Similar Documents at Salem |
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Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML18107A3441999-06-0101 June 1999 Interim Part 21 Rept Re Premature Over Voltage Protection Actuation in Circuit Specific Application in Dc Power Supply.Testing & Evaluation Activities Will Be Completed on 990716 ML18106B0931999-02-25025 February 1999 Part 21 Rept Re Possible Defect in Swagelok Pipe Fitting Tee,Part Number SS-6-T.Caused by Crack Due to Improper Location of Heated Bar.Only One Part Out of 7396 Pieces in Forging Lot Was Found to Be Cracked.Affected Util,Notified ML18106B0551999-02-0101 February 1999 Part 21 Rept Re Possible Matl Defect in Swagelok Pipe Fitting Tee,Part Number SS-6-T.Defect Is Crack in Center of Forging.Analysis of Part Is Continuing & Further Details Will Be Provided IAW Ncr Timetables.Drawing of Part,Encl ML18106B0441999-01-29029 January 1999 Part 21 Rept Re Possible Defect in Swagelok Pipe Fitting Tee Part Number SS-6-T.Caused by Crack in Center of Forging. Continuing Analysis of Part & Will Provide Details in Acoordance with NRC Timetables ML17354B0971998-09-0909 September 1998 Part 21 Rept Re Possible Machining Defect in Certain One Inch Stainless Steel Swagelok Front Ferrules,Part Number SS-1613-1.Caused by Tubing Slipping Out of Fitting at Three Times Working Pressure of Tubing.Notified Affected Utils ML17264A9381997-07-10010 July 1997 Deficiency Rept Re Potential Safety Hazard Associated w/FM-Alco 251 Engin,High Pressure Fuel tube-catalog: 4401031-2 in Which Dual Failure Mode Exists.Caused by Incorrect Forming Process ML18102A3701996-09-0606 September 1996 Part 21 Rept Re Installation of NUS Model OCA 801 Signal Isolator Modules & Model Mth 801 Signal Summator Modules. Replacement Modules Including Spares for Plant,Unit 2 Have Been Inspected by Vendor & Repaired ML18102A3381996-08-21021 August 1996 Part 21 Rept Re Chipping of Latching Mechanism Props Installed in GE 4 Kv magne-blast Circuit Breakers,Type AM-4.16-350-2H.Two Affected Breakers Have Been Returned to Vendor ML18102A5591996-08-0808 August 1996 Part 21 Rept Re Defect in NUS Model OCA801 Signal Isolator Modules.Replacement Modules Installed in Reactor Control & Protection Sys ML18101A8771995-08-0404 August 1995 Interim Part 21 Rept Re Potentially Reportable Deficiency in Edward Valve Model 838YT Check Valves Due to Disk Exhibiting Excessive Leakage.Disk from Original Valve Cleaned, Inspected & Installed in Replacement Valve ML18101A8611995-08-0101 August 1995 Interim Part 21 Rept Re Velan Valve Corp Check Valve Failure to Close.Insp of Internals Showed Moderate Wear in Gap Between Valve Disc & Hanger Arm.New Disc Installed & Valve Tested Satisfactorily ML18038A8971994-09-0707 September 1994 Part 21 Rept Re Defect in Latching Mechanism of Potter & Brumfield Relay on C&D High Voltage Shut Down Alarm Assembly Printed Circuit Boards.Pull Test on Relay Reset Button Incorporated Into Receiving Insp Procedures ML18100B2391994-07-27027 July 1994 Part 21 Rept Re Signal Summators PM-505B & 506B Found to Saturate High When Summators Lose Power & Reenergized. Summators Powered from Independent Vital Instrument Buses & Inverters.Design Changes Implemented ML18100B2271994-07-25025 July 1994 Part 21 Rept Re Cracking in Valve Stem & Plug Connection Pinning Collar Area on PORVs 1PR1 & 1PR2.Caused Attributed to Either IGSCC or Hydrogen Assisted Cracking.Porv Internals Replaced W/Internals Mfg from SS 316 Matl W/Plug Stellited ML18100B2101994-07-14014 July 1994 Deficiency Rept Re PORV Plug & Stem Material Defects. Initially Reported 940714.PORV Internals Were Replaced W/Plug Stellited ML18100B1911994-06-30030 June 1994 Initial Part 21 Rept Re Deficiency in Signal Summators PM-505B & PM-506B Supplied by Westinghouse.Design Changes Implemented & Operators Made Aware of Affects of Power Supply Transient on Summator Operability ML18100A7681993-12-13013 December 1993 Interim Part 21 Rept Re Discovery That Ge/Alco EDGs High Pressure Injection Tube Studs Did Not Meet Correct Matl non- Std & Not Correct Geometry.All Nonconforming Studs Identified & Replaced ML18096B2421993-02-0101 February 1993 Part 21 Rept Re Possible Matl Defect in Stainless Steel Swagelock Tube Fittings.Initially Reported on 921218.List of Part Numbers,Heat Codes & Addl Affected Customers Encl ML20126J5961992-12-31031 December 1992 Part 21 Rept Re Potential Loss of RHR Cooling During Nozzle Dam Removal.Nozzle Dams May Create Trapped Air Column Behind Cold Leg Nozzle Dam.Mod to Nozzle Dams Currently Underway. Ltrs to Affected Utils Encl ML20118B4391992-09-11011 September 1992 Part 21 Rept Re Degradation in Abb Type 27N Undervoltage Relays Used in Electrical Switchgear.Recommends That Users Review Applications Requiring Exposures Greater than 1E03 Rads TID W/Time Delay Function Option ML18095A4031990-08-0202 August 1990 Part 21 Rept Re MSIV Design Deficiency at Plant.Design Spec Provided by Westinghouse Did Not Specify Requirement to Provide Seal in Capability & Util Design Process Failed to Recognize Deficiency ML18095A2321990-05-24024 May 1990 Part 21 Rept Re Discrepancies Identified in ECCS Flow Orifice K Factors Supplied by Westinghouse.Initially Reported on 900518.Util Fabricated New Orifice Plates to Original Specs ML18095A2251990-05-22022 May 1990 Part 21 Rept Re Insufficient Welds on Pedestal Support Alignment Lug & Slide Shoe for 11,12,21 & 22 Charging/Safety Injection Pumps.Initially Reported on 900516.Windows Cut in Support Pedestals to Gain Access to Affected Areas ML18094B4461990-04-27027 April 1990 Part 21 Rept Re shaft-to-pinion Key Failures in Limitorque Actuators.Initially Reported on 900424.Caused by Reduction of cross-sectional Area & Ultimate Propagation of Cracks. Util Intends to Replace Keys in Actuators W/Keys of Steel ML18094A4421989-05-16016 May 1989 Part 21 Rept Re Defect in Solid State Protection Sys. During Mods in Solid State Protection Sys Cabinets,Noted That Two Wires Became Dislodged from Circuit Board.Visual Insp & Complete Pull Test Performed ML18093A8281988-05-0606 May 1988 Part 21 & Deficiency Rept Re Asea Brown Boveri,Power Distribution,Inc Low Voltage K-Line Circuit Breakers. Efforts Underway to Define Quantity & Type of Component Parts That May Need to Be Replaced ML20153G0111988-05-0606 May 1988 Part 21 Rept Re Potential Defect in Bussman Buss KTK-R Fuse Blocks W/Part Numbers 2078,2079 & 2080.Purchasing Records Reviewed to Identify If Any Parts Were Actually Used or Shipped to Customers.Results Listed ML18093A4721987-10-23023 October 1987 Part 21 Rept Re Calibr Gas Leakage Problem in Exo-Sensors, Inc Containment Hydrogen Analyzer Sys.Caused by Design Deficiency Associated W/Calibr Gas Subassembly.Monitoring Program to Be Maintained for Period After Sys Mods ML20215G2441987-06-16016 June 1987 Part 21 Rept Re Failure of Load Sequencing Equipment Supplied in Aug 1977 During Scheduled Testing.Caused by Open Electrical Connection on One Crimp Lug.Since 1978,insulated Lugs Used on All Equipment FVY-86-105, Part 21 Rept Re Design Defect Relating to Limitorque Motor Operators Mfg Prior to 1975.Mfg Contacted & Retrofit Kits Installed on safety-related & nonsafety-related Operators. Addl Info Encl1986-11-10010 November 1986 Part 21 Rept Re Design Defect Relating to Limitorque Motor Operators Mfg Prior to 1975.Mfg Contacted & Retrofit Kits Installed on safety-related & nonsafety-related Operators. Addl Info Encl ML20215G5351986-10-10010 October 1986 Part 21 Rept Re Vendor Tests of air-operated Diaphragm Valves Revealing Natural Frequencies Less than Required Values of 33 Hz.Initially Reported on 841227.No Adverse Effects Noted During Testing ML20215G6801986-10-10010 October 1986 Part 21 Rept Re Vendor Tests of air-operated Diaphragm Valves Revealing Natural Frequencies Less than Required Values of 33 Hz.Initially Reported on 841227.No Adverse Effects Noted During Testing ML20206S0841986-06-30030 June 1986 Part 21 Rept Re Possible Cut Wires in Wire Harness of Bbc Brown Boveri K600/K800 Circuit Breakers.Initially Reported on 860509.Safety Implications Listed.Gear Guard Designed to Prevent Cut Wires ML20140J4261986-03-31031 March 1986 Part 21 Rept Re Nuclear Valves Shipped to Pse&G.Internal Parts Lapped Which Could Reduce or Eliminate Nickel Plating Resulting in Seat Leakage & Shifting Problems ML20210G9921985-08-13013 August 1985 Part 21 Rept Re Failure of Isolated Worm Shaft Gear When Certain Critical Speeds Combined W/Repetitive Transfer of Actuator Clutch Mechanism from Manual (Handwheel) to Motor Drive Mode.Two Possible Solutions Noted ML20116E8481985-04-23023 April 1985 Part 21 Rept Forwarding Rev 1 to Insp Procedure for Investigating Emergency Diesel Generators for Fractured Welds on Air Deflectors.Rev Will Be Forwarded to Each Facility ML20092D9711984-06-15015 June 1984 Part 21 Rept Re Thermal Nonrepeatability & Other Calibr Errors in Barton Lot 1 Transmitters.Initially Reported on 840615.Transmitter Defects Identified & Expected Error Deviations Calculated.Utils Notified ML20082F3621983-11-17017 November 1983 Part 21 Rept Responding to IE Bulletin 83-06, Nonconforming Matls Supplied by Tube-Line Corp. List of Matls & Sys in Which Installed Encl ML18082A1421980-02-15015 February 1980 Final Deficiency Rept:Check Valve 2DR-7 Failed to Meet Applicable Seismic Class I Loading.Caused by Design Defect. Addl Support Will Be Completed by 800228 ML18081B0481979-12-21021 December 1979 Final Deficiency Rept Re Undetectable Failure in Engineered Safety Features Actuation Sys.Testing Procedures Revised to Include Testing of Permissive Circuitry P4 on Periodic Basis.Unit Will Be Tested Prior to Operation ML18081B0601979-12-0303 December 1979 Initial Deficiency Rept Re Potential Dropped Rod Events Leading to Calculated DNB Ratios Lower than Reported to NRC for Certain Westinghouse Plants.Util Is Investigating Condition for Applicability to Facility ML18081A3751979-10-0505 October 1979 Significant Deficiency Rept Re Containment Purge & pressure- Vacuum Relief Valves.Actuator Torque Values Were Insufficient to Move Valves from Open to Closed Positions W/ Design Differential Pressure of 60 Psi.Design Reviewed ML18081A3781979-10-0505 October 1979 Significant Deficiency Rept 79-06 Re Steam Generator Water Level Instrumentation.Pipe Breaks in Containment Could Lead to Elevated Temp Readings Which Could Result in Delayed Protection Sys Actuation.Setpoints to Be Changed ML18081A7551979-10-0404 October 1979 Interim Deficiency Rept Re Max Flow of RHR Pump During post- LOCA Mode.Caused by Low Sys Resistance to Pump Runout Conditions.Sys Resistance Increased by Placement of Resized Orifices ML18079A9521978-10-28028 October 1978 Deficiency Rept:On 780928,during Routine Design Review, Undersizing of Refueling Water Storage Tank Was Discovered. Tank Storage Capacity Has Been Increased.Design Drawings for Tank Piping & Foundation Will Be Modified ML20086C0041976-07-0101 July 1976 Interim Deficiency Rept Re Fan Coil Unit Motor 15 Failure to Meet Test Requirements.Initially Reported on 760611.Fan Coil Unit Motor from Unit 1 Installed in Place of Motor 15.Faulty Motor Returned to Westinghouse for Repair ML20086C0201976-06-17017 June 1976 Interim Deficiency Rept Re Polar Gantry Crane Gear Misalignment.Initially Reported on 760611.Caused by Misalignment of Hoist Drum Gear & Pinion.Drum Assembly Realigned & Secured & Dressing Gears Initiated ML20086C0301976-06-10010 June 1976 Final Deficiency Rept Re Pressurizer Snubber Malfunction. Initially Reported on 760402.Caused by Heavy Corrosion Buildup.Nine Units Replaced W/Pacific Scientific Units & 54 Units Replaced W/Combination of Redesigned Units ML20086C0421976-06-0202 June 1976 Interim Deficiency Rept Re Automatic Transfer of 4-kV Outside Feed.Initially Reported on 760512.Caused by Design Error.Circuitry for Automatic Bus Transfer Redesigned to Eliminate Possibility of Transfer ML20086C0741976-05-28028 May 1976 Suppl to Deficiency Rept Re Steam Generator Head Cladding Indications.Initially Reported on 760408.Cause Still Under Investigation.Ultrasonic Exam Conducted 1999-06-01
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data ML18107A5581999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Salem,Unit 2.With 991014 Ltr ML18107A5571999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Salem,Unit 1.With 991014 Ltr ML18107A5301999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Salem,Unit 2.With 990913 Ltr ML18107A5311999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Salem,Unit 1.With 990913 ML18107A5031999-08-26026 August 1999 LER 99-006-00:on 990729,determined That SG Blowdown RMs Setpoint Was non-conservative.Caused by Inadequate ACs for Incorporating Original Plant Licensing Data Into Plant Procedures.Blowdown Will Be Restricted.With 990826 Ltr ML18107A5201999-08-12012 August 1999 Rev 0 to Sgs Unit 2 ISI RFO Exam Results (S2RFO#9) Second Interval,Second Period, First Outage (96RF). ML18107A4811999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Salem,Unit 1.With 990813 Ltr ML18107A4821999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Salem,Unit 2.With 990813 Ltr ML18107A4691999-07-28028 July 1999 LER 99-008-00:on 990714,determined That Limit Switch Cables Were Subject to Multiple Hot Shorts in Same Fire Area.Caused by Inadequate Original Post Fire Safe Shutdown Analysis.All Limit Switch Cables for MOVs Were Reviewed.With 990728 Ltr ML18107A4441999-07-0606 July 1999 LER 99-007-00:on 990605,surveillance for Quadrant Power Tilt Ratio (QPTR) Was Missed.Caused by Human Error.Qptr Calculation Was Performed & Personnel Involved Have Been Held Accountable IAW Pse&G Policies.With 990706 Ltr ML18107A4211999-07-0202 July 1999 LER 99-005-00:on 990605,11 Containment Declared Inoperable. Caused by Valves 11SW72 & 11SW223 Both Leaking.Procedure S1.OP-ST.SW-0010(Q) Was Enhanced to Provide Specific Instructions to Ensure Proper Sequencing.With 990702 Ltr ML18107A4331999-07-0101 July 1999 LER 99-002-01:on 990405,determined That 2SA118 Failed as Found Leakrate Test.Caused by Foreign Matl Found in 2SA118 valve.2SA118 Valve Was Cycled Several Times & Seat Area Was Air Blown in Order to Displace Foreign Matl.With 990701 Ltr ML18107A4321999-07-0101 July 1999 LER 99-006-01:on 990501,determined That There Was No Flow in One of Four Injection Legs.Caused by Sticking of Valve in Safety Injection Discharge Line to 21 Cold Leg.Valve Was Cut Out of Sys & Replaced.With 990701 Ltr ML18107A5211999-07-0101 July 1999 Rev 0 to Sgs Unit 2 ISI RFO Exam Results (S2RFO#10) Second Interval,Second Period,Second Outage (99RF). ML18107A4351999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Salem,Unit 1.With 990713 Ltr ML18107A4341999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Salem,Unit 2.With 990713 Ltr ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML18107A3951999-06-17017 June 1999 LER 99-004-00:on 990520,reactor Tripped from 100% Power,Due to Negative Flux Trip Signal from Nuclear Instrumentation. Cause Has Not Been Determined.Discoloration Was Identified on One of Penetrations.With 990617 Ltr ML18107A3661999-06-0909 June 1999 LER 99-003-00:on 990513,unplanned Entry Into TS 3.0.3 Was Made.Caused by Human error.Re-positioned Creacs Supply Fan Selector Switches & Revised Procedures S1 & S2.OP-ST.SSP-0001(Q).With 990609 Ltr ML18107A3551999-06-0202 June 1999 LER 99-005-00:on 990504,failure to Meet TS Action Statement Requirements for High Oxygen Concentration in Waste Gas Holdup Sys Occurred.Caused by Inability of Operators. Existing Procedures Will Be Evaluated.With 990602 Ltr ML18107A3441999-06-0101 June 1999 Interim Part 21 Rept Re Premature Over Voltage Protection Actuation in Circuit Specific Application in Dc Power Supply.Testing & Evaluation Activities Will Be Completed on 990716 ML18107A3541999-06-0101 June 1999 LER 99-006-00:on 990501,HHSI Flow Balance Discrepancy Was Noted During Surveillance.Caused by Sticking of Check Valve in SI Discharge Line to 21 Cold Leg.Valve 21SJ17,was Cut Out of Sys & Replaced.With 990601 Ltr ML18107A3681999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Salem Generating Station,Unit 1.With 990611 Ltr ML18107A3721999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Salem Generating Station,Unit 2.With 990611 Ltr ML18107A2931999-05-12012 May 1999 LER 99-002-00:on 990413,determined That Number 12 Auxiliary Bldg Exhaust Fan Was Rotating Backwards.Caused by mis-wiring of Motor Due to Human Error by Maint technician.Mis-wiring Was Corrected & Fan Was Returned to Svc.With 990512 Ltr ML18107A2781999-05-10010 May 1999 LER 99-004-00:on 990411,automatic Actuation of ESF Occurred During Reactor Vessel Head Removal in Support of Refueling Operations.Caused by High Radiation Condition.Containment Atmosphere Was Monitored.With 990505 Ltr ML18107A2791999-05-0404 May 1999 LER 99-003-00:on 990406,all Salem Unit 2 Chillers Rendered Inoperable.Caused by Human Error.Lessons Learned from Event Were Communicated to All Operators by Including Them in Night Orders.With 990504 Ltr ML18107A2741999-05-0303 May 1999 LER 99-002-00:on 990405,determined That Containment Isolation Valve Failed as Found Leakrate Test.Caused by Foreign Matl Blocking Valves from Closing.Check Valve Mechanically Agitated.With 990504 Ltr ML18107A3711999-04-30030 April 1999 Corrected Monthly Operating Rept for Apr 1999 for Salem Generating Station,Unit 1 ML18107A3151999-04-30030 April 1999 Submittal-Only Screening Review of Salem Generating Station Individual Plant Exam for External Events (Seismic Portion), Rev 1 ML18107A2991999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Salem Unit 1.With 990514 Ltr ML18107A2971999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Salem Unit 2.With 990514 Ltr ML18107A2351999-04-23023 April 1999 LER 99-001-00:on 990330,MSSV Failed Lift Set Test.Caused by Setpoint Variance Which Is Result of Aging.Valves Were Adjusted & Retested to Ensure TS Tolerance.With 990423 Ltr ML18107A2881999-04-0707 April 1999 Rev 0 to NFS-0174, COLR for Salem Unit 2 Cycle 11. ML18107A1821999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Salem,Unit 1.With 990414 Ltr ML18107A1831999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Salem,Unit 2.With 990414 Ltr ML18106B1471999-03-29029 March 1999 LER 99-001-00:on 990228,reactor Scram Was Noted as Result of Turbine Trip.Caused by Operator Error.Lesson Plans Revised to Explicitly Demonstrate Manner in Which Valve Functions. with 990329 Ltr ML18106B1021999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Salem Unit 2.With 990315 Ltr ML18106B1011999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Salem Unit 1.With 990315 Ltr ML18106B0931999-02-25025 February 1999 Part 21 Rept Re Possible Defect in Swagelok Pipe Fitting Tee,Part Number SS-6-T.Caused by Crack Due to Improper Location of Heated Bar.Only One Part Out of 7396 Pieces in Forging Lot Was Found to Be Cracked.Affected Util,Notified ML18106B0701999-02-16016 February 1999 LER 98-015-00:on 981208,inadvertent Discharge Through RHR Relief Valve During Startup Was Noted.Caused by Operator Performing Too Many Tasks Simultaneously.Appropriate Actions Have Been Taken IAW Policies & Procedures.With 990216 Ltr ML18106B0551999-02-0101 February 1999 Part 21 Rept Re Possible Matl Defect in Swagelok Pipe Fitting Tee,Part Number SS-6-T.Defect Is Crack in Center of Forging.Analysis of Part Is Continuing & Further Details Will Be Provided IAW Ncr Timetables.Drawing of Part,Encl ML18106B0561999-01-31031 January 1999 Monthly Operating Rept for Jan 1999 for Salem Generating Station,Unit 2.With 990212 Ltr ML18106B0571999-01-31031 January 1999 Monthly Operating Rept for Jan 1999 for Salem Generating Station,Unit 1.With 990212 Ltr ML20205P1671999-01-31031 January 1999 a POST-PLUME Phase, Federal Participation Exercise ML18106B0441999-01-29029 January 1999 Part 21 Rept Re Possible Defect in Swagelok Pipe Fitting Tee Part Number SS-6-T.Caused by Crack in Center of Forging. Continuing Analysis of Part & Will Provide Details in Acoordance with NRC Timetables ML18106B0491999-01-28028 January 1999 LER 98-007-01:on 980730,reactor Coolant Instrument Line through-wall Leak Was Noted.Caused by Transgranular Stress Corrosion Cracking.Replaced Affected Tubing.With 990128 Ltr ML18106B0401999-01-18018 January 1999 LER 98-016-00:on 981219,ECCS Leakage Was Outside of Design Value.Caused by Leakage Past Seat of 21RH34 Manual Drain. Valve 21RH34 Was Reseated.With 990118 Ltr ML18106B0251998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Salem Unit 2.With 990115 Ltr 1999-09-30
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s John F. Beta Pubhc Service Electnc and Gas Company 80 Park Place Newark, N J. 07101 201/622-7000 Vice-President in charge of Electric Operation October 20, 1972 4 ,
U. S. Atomic Energy Commission Directo r of Regulatory Operations 7920 Norfolk Avenue Bethesda, Maryland 200114 .
Attention of Mr. Frank E. Cruesi ~
Director .
~
v Gentlemen: -
' ~
REACTOR LOWER INTERNALS '
FAILURE OF MOVING EQUIPMENT NO. 2? UNIT SALEM NUCLEAR GENERATING STATION '-
Ad On September 28, 1972,_ at Salem Nuclear Generating Station, Lower Alloways Creek Township, Salem County, New Jersey,-
a rail cart bolster beam,<used^in the lateral movement of the No. 2 Unit reactor lower, internals along-the access bridge and- '
onto the containment building operating floor, yielded and ,
lowered the front end- of thbskid mounted internals to the '
containment operating floor; IrLaccordance with 50.55(e).of".
D 10CFR50, this incident wac. verbally reported on.Sepyember 28 to U.S. Atomic Energy Commission,-Directorateof(RegulatoryL m M^
~
Operations, Region 1 as a possible reportable item.
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External and inte rnal' inspections of the internals, and shipping skid, performed at[th'e . time of the inciderit and- ,-
after the assembly had been restored-to a horizontal' position, -
indicated that there was no d'amage to the internals.nor'to the v shipping skid. There was~no was eased down as the bolsiir\evideiicE~ of: impact
' beam" yielded during since the ;the- failure-load interval. These observations are substantiated,by a mot. ion" m.
picture record of the incident. &! . e-p ,
Following the 'liiuident, procedures were' developed to -
restore the assembly.to its previous position. Work then. 2 proceeded toward the normal completion of the handling operation- /
of-upending the assembly, remova1 from the shipp.;ng skid,."and
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placement in storage in4the~ containment building. .
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, U.S. Atomic Energy 10-20-72 Commission FAILURE OF MOVING EQUIPMENT In its horizontal position on elevation 130 of the reactor containment building, the rear of the reactor lower internals skid mounted assembly rested pn an upending cart, and the front was supported by a transverse bolster beam supported at each end on a three-wheel rail truck. The towing of the assembly along the access bridge rails on elevation 130 was accomplished by an air driven winch with the towing c ible attached to the upending cart. During the towing operation, an approximate vertical misalignment of
~
1/8" in the innermost rail splice presenf.ed an obstruction to the rail tru:k wheels; supporting the bolster beam at the front of the assembly. A force couple was thereby established wtich tended to rotate the bolster beam forward about its attachment poirls on the rail truck" axles. The rear flange of the bolster beam, attempting to resist the rotation, yielded, and allowed the rotation to continue. The bolster beam proceeded to yield plastically, forcing the rail tracks to spread out, and lowering the front of:the skid mounted assembly to the operating floor. The total distance that the front of the assembly was lowered was approximately 6'-6",
and the horizontal forward movement from start of descent to rest was approx imately 3 '- 10" .
. EQUIPMENT INSPECTION At the request of PSE&G, this incident was immediately reported by Westinghouse site engineers to their headquarters.
Westinghouse Core Structure Engineering, Quality Assurance and Nuclear Construction Departments became directly involved with the site engineers and PSE&G in specifying, supervising, and performing Fequired inspections. The inspections assured that no damage was custained or dimensiunal changes occurred to the lower internals which would affect the design or operation of the ecmponent.
Inspections which have been performed by Westinghouse QA and site engineers and PSE&G sponsor, engineers are:
- 1. External Inspection of LowerfInternals and Skid:
The wooden shims placed between the radial core support keys and tha, skid and between the plywood c flange cover and the skid remained in place and intact. The internals-to-skid tie-down-cables remained. tight with no evidence of movement away from the assembled position. The skid runner beams showed no evidence of, deflection,-the bolted joints of the skid (vere intact and tight,
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o o U.S. Atomic Energy 10-20-72 Commission EQUIPMENT INSPECTION (Continued) and the internals packaging material was intact.
The bottom flanges of the skid runners at the
, point of contact with the front truck bolster beam became slig htly beat. The inspecting parties concluded from their external inspec-tion that there was no evidence of the load shifting in the skid.
- 2. Internal Inspection of Lower Internals: The pads of the baffle (fuel) cavity shipping braces were found to be tight with no apparent movement from the installed poaition. The secessible lower support columns showed no evidence of movement or looseness. The baffle cavity measurements were taken and no change was noted from the measurements taken while the internals were in pre-installation storage.
The inspecting parties concluded from their internal inspection that there was no evidence of damage from the incident or other causes.
The Westinghouse Core Structure Engineering Department concurred with the inspecting engineers in this conclusion and work was resumed in placing the assembly in its storage position in the containment building.
PRECAUTIONS TO PREVENT RECURRENCE The front rail truck bolster beam was replaced by a box beam which is inherently better able to resist eccentrically I applied loads. .The original bolster beam was a wide flange beam
! with unstiffened' flanges where the load was applied. However, to~
! preclude eccentric loading, intermediate outrigger beams were placed between the bolster beam and the internals assembly skid runners in a direction parallel to the runners. Tha outriggers would then develop the necessary restorind moments should the front bolster beam and rail truck assembly encounter an obstruction.
The outrigger beams were laterally braced and stiffened.
l.
l' The rail splices were adjusted to eliminate steps,and steel bearing plates were used beneath the . splices.
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U.S. Atomic Energy 10-20-72 Commission l
l FO LLOW- UP On completion of erection of the clean area protective enclosure arcund the upended reactor lower internals, PSE&G will, for added assurance, have Westinghouse perform additional inspections. Should those inspections reveal previously hidden damage, an amended report will be submitted; otherwise no further reports relative bo this incident will be made.
If you should have any questions on the subject report, we will be pleased to further discuss them with you.
Very truly yours, 1
CC Mr. J. P. O'Reilly Newark, N. J.
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