LER-1981-011, Forwards LER 81-011/01T-0 |
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| 2471981011R00 - NRC Website |
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John 0. 0'1oole Vlck. Pr eh;Icjl Consolidated Edison Company of New York, Inc.
4 Irving Place. Now York. NY 10003 "elephone (212) 460-2533 I<
I May 22, 1981 Re:
Indian Point Unit No. 2 Docket No. 50-247 LE R-8 1- 011/l" 0 OJT Mr. Boyce H. Grier, Director Office of Inspection and Enforcement Region I U. S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, Pa 19406
Dear Mr. Grier:
01l The attached Licensee Event Report LER-8-0ll/Q-3, -0 is hereby sub mitted in accordance with the requirements of Technical Specification 6.9.1.7.
This event is of the type described in Technical Specification 6.9.1.7.1.i.
Three copies of this letter and the attachment are enclosed as required.
Ve truly yours,
/77 attach.
cc:
Mr. Victor Stello, Jr., Director (30 copies)
Office of Inspection and Enforcement c/o Distribution Services Branch, DDC, ADM Washington, D. C. 20555 Mr. William G. McDonald, Director (3 copies)
Office of Management Information and Program Control U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Mr. T. Rebelowski, Resident Inspector U. S. Nuclear Regulatory Commission P. 0. Box 38 Buchanan, N. Y.
10511 AoO'~
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8 I aS0
- - a 50
LICLNSLE LVLN I HLKPUH I CONTROL BLOCK:
I (PLEASE PRINT OR TYPE EQUI ED INFORMATION)
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1 l ! 14 1 1l l l l G) 7 8
9 LICENSEE CODE 14 15 LICENSE NUMBER 25 26 LICENSE TIfe 30 57 CAT 58 CON'T RE F11 1
SEPORT L 1J@ I 0 51 0 l0o o 12 I 4I 71 1o I 5 I 01 8 ! 1@ 1 o 1 51 212 1Il 110 7
8 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES 0
O 2 I During inspection of service water pump discharge pipinapits were
- 6-3 I observed on the exterior surface.
Non-destructive examinat-ion nf the O 4 I pits indicated that the pipe wall thickness under four small plif wasi O 5 less than the minimum wall thickness required to meet seismic design [O6 J criteria, (0.135 inches).
Possible consequences could nave been the O
I eventual development of small pinhole leaks with no degradation in the 081 operability of the service water system.
7 8 9 80 SYSTEM
CAUSE
CAUSE COMP.
VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE 9]
IWIA(I W@ L D IFIIIPIE Ixi xl L1J
@6, 7
.8 9
10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION LE R/R0 EVENT YEAR REPORT NO.
CODE TYPE NO.
17 REPORT 18 11 L-J Lu I 11111 L ji LT Li LOi NUMBER 226 28
- 29.
30......
231 32 ACTION FUTURE EFFECT SHUTDOWN f'
ATTACHMENT NPRD-4 PRIME COMP.
COMPCNENT TAKEN ACTION ON PLANT METHOD HOURS ( 22 SUBMITTED FORM SUB.
SUPRLIER MANUFACTURER I
B11cI L@ I.z10 IWo I uI ol WO 1
x1jIJN I xl1 9 1910 33 34 35 36 37 40 41.42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS 44
[
I External corrosicn caused four pits to be formed in the service water W
I pumps discharge piping which resulted in local areas below minimum walli 2I thickness.
The areas were sand blasted, a patch was welded over each 1 3 pitted area and the entire surfaces of the pipes repainted to prevent I
'- 4 I further corrosion.
7 8 9 80 FACILITY METHOD OF 80 STATUS
%POWER OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION @
LJ I ol 0 o101 N/A 1 LcUI Special test of depth of pits I
7 8
9 10 12 13 44 45 46 80 ACTIVITY CONTENT_
RELEASED OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE @
16 LI 51LII N/A
,N/A.I 7
8 9
10 11 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE
DESCRIPTION
- 17Z, L olD N/A
- - I 7
8 9
11 12 13 80 PERSONNEL INJURIES NUMBER
DESCRIPTION
7 8
9 11 1
80 LOSS OF OR DAMAGE TO FACILITY IYPE DE SCRI PTION
\\~~
~
ELJBI N/A 7
8 9 10 80 PUBLICITY NRC USE ONLY ISSUED DESCRIPTION @
10 68 69 80; NAME OF PREPARER PHONE:
ATTACHMENT I Docket No. 05000247 Consolidated Edison Company LER 81-01.1/03L-0 of New York, Inc.
Indian Point Unit No. 2 While in cold shutdown the service water piping in the pump pit was sand blasted to remove surface corrosion. Visual inspection of the cleaned pipe showed a total of seven (7) pits had formed on three of six service water pump discharge lines.
The depth of the pits and surrounding wall thickness were measured using a pipe pit gage and an ultrasonic meter respectively.
The remain ing wall thickness under each pit was then calculated using the measured values.
Using an allowable wall thickness of 0.135 inches, which was based on seismic considerations, it was found that there were four pits which were below the value. These wall thicknesses were:
Line No. 23, 0.060 inches; Line No. 24, 0.060, 0.105 and 0.125 inches.
The cause of the pitting is believed to have been external
._corrosion resulting-from thedamnpconditions found-in the pump pit. A patch was welded over each pitted area and the entire surfaces of the pipes repainted to prevent further corrosion.
The size and small number of pits did not reduce the ability of the piping to withstand a design basis seismic event. Had one or more pits developed into through holes, the result would have been "pinhole" leaks which would not have significantly degraded the operability of the system.
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| 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 | |
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