LER-1979-024, /03L-0:on 790724,pressure Suppression Chamber Reactor Bldg Vacuum Breaker Pressure Switch Was Found to Actuate Below Limiting Condition for Operation Level.Caused by Instrument Setpoint Drift.Switch Recalibr |
| Event date: |
|
|---|
| Report date: |
|
|---|
| 2541979024R03 - NRC Website |
|
text
N RC F CA M 366f U. S. NUCLEAR REGULATORY COMMIS5 ton (7 77)
LICENSEE EVENT REPORT CONTROL 8 LOCK: l l
l l
l l
l (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) i 6
lo lil l1 l Lj Ql A j Dl 1 l@l 0 l 0 l 0 l - l 0 l 0 0 l-l0 [0 l0 [g 4 1l1l1 1 l@l l
[g 7
8 9 LICENSEE CODE 14 15 LICENSE NUMBER 25 26 LICENSE TvPE JO
$7 CAT $8 CCN'T SDiCE I L l@l 01 5 0 l 010 l 2 l 5 l 0 @l Ol 7 21 4 71 9 @l 0 l 8 l 1 l 0 l 71jtj@
o i
8 60 61 00CKET NUMBER 68 63 EVENT DATE 74 75 REPCRT CATE 83 EVENT DESCRIPTION AND PROBA8LE CONSECUENCES h O
2 l While performing the Pressure Suppression Chamber Reactor Building Vacuum Breaker l
g Actuation Calibration and Functional Test, procedure QlS 48-1, pressure switch l
o 3
o 4
l PS 1-16228 was found to actuate at 0.61 psid. This was less conservative than the l
0.5 psid LCO established in T.S.3.7.A.3 The redundant pressure switch, PS 1-1622A, l
o s
l was found to actuate within limits and would have opened vacuum breaker A01-1601-20A l 0
6 if needed.
In addition, the vacuum breakers were at all times remotely-manually
[
o 7
operable from the control room, and the su.pression chamber pressure indicator was l
g 7
8 9 sui 6/ vrciduit.
80 SY ST E M
CAUSE
CAUSE COMP.
VA LV E COOE CODE SUBCODE COMPONENT CODE SUBCCCE SUSCOCE Sl Dj@ l El@ l E l@ l ll Nl Sl Tl Rl U j@ lS l@ l Zl@
O 9
7 8
9 to 11 12 13 18 19 20 SEQUENTI AL OCCURRENCE REPCRT REVISION LER RO EVENT YE AR REPORT NO.
COCE TYPE NO.
O aEPORT l7l9l l-l0 l2 l4 l l/l 10l3l lC l l-l l0 l
_ 25 22 23 24 6
27 28 29 30 31 32 ACTION FuTUAE EF8ECT SHUTDOWN ATT ACHM ENT NP A D-4 PRI'.*E CCVP.
COVPONENT TAKEN ACTION ON PLANT VETHOD HOURS SU6 MITT E D FORM 3UB.
SUFPLIER MANUFACTURER l Elg Z lg l35Z[@ lZl@
0 0l 0l l
l Yl@
N lg l N l@
lS 3 l 8 l 2 l@
33 J4 56 37 40 41 42 43 44 47 CAUsE DESCRIPTION AND CCARECTIVE ACTIONS i
o j The cause of this occurrence is attributed to instrument setooint drift. There was no l i ijl evidence of physical damage to the switch. Corrective action taken was to recalibrate I 7
l and functionally test pressure switch PS 1-1622B immediately.
1 3
l
[_
l i
A 7
a 9 so A
%PCWER CTHER STATUS O SCO RY OISCOVERY DESCRIPTION W @ l0l9l8l@l NA l
lB l@l Routine Test i
s ACTIVITY CONTENT RELEASED CF RELEASE AMOUNT OF ACTIVITY LOCATICN CF RELEASE lZl@
l NA l
l NA l
1 6
7 d 3 10 11 44 45 80 PERSONNEL EXDOSLRES N L P.8 8 E A TYPE C E SCRIPTIC N 10 l 010 !@lz l@L I
i 7
3 9 11
?2 13 30 DERSCNNEL NAPIES 7
5 NUYBEA OE3CR?PTICN l
l 0 l 0 l 0 l@l NA
$ 3 11 12 80 LOSS OF C A C AVAGE TO C AC:LITv Tve!
O E SC Alp T; CN l2l O
Q () q.g g 3 i
)
d 3 o
- V 33 PU e UCI TY NpC USE CNLY
?SS':E0 OESC A+PTION j 0
l l
l l
lilllll!!! !I 7
3 3 10 68 63 10* 3 PwCNE.339-654-2241 Ext. 175
?
M.
Kooi t
NAME 4 P A e p t. P n
1.
LER NUMBER: LER/R0 79-24/03L-0 11.
LICENSEE NAME: Commonwealth Edison Company Quad-Cities Nuclear Power Station Ill.
FACILITY NAME: Unit One IV.
DOCKET NUMBER: 050-254 V.
EVENT DESCRIPTION
On July 24, 1979, while performing the Pressure Suppression Chamber Reactor Building Vacuum Breaker Actuation Calibra-tion and Functional Test, procedure QTS 48-1, pressure switch PS 1-16228 was found to actuate at 0.61 psid. This is in excess of Technical Specification 3.7.A.3.a limiting condition for operation of 0.5 psid.
The immediate corrective action was to recalibrate the switch. There have been occurrences of this type on Unit One in the past, with the latest being documented by R0 78-22/03L which occurred on July 26, 1978.
VI.
PROBABLE CONSEQUENCES OF THE OCCURRENCE: The reactor building to sup-pression chamber vacuum breaker system consists of two, 100 percent flow capacity systems.
Pressure switch PS 1-1622A was found to trip within limits and would have actuated within the required differential pressure and opened vacuum breaker A0 1-1601-20A, relieving any negative pressure in the suppression chamber, had the need arose.
Pressure switch PS 1-1622B would have tripped at 0.61 psid, which is well under the 2 psid suppression chamber design external pressure. Therefore, the safety implications of this event were minimal.
In addition to this, the vccuum breakers were at all times remotely-manually operable from the Control Room, and the suppression chamber pressure indicator was fully operable.
Vll.
CAUSE
The cause of this occurrence is attributed to instrument setpoint drift.
There was no evidence of physical damage to the switch. The switch is manufactured by the Static-0-Ring Company and are of a diaphram type, model number 12NN-KK215-VX.
Vill. CORRECTIVE ACTION: The corrective action was to recalibrate and functionally test the pressure switch. This is the second instance of instrument set-point drift since these particular switches were installed on Unit One on December 13, 1977 1
(\\
(j. v; A
|
|---|
|
|
| | | Reporting criterion |
|---|
| 05000265/LER-1979-001-03, /03L-0 on 790104:during Monthly Operability Test, Inlet Air Heater on a Standby Gas Treatment Sys Was Found Inoperable.Caused by Setpoint Drift of Flow Switch 1/2-7541-8A | /03L-0 on 790104:during Monthly Operability Test, Inlet Air Heater on a Standby Gas Treatment Sys Was Found Inoperable.Caused by Setpoint Drift of Flow Switch 1/2-7541-8A | | | 05000254/LER-1979-001, Forwards LER 79-001/03L-0 | Forwards LER 79-001/03L-0 | | | 05000265/LER-1979-001, Forwards LER 79-001/03L-0 | Forwards LER 79-001/03L-0 | | | 05000254/LER-1979-001-03, /03L-0 on 790107:high Steam Line Flow Alarm & Automatic Isolation of Reactor Core Isolation Cooling Steam Supply Line Occurred.Caused by Failure of Micro Switch Inside Steam Line High Flow Differential Pressure Switch | /03L-0 on 790107:high Steam Line Flow Alarm & Automatic Isolation of Reactor Core Isolation Cooling Steam Supply Line Occurred.Caused by Failure of Micro Switch Inside Steam Line High Flow Differential Pressure Switch | | | 05000265/LER-1979-002, Forwards LER 79-002/03L-0 | Forwards LER 79-002/03L-0 | | | 05000265/LER-1979-002-03, /03L-0 on 790110:during Routine Insp of Reactor Water Cleanup Pump Rooms,Small Leak Was Found on 2-1205B Cleanup Pump Suction Line.Cause Unknown.Leak Was Isolated & Linear Indication on Flange Ground Out | /03L-0 on 790110:during Routine Insp of Reactor Water Cleanup Pump Rooms,Small Leak Was Found on 2-1205B Cleanup Pump Suction Line.Cause Unknown.Leak Was Isolated & Linear Indication on Flange Ground Out | | | 05000254/LER-1979-002-03, /03L-0 on 790110:during Freon Test,Noted That Freon Penetration Through Charcoal Absorbers Exceeded Tech Spec Max.Caused by One of Charcoal Clamping Levers Not Being Fully Latched | /03L-0 on 790110:during Freon Test,Noted That Freon Penetration Through Charcoal Absorbers Exceeded Tech Spec Max.Caused by One of Charcoal Clamping Levers Not Being Fully Latched | | | 05000254/LER-1979-002, Forwards LER 79-002/03L-0 | Forwards LER 79-002/03L-0 | | | 05000265/LER-1979-003-03, /03L-0 on 790214:during High Temp Isolation Calibr Procedure,Temp Switch TS 2-2373A Was Found to Trip in Excess of Tech Spec Limit.Caused by Setpoint Drift.Switch Recalibrated & Retested | /03L-0 on 790214:during High Temp Isolation Calibr Procedure,Temp Switch TS 2-2373A Was Found to Trip in Excess of Tech Spec Limit.Caused by Setpoint Drift.Switch Recalibrated & Retested | | | 05000254/LER-1979-003, Forwards LER 79-003/03L-0 | Forwards LER 79-003/03L-0 | | | 05000265/LER-1979-003, Forwards LER 79-003/03L-0 | Forwards LER 79-003/03L-0 | | | 05000254/LER-1979-003-03, /03L-1 on 790119:MSIV Local Leak Rate Showed Seven Valves Leaking Excessively.Causes Unspecified.Valve Stroke Adjusted,Certain Valves Dismantled,Discs & Seats Were Lapped & Machined | /03L-1 on 790119:MSIV Local Leak Rate Showed Seven Valves Leaking Excessively.Causes Unspecified.Valve Stroke Adjusted,Certain Valves Dismantled,Discs & Seats Were Lapped & Machined | | | 05000254/LER-1979-004, Forwards LER 79-004/01T-0 | Forwards LER 79-004/01T-0 | | | 05000254/LER-1979-004-01, /01T-0 on 790122:piece of Control Rod Drive Return Nozzle Thermal Sleeve Retaining Ring Was Missing.Cause Unknown | /01T-0 on 790122:piece of Control Rod Drive Return Nozzle Thermal Sleeve Retaining Ring Was Missing.Cause Unknown | | | 05000265/LER-1979-004-03, /03L-0 on 790211:suction Isolation Valve Mo 2-1001-50 Failed to Close from Control Room.Caused by Failed Circuit Breaker in Valve Motor Control Center. Valve Taken Out of Svc for Repair During Outages | /03L-0 on 790211:suction Isolation Valve Mo 2-1001-50 Failed to Close from Control Room.Caused by Failed Circuit Breaker in Valve Motor Control Center. Valve Taken Out of Svc for Repair During Outages | | | 05000265/LER-1979-004, Forwards LER 79-004/03L-0 | Forwards LER 79-004/03L-0 | | | 05000254/LER-1979-005-03, /03L-0 on 790123:during Unit 1/2 Diesel Generator Monthly Load Test Qos 6600-1,pilot Solenoid Valve to Air Starting Motors Failed & Unit 1/2 Diesel Was Shutdown. Caused by Mechanical Failure of Valve.Valve Was Replaced | /03L-0 on 790123:during Unit 1/2 Diesel Generator Monthly Load Test Qos 6600-1,pilot Solenoid Valve to Air Starting Motors Failed & Unit 1/2 Diesel Was Shutdown. Caused by Mechanical Failure of Valve.Valve Was Replaced | | | 05000254/LER-1979-005, Forwards LER 79-005/03L-0 | Forwards LER 79-005/03L-0 | | | 05000265/LER-1979-005-03, /03L-0 on 790223:2A Recirculation Motor Generator Field Breaker Opened,Causing Flow Mismatch.Caused by Loosening of Coupling Between Main Shaft & Recirculation Motor Generator Set Tachometer.Tachometer Coupling Reset | /03L-0 on 790223:2A Recirculation Motor Generator Field Breaker Opened,Causing Flow Mismatch.Caused by Loosening of Coupling Between Main Shaft & Recirculation Motor Generator Set Tachometer.Tachometer Coupling Reset | | | 05000265/LER-1979-005, Forwards LER 79-005/03L-0 | Forwards LER 79-005/03L-0 | | | 05000254/LER-1979-006-03, /03L-0 on 790125:during Primary Containment Isolation Valve Closure Timing,Valve AO 1-1601-21 Failed to Close in 10 Seconds.Caused by Improper Adjustment of Valve Speed Control from Operational Wear.Control Was Readjusted | /03L-0 on 790125:during Primary Containment Isolation Valve Closure Timing,Valve AO 1-1601-21 Failed to Close in 10 Seconds.Caused by Improper Adjustment of Valve Speed Control from Operational Wear.Control Was Readjusted | | | 05000254/LER-1979-006, Forwards LER 79-006/03L-0 | Forwards LER 79-006/03L-0 | | | 05000254/LER-1979-007, Forwards LER 79-007/03L-0 | Forwards LER 79-007/03L-0 | | | 05000254/LER-1979-007-03, /03L-0 on 790201:main Steam Line Leak Detection Temp Switches TS 1-261-16A,MTS 1-261-18A & TS 1-261-15C Tripped in Excess of Setpoint.Caused by Instrument Setpoint Drift.Temp Switches Recalibrated | /03L-0 on 790201:main Steam Line Leak Detection Temp Switches TS 1-261-16A,MTS 1-261-18A & TS 1-261-15C Tripped in Excess of Setpoint.Caused by Instrument Setpoint Drift.Temp Switches Recalibrated | | | 05000254/LER-1979-008, Forwards LER 79-008/03L-0 | Forwards LER 79-008/03L-0 | | | 05000254/LER-1979-008-03, /03L-0 on 790202:temp Switch TS-1-1360-15D Had Trip Setpoint in Excess of Tech Spec Limit.Caused by Setpoint Drift.Switch Recalibrated & Satisfactorily Tested | /03L-0 on 790202:temp Switch TS-1-1360-15D Had Trip Setpoint in Excess of Tech Spec Limit.Caused by Setpoint Drift.Switch Recalibrated & Satisfactorily Tested | | | 05000254/LER-1979-009-03, /03L-0 on 790203:bed Plate Drain Valves AO 1-4999-57,58 & 60 Did Not Fully Close.Caused by Corrosion & Failure of Internal Return Springs.Springs Replaced & Valves Satisfactorily Retested | /03L-0 on 790203:bed Plate Drain Valves AO 1-4999-57,58 & 60 Did Not Fully Close.Caused by Corrosion & Failure of Internal Return Springs.Springs Replaced & Valves Satisfactorily Retested | | | 05000254/LER-1979-009, Forwards LER 79-009/03L-0 | Forwards LER 79-009/03L-0 | | | 05000265/LER-1979-009, Forwards LER 79-009/03L-0.Corrects Docket Number of Original Forwarding Ltr | Forwards LER 79-009/03L-0.Corrects Docket Number of Original Forwarding Ltr | | | 05000265/LER-1979-009-03, /03L-0:on 790429,switch Trip Positions Found at Greater than 10% of MSIV Closure.Caused by Failure to Set Field Calibr for Switch Trip Point Limit.Switches Were Adjusted to 10% Closure or Less | /03L-0:on 790429,switch Trip Positions Found at Greater than 10% of MSIV Closure.Caused by Failure to Set Field Calibr for Switch Trip Point Limit.Switches Were Adjusted to 10% Closure or Less | | | 05000254/LER-1979-010-03, /03L-1 on 790205:diesel Fire Pump 1/2A Out of Svc Beyond Tech Spec Limit.Caused by Personnel Error.Pump Returned to Svc | /03L-1 on 790205:diesel Fire Pump 1/2A Out of Svc Beyond Tech Spec Limit.Caused by Personnel Error.Pump Returned to Svc | | | 05000254/LER-1979-010, Forwards LER 79-010/03L-1 | Forwards LER 79-010/03L-1 | | | 05000265/LER-1979-010, Forwards LER 79-010/03L-0 | Forwards LER 79-010/03L-0 | | | 05000265/LER-1979-010-03, /03L-0 on 790514:2A Fuel Pool Radiation Monitor Failed Upscale & Failed Again on 790601 & 02.Caused by Failure of GM-tube in Sensor Conventor Unit.Tube Finally Replaced W/Amperex 18529 | /03L-0 on 790514:2A Fuel Pool Radiation Monitor Failed Upscale & Failed Again on 790601 & 02.Caused by Failure of GM-tube in Sensor Conventor Unit.Tube Finally Replaced W/Amperex 18529 | | | 05000254/LER-1979-011, Forwards LER 79-011/03L-0 | Forwards LER 79-011/03L-0 | | | 05000254/LER-1979-011-03, /03L-0 on 790202:drywell Vent Valve AO 1-1601-23 Closed in Excess of Tech Spec Max Time Limit.Caused by Worn & Leaking Seals on Air Operating pistons.U-cup Piston Seals Replaced | /03L-0 on 790202:drywell Vent Valve AO 1-1601-23 Closed in Excess of Tech Spec Max Time Limit.Caused by Worn & Leaking Seals on Air Operating pistons.U-cup Piston Seals Replaced | | | 05000265/LER-1979-011, Forwards LER 79-011/03L-0 | Forwards LER 79-011/03L-0 | | | 05000265/LER-1979-011-03, /03L-0 on 790521:three Cables Not Installed in Accordance W/Drawings.Caused by Error in Cable Routing During Initial Const.Reroute of Cables Will Take Place During Nov 1979 Refueling Outage | /03L-0 on 790521:three Cables Not Installed in Accordance W/Drawings.Caused by Error in Cable Routing During Initial Const.Reroute of Cables Will Take Place During Nov 1979 Refueling Outage | | | 05000265/LER-1979-012-03, /03L-0 on 790622:nut Inadvertantly Droppoed Into Diesel Generator Winding During Preventive Maint.Outage Time of Generator Extended 20 Minutes Beyond 1.5-h Time Limit. Caused by Personnel Error | /03L-0 on 790622:nut Inadvertantly Droppoed Into Diesel Generator Winding During Preventive Maint.Outage Time of Generator Extended 20 Minutes Beyond 1.5-h Time Limit. Caused by Personnel Error | | | 05000265/LER-1979-012, Forwards LER 79-012/03L-0 | Forwards LER 79-012/03L-0 | | | 05000254/LER-1979-012, Forwards LER 79-012/03L-0 | Forwards LER 79-012/03L-0 | | | 05000254/LER-1979-012-03, /03L-0 on 790214:air Found Blowing Through Weld on 3/4 Inch Vent Line.Caused by Component Failure.Vent Line Inserted Into Sockolet & re-welded | /03L-0 on 790214:air Found Blowing Through Weld on 3/4 Inch Vent Line.Caused by Component Failure.Vent Line Inserted Into Sockolet & re-welded | | | 05000254/LER-1979-013-03, /03L-0 on 790217:check Valves 1-263-2-31B & 1-263-42A Failed to Check Flow Through Instrument Lines. Caused by Dirt in Valve Internals.Internals Removed,Cleaned & Reassembled | /03L-0 on 790217:check Valves 1-263-2-31B & 1-263-42A Failed to Check Flow Through Instrument Lines. Caused by Dirt in Valve Internals.Internals Removed,Cleaned & Reassembled | | | 05000254/LER-1979-013, Forwards LER 79-013/03L-0 | Forwards LER 79-013/03L-0 | | | 05000265/LER-1979-013, Forwards LER 79-013/03L-0 | Forwards LER 79-013/03L-0 | | | 05000265/LER-1979-013-03, /031-0 on 790712:while Performing Motor Operated Valve Operability Test,Thermal Overload Relay for Pump Suction Valve 1C RHR Tripped & Could Not Be Reopened.Caused by Loose Electrical Connections at Breaker | /031-0 on 790712:while Performing Motor Operated Valve Operability Test,Thermal Overload Relay for Pump Suction Valve 1C RHR Tripped & Could Not Be Reopened.Caused by Loose Electrical Connections at Breaker | | | 05000254/LER-1979-014, Forwards LER 79-014/03L-0 | Forwards LER 79-014/03L-0 | | | 05000265/LER-1979-014, Forwards LER 79-014/03L-0 | Forwards LER 79-014/03L-0 | | | 05000265/LER-1979-014-03, /031-0 on 790723:steam Inlet Valve Mo 2-1301-16 Failed to Close During Reactor Core Isolation Cooling Monthly Valve Operability Test.Caused by Component Failure of Torque Switch on Valve Mo 2-1301-16.Switch Replaced | /031-0 on 790723:steam Inlet Valve Mo 2-1301-16 Failed to Close During Reactor Core Isolation Cooling Monthly Valve Operability Test.Caused by Component Failure of Torque Switch on Valve Mo 2-1301-16.Switch Replaced | | | 05000254/LER-1979-014-03, /03L-0 on 790214:automatic Blowdown Timers Exceeded Tech Spec Limits During Tests.Caused by Instrument Setpoint Drift.One Timer Readjusted,Another Replaced | /03L-0 on 790214:automatic Blowdown Timers Exceeded Tech Spec Limits During Tests.Caused by Instrument Setpoint Drift.One Timer Readjusted,Another Replaced | |
|