LER-1981-021, /99X-0:on 810829,pinhole Leak Discovered in Elbow on 2-inch Svc Water Outlet Line.Caused by Erosion of Pipe Matl.Elbow & Pipe Replaced |
| Event date: |
|
|---|
| Report date: |
|
|---|
| 2471981021R99 - NRC Website |
|
text
NHC F ORM 366 U. S NUCLE AH ltE GUL A luHV CLMEti' (7 F11 LICENSEE EVENT REPORT CONT HOL BLOCCC l
l l
l l
l (PLE ASE PRINT OR TYPE ALL REQUIRED 1RFOf1MATIORf fo~lT) lN l YlI l P lS l 2 l@j 0 l0 l - l0 l 0 l0 l0l0 l -l 0 l 0- l@l4 l 1 l1 l1l1l@l l
l{
- - e uC su n,nt i.
uaNsE Num,4 o
L u Na is L..
.. i t'41*.
s I _1g{
l.. l i l
'f, "" l L lgl 015 l 0 l 0l 0 l 2! 4 l 7 Ql 0l 8 l 2 l9 l 8 ] 11@l0l9l11 41 i
w u
w.. t r
.v... t..
u t v e.r O.m a
- - 4
.u o.o... n ts eNi ocsuoPiioN ANu Poautt cos.t e.as @
- o l 2 l [While the unit was at cold shutdown on 8-29-81 a pin hole leak was
- discovered in an elbow on the 2" service water outlet line from in j,;
g n j., ;.No. 25 Fan Cooler Motor Cooler.
No significant occur.ience terk place v
as a result of the leak.
The seismic capability of the line was not
- o,,, j i l significutiv reduced by the pin hole leak.
O c 10171 I l
i a9 SY'TF M OAUSE CA'5E C O*.? P valse CODE COOE SLFCOOE CO'.?PONENT CODE SUSCCOE SUBCO;E g
l Wl A l @ [E_j @ l X l @ l P l I l P l E l X l X l@ J @ ] @
7 8
9 to 11 12 tJ 18 19 2J SEQUENTI AL OCCURRENCE REPORT SEV:30i LE R PO EVENT YE AR REPORT NO.
CODE TYPE NO O.ay.La' I 8 ll 1-1 1 012l11 1/l 1 9 l 21 lXl I-l 1 01
_2' n
- s
- s 2r
- a n
ao as u
T1 EP ACTC N PL A
'T4 HOUR $ 22
$9 7 60 t B
$ PP t{
",* A 9
l A ]@lF l@
l Z l@
l Zl@
l 0 l0 l 0 l0 !
Jg l N[g lN l@
l Xl9 i 9 13 J4 32 Jta 31 40 44 42 43 44 CAUSE OESCRIPTION AND COARECTIVE ACTIONS h lThe elbow and a short portion of the pipe was cut out.
A metallurgical i,;Oi The examination indicate'd iexamination of the affected area was made.
g'the leak was caused by erosion of the pipe material adjacent to the gg,gl downstream side of the elbow.
The elbow and pioe were replaced.
1 4
\\
7 8 9 F AciLITY h
METHODOF STATUS
% POWER OTH ER ST ATUS v DISCOVE RY DISCOVERY OESCRIPT:ON 32 W@ l0 l0 10l@l N/A l
lBl@l Operator Observation i s 6
A flVITY CON T5NT RELE ASED OF RE LE ASE AVOuNT OF AC'TIVITY I.OCATION OF RELEASE W [Zj @ [Z_j@l N/A l
l N/A 7
8 9 to iI 44 45 Pt RSONwf L ()tPOSunE S N UP.'O E R TYPE
DESCRIPTION
10l 0 l Ol@LZJ@l n/A i 7
' PERsmNE L iN;u'd.as ot:CniPTiONh suwE u l 0l 010 l@j N/A j
i a g-7 8 9 11 17 LOSS OF On OAVAGE TO FACILITY TYPE D E t>C nip rioN [0j@l One 2" elbow pipe developed a pin hole leak.
l
- 9 g
7 U 9 tu oEcnieriON @ 810929 g 1 [ h R NRC USE ONLY
~""
7 issuStL 81N/A l
lllllllllllilj
$"^
PD e
7 o SB 63 s '* 3 7
a 9 to Galm1m C. Smith (914)526-5182
?
_~... -
ATTACHMENT Docket No. 247 Consolidated Edison Co. of N.Y.-Inc.
LER - S1-021/ 99%/-0 Indian Point No. 2-
Description
While the unit was at cold shutdown on August 29, 1981 a pin hole leak was discovered on the 2 inch service water outlet line from No. 25-fan cooler motor cooler.
The material of the pipe was 90/10 copper nickel with a nominal wall thickness of 0.120".
The service water system contains brackish salt water at a pressure which is normally less than 100 psig.
The pin hole leak was in the pipe material in an area adjacent to the down-stream side of the elbow weld in the heat affected zone.
The elbow and a short portion of pipe was cut out.. A metallurgical examination indicated that the most probable cause of the leak was erosion.
A flow test of the motor coolers showed a fluid velocity over 10 ft./sec.
Imme'diate Corrective Action 1.
The elbow and short piece of pipe was replaced.
2.
In ordar to determine if the condition was generic to all of the 2" elbows in the motor cooler piping,a non-destruc-tive examination program was instituted.
An evaluation was first performed to identify those elbows which would be most susceptible to erosion caused by fluid velocity and turbulence and which should be inspected.
Of the total of 228 welds on the 90* elbows on the supply and return side of the motor coolers 81 were selected for radiographic exami-nation.
In addition, a mitered elbow and a flexible hose were also examined.
There were-12 indications of reduced wall thickness using the x-ray examinations.
These areas were then ultrasonically examined.
Of the 12 only 2 showed wall thicknesses below the minimtra acceptable thickness of 0.090".
These 2 welds were repaired using 90-10 copper nickel filler by means of a standard industry practice of pad welding to increase the thickness of the effected areas.
The repairs were inspected by visual and dye pentrant exami-nation., and were found to be satisfactory.'
3.
In order to reduce the velocity and therefore the erosive effect on the motor cooler elbows the normal operation of-the " vital" service water header will be modified until permanent system changes can be made to effect the same result.
The interim change will. consist of having Valve TCV 1104 secured in the locked open position.during the-normal mode of operation.
Service Water System tests during the present outage have verified that velocitv through the motor _ coolers under this mode of operations will be re-duced to acceptable values.
Since valve TCV-1104 automati-cally goes open in the accident condition this method.of-operating is not considered unsafe.
e Q
s Long Range Corrective Action 1.
As soon as practicable after return to service from the present outage an on line test will be made of the Fan Cooler / Motor Cooler Service Water Systems.
These are ex-pected to verify data previously recorded.
2.
By the end of the next refueling outage, system modifica-tions will have been made so that valve TCV-1104 can be placed in its normally closed position during normal plant operation 3.
During the next refueling outage the 12 welds that indi-cated reduced wall thickness, including the 2 that were pad welded, will be radiographically and ultrasonically examined again to verify that their wall thicknesses are still satisfactory.
i 9
G -
Ob 5:
s n
,,,--7 r- -,
y
,y,-
r 4
3-
|
|---|
|
|
| | | Reporting criterion |
|---|
| 05000247/LER-1981-003-03, During Surveillance Test PT-R35 Shutoff Valve 822B in Component Cooling Water Return Line 21 for RHR Heat Exchange Would Not Open.Caused by Loose Torque Switch.Switch Tightened | During Surveillance Test PT-R35 Shutoff Valve 822B in Component Cooling Water Return Line 21 for RHR Heat Exchange Would Not Open.Caused by Loose Torque Switch.Switch Tightened | | | 05000286/LER-1981-003-03, /03L-1:on 810223,during Seismic Restraint Test, Snubber RC-R-344-5-H Failed to Lock Up in Extension Position.Caused by Excessively High Bleed Rate W/Result That Lockup Was Unobservable.Snubber Rebuilt & Tested | /03L-1:on 810223,during Seismic Restraint Test, Snubber RC-R-344-5-H Failed to Lock Up in Extension Position.Caused by Excessively High Bleed Rate W/Result That Lockup Was Unobservable.Snubber Rebuilt & Tested | | | 05000286/LER-1981-003, Forwards LER 81-003/03L-1 | Forwards LER 81-003/03L-1 | | | 05000247/LER-1981-004-03, During Surveillance Test PT-R35 Opening Time for One of Two Power Operated Relief Valves (PCV-456) Was 2.5-s Longer than Permitted.Caused by Nitrogen Supply Valve Inadvertently Closed.Valve Reopened | During Surveillance Test PT-R35 Opening Time for One of Two Power Operated Relief Valves (PCV-456) Was 2.5-s Longer than Permitted.Caused by Nitrogen Supply Valve Inadvertently Closed.Valve Reopened | | | 05000286/LER-1981-005, Forwards LER 81-005/03L-1.Detailed Event Analysis Encl | Forwards LER 81-005/03L-1.Detailed Event Analysis Encl | | | 05000286/LER-1981-005-03, /03L-1:on 810305,snubber RC-R-70-8-H Was Declared Inoperable Because of Oil Leak.Caused by Failure of O-ring in Main Cylinder Flange & Scoring on Extension & Compression Poppets.Snubber Repaired,Rebuilt & Tested | /03L-1:on 810305,snubber RC-R-70-8-H Was Declared Inoperable Because of Oil Leak.Caused by Failure of O-ring in Main Cylinder Flange & Scoring on Extension & Compression Poppets.Snubber Repaired,Rebuilt & Tested | | | 05000286/LER-1981-006, Forwards LER 81-006/03L-0 | Forwards LER 81-006/03L-0 | | | 05000286/LER-1981-006-03, /03L-0:on 810706,battery Charger 32 Discovered in Tripped Position.Caused by Faulty delta-P Air Flow Sensing Switch.Switch Replaced | /03L-0:on 810706,battery Charger 32 Discovered in Tripped Position.Caused by Faulty delta-P Air Flow Sensing Switch.Switch Replaced | | | 05000286/LER-1981-007-01, /01T-0:on 810928,following Hydrostatic Testing of Rcs,Leakage of Coolant Observed in Steam Generator 31.Cause Not Specified.Unit in Cold Shutdown.Eddy Current Insp of Steam Generators Underway | /01T-0:on 810928,following Hydrostatic Testing of Rcs,Leakage of Coolant Observed in Steam Generator 31.Cause Not Specified.Unit in Cold Shutdown.Eddy Current Insp of Steam Generators Underway | | | 05000286/LER-1981-007, Forwards LER 81-007/01T-0.Detailed Event Analysis Encl | Forwards LER 81-007/01T-0.Detailed Event Analysis Encl | | | 05000286/LER-1981-008, Forwards LER 81-008/01T-0.Detailed Event Analysis Encl | Forwards LER 81-008/01T-0.Detailed Event Analysis Encl | | | 05000286/LER-1981-008-01, /01T-0:on 811109,at Hot Shutdown,Two Manual Isolation Vlaves in Weld Channel & Containment Penetration Pressurizaiton Sys Were Closed.Caused by Administrative Error.Valves Opened | /01T-0:on 811109,at Hot Shutdown,Two Manual Isolation Vlaves in Weld Channel & Containment Penetration Pressurizaiton Sys Were Closed.Caused by Administrative Error.Valves Opened | | | 05000286/LER-1981-009-03, /03L-0:on 811110,battery Charger 31 Tripped.Cause Not specified.Delta-P Air Flow Sensing Switch Replaced | /03L-0:on 811110,battery Charger 31 Tripped.Cause Not specified.Delta-P Air Flow Sensing Switch Replaced | | | 05000286/LER-1981-009, Forwards LER 81-009/03L-0 | Forwards LER 81-009/03L-0 | | | 05000286/LER-1981-010, Forwards LER 81-010/01T-0 | Forwards LER 81-010/01T-0 | | | 05000286/LER-1981-010-01, /01T-0:on 811208,leak of Approx 1 Pint Per Minute Identified in Fan Cooler Unit 34.Caused by Leak in Tube of Cooling Coils for Motor Cooler.Tube Repaired | /01T-0:on 811208,leak of Approx 1 Pint Per Minute Identified in Fan Cooler Unit 34.Caused by Leak in Tube of Cooling Coils for Motor Cooler.Tube Repaired | | | 05000247/LER-1981-011-01, /01T-0:on 810508,pits Observed on Exterior Surface of Svc Water Pump Discharge Piping.Caused by External Corrosion,Resulting in Local Areas Below Min Wall Thickness. Areas Sand Blasted,Patch Welded & Repainted | /01T-0:on 810508,pits Observed on Exterior Surface of Svc Water Pump Discharge Piping.Caused by External Corrosion,Resulting in Local Areas Below Min Wall Thickness. Areas Sand Blasted,Patch Welded & Repainted | | | 05000247/LER-1981-011, Forwards LER 81-011/01T-0 | Forwards LER 81-011/01T-0 | | | 05000247/LER-1981-012, Forwards LER 81-012/01T-0 | Forwards LER 81-012/01T-0 | | | 05000247/LER-1981-012-01, /01T-0:on 810511,3/4-inch Swagelok Union in Remote Reactor Head Vent Line Parted During Test to Assure Operability of Low Power Injection/Rhr Check Valves Prior to Restart.Caused by Improper Installation.Valve Closed | /01T-0:on 810511,3/4-inch Swagelok Union in Remote Reactor Head Vent Line Parted During Test to Assure Operability of Low Power Injection/Rhr Check Valves Prior to Restart.Caused by Improper Installation.Valve Closed | | | 05000247/LER-1981-013-01, /01T-0:on 810520,low Flow from Two Motor Driven Auxiliary Boiler Feed Pumps at Hot Shutdown Discovered During Surveillance Testing.Caused by New Trim in Generator Level Control Valves Restricting Auxiliary Feedwater Flow | /01T-0:on 810520,low Flow from Two Motor Driven Auxiliary Boiler Feed Pumps at Hot Shutdown Discovered During Surveillance Testing.Caused by New Trim in Generator Level Control Valves Restricting Auxiliary Feedwater Flow | | | 05000247/LER-1981-013, Forwards LER 81-013/01T-0 | Forwards LER 81-013/01T-0 | | | 05000247/LER-1981-014, Forwards LER 81-014/03L-0 | Forwards LER 81-014/03L-0 | | | 05000247/LER-1981-014-03, /03L-0:on 810517,one Sensing Device Found Not Operating on Level Transmitters LT-940 & LT-941.Caused by Foreign Matl Buildup on Instrument Stalks of Gem Level Transmitters.Matl Removed & Transmitter Tested | /03L-0:on 810517,one Sensing Device Found Not Operating on Level Transmitters LT-940 & LT-941.Caused by Foreign Matl Buildup on Instrument Stalks of Gem Level Transmitters.Matl Removed & Transmitter Tested | | | 05000247/LER-1981-015-01, /03L-0:on 810528,during Low Power Operation, Control Room Instrumentation Indicated Control Rod in Inserted Position.Cause Undetermined.Control Rod Returned to Bank Position.Subsequent Tests Satisfactory | /03L-0:on 810528,during Low Power Operation, Control Room Instrumentation Indicated Control Rod in Inserted Position.Cause Undetermined.Control Rod Returned to Bank Position.Subsequent Tests Satisfactory | | | 05000247/LER-1981-015, Forwards LER 81-015/03L-0 | Forwards LER 81-015/03L-0 | | | 05000247/LER-1981-016, Forwards LER 81-016/03L-0 | Forwards LER 81-016/03L-0 | | | 05000247/LER-1981-016-03, /03L-0:on 810705,during Routine Check of Diesel Generator 23,water Found in Crankcase.Caused by Water Leaking from Lube Oil Cooler Into Lube Oil.Leaking Tube Plugged & Oil Changed | /03L-0:on 810705,during Routine Check of Diesel Generator 23,water Found in Crankcase.Caused by Water Leaking from Lube Oil Cooler Into Lube Oil.Leaking Tube Plugged & Oil Changed | | | 05000247/LER-1981-017-03, /03L-0:on 810630,feed Breaker for 480-volt Bus 5A Opened & Associated Lockout Relay Actuated.Caused by Defective Westinghouse DB-75 Breaker Tripping Device. Device Replaced | /03L-0:on 810630,feed Breaker for 480-volt Bus 5A Opened & Associated Lockout Relay Actuated.Caused by Defective Westinghouse DB-75 Breaker Tripping Device. Device Replaced | | | 05000247/LER-1981-017, Forwards LER 81-017/03L-0 | Forwards LER 81-017/03L-0 | | | 05000247/LER-1981-018-03, /03L-0:on 810710,during Attempt to Automatically Start,Diesel Generator 21 Shut Down.Caused by Over Crank Due to Incorrectly Set Timer Relays.Relays Reset | /03L-0:on 810710,during Attempt to Automatically Start,Diesel Generator 21 Shut Down.Caused by Over Crank Due to Incorrectly Set Timer Relays.Relays Reset | | | 05000247/LER-1981-018, Forwards LER 81-018/03L-0 | Forwards LER 81-018/03L-0 | | | 05000247/LER-1981-019-03, /03L-0:on 810810,safety Injection Pump 23 Tripped After Flash & Smoke Observed in Pump Motor.Caused by Two Rotor Bars Lifting,Making Contact W/Stator Windings & Rubbing Through Insulation.Motor Replaced | /03L-0:on 810810,safety Injection Pump 23 Tripped After Flash & Smoke Observed in Pump Motor.Caused by Two Rotor Bars Lifting,Making Contact W/Stator Windings & Rubbing Through Insulation.Motor Replaced | | | 05000247/LER-1981-019, Forwards LER 81-019/03L-0 | Forwards LER 81-019/03L-0 | | | 05000247/LER-1981-020, Forwards LER 81-020/03L-0 | Forwards LER 81-020/03L-0 | | | 05000247/LER-1981-020-03, /03L-0:on 810821,during Normal Operation,Control Rod G-3 Dropped Into Core,Initiating Turbine Runback.Caused by Spray from Leaking Plug Needle Valve on Control Rod H-2, Causing Coil Stack Connector to Fault.Connector Repaire | /03L-0:on 810821,during Normal Operation,Control Rod G-3 Dropped Into Core,Initiating Turbine Runback.Caused by Spray from Leaking Plug Needle Valve on Control Rod H-2, Causing Coil Stack Connector to Fault.Connector Repaired | | | 05000247/LER-1981-021-99, /99X-0:on 810829,pinhole Leak Discovered in Elbow on 2-inch Svc Water Outlet Line.Caused by Erosion of Pipe Matl.Elbow & Pipe Replaced | /99X-0:on 810829,pinhole Leak Discovered in Elbow on 2-inch Svc Water Outlet Line.Caused by Erosion of Pipe Matl.Elbow & Pipe Replaced | | | 05000247/LER-1981-021, Forwards LER 81-021/99X-0 | Forwards LER 81-021/99X-0 | | | 05000247/LER-1981-022, Forwards LER 81-022/03L-0 | Forwards LER 81-022/03L-0 | | | 05000247/LER-1981-022-03, /03L-0:on 810916,during Normal Operation W/Reactor at 100% Power,Lubricating Oil of Diesel Generator 21 Had Unusual Appearance.Caused by Leaking Water Into Lube Oil. Cooler Tube Bundle Replaced & Generator Returned to Svc | /03L-0:on 810916,during Normal Operation W/Reactor at 100% Power,Lubricating Oil of Diesel Generator 21 Had Unusual Appearance.Caused by Leaking Water Into Lube Oil. Cooler Tube Bundle Replaced & Generator Returned to Svc | | | 05000247/LER-1981-023-03, /03L-0:on 811014,perturbation in Secondary Blowdown Piping Associated W/Steam Generator 21 Resulted in Failure of Bolts Between Strut Assembly & Base of Snubber 46-SR-3.Cause Due to Water Hammer.Bolts & Snubber Replaced | /03L-0:on 811014,perturbation in Secondary Blowdown Piping Associated W/Steam Generator 21 Resulted in Failure of Bolts Between Strut Assembly & Base of Snubber 46-SR-3.Cause Due to Water Hammer.Bolts & Snubber Replaced | | | 05000247/LER-1981-024-03, /03L-0:on 811014,snubber 70-SR-13 on Pressurizer Relief Line & Bergen Patterson Hydraulic Snubber Hssa 3 Shaft Found Broken.Caused by Transverse Impact Load on Snubber Piston Rod.Snubber Replaced & Rod Analyzed | /03L-0:on 811014,snubber 70-SR-13 on Pressurizer Relief Line & Bergen Patterson Hydraulic Snubber Hssa 3 Shaft Found Broken.Caused by Transverse Impact Load on Snubber Piston Rod.Snubber Replaced & Rod Analyzed | | | 05000247/LER-1981-025, Forwards LER 81-025/99X-0 | Forwards LER 81-025/99X-0 | | | 05000247/LER-1981-025-99, /99X-0:on 811009,code Safety Valve Ms 48A on Main Steam Line 21 Was Found Lifting at Lower than Specified Pressure.Caused by Broken Section on Disc Holder in Valve. Defective Parts Replaced | /99X-0:on 811009,code Safety Valve Ms 48A on Main Steam Line 21 Was Found Lifting at Lower than Specified Pressure.Caused by Broken Section on Disc Holder in Valve. Defective Parts Replaced | | | 05000247/LER-1981-026, Forwards LER 81-026/03L-0 | Forwards LER 81-026/03L-0 | | | 05000247/LER-1981-026-03, /03L-0:on 811029,reduction Observed in Delta & Average Temp on Loop 23.Caused by Defect in Hot Leg Model 176JA Resistance Temp Detector Circuit.Resistance Temp Element Replaced | /03L-0:on 811029,reduction Observed in Delta & Average Temp on Loop 23.Caused by Defect in Hot Leg Model 176JA Resistance Temp Detector Circuit.Resistance Temp Element Replaced | | | 05000247/LER-1981-027-03, /03L-0:on 811110,primary Heat Trace Circuit for Balance Leakoff Line of Safety Injection Pump 23 Failed. Caused by Burned & Broken Connection at Chromalox Strip Heater Element for Thrust Balance Line | /03L-0:on 811110,primary Heat Trace Circuit for Balance Leakoff Line of Safety Injection Pump 23 Failed. Caused by Burned & Broken Connection at Chromalox Strip Heater Element for Thrust Balance Line | | | 05000247/LER-1981-027, Forwards LER 81-027/03L-0 | Forwards LER 81-027/03L-0 | | | 05000247/LER-1981-028-03, /03L-0:on 811120,pressurizer Safety Valve PCV-464 Found to Actuate Approx 4% Below Tech Spec Min.Cause Unknown.Valve Readjusted & Retested | /03L-0:on 811120,pressurizer Safety Valve PCV-464 Found to Actuate Approx 4% Below Tech Spec Min.Cause Unknown.Valve Readjusted & Retested | | | 05000247/LER-1981-029-03, /03L-0:on 811119,during Test Run of Safety Injection Pump,Motor Emitted Smoke & Did Not Turn.Caused by Frozen Shaft Bushings on Pump Rotating Elements.Pump Replaced | /03L-0:on 811119,during Test Run of Safety Injection Pump,Motor Emitted Smoke & Did Not Turn.Caused by Frozen Shaft Bushings on Pump Rotating Elements.Pump Replaced | |
|