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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h Public Service Electric and Gas Company 80 Park Placo Newark, N.J. 07101 Phono 201/622-7000 Kf,7'.
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- May 28, 1976 p.jg l
- Mr. James P. O'Reilly, Director tJ03 fS h
l2:YV,'F U.S. Nuclear Regulatory Commission $d Y. 2 k Office of Inspection and Enforcement % C . j
r Region 1 $f k.P ' i 631 Park Avenue f-Y ~~-
King of Prussia, Pennsylvania 19406 Q.' *.
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Dear Mr. O'Reilly:
STEAM GENERATOR HEAD CLADDING INDICATIONS NO. 1 UNIT SALEM NUCLEAR GENERATING STATION i
DOCKET NO. 50-272 c Supplenentary to our verbal report of April 8, 1976 and pre- gm .
liminary written report of May 5, 1976 concerning indications bi?.g. y' - .
in the stainless steel cladding of No. 1 Unit Steam Generator ((;.c 'r J E Heads, the following detailed report is submitted in accordance h*[.:h,.J.:
with orovisions of 10CFR50.55(c).
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01nraonuor1on b&g:
A Subsequent to our May 5, 1976 report, nondestructive examinations of the stsinless steel cladding in the heads of No. 1 Unit Steam kf j #91
.7 r Generators (11-14) were conducted using the water washable dye --/'j',%
- penetrant method. The results of these examinations Along with P
- L : .' .
7 metallurgical evaluation using replicar, have been reviewed by Westinghouse at Tampa, Florida. These evaluations have not re- M*);l[O i vealed the cause of the cladding indications. A program for YQy,g
- 74 ultrasonically monitoring a representative single area of clad-
_ ding indications in 'the cold leg of No. 14 Steam Generator is L f,,W,sg f planned, access permitting. If the studies show that these re- A;-
[ presentative cladding indications can be referenced successfully, %p.Q ,
a surveillance schedule vill be incorporated into the nuclear ((fy plant inservice inspection program. gig y p q. , w -
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- c. s Mr. J. P. O'Reilly 5/28/76 EXAMINATIONS A. NDE '
Nondestructive examination of the Unit 1 Steam Generators (ll-lb) using the water washable dye penetrant method revealed -
extensive transverse and longitudinal cladding indications at ___
bead overlaps and within the weld beads on the No. 14 Steam Generator. These defects were concentrated at one location -
on the upper bowl of the cold leg side in an area approximately 2' x 4'. The other steam generators No. 11, 12 and 13 and the hot leg cide of No. 14 Steam Generator showed minor, randomly _
scattered indications. In addition, the No. 11 hot leg ~and j No. 14 cold leg have indications at the toe of fillet veld on , __
the cladding joining the partition plate, to the head.
Although there were some clad indications in the nozzle of -
No. 14 Steam Generator cold leg, and minor indications in
~
other steam generator nozzles, there were no clad defects ta evident in any inner corner radii of the nozzle s.
~
E B. FERRITE ANALYSIS 2, A ferrite composition examination was conducted on the No. 14 ?
Steam Generator within the indication (2' x 4') zone as well ^
O as in areas where dye penetrant found no indications. .
Starting from the top of the channel head bowl, at the junction .:
of the tube sheet cladding to bowl cladding, each weld bead O was measured for ferrite with a Severn Gage. A series of _
locations across the No. 14 steen generator, approximately .c-'
18" apart, were checked for ferrite level. Results of the ;
analysis revealed that weld beads measured by the Severn Gage contained 3.5% to 12.5% measured ferrite. There was no significant difference in ferrite content between the areas -
with dye penetran.t indications and areas free from indications. -
C. MPLICATION h Four areas with dye penetrant indications were selected for replication of the surface condition. Replicas of acetate film were taken of the No. 14 Steam Generator cladding of the _
following surface conditions: -
(1) as deposited clad .
(2) polished clad (3) polished and etched clad.
- These replicas were examined at the Westinghouse Tampa Metallography Laboratory at 50 to 500 magnifications. The results show the indications to be fine, intergranular cracks.
O The mechanism explaining the formation and the d.ynamics of its propagation has not been formulated. -
7 T
1 O O Mr. J. P. O 'Reilly 5/28/76
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EXPLORATORY GRINDING Four areas where cracks were present in No. 14 cold leg were ground to a depth approximately one-half of the nominal cladding thickness to avoid exposing base metal. The cladding is nominally 0.250", therefore the maximum depth excavated was 0.125". All explored cracks propaged into the cladding normal to the clad surface. The four ground areas were re-examined with dye penetrant.
Three areas following grinding showed the cracks still present, while the fourth area 2" x 3", where grinding for chemistry was conducted, was free of any dye penetrant indications.
CHEMICAL ANALYSIS An area approximately 2" x 3" in the cracking zone of No. 14 Steam Generator was selected for chemical analysis. Results of spectrographic and chemical analysis of the chips revealed the clad metal to be within the specification for all metallic elements.
The carbon content was above the specification, however, this could be traced to the particles of grinding cutter abraded into the sample.
CONC LUSION S
\-The work jointly conducted by Westinghouse and PSE&G has succeeded in defining the scope of the problem at Salem Buelcar Generating Station (No. 1 Unit). The transverse and longitudin'al cracking is concentrated in one area (2' x 4') of the upper bowl of the cold leg of No. 14 Steam Generator. There are minor indications in the No. 11, 12 and 13 Steam Generators as well as the hot leg side of No. 14. The investigation to date has not determined the cause of the cracking but it.has determined that the condition at Salem closely parallels the defects revealed in channel head cladding at Consolidated Edison's Indian Point No. 3 Huclear Generating Station.
The controlled investigation conducted at Salem by Westinghouse and PSE&G has shown that in one isolated area 2" x 3', the defects in the cladding were removed prior to exposure of base metal.
Exposure of base metal was averted at Salem to prevent extensive veld repairs which have been previously experienced by others.
A review of the safety implications conclude that the cracks in the cladding at Salem Nuclear Generating Station, No. 1 Unit are acceptable as the integrity of the system is not compromised.
The Boiler and Pressure Code allows cladding indications and the subject of surface indications in cladding is defined as part of Section XI Code Case No. 1738 (attached).
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O O Mr. J. P. O'Reilly 5/28/76 OCONCLUSIONS (Continued)
The intent of the code case is to verify that the cracks are indeed confined to the cladding and do not progress into the base metal.
This condition can be reasonably substantiated by ultrasonic examination of representative cladding defects.
l This inspection conducted on the channel head will attempt to:
l l (a) identify the cladding indications on the cladding surface from the 0.D. of the head.
(b) measure the thickness of the cladding in the vicinity of the indication from the I.D. of the head (c) verify whether the cladding defect has propagated into the base metal.
If successlul, the ultrasonic exc.mination will then serve as the baseline pre:ervice inspection of the steam generator cladding.
The cladding indications will then be monitored as part of the inservice inspection program for the life-time of the nuclear plant. This examination will be complete by June 30, 1976.
( )fhe results of these exaninations will be available at the site.
If you require additional information our engineers will be available to discuss the details with you.
Very truly yours, k N.bc '
i E.N. Schwalje Manager of Quality Assurance Engineering and Construction Department CC: Dr. Ernst Volgenau Washington, D.C. 20555
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, CASI AS.\1Eltoll.Elt AND Pltr.SSt;IIC VESSEL COI Approved by Council, December 22, I975 ,
O .
Case 1738 Examination-Acceptance Standarcis for Surface Indica.
tions in Cladding Section XI
- l Inguiry: Isit permiwihlc to accept surface indications in the patches of clad surf.:cea examined in accordance with Category 1:l.1 and I:12.Tahte IWl:"600,iretion XI, gmided that the dtpths of the flaws are within the cladilin;; material?
Reply: It is the oi. inion of the Conunit tee that surface indications in the i.atches of clail >urfaces, namined in accordance with Catep.ry it i 1 and 111-2. Ta!.le IWII.
2600,Section XI, may 1.e permitted and the acceptance stand.irds of IWit.3'217.1 n:ay be waised, provith d the depths of the flaws are within the cl.nhiin: material.The prosisions of this Case may not !.c applied for the exand.
nation of clad surfaces on the inner corner r.idii of nozz!cs.
O Mectise of Octotcr 31,19n ,
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g UNITED STATES g
. NUCLEAR REGULATORY COMMISSION REGION 1 7#
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.Public Service Electric & Cas Company Docket No. 50-272 Attention: Mr. E. N. Schwalje QA Manager 80 Park Place Newark, New Jersey 07101
Reference:
Steam Cencrator Cladding Indications .
Salem Unit 1 Centlemen:
Thank you for your letter dated May 28, 1976 which forwarded a report pursuant to 10 CFR 50.55(e) regarding the above referenced item.
Please note that your final report of this matter must include the results of the proposed nondestructive examination of the cladding as stated in yor.r letter and any cther relevant information, such as your planned inservice monitoring program of the steam generator cladding.
Your ccoperation is appreciated.
Sincerely, lk{ Yr James P. O'Reilly
' Director a bec: .
IE Mail & Files (For Appropriate Distribution)
Central Files Public Document Room (PDR) -
Local Public Document Room (LPDR)
Nuclear Safety Information Center (NSIC)
Technical Information Center (TIC)
REG:I Reading Room State of New Jersey C 04 gyp (, $0CRWt*nh oh fr(VtOLU gOjhi tIW ') ')'A')*5~
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Public Service Doctric and Gas Company 80 Park Place Newark,N.J. 07101 Phone 201/622 7000
_ May 28, 1976 Mr. James P. O'Reilly, Director U.S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region 1 631 Park Avenue King of Prussia, Pennsylvania 19406
Dear Mr. O'Reilly:
STEAM GENERATOR HEAD CIADDING INDICATIONS NO. 1 UNIT SALEM NUCLEAR GENERATING STATION DOCKET NO. 50-272
' Supplementary to our verbal report of April 8, 1976 and pre-liminary written report of May 5, 1976 concerning indications in the stainless steel cladding of No. 1 Unit Steam Generator Heads, the follcwing detailed report is submitted in accordance with provisions of 10CFR50.55(c).
INTRO DUCTION Subacquent to our May 5, 1976 report, nondestructive examinations of the stainless steel cladding in the heads of No. 1 Unit Steam Generators (11-14) were conducted using the water washable dye penetrant method. The results of these examinations along with me tallurgical evaluation using replicas , have been reviewed by Westinghouse at Tampa, Florida. These evaluations have not re-vealed the cause of the cladding indications. A, program for ultrasonically monitoring a representative single' area of clad-
-ling indications in 'the cold leg of Ho. 14 Steam Generator is planned, access permitting. If the studies show that these re-presentative cladding indications can be referenced successfully, a surveillance schedule will be incorporated into the nuclear plant inservice inspection program. .
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The Enc.4w Fancle n ..
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O O 5/28/76
^
P. O'Reilly Mr. J. EXAMINATIONS NDE A.
Nondestructive examination of the Unit 1 Steam Generators
( 11- 14 ) u s i n g the wate r washable dye penetrant method revealed extensive transverse and longitudinal cladding indications at bead overlaps and within the veld beads on the No. 14 Steam Generator. These defects were concentrated at one location on the upper bowl of the cold leg side in an area approximately 2' x 4'. The other steam generators No. 11, 12 and 23 and the hot leg side of No. 14 Steam Generator showed minor, randomly scattered indications. In addition, the No. 11 hot le g and No. 14 cold leg have indications at the toe of fillet weld on the cladding joining the partition plate, to the head.
Although there were some clad indications in the nozzle of - -
No. 14 Steam Generator cold leg, and minor indications in other steam generator no r t le s , there were no clad defects .
evident in any inner corner radi1 of the noz z le s .
B. FERRITE AN A LY S I S A ferrite corrosition examination was conducted on the No. 14
^
Steam Generator within the indication (2' x 4') zone as well as in areas where dye penetrant found no indications.
Starting from the top of the channel heed bowl, at the junction of the tube sheet cladding to bowl cladding, each w eld bead was measured for ferrite with a Severn Gage. A series of locations across the No. 14 steam generator, app r o x ima t e ly 18" apart, were checked for ferrite level. Results of the an a ly s i s re ve a le d that veld beads measured by the Severn Gage contained 3.55 to 12.56 measured ferrite. There was no s i r,n _ f i c a n t difference in ferrite content between the areas with dye p e ne t ra n.t indications and areas free from indications.
C. RE P LI C A TI O N Four areas with dye penetrant indications were s e le c te d for replication of the surface condition. Replicas of acetate film were taken of the No. 14 Steam Generator cladding of the following surface conditions:
(1) as deposited clad (2) polished clad --
(3) polished and etched clad.
These replicas were examined at the Westinghouse Tampa Metallography L1boratory at 50 to 500 magnifications. The .
results show the indications to be fine, intergranular crackc. ~
The mechanism explaining the formation and the d.ynamics of its propagation has not been formulated. _
m-imm
Mr. J. 'P. O 'Reilly 5/28/76 EXPLORATORY GRIUDING s
Four areas where cracks were present in No. 14 cold leg were ground to a depth approximately one-half of the nominal cladding thickness to avoid exposing base metal. The cladding is nominally 0.250", therefore the maximum depth excavated was 0.125". All explored cracks propaged into the cladding normal to the clad surface. The four ground areas were re-examined with dye penetrant.
Three areas following grinding showed the cracks still present,
- while the fourth area 2" x 3", where grinding for chemistry was conducted, was free of any dye penetrant indications. ..
CHEMICAL AUAlYSIS -
An area approximately 2" x 3" in the cracking none of No. 14 Steam Generator was selected for chemical analysis. Results of spectro 6raphic and chemical analysis of the chips revealed the clad metal to be w. thin the specification for all metallic elements.
- The carbon content was above the specification, however, this could be traced to the particles of grinding cutter abraded into
- the sample.
[ CONC LUSIO N S The work jointly corducted by Westinghouse and PSE&G has succeeded in defining the scope of the problem at Salem Kuclear Gererating
=
- Station (No. 1 Unit). The transverse and longitudinal cracking is concentrated in one area (2' x 4') of the upper bowl of the cold leg of Uo. 14 Steam Generator. There are minbr indicativ.Es in the
- No. 11, 12 and 13 Steam Generators as well as the hot les cide of
[ No. 14 The investigation to date has not determined the cause of E
the cracking but it has determined that the condition at Sale =
F closely parallels the defects revealed' in channel head cladding a t Consolidated Edison's Indian Point No. 3 Nuclear Generating Station.
1 The controlled investigation conducted at Salem by Westinghouse and PSE&G has shown that in one isolated area 2" x in the cladding were removed prior to exposure of base metal.
3", the defects i]li ~ ~ - ~
Exposure of base metal was averted at Salem to prevent extensive weld repairs which have been previously experienced by others.
w A review of the safety implications conclude that the cracks in the cladding at Salem Nuclear Generating Station, No. 1 Unit are s acceptable as the integrity of the system is not compromised.
The Boiler and Pressure Code allows cladding indications and the subject of surface indications in cladding is defined as part of E '
Section XI Code Case No. 1738 (attached).
E L-r
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O Mr. J. P. O'Reilly -h- 5/28/76 _
CONC LUSION S (Continued) .
The intent of the code case is to verify that the cracks are indeed confined to the cladding and do not progress into the base metal.
This condition can be reasonably substantiated by ultrasonic
- cxamination of representative cladding defects. .
This inspection conducted on the channel head will attempt to:
(a) identify the cladding indications en the cladding surface from the O.D. of the head. . - ,
(b) mecsure the thickness of the cladding in the vicinity of the indication from the I.D. of the head (c) verify whether the cladding defect has propagated into the base metal.
If succcesful, the ultrasonic examination will then serve as the baseline pre se rvice inspection of the steam generator cladding.
The cladding indications will then be monitored as part of the inservice inspection program for the life-time of the nuclear .
plant. This examination vill..be complete by June 30, 1976. .
The results of these examinations vill be available at the site.
If you require additional information our engineers will be available to discuss the details with you.
Very truly yours,
_ 6 19. 5 : k E.N. S chwalj'e Manager of 0.uality Assurance Engineering and Construction Department CC: Dr. Ernst Volgenau Washington, D.C. 20555 6
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.. *t CASI' - AS11Cllull.Elt ANI)1*Ill3SI:ltU VD8El. Col Approved lay Council, Decernber 22, I975 Case 1738 Examination-Acceptance Standards for Surface Indica.
tions in Clodding ,
Section XI fnguiry: Is it perini=>ilde to accept surface indicatiuns in the pstches of cl.id entf.:cet emnine d in accordance with Category ll l.1 and 1: 12. Tahic IWl: 2(;00. itction XI, provided that the depths of the flaws.tre within the
- cladding niatcrial!
, Reply: It is the opinion of the Conunittre that surface indications in the pateir of clail >ntfaces cssinined in accordsuce with Categ ory 1:11 and 1312. Table IWil.
2000, Section NI, insy 1,e :.erinitted and the secri.tsnee standards of IWittl7.1 n:ay be wahed providctl the l depths of the fisws are within the claddin::inateris!.The provisions of this Case snay not he app!ied ic.r the exand.
nation of clad surfaces on the inner corner radii of nozzles.
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