LER-1980-034, /01T-0:on 800727,while Operating at 100% Power for 4,days Unit Exceeded Tech Specs by 8 Mwt.Caused by Leak in Steam Generator Blowdown Recovery Heat Exchanger 21 Which Resulted in Calorimetric Power Calculation Error |
| Event date: |
|
|---|
| Report date: |
|
|---|
| 3181980034R01 - NRC Website |
|
text
f FORM 366 1
LICENSEE EVENT REPORT wNTGOL SLOCs(: l l
l l
l l
l (PLEASE PRINT OR TYPE ALL CECUCED INFC'.MATi"N1 1
6 l M i o i c l c lN l 2 l@l 0101 -l 0l 0l 0l 010l -! 0l Ol@l 4I il 1111 lj@l l
l@
o i 7
8 9 tickNSEE CODE 14 15 LsCENSE Nww8tR 25 26 LICENSE TV,( Js*
$7 CAT bd con 4 10151 l'"C dl0151010101311 18 l@l01712 171810 l@l 018101818l Ol@
8 60 61 OOCK ET NUVS E R 68 69 EVENT DATE 74 75 REPORT D ATE 80 EVENT DESCRIPTION AND pro 8ABLE CONSEQUENCES h Lo_L ! 10n 7/27/80, it was confirmed that Unit 2 exceeded 2700 MWth (T.S.1.3) by 8 MWth i
10131 Iwhile the unit was operating at 100% power for approximately four days due to l
1o 91 l an undetected leak in #21 steam generator blowdown recovery heat exchanger l
1 o # si l(SG80RHX) which resulted in a nonconservative error in computer calorimetric l
o 6 l calculation power. The leak was isolated and correct blowdown flow was l
iTTT) I entered into the calculation at 1315 on 7/27/80.
LER 80-35 (U-2) describes i
I 1 o Ie I LLsimilar event.
80 E
CC"D E su C E CCVPON ENT COCE SLS CE S
DE FoTTl I z 1 z l@ LxJ@ l zi@ l 21 zl zi z l z i z i@ i zl@ Lz_j @
7 8
9 to 11 12 13 18 is 20 SE QUE NTI A L CCCURRENCE REPCRT R E vistDN t ER no EVENTVEAR R(PORT NO.
CODE TYPE NO.
@,afg 18 10 I l-l 1013141 M
10111 1 Tl 1---J LOJ 21 22 23 24 26 27 28 29 30 31 32 vhm
$8 i O
FOR B-5 LE MANLFAC RER TAE N ACT ON ON PL NT [G_j@[_zj@
[Z_j@
[_z_j@
l 010l 010l
[,YJ @
[ N_j@
l z l@
l X l 9 l 9 l 9 Ig 33 34 35 36 31 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h 1:101IThe cauw was dua to tube failure in di21 SGBDRHX which is coo' led by condensate.
I L'_L'J l This caused an erroneously high blowdown flow rate which resulted in an error I
l in the nonconservative direction for the calod metric power calculation.
A I
i,12i L'_L3_J l weekly preventative maintenance channel check will be imolemented to verify l
I
, L'_LJ l blowdown flow rate.
so fA
% POWE R OTHER STATUS DISCO RV O'SCOVERY DESCR'PTION L2J@ l of s10181 NA I
L sJ@l special Test I
li s
'5
.!Tivm CCETENT TOC,T.ONC,REuisE@
.oOuNT C, CTiv,Tv @ l r.E u.sEo 0,RE u.sE NA l
NA l
L1]@ [Z_j@l i 6
,ERsONNELnPCsSEs cEsCR,, TION @
~uu.ER Tv,E l
10101 Ol@LZ_J@l NA li 2
,ERsONNEL,NJEs t'
cEsCR:, TION @ NA l
Nev.E R l0101Ol@l i a 80 7
8 9 11 12 T E CESCR 8T ON I
LZj@l NA i 9 7
8 9 10 tSSUE @ DESCRIPTION [yj l
NA I
IIIIIIIIIII!II 2 o
' s d (f8 i s gg......,
s. M. Davis (301)269-4742
, oN E.
LER NO.
80-34/1T DOCKET NO.
50-318 EVENT DATE 07/27/80 ',
REPORT DATE 08/08/80 ATTACHMENT EVENTDESCRIPTIONANDPRO3ABLECONShuENCES:
On July 27, 1980, it was confimed that Unit 2 had exceeded rated thermal power of 2700 K4th (T.S.1.3) for approximately four (4) days when the unit was operating at 100% power.
This event was caused by an undetected leak in #21 steam generator blowdown recovery heat exchanger which resulted in an erroneous input to the plant computer's calorimetric power calculation.
On July 26, 1980, !21 steam generator blowdown recovery heat exchanger which is cooled by condensate water was discovered to have an approximately 230 gpm leak from the condensate side to the blowdcwn recovery side. As the -
leak increased in magnitude, the Operator closed the throttle valve to maintain the required indicated blowdown flow rate.
This action resulted in an ermr in the nonconservative direction between actual blowdown flow rate and indicated blowdown flow rate.
It has been estimated by conducting a hand calculated heat balance and confirmed by an actual test that the leak caused an error of approximately 8 Kith in calorimetric power.
At 1315 on July 27, 1980, the heat exchanger was isolated and placed out of service after it was confimed to have failed tubes.
After the heat exchanger was placed out of service and proper response of the blowdown flow rate meter was verified, the correct blowdown flow rate was entered into the computer calorimetric calculation.
An investigation was conducted in an attempt to verify the actual inception date of the leak so that a best estimate could be made as to the actual length of time the unit exceeded 2700 !s'th.
Two parameters were studied.
First a comparison of calorimetric power to incore instrument power was made, however, the results were inconclusive.
The second parameter studied was steam generator chemistry.
This data showed that blowdown became ineffective on 7/22/80.
Therefore, it.was concluded that the # 21 steam generator blowdown recovery heat exchanger tubes failed on that date.
Af ter reviewing the unit's power history and assuming that the Icak started on 7/22/80, it has been concluded that the unit exceeded power for91 hours.
$n cssessment of the significance of the overpower condition on tne Safety nnalysis concluded tnat tne overpower condition was more than offset, since local peaking factors (F t and F t) remained at least 8% below their Technical x
Specification limit duri"ng the ev3nt.
Therefore, an adequate margin of safety r-r.a i ned.
CAUSE DESCRIPTION AND CORRECTIVE ACTIONS:
The cause of this event was due to tube failure in ! 21 steam generator blowdown heat exchanger which resulted in an erroneous input to the plant co.rputer calcrimetric power calculation.
Corrective action to prevent recurrence will be to implement a weekly preventative maintenance functicnal check to verify proper blowdown flow rate.
|
|---|
|
|
| | | Reporting criterion |
|---|
| 05000317/LER-1980-001, Forwards LER 80-001/03L-0 | Forwards LER 80-001/03L-0 | | | 05000317/LER-1980-001-03, /03L-0:on 800104,high Pressure Safety Injection Loop 12A Stop Would Not Move to Throttled Position.Caused by Loose Termination on One Electrical Lead Terminating at Valve Torque Switch.Terminal Screw Tightened | /03L-0:on 800104,high Pressure Safety Injection Loop 12A Stop Would Not Move to Throttled Position.Caused by Loose Termination on One Electrical Lead Terminating at Valve Torque Switch.Terminal Screw Tightened | | | 05000318/LER-1980-001, Forwards LER 80-001/03L-0 | Forwards LER 80-001/03L-0 | | | 05000318/LER-1980-001-03, /03L-0:on 800225,although Low Pressure Safety Injection Pump 21 Was Placed Out of Svc for Maint, Containment Spray Pump 21 Was Disassembled.Caused by Verbal Communication Error | /03L-0:on 800225,although Low Pressure Safety Injection Pump 21 Was Placed Out of Svc for Maint, Containment Spray Pump 21 Was Disassembled.Caused by Verbal Communication Error | | | 05000318/LER-1980-002-03, /03L-0:on 800107,refueling Water Tank Narrow Range Level Indicator Was in Alarm W/Low Level,But Instrument Did Not Indicate Alarm Conditions.Caused by Faulty Indicator Alarm light-emitting Diode.Diode Replaced | /03L-0:on 800107,refueling Water Tank Narrow Range Level Indicator Was in Alarm W/Low Level,But Instrument Did Not Indicate Alarm Conditions.Caused by Faulty Indicator Alarm light-emitting Diode.Diode Replaced | | | 05000318/LER-1980-002, Forwards LER 80-002/03L-0 | Forwards LER 80-002/03L-0 | | | 05000317/LER-1980-002-04, /04T-0:on 800322,instantaneous Hourly Average for Condenser Temp Rise Observed in Excess of Tech Spec Limit. Caused by Operator Inattention to Temp Rise Across Condenser & Environ Conditions | /04T-0:on 800322,instantaneous Hourly Average for Condenser Temp Rise Observed in Excess of Tech Spec Limit. Caused by Operator Inattention to Temp Rise Across Condenser & Environ Conditions | | | 05000317/LER-1980-002, Forwards LER 80-002/04T-0 | Forwards LER 80-002/04T-0 | | | 05000317/LER-1980-003-03, /03L-0:on 800108,during Routine Containment Air Lock Surveillance,Emergency Escape Lock Leakage Found Greater than Allowed.Caused by Excessive Leaking of Packing Glands for Doors Handwheels.Packing Tightened | /03L-0:on 800108,during Routine Containment Air Lock Surveillance,Emergency Escape Lock Leakage Found Greater than Allowed.Caused by Excessive Leaking of Packing Glands for Doors Handwheels.Packing Tightened | | | 05000317/LER-1980-003, Forwards LER 80-003/03L-0 | Forwards LER 80-003/03L-0 | | | 05000318/LER-1980-003-03, /03L-0:on 800110,repairs to Number 21 Diesel Generator Jacket Coolant Sys Required Diesel Be Out of Svc. Caused by Leaking Gasket on Jacket Cooling Water Discharge Header.Leak Located & Repaired | /03L-0:on 800110,repairs to Number 21 Diesel Generator Jacket Coolant Sys Required Diesel Be Out of Svc. Caused by Leaking Gasket on Jacket Cooling Water Discharge Header.Leak Located & Repaired | | | 05000318/LER-1980-003, Forwards LER 80-003/03L-0 | Forwards LER 80-003/03L-0 | | | 05000317/LER-1980-004, Forwards LER 80-004/03L-0 | Forwards LER 80-004/03L-0 | | | 05000317/LER-1980-004-03, /03L-0:on 800110,low Flow Alarm Received for Containment Particulate & Gaseous Radiation Monitor Sys. Caused by Gasket Leakage at Particulate Detector Sample Psig.Gaskets Replaced & Flow Restored to Normal | /03L-0:on 800110,low Flow Alarm Received for Containment Particulate & Gaseous Radiation Monitor Sys. Caused by Gasket Leakage at Particulate Detector Sample Psig.Gaskets Replaced & Flow Restored to Normal | | | 05000318/LER-1980-004-03, /03L-0:on 800121,during Steady State Operation, Received Indication of Several Spurious Loss of Load Trips on Channel B.Cause of Event Unknown.Troubleshooting Revealed Electrical Noise on Input Leads | /03L-0:on 800121,during Steady State Operation, Received Indication of Several Spurious Loss of Load Trips on Channel B.Cause of Event Unknown.Troubleshooting Revealed Electrical Noise on Input Leads | | | 05000318/LER-1980-004, Forwards LER 80-004/03L-0 | Forwards LER 80-004/03L-0 | | | 05000318/LER-1980-005, Forwards LER 80-005/03L-0 | Forwards LER 80-005/03L-0 | | | 05000318/LER-1980-005-03, /03L-0:on 800122,five Channel B Trip Units Were Bypassed Due to Spurious High Power Levels.Caused by Noise from Excore Nuclear Instrument Upper Subchannel Detector. Troubleshooting Planned for Next Cold Shutdown | /03L-0:on 800122,five Channel B Trip Units Were Bypassed Due to Spurious High Power Levels.Caused by Noise from Excore Nuclear Instrument Upper Subchannel Detector. Troubleshooting Planned for Next Cold Shutdown | | | 05000317/LER-1980-005, Forwards LER 80-005/03L-0 | Forwards LER 80-005/03L-0 | | | 05000317/LER-1980-005-03, /03L-0:on 800325,during Normal Operation,Control Room Air Conditioning Unit 12 Tripped.Caused by Failure of Diaphragm on Unipressure Valve.Valve Replaced & Unit Returned to Svc | /03L-0:on 800325,during Normal Operation,Control Room Air Conditioning Unit 12 Tripped.Caused by Failure of Diaphragm on Unipressure Valve.Valve Replaced & Unit Returned to Svc | | | 05000317/LER-1980-006, Forwards LER 80-006/03L-0 | Forwards LER 80-006/03L-0 | | | 05000317/LER-1980-006-03, /03L-0:on 800103,while Performing Routine Surveillance Test,Control Element Assembly 60 Was Dropped Into Core.Cause Unknown.All Parameters Found Normal & No Problems Encountered.No Further Action Anticipated | /03L-0:on 800103,while Performing Routine Surveillance Test,Control Element Assembly 60 Was Dropped Into Core.Cause Unknown.All Parameters Found Normal & No Problems Encountered.No Further Action Anticipated | | | 05000318/LER-1980-006, Forwards LER 80-006/03L-0 | Forwards LER 80-006/03L-0 | | | 05000318/LER-1980-006-03, /03L-0:on 800126,during Steady State Operation, Reactor Protective Sys Channel a High Power,Low Flow,Axial Flux Offset & Thermal Margin/Low Pressure Trip Units Bypassed for Corrective Maint.Meter Input Jacks Cleaned | /03L-0:on 800126,during Steady State Operation, Reactor Protective Sys Channel a High Power,Low Flow,Axial Flux Offset & Thermal Margin/Low Pressure Trip Units Bypassed for Corrective Maint.Meter Input Jacks Cleaned | | | 05000317/LER-1980-007-01, /01X-0:on 800129,while Conducting Core Flush, Emergency Relief Valve RC-404 Opened.Apparently Caused by High Pressure Signal from Overpressure in Protection Circuit.Valve Shut W/Manual Override | /01X-0:on 800129,while Conducting Core Flush, Emergency Relief Valve RC-404 Opened.Apparently Caused by High Pressure Signal from Overpressure in Protection Circuit.Valve Shut W/Manual Override | | | 05000318/LER-1980-007, Forwards LER 80-007/03L-0 | Forwards LER 80-007/03L-0 | | | 05000318/LER-1980-007-03, /03L-0:on 800130,while Performing Routine Surveillance Testing,Discovered Control Element Assembly 54 Would Not Drive Down Electrically.Cause Not Known.Rod Became Operable During Investigation of Rod Circuitry | /03L-0:on 800130,while Performing Routine Surveillance Testing,Discovered Control Element Assembly 54 Would Not Drive Down Electrically.Cause Not Known.Rod Became Operable During Investigation of Rod Circuitry | | | 05000317/LER-1980-007, Forwards LER 80-007/01T-0 | Forwards LER 80-007/01T-0 | | | 05000317/LER-1980-008, Forwards LER 80-008/03L-0 | Forwards LER 80-008/03L-0 | | | 05000317/LER-1980-008-03, /03L-0:on 800126,while Cooling Down for Scheduled Outage,Survey Technician Discovered Steam Blowing from 11A Reactor Coolant Pump.Sensing Line lPDT-123A Had through-wall Leak.Caused by Friction of Sensing Line W/Another Pipe | /03L-0:on 800126,while Cooling Down for Scheduled Outage,Survey Technician Discovered Steam Blowing from 11A Reactor Coolant Pump.Sensing Line lPDT-123A Had through-wall Leak.Caused by Friction of Sensing Line W/Another Pipe | | | 05000318/LER-1980-008-03, /03L-0:on 800125,containment Spray Header 22 Was Isolated.Caused by Need to Repair Shutdown Heat Exchanger Inlet Cross Connect Valve.New Packing Installed | /03L-0:on 800125,containment Spray Header 22 Was Isolated.Caused by Need to Repair Shutdown Heat Exchanger Inlet Cross Connect Valve.New Packing Installed | | | 05000318/LER-1980-008, Forwards LER 80-008/03L-0 | Forwards LER 80-008/03L-0 | | | 05000318/LER-1980-009-03, /03L-0:on 800131,while Conducting Routine Test, Control Element Assembly (CEA) 32 Dropped Into Core.Cause Unknown.Technician Will Be Assigned During Next STP 0-29 to Monitor Operating Parameters of All CEAs on real-time Basi | /03L-0:on 800131,while Conducting Routine Test, Control Element Assembly (CEA) 32 Dropped Into Core.Cause Unknown.Technician Will Be Assigned During Next STP 0-29 to Monitor Operating Parameters of All CEAs on real-time Basis | | | 05000318/LER-1980-009, Forwards LER 80-009/03L-0 | Forwards LER 80-009/03L-0 | | | 05000317/LER-1980-009, Forwards LER 80-009/03L-0 | Forwards LER 80-009/03L-0 | | | 05000317/LER-1980-009-03, /03L-0:on 800201,during Surveillance Testing, Discovered Hose for One of Two Containment Elevator Hose Stations Missing.Caused by Work Group Using Fire Sys for Cleaning Purposes on Elevation of Containment | /03L-0:on 800201,during Surveillance Testing, Discovered Hose for One of Two Containment Elevator Hose Stations Missing.Caused by Work Group Using Fire Sys for Cleaning Purposes on Elevation of Containment | | | 05000318/LER-1980-010, Forwards LER 80-010/03L-0 | Forwards LER 80-010/03L-0 | | | 05000318/LER-1980-010-03, /03L-0:on 800224,during Surveillance Testing, Control Element Assemblies 31 & 34 Dropped Into Core.Caused by Fault in Timer Module.Module Replaced | /03L-0:on 800224,during Surveillance Testing, Control Element Assemblies 31 & 34 Dropped Into Core.Caused by Fault in Timer Module.Module Replaced | | | 05000318/LER-1980-011, Forwards Updated LER 80-011/01X-1 | Forwards Updated LER 80-011/01X-1 | | | 05000318/LER-1980-011-01, Diesel Generator 21 Failed to Achieve 10-s Rated Speed,Rendering Low Pressure Safety Injection Pump 22 Inoperable.Caused by Slow Response of Diesel Generator Governor.Governor Replaced | Diesel Generator 21 Failed to Achieve 10-s Rated Speed,Rendering Low Pressure Safety Injection Pump 22 Inoperable.Caused by Slow Response of Diesel Generator Governor.Governor Replaced | | | 05000317/LER-1980-011-03, W/Rcs at 130 Degrees & 250 Psia,Shutdown Cooling Suction Header Relief Lifted & Failed to Reset.Caused by Personnel Error.Valve Reset | W/Rcs at 130 Degrees & 250 Psia,Shutdown Cooling Suction Header Relief Lifted & Failed to Reset.Caused by Personnel Error.Valve Reset | | | 05000317/LER-1980-011, Forwards Updated LER 80-011/03X-1 | Forwards Updated LER 80-011/03X-1 | | | 05000317/LER-1980-012, Forwards LER 80-012/03L-0 | Forwards LER 80-012/03L-0 | | | 05000317/LER-1980-012-03, /03L-0:on 800211,while Performing Routine Surveillance Test,Control Element Assembly (CEA) 35 Dropped Into Core.Cause Unknown.Technician Will Be Assigned to Monitor Operating Parameter of All CEAs During Next STP | /03L-0:on 800211,while Performing Routine Surveillance Test,Control Element Assembly (CEA) 35 Dropped Into Core.Cause Unknown.Technician Will Be Assigned to Monitor Operating Parameter of All CEAs During Next STP | | | 05000318/LER-1980-012-03, /03L-0:on 800219,during Routine Surveillance,Small Leak Discovered on Charging Pump Common Suction Header Relief Valve.Caused by Vibration Induced Metal Fatigue in heat-affected Zone of Welded Penetration in Header | /03L-0:on 800219,during Routine Surveillance,Small Leak Discovered on Charging Pump Common Suction Header Relief Valve.Caused by Vibration Induced Metal Fatigue in heat-affected Zone of Welded Penetration in Header | | | 05000318/LER-1980-012, Forwards LER 80-012/03L-0 | Forwards LER 80-012/03L-0 | | | 05000318/LER-1980-013-03, /03L-0:on 800303,channel Zf Pressure Input Signal for Steam Generator Isolation 22 Was Bypassed.Caused by Signal Isolater 2-E/E-1023C Being Out of Calibr Due to Nonlinear Response | /03L-0:on 800303,channel Zf Pressure Input Signal for Steam Generator Isolation 22 Was Bypassed.Caused by Signal Isolater 2-E/E-1023C Being Out of Calibr Due to Nonlinear Response | | | 05000318/LER-1980-013, Forwards LER 80-013/03L-0 | Forwards LER 80-013/03L-0 | | | 05000317/LER-1980-013-03, During Surveillance Test, Channel D Containment High Pressure Setpoint Less Conservative than Tech Specs.Caused by Failed Signal Isolator 1-E/E-5313D.Instrument Returned for Repair | During Surveillance Test, Channel D Containment High Pressure Setpoint Less Conservative than Tech Specs.Caused by Failed Signal Isolator 1-E/E-5313D.Instrument Returned for Repair | | | 05000317/LER-1980-013, Forwards Updated LER 80-013/03X-1 | Forwards Updated LER 80-013/03X-1 | |
|