LER-1980-033, /01T-0:on 800425,determined from Bechtel Study That Bleed Rate for 12 Hydraulic Snubbers Would Be Insufficient to Permit Thermal Growth of Piping During Transient Concurrent W/Locked Snubber |
| Event date: |
|
|---|
| Report date: |
|
|---|
| 3461980033R01 - NRC Website |
|
text
_
(7 77)
"S"'""""'"'""'
O.
s o osi sos'>t CONTROL BLOCK: l l
l l
l l
lh (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 8 8
6 l0 lIl lD lB lS l1 l@l0 l0 l0 l0 l0 l0. l0 l0 l0 l0 l0 l@l 4 l 1l 1l 1l 1l@l l
l@
o i 7
8 9 LICENSEE CODE 14 15 LICENSE NuvuEH 23 26 LICENSE TYPE J0 5 7 CA T Sd CON'T loltl
,"gy lL l@l0 l 5 l0 l-l0 l3 l4 l6 @l0 l4 l2 l5 l8 l0 l@l0 l 5 l 0 l 6 l 8 l 0 l@
7 8
60 61 OOCKET NUY8ER 68 63 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h fiiTTl l(NP-32-80-07) on 4/25/80 Toledo Edison determined it had an immediately reportabic l
g l finding based on a study conducted by Bechtel Associates in response to LER NP-32-79-07 j o l4 l lwhich concerned hydraulic snubber deficiencies. The study showed that for 12 snubbersl g o l s j lthe bleed rate would be insuf ficient to permit thermal growth of the piping during a l
l o is l ltransient concurrent with a locked snubber. There was no danger to the public or sta-l lo l 71 [ tion personnel.
Only under extremely improbable conditions would the snubbers have l
l o l R I l been called upon to function as described.
1 80 7
8 9 DE CODE SU8C E COMPONENT CODE SUSCODE SU E
lX lX l@
@ l S l U l P l 0 l R l T l@ lD l@ lZ J @
O 9 7
8 9
10 11 12 13 18 19 20_
SEQUENTI AL OCCURRENCE REPORT REVISION
,.EVENTYEAR REPORT NO.
CODE TYPE N O.
b "LE R;RO l248l0l l-l 10 l 3l 3l y
1011 l l Tl l-l
[ 0_J nug E
22 23 24 26 27 28 29 30 31 32 K N A T ON O PLANT H
HOURS 22 SB IT FoR bb8.
SUPPLIE MAN F CTUHER lE_.l@l Z l@
l Z@
l Z l@
l0l0l0l l
W@
l N l@
l A lg l I l 2 l 0 l 7 lg 33 J4 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h li l 0 l lThe original acceptance value for a bleed rate of 4 1"/ minute was from the manufacturi-ler's recommendations. The architect / engineer math model requires the bleed rate to be l i i
- between 6-10" per minute. The bleed rates for all the remaining snubbers have l
,, lbeen reviewed and found to be conservative.
The 12 snubbers will be reset during the l l current refueling outage under Maintenance Work Order 80-2110.
l i 4 7
8 9 80 ST S
% POWER oTHER STATUS IS O RY DISCOVERY CESCRIPTION y@ l 0 l 0 l 01@l NA l
l D l@l Notification From Bechtel l
i s ACTIVITY CO TENT RELE ASE@D OF RELEASE @l NA l
l NA l
AMOUNT OF ACTIVITY LOCATION OF RELEASE lZ l i 6 7
8 9 10 11 44 45 80 PERSONNEL EXPOSURES NUM8ER TYPE DESCHIPTION l 0 l 0 10 l@lZ l@l NA l
i 7 PERSONNEL INJUP ES DESCRIPTION @
NUMBER 10 l 0 10 l@l NA l
i a 7
8 9 11 12 80 LOSS oF OR DAMAGE TO FACILITY TYPE DE SCRIPTION lZ l@l NA l
i 9 7
8 9 10 80 ESCRIPTION ISSUEf@t llL NA l
lllllllllllll5 2 o 1
8 9 to 68 69 80 %
419-259-5000, Ext. 239 g DVR 80-075 Stephen M. QuennoZ PHONE:
NAME OF PREPARER
[
TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION UNIT ONC SUPPLEMENTAL INFORMATION FOR LER NP-32-80-07 DATE OF EVENT: April 25, 1980 FACILITY: Davis-Besse Unit 1 IDENTIFICATION OF OCCURRENCE:
Hydraulic Snubber Deficiency Conditions Prior to Occurrence: The unit was in Mode 6, with Power (MRT) = 0 and Load (Gross MWE) = 0.
Description of Occurrence: As a part of the corrective action described in Licensee Event Report NP-32-79-07 concerning hydraulic snubber deficiencies, the architect /
engineer conducted a study to determine realistic requirements for hot and cold pis-ton settings, and lockup and bleed rates. As expected, it was determined that for most snubbers the original tolerances were unnecessarily restrictive, and could be relaxed without impairing clant safety.
However, during this review, some uncertainties appeared regarding snubber bleed rates.
Subsequent investigation, including discussions with the snubber uanufacturer, showed that for 12 snubbers the as-installed bleed rate would be insufficient to permit ade-quate thermal growth of the piping during a transient concurrent with a locked snubber.
If the snubber were to lock up due to a seismic event which would cause or result in a l.':
concurrent event where a pressurizer relief valve lif ted (either code safety or elec-tromatic) or where auxiliary feedwater turbine 1-1 was started, the affected snubbers i
would have impeded the thermal expansion resulting from the steam flow in the associated piping.
of the stresses involved. Resultant failure of the piping system was thus assumed without further ana Designation of Apparent Cause of Occurrence: As a result of combining a seismic event with either of the upset conditions described above, the bleed rates previously set were not adequate to allow unrestricted growth of the piping.
The setting for bleed rate of 4 i 1 inches per minute was from the manufacturer's recommendations.
The architect /
engineer math model requires the bleed rate to be between 6-10 inches per minute.
The bleed rates for all the remaining snubbers have been reviewed and found to be conserva-tive.
Analysis of Occurrence:
There was no danger to the health and safety of the public or I
to station personnel.
The insufficient bleed rate of the hydraulic snubbers could have prevented the fulfillment of the functional requirements of systems required to i
ecpe with accidents analyzed in the Final Safety Analysis Report and therefore is a rsportable occurrence per Technical Specification 6.9.1.8.f.
Only under extremely improbable conditions would the snubbers have been called upon to function as des'cribed.
LER 680-033 w
- TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION UNIT ONE SUPPLEMENTAL INFORE\\ TION FOR LER NP-32-80-07 PAGE 2
Corrective Action
The 12 snubbers of concern will be reset during the current refueling shutdown and prior to restart of the unit.
Failure Data: There have been no known previous occurrences of non-conservative snuhbor settings.
LER #80-033 e
|
|---|
|
|
| | | Reporting criterion |
|---|
| 05000346/LER-1980-001, Forwards LER 80-001/01T-0 | Forwards LER 80-001/01T-0 | | | 05000346/LER-1980-001-01, /01T-0:on 800103,during Plant Heatup,Safety Features Actuation Sys Channels 1 & 3 Tripped at 1,600 Psig, Causing Level 2 Actuation.Operators Correctly Tripped Reactor Coolant Pumps.Caused by Procedural Deficiency | /01T-0:on 800103,during Plant Heatup,Safety Features Actuation Sys Channels 1 & 3 Tripped at 1,600 Psig, Causing Level 2 Actuation.Operators Correctly Tripped Reactor Coolant Pumps.Caused by Procedural Deficiency | | | 05000346/LER-1980-002, Forwards LER 80-002/03L-0 | Forwards LER 80-002/03L-0 | | | 05000346/LER-1980-002-03, /03L-0:on 800103,after Actuating of Safety Features Actuation Sys Level 2,demin Water Valve DW68318 Did Not Indicate Closed & Monitor Light Did Not Indicate Properly.Caused by Maladjusted Position Indicator Switch | /03L-0:on 800103,after Actuating of Safety Features Actuation Sys Level 2,demin Water Valve DW68318 Did Not Indicate Closed & Monitor Light Did Not Indicate Properly.Caused by Maladjusted Position Indicator Switch | | | 05000346/LER-1980-003-03, /03L-0:on 800103,during Auxiliary Feedwater Pump Test,Pump l-1 Was Declared Inoperable.Caused by Improperly Adjusted Slip Clutch Between Governor Manual Speed Adjustment Shaft & Remotely Controlled Speed Changer Motion | /03L-0:on 800103,during Auxiliary Feedwater Pump Test,Pump l-1 Was Declared Inoperable.Caused by Improperly Adjusted Slip Clutch Between Governor Manual Speed Adjustment Shaft & Remotely Controlled Speed Changer Motion | | | 05000346/LER-1980-003, Forwards LER 80-003/03L-0 | Forwards LER 80-003/03L-0 | | | 05000346/LER-1980-004-03, /03L-0:on 800107,control Rod 5-11 Absolute Position Indication Declared Inoperable Due to Fluctuating Signals.Possibly Caused by Isolation of Position Indication Cabling & Electrical Penetration | /03L-0:on 800107,control Rod 5-11 Absolute Position Indication Declared Inoperable Due to Fluctuating Signals.Possibly Caused by Isolation of Position Indication Cabling & Electrical Penetration | | | 05000346/LER-1980-004, Forwards LER 80-004/03L-0 | Forwards LER 80-004/03L-0 | | | 05000346/LER-1980-005, Forwards LER 80-005/03L-0 | Forwards LER 80-005/03L-0 | | | 05000346/LER-1980-005-03, /03L-0:on 800110,Tech Spec Late Date Passed W/O Performance of Boric Acid Flowpath Heat Tracing Weekly Test. Caused by Known Deficiency in Design of Sys Resulting in Inability to Maintain Min Temp Necessary During Startup | /03L-0:on 800110,Tech Spec Late Date Passed W/O Performance of Boric Acid Flowpath Heat Tracing Weekly Test. Caused by Known Deficiency in Design of Sys Resulting in Inability to Maintain Min Temp Necessary During Startup | | | 05000346/LER-1980-006-03, /03L-0:on 800112,found Fiberglass Insulation Stuffed Into Open Wall Ventilator Between Water Treatment Bldg & Svc Water Valve Room,Causing Fire Damper to Be Inoperable.Figerglass Removed | /03L-0:on 800112,found Fiberglass Insulation Stuffed Into Open Wall Ventilator Between Water Treatment Bldg & Svc Water Valve Room,Causing Fire Damper to Be Inoperable.Figerglass Removed | | | 05000346/LER-1980-006, Forwards LER 80-006/03L-0 | Forwards LER 80-006/03L-0 | | | 05000346/LER-1980-007, Forwards LER 80-007/03L-0 | Forwards LER 80-007/03L-0 | | | 05000346/LER-1980-007-03, /03L-0:on 800116,ref Position Verification for Group 5,rod 11,was Made 1-h & 40 Minutes Late.Caused by Operator Oversight Due to Lack of Adequate Reminder Sys. Multiple Timer Sys Will Prevent Recurrence | /03L-0:on 800116,ref Position Verification for Group 5,rod 11,was Made 1-h & 40 Minutes Late.Caused by Operator Oversight Due to Lack of Adequate Reminder Sys. Multiple Timer Sys Will Prevent Recurrence | | | 05000346/LER-1980-008-03, Gap Discovered in Wall Where Five two-inch Conduits Go from Electrical Penetration Room 2 to Cable room.Six-inch Gap Around Ventilation Duct Also Found.Caused by Improper Initial Installation | Gap Discovered in Wall Where Five two-inch Conduits Go from Electrical Penetration Room 2 to Cable room.Six-inch Gap Around Ventilation Duct Also Found.Caused by Improper Initial Installation | | | 05000346/LER-1980-008, Forwards Revised LER 80-008/03L-1 | Forwards Revised LER 80-008/03L-1 | | | 05000346/LER-1980-009, Forwards LER 80-009/03L-0 | Forwards LER 80-009/03L-0 | | | 05000346/LER-1980-009-03, /03L-0:on 800122,discovered That NI-7 Indication on Computer Group 38 Was Reading Less than Heat Balance Power,Putting NI-7 Below Instrumentation Operability Limit Line.Caused by Extremely Tight Calibr Band at 100% Power | /03L-0:on 800122,discovered That NI-7 Indication on Computer Group 38 Was Reading Less than Heat Balance Power,Putting NI-7 Below Instrumentation Operability Limit Line.Caused by Extremely Tight Calibr Band at 100% Power | | | 05000346/LER-1980-010-01, /01T-0:on 800214,reanalysis of RCS Pipe Restraints Per IE Insp Rept 50-346/79-23 Revealed Design Deficiency on Two Reactor Coolant Hot Leg Pipe Whip Restraints at Top of Each RCS Hot Leg.Caused by Design Error | /01T-0:on 800214,reanalysis of RCS Pipe Restraints Per IE Insp Rept 50-346/79-23 Revealed Design Deficiency on Two Reactor Coolant Hot Leg Pipe Whip Restraints at Top of Each RCS Hot Leg.Caused by Design Error | | | 05000346/LER-1980-010, Forwards LER 80-010/01T-0 | Forwards LER 80-010/01T-0 | | | 05000346/LER-1980-011, Forwards LER 80-011/03L-0 | Forwards LER 80-011/03L-0 | | | 05000346/LER-1980-011-03, /03L-0:on 800131,during Normal Operation, Operations Personnel Received Half Trip on Steam & Feedwater Rupture Control Sys Channels 1/3.Caused by Spurious Trip from +25 Volt Dc Power Supply PS03 in Sglic Channel 1 | /03L-0:on 800131,during Normal Operation, Operations Personnel Received Half Trip on Steam & Feedwater Rupture Control Sys Channels 1/3.Caused by Spurious Trip from +25 Volt Dc Power Supply PS03 in Sglic Channel 1 | | | 05000346/LER-1980-012-03, /03L-0:on 800201,operator Noticed Loss of Control Room Position Indication for Letdown Cooler Isolation Valve MU2A.Caused by Design Deficiency.Apparently,Someone Brushed Up Against Disconnect Breaker Switch.Switch Reposition | /03L-0:on 800201,operator Noticed Loss of Control Room Position Indication for Letdown Cooler Isolation Valve MU2A.Caused by Design Deficiency.Apparently,Someone Brushed Up Against Disconnect Breaker Switch.Switch Repositioned | | | 05000346/LER-1980-012, Forwards LER 80-012/03L-0 | Forwards LER 80-012/03L-0 | | | 05000346/LER-1980-013, Forwards LER 80-013/03L-0 | Forwards LER 80-013/03L-0 | | | 05000346/LER-1980-013-03, /03L-0:on 800208,w/reactor Startup in Progress, Personnel Noted Control Rod 5-11 Absolute Position Indication Was Not Responding.Caused by Blown Fuse F14 in Position Ref Panel | /03L-0:on 800208,w/reactor Startup in Progress, Personnel Noted Control Rod 5-11 Absolute Position Indication Was Not Responding.Caused by Blown Fuse F14 in Position Ref Panel | | | 05000346/LER-1980-014, Forwards LER 80-014/03L-0 | Forwards LER 80-014/03L-0 | | | 05000346/LER-1980-014-03, /03L-0:on 800208,pressurizer Sample Sys Containment Isolation Valve RC240B Failed to Close Twice. Caused by Improper Torque Switch Setting & Stripped Screw on Closing Contactor.Settings Readjusted & Switch Replaced | /03L-0:on 800208,pressurizer Sample Sys Containment Isolation Valve RC240B Failed to Close Twice. Caused by Improper Torque Switch Setting & Stripped Screw on Closing Contactor.Settings Readjusted & Switch Replaced | | | 05000346/LER-1980-015, Forwards LER 80-015/03L-0 | Forwards LER 80-015/03L-0 | | | 05000346/LER-1980-015-03, /03L-0:on 800210,during Normal Startup,Control Rod 5-11 Absolute Position Indication Declared Inoperable.Caused by Numerous Asymmetric Rod Alarms.Data from Current Failure Evaluated | /03L-0:on 800210,during Normal Startup,Control Rod 5-11 Absolute Position Indication Declared Inoperable.Caused by Numerous Asymmetric Rod Alarms.Data from Current Failure Evaluated | | | 05000346/LER-1980-016, Forwards LER 80-016/03L-0 | Forwards LER 80-016/03L-0 | | | 05000346/LER-1980-016-03, /03L-0:on 800213,while Reviewing Station Log,Shift Foreman Discovered That Containment Airlock Seal Leakage Test Had Not Been Performed After Last Entry Into Containment During Startup.Caused by Procedural Inadequacy | /03L-0:on 800213,while Reviewing Station Log,Shift Foreman Discovered That Containment Airlock Seal Leakage Test Had Not Been Performed After Last Entry Into Containment During Startup.Caused by Procedural Inadequacy | | | 05000346/LER-1980-017-03, /03L-0:on 800217,operations Personnel Noted That Safety Features Actuation Sys Channel 3 Borated Water Storage Tank Level Indication Was Six Feet Higher than Other Meters.Caused by Freezing of Transmitter Sensing Line | /03L-0:on 800217,operations Personnel Noted That Safety Features Actuation Sys Channel 3 Borated Water Storage Tank Level Indication Was Six Feet Higher than Other Meters.Caused by Freezing of Transmitter Sensing Line | | | 05000346/LER-1980-017, Forwards LER 80-017/03L-0 | Forwards LER 80-017/03L-0 | | | 05000346/LER-1980-018-03, /03L-0:on 800226,safety Features Actuation Sys Channel 3 Borated Water Storatge Tank Level Indication Was Discovered Reading Four Feet Higher than Other Three Channels.Caused by Inadequate Design of Freeze Protection | /03L-0:on 800226,safety Features Actuation Sys Channel 3 Borated Water Storatge Tank Level Indication Was Discovered Reading Four Feet Higher than Other Three Channels.Caused by Inadequate Design of Freeze Protection | | | 05000346/LER-1980-018, Forwards LER 80-018/03L-0 | Forwards LER 80-018/03L-0 | | | 05000346/LER-1980-019, Forwards LER 80-019/01T-0 | Forwards LER 80-019/01T-0 | | | 05000346/LER-1980-019-01, /01T-0:on 800325 Reactor Flux/Flow Trip Setpoints Were Not Verified to Be Properly Reset within 4-h of Manual Shutdown of Rcp.Caused by Attention Given to Feedwater Swings.Trip Setpoints Verified Later | /01T-0:on 800325 Reactor Flux/Flow Trip Setpoints Were Not Verified to Be Properly Reset within 4-h of Manual Shutdown of Rcp.Caused by Attention Given to Feedwater Swings.Trip Setpoints Verified Later | | | 05000346/LER-1980-020, Forwards LER 80-020/03L-0 | Forwards LER 80-020/03L-0 | | | 05000346/LER-1980-020-03, /03L-0:on 800306,control Operator Noted No Control Room Indication for Containment Vacuum Relief Isolation Valve CV5072.Caused by Breaker BE1139 Being Closed,Probably Resulting from Someone Bumping Into Breaker | /03L-0:on 800306,control Operator Noted No Control Room Indication for Containment Vacuum Relief Isolation Valve CV5072.Caused by Breaker BE1139 Being Closed,Probably Resulting from Someone Bumping Into Breaker | | | 05000346/LER-1980-021, Forwards LER 80-021/03L-0 | Forwards LER 80-021/03L-0 | | | 05000346/LER-1980-021-03, /03L-0:on 800313,during Diesel Fire Protection Pump Weekly Test,Pump Could Not Be Stopped W/Control Button. Once Stopped,Pump Could Not Be Started.Cause Not Determined by Scheme Check.Retrial of Pump Proved Successful | /03L-0:on 800313,during Diesel Fire Protection Pump Weekly Test,Pump Could Not Be Stopped W/Control Button. Once Stopped,Pump Could Not Be Started.Cause Not Determined by Scheme Check.Retrial of Pump Proved Successful | | | 05000346/LER-1980-022-03, /03L-0:on 800317,operations Personnel Noticed Loss of Control Room Indication for Containment Dihydrogen Analyzer 2 Discharge Line Valve CV5010E.Caused by Const Personnel Accidentally Opening Breaker | /03L-0:on 800317,operations Personnel Noticed Loss of Control Room Indication for Containment Dihydrogen Analyzer 2 Discharge Line Valve CV5010E.Caused by Const Personnel Accidentally Opening Breaker | | | 05000346/LER-1980-022, Forwards LER 80-022/03L-0 | Forwards LER 80-022/03L-0 | | | 05000346/LER-1980-023, Forwards LER 80-023/03L-0 | Forwards LER 80-023/03L-0 | | | 05000346/LER-1980-023-03, /03L-0:on 800327,discovered That Control Rod Groups 3 & 4 Were Moving in on Their Own.Group 3 Was 0% Withdrawn.Group 4 Was 90% Withdrawn.Caused by Component Failure.Component Replaced | /03L-0:on 800327,discovered That Control Rod Groups 3 & 4 Were Moving in on Their Own.Group 3 Was 0% Withdrawn.Group 4 Was 90% Withdrawn.Caused by Component Failure.Component Replaced | | | 05000346/LER-1980-024-03, /03L-0:on 800327,following Normally Initiated Reactor Trip,Auxiliary Feed Pump Turbine 1-2 Main Steam Isolation Valve MS-107 Closed.Cause Unknown.Further Investigation of Valve & Operator Will Be Pursued | /03L-0:on 800327,following Normally Initiated Reactor Trip,Auxiliary Feed Pump Turbine 1-2 Main Steam Isolation Valve MS-107 Closed.Cause Unknown.Further Investigation of Valve & Operator Will Be Pursued | | | 05000346/LER-1980-024, Forwards LER 80-024/03L-0 | Forwards LER 80-024/03L-0 | | | 05000346/LER-1980-025-03, /03X-1:on 800330,control Rod Group 5,rod 11 Absolute Position Indication Declared Inoperable.Caused by Fluctuating Signals Resulting in Numerous Asymmetric Rod Alarms Due to Defective Reed Switch Assemblies | /03X-1:on 800330,control Rod Group 5,rod 11 Absolute Position Indication Declared Inoperable.Caused by Fluctuating Signals Resulting in Numerous Asymmetric Rod Alarms Due to Defective Reed Switch Assemblies | | | 05000346/LER-1980-025, Forwards LER 80-025/03X-1 | Forwards LER 80-025/03X-1 | |
|