on 820713,camera Insp of Steam Generators Revealed Foreign Objects & Minor Tube Damage.Leak & Minor Tube Damage Caused by Foreign Objects Near Tube Sheet Elevations.Metal Impact Monitoring Sys Installed | /03L-0:on 820713,camera Insp of Steam Generators Revealed Foreign Objects & Minor Tube Damage.Leak & Minor Tube Damage Caused by Foreign Objects Near Tube Sheet Elevations.Metal Impact Monitoring Sys Installed | | | 05000251/LER-1982-010, Forwards LER 82-010/03L-0 | Forwards LER 82-010/03L-0 | | | 05000250/LER-1982-011, Forwards LER 82-011/03L-0 | Forwards LER 82-011/03L-0 | | | 05000250/LER-1982-011-03, /03L-0:on 820713,quarterly Surveillance Test of Seismograph Completed 3 Days After Last Allowable Tech Spec Date.Caused by Const Equipment Blocking Access to Seismograph.Test Successfully Completed on 820716 | /03L-0:on 820713,quarterly Surveillance Test of Seismograph Completed 3 Days After Last Allowable Tech Spec Date.Caused by Const Equipment Blocking Access to Seismograph.Test Successfully Completed on 820716 | | | 05000251/LER-1982-011-03, /03L:on 820805,low Pressure Alarm (Set at 625 Psig) Received on 4B Accumulator.When Supply & Fill Valves Opened,Accumulator Pressure Dropped to 460 Psig. Caused by Loose Setting on Control Potentiometer | /03L:on 820805,low Pressure Alarm (Set at 625 Psig) Received on 4B Accumulator.When Supply & Fill Valves Opened,Accumulator Pressure Dropped to 460 Psig. Caused by Loose Setting on Control Potentiometer | | | 05000251/LER-1982-011, Forwards LER 82-011/03L-0 | Forwards LER 82-011/03L-0 | | | 05000251/LER-1982-012, Forwards LER 82-012/01T-0 | Forwards LER 82-012/01T-0 | | | 05000251/LER-1982-012-01, /01T-0:on 820831,clearance Found Denoting Inoperability of safety-related Heat Tracing Circuit Associated W/Boric Acid Flow Path to Chemical & Vol Control Sys Blender.Caused by Personnel Error.Circuit Repaired | /01T-0:on 820831,clearance Found Denoting Inoperability of safety-related Heat Tracing Circuit Associated W/Boric Acid Flow Path to Chemical & Vol Control Sys Blender.Caused by Personnel Error.Circuit Repaired | | | 05000250/LER-1982-012, Forwards LER 82-012/01T-0 | Forwards LER 82-012/01T-0 | | | 05000250/LER-1982-012-01, /01T-0:on 820917,insp Revealed That Electrical Penetration Did Not Meet Double Barrier Criteria of 10CFR50 & Testability Requirements of App J.Caused by Failure to Properly Document Plant Changes.Plant Change Implemented | /01T-0:on 820917,insp Revealed That Electrical Penetration Did Not Meet Double Barrier Criteria of 10CFR50 & Testability Requirements of App J.Caused by Failure to Properly Document Plant Changes.Plant Change Implemented | | | 05000250/LER-1982-013, Forwards LER 82-013/03L-0 | Forwards LER 82-013/03L-0 | | | 05000250/LER-1982-013-03, /03L-0:on 820917,steam Turbine Pressure Control Valve CV-3707 Did Not Close Completely,Resulting in Poor Pressure & Causing Safety Relief Valve to Trip Auxiliary Feedwater Pump C.Caused by Foreign Matter Under Valve Seat | /03L-0:on 820917,steam Turbine Pressure Control Valve CV-3707 Did Not Close Completely,Resulting in Poor Pressure & Causing Safety Relief Valve to Trip Auxiliary Feedwater Pump C.Caused by Foreign Matter Under Valve Seat | | | 05000251/LER-1982-013-03, /03L-0:on 820906,RCS Experienced Rapid Decrease in Pressure.Caused by Failed Open Pressurizer Spray Valve. Reactor Manually Tripped & Automatic Safety Injection Actuated.Pressure Control Regained Using Charging Pumps | /03L-0:on 820906,RCS Experienced Rapid Decrease in Pressure.Caused by Failed Open Pressurizer Spray Valve. Reactor Manually Tripped & Automatic Safety Injection Actuated.Pressure Control Regained Using Charging Pumps | |
|