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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217M2101999-10-19019 October 1999 Forwards NRC Rept Number 17, Requal Tracking Rept from Operator Licensing Tracking Sys.Rept Was Used by NRC to Schedule Requalification Exam for Operators & Record Requal Pass Dates ML18107A5601999-10-18018 October 1999 Submits 30-day Fuel Clad Temp Rept,Iaw 10CFR50.46.Rept Describes Changes to Calculated Peak Clad Temp (PCT) for Salem Generating Station Large & Small Break LOCA Analyses ML18107A5531999-10-0808 October 1999 Forwards Summary Rept of Plant Startup & Power Ascension Testing for Sgs,Unit 2 Cycle 11,per Requirements of TS 6.9.1.1 ML18107A5561999-10-0707 October 1999 Requests Relief Associated with Containment Examinations at Hope Creek & Salem Generating Stations.Attachment 1 Includes Proposed Alternatives & Supporting Justification for Relief Requests ML18107A5501999-10-0505 October 1999 Provides Current Status of Pse&G Actions Re GL 98-01, Y2K Readiness of Computer Sys at Npps, for Salem Nuclear Generating Station,Units 1 & 2 & Hope Creek Nuclear Generating Station ML18107A5521999-10-0505 October 1999 Encourages NRC to Support Abb Combustion Engineering Nuclear Power Request for Priority Review of Generic TR Re Crossflow Ultrasonic Flow Measurement Sys ML18107A5591999-10-0505 October 1999 Informs That Nj Dept of Environ Protection Has No Comments on License Change Request S99-07 for Sgs,Units 1 & 2 IR 05000272/19990071999-09-28028 September 1999 Forwards Insp Repts 50-272/99-07 & 50-306/99-07 on 990721- 0831.One Potentially Safety Significant Issue Identified Dealing with Control Room Special Ventilation System.Four Addl Issues of Low Safety Significance Identified ML18107A5341999-09-22022 September 1999 Provides Data Re Operator Licensing Exam for Salem & Hope Creek Station,In Response to NRC Form 536 (7-1999) ML18107A5421999-09-22022 September 1999 Forwards Discharge Monitoring Rept for Salem Generating Station for Aug 1999.Rept Is Required by & Prepared Specifically for EPA & Nj Dept of Environ Protection ML20212B3631999-09-14014 September 1999 Forwards Rev 13 to Salem - Hope Creek Security Plan,Iaw 10CFR50.54(p).Summary of Proposed Changes to Plan,Encl. Encl Withheld ML18107A5331999-09-13013 September 1999 Provides Notification That PSEG Intends to Utilize ASME Code Case N-481 During Second ISI Interval at Sgs Units 1 & 2 ML18107A5351999-09-13013 September 1999 Informs That NRC Has Reviewed Pse&G Request Proposing to Modify TS Which Allow EDG to Be Operated for 24 Surveillance Test During Any Mode,Iaw 10CFR50.91(b) & Has No Comments ML18107A5321999-09-13013 September 1999 Forwards Revised 10CFR50.92 Evaluation to Clarify Util Response to Question Number 1 Re Amend to Modify TS 3/4 8.1, AC Power Sources. ML18107A5221999-09-0808 September 1999 Requests Approval to Use ASME Code Case N546,which Provides Alternative Qualification Requirements That Allow Personnel Most Familiar with Walkdown of Plant Sys,Like License Operators to Perform VT-2 Examinations ML18107A5231999-09-0808 September 1999 Forwards Salem Generating Station Semiannual Radioactive Effluent Release Rept for Jan-June 1999. Rept Summarizes Liquid & Gaseous Releases & Solid Waste Shipments from Salem Generating Station for Period of Jan-June 1999 ML18107A5181999-08-26026 August 1999 Forwards Ninety Day Rept for ISI Activities Conducted at Sgs,Unit 2 During Ninth Extended Outage & Tenth Refueling Outage.List of Encl,Provided ML18107A5061999-08-26026 August 1999 Provides First Feedback from Observation of NRC Insp Under Pilot Nuclear Power Plant Insp Program.Attached Are Completed Insp Feedback Forms for Procedure 71111, Attachment 21 & Procedure 71151 ML18107A4981999-08-26026 August 1999 Forwards Response to NOV That Resulted from Predecisional Enforcement Conference Conducted on 990624.Corrective Actions:Communications to Supervisors Reinforced Employee Right & Duty to Raise Nuclear Safety Issues ML18107A5051999-08-24024 August 1999 Informs That Nj Dept of Environ Protection Bureau of Nuclear Engineering Has Reviewed Request IAW Requirements of 10CFR50.91(b) & Has No Comments Re Amend to FOL Change Request S99-02 to Modify TS Re Penetration Valves ML18107A4921999-08-23023 August 1999 Provides Suppl Info Re 971024 Amend Request to Modify TS 3/4 7.7, Auxiliary Bldg Exhaust Air Filtration Sys. Util Withdraws from Request All Proposed Changes Associated with Filter Testing,Per Issuance of GL 99-02 ML18107A4911999-08-20020 August 1999 Forwards Revised Plant Attribute Libraries for Salem & Hope Creek Generating Stations,Iaw 10CFR50,App E,Vi, Emergency Response Data Sys, 3.b.Changes Are Identified by Rev Bars ML18107A4861999-08-19019 August 1999 Forwards NPDES Discharge Monitoring Rept, for Salem Generating Station for Month of Jul 1999.Rept Required by & Prepared Specifically for EPA & Nj Dept of Environ Protection ML18107A4831999-08-18018 August 1999 Submits Licensee Comments on NRC 990730 Ltr Which Provided Notification of Close Out of TAC Numbers MA0567 & MA0568 Re GL 92-01,Rev 1,Suppl 1 ML18107A4801999-08-13013 August 1999 Requests That Pse&Gs Contact in NUREG-0383, Directory of Compliance for Radioactive Matl Packages, Be Changed ML18107A4751999-08-0505 August 1999 Forwards Fitness for Duty Performance Data Rept for Six Month Period Ending 990630 ML20210M7571999-08-0404 August 1999 Forwards Response to Requesting Addl Info Re Status of Decommissioning Funding for Lgs,Pbaps & Sngs. Attachment Provides Restatement of Questions Followed by Response ML18107A4531999-07-20020 July 1999 Forwards Discharge Monitoring Rept for Salem Generating Station, for June 1999.Rept Is Required by & Prepared for EPA & Nj Dept of Environ Protection ML18107A4431999-07-0606 July 1999 Informs That Nj Dept of Environ Protection Bureau of Nuclear Engineering Has Reviewed Pse&G License Change Request S98-17 Re Permissible Enrichment Values for New Fuel Storage & Has No Comments ML20196J6301999-07-0101 July 1999 Requests Addl Info Re Status of Decommissioning Funding for Limerick Generating Station,Units 1 & 2,Peach Bottom Atomic Power Station,Units 1,2 & 3 & Salem Nuclear Generating Station,Units 1 & 2 ML18107A4181999-06-30030 June 1999 Submits Response to NRC Request for Info Re Y2K Readiness at Npps,Per GL 98-01,suppl 1.Disclosure Encl ML20209B6751999-06-29029 June 1999 Ack Receipt of from Dr Powell in Response to NRC Re Fitness for Duty.Attachment 2 of Will Be Withheld from Public Disclosure,Per 10CFR2.790 ML18107A4131999-06-25025 June 1999 Provides Further Clarification of Licensing & Design Basis for 125 Vdc Battery Margins for Sgs & HCGS for Meeting Station SBO & Loca/Loop Loading Requirements,Per Util 990426 Ltr & Discussion with NRC ML18107A4091999-06-22022 June 1999 Forwards Discharge Monitoring Rept for May 1999,containing Info as Required by Permit NJ0005622.Rept Prepared Specifically for EPA & Nj Dept of Environ Protection ML18107A4061999-06-21021 June 1999 Provides Supplemental Info to Proposed License Amend, Modifying TS 3/4 7.7, Auxiliary Bldg Exhaust Air Filtration Sys. Info Re Acceptance Criterion Discussed ML18107A3691999-06-11011 June 1999 Forwards Corrected Monthly Operating Rept for Apr 1999 for Salem Generating Station,Unit 1.Original Submittal Contained Typo for year-to-date Value for Numbers of Hours Generator Was on Line (Service Hours) ML18107A3641999-06-0404 June 1999 Requests Enforcement Discretion for TS 3/4.6.2.3 Re Containment Cooling Sys for Salem Generating Station,Unit 1 ML18107A3561999-06-0303 June 1999 Informs That Nj Dept of Environ Protection Bureau of Nuclear Engineering Has Reviewed Pse&G License Change Request S99-05 & Has No Comments ML18107A3611999-05-27027 May 1999 Forwards Responses to NRC 990301 & 990323 RAIs for Salem & Hope Creek Generating Stations Relating to GL 96-05 ML18107A3301999-05-24024 May 1999 Forwards Suppl Info Re GL 95-07, Pressure Locking & Thermal Binding of Safety Related Power Operated Gate Valves. Encl Contains Methodology Used in Determination of Pressure Locking Susceptibility of PORVs Block Valves ML18107A3371999-05-21021 May 1999 Forwards NPDES Discharge Monitoring for Salem Generating Station for Apr 1999, Containing Info as Required by Permit NJ0005622 ML18107A3291999-05-20020 May 1999 Forwards Redacted Response to NRC 990322 RAI Re Notification of Licensed Operator That Tested Positive for Alcohol. Attachment 2 Withheld,Per 10CFR2.790(a)(6) ML18107A3031999-05-18018 May 1999 Provides Summary of Changes to NRC Commitments That Have Been Made But Not Reported by Other Means,Iaw with NEI Process for Managing NRC Commitments ML18107A2891999-05-13013 May 1999 Forwards Rev 36 to Pse&G Nuclear Business Unit Emergency Plan. Rev 36 Incorporates Changes to Section 1-3,6 & 7 & 9-17.Attached Copy Includes All Sections of EP for Completeness ML18107A2951999-05-12012 May 1999 Submits SG Tube Plugging Rept,Per Plant TS 4.4.6.5.a.Total of 47 Tubes Were Plugged During SG Tube Insps,Which Were Completed During Plant Tenth RFO ML18107A2861999-05-11011 May 1999 Forwards Rev 0 to NFS-0174, COLR for Salem Unit 2 Cycle 11. COLR Rept Was Received by Util as Part of Reload SE ML18107A2481999-04-29029 April 1999 Forwards 1998 Annual Radiological Environ Operating Rept for Salem & Hope Creek Generating Stations. Rept Summarizes Results of Radiological Environ Surveillance Program for 1998 ML18107A2511999-04-27027 April 1999 Submits 30-day Fuel Clad Temp Rept for Salem Generating Station,Units 1 & 2.Rept Describes Changes to Calculated Peak Clad Temp (PCT) for Plant Large & Small LOCA & Small Break LOCA Analyses ML18107A2631999-04-26026 April 1999 Provides Clarification on Licensing & Design Basis for 125 Vdc Battery Margins for Sgs & HCGS for Meeting SBO & Loca/ LOOP Loading Requirements ML18107A2371999-04-26026 April 1999 Forwards Corrected Response to NRC RAI Re Licensee Request for Change to TS Permissible Enrichment Values for New Fuel Storage.Incorrect Attachment Was Provided with Util 990412 Ltr to Nrc.Encl Supersedes 990412 Submittal 1999-09-08
[Table view] 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
[Table view] Category:UTILITY TO NRC
MONTHYEARML18095A4881990-09-17017 September 1990 Requests Regional Waiver of Compliance from Tech Spec 3.6.2.3, Containment Cooling Sys. Waiver Requested in Order to Allow Replacement of Containment Fan Cooler Unit Motor #22 W/O Requiring Plant Shutdown ML18095A4901990-09-13013 September 1990 Provides Supplemental Info Applicable to Clarification of 10CFR50,App R Exemption Request Re Fire Suppression Sys for Panel 335,per NRC Request ML20059E6821990-09-0404 September 1990 Forwards Info Re Temporary Mod to Security Plan Concerning Protected Area.Info Withheld ML18095A4641990-08-31031 August 1990 Forwards Revised Response to NRC Bulletin 88-004 Re Potential pump-to-pump Interaction.Util Pursuing Permanent Solution to Issue & Will Implement Appropriate Permanent Field Change by End of Unit 1 10th Refueling Outage ML18095A4621990-08-31031 August 1990 Provides Revised Response to Generic Ltr 89-13, Svc Water Problems Affecting Safety-Related Equipment. Only HXs Exhibiting Unsatisfactory Test Results Will Be Inspected & Possibly Cleaned ML18095A4431990-08-30030 August 1990 Forwards Salem Generating Station Semiannual Radioactive Effluent Release Rept,Jan-June 1990 & Rev 6 to Odcm. ML18095A4531990-08-30030 August 1990 Forwards RERR-28, Salem Generating Station Semiannual Radioactive Effluent Release Rept for Jan-June 1990 & Revised Odcm.W/O Revised ODCM ML18095A4391990-08-29029 August 1990 Forwards Semiannual Rept Re fitness-for-duty Performance Data for 6-month Period Ending 900630,per 10CFR26.71(d).Rept Includes Testing Results,Random Testing Program Results & Confirmed Positive Tests for Specific Substances ML18095A4421990-08-28028 August 1990 Clarifies 900710 Request for Amends to Licenses DPR-70 & DPR-75,changing Sections I & M.Under Proposed Change,Section I Should Be Changed to Read Section 2.J for License DPR-70 & Section M Changed to Read Section 2.N for License DPR-75 ML20059B6611990-08-22022 August 1990 Confirms That 10 Anchor/Darling Model S350W Swing Check Valves Installed at Plant,Per NRC Bulletin 89-002.All 18 Valves Inspected & Retaining Block Studs Replaced W/Upgraded Matl.No Crack Noted on Any Studs Which Were Replaced ML20059C2861990-08-21021 August 1990 Provides Correction to 900810 Response to Request for Addl Info Re Util Request for Restatement of OL Expiration Dates ML18095A4151990-08-10010 August 1990 Forwards Response to Request for Addl Info Re Reinstatement of OL Expiration Dates Based on Original Issuance of Ols. Advises That Correct Expiration Date for OL Proposed to Be 200418 ML18095A4091990-08-0909 August 1990 Forwards Responses to NRC Comments Re Plant Simulator Certification for 10CFR55.45(b)(2),per 891228 Ltr ML18095A4061990-08-0808 August 1990 Forwards Corrected marked-up Pages for Tech Spec Table 3.3-11 Re Subcooling Margin Monitor & Reactor Vessel Level Instrumentation Sys,Per 900223 Ltr.Administrative Changes Made as Indicated ML18095A3861990-07-30030 July 1990 Forwards Listing of Station Blackout Major Audit Items Resolution Scope,Per Station Blackout Schedule Commitment ML18095A3661990-07-26026 July 1990 Forwards Decommissioning Repts for Hope Creek,Peach Bottom & Salem Nuclear Generating Stations ML18095A3761990-07-26026 July 1990 Forwards Decommissioning Repts & Certification of Financial Assurance for Plants ML18095A3721990-07-24024 July 1990 Forwards Rept & Certification of Financial Assurance for Decommissioning for Plants,Per 10CFR50.75 ML18095A3751990-07-18018 July 1990 Provides Status of Commitments Made to NRC by Util in 900109 Ltr Re NUREG-0737,Item II.D.1,per 900628 Telcon ML18095A3741990-07-18018 July 1990 Provides Supplemental Info Re Facility sub-cooling Margin Monitor ML18095A3611990-07-18018 July 1990 Responds to NRC Bulletin 90-001, Loss of Fill-Oil in Transmitters Mfg by Rosemount. ML18095A3621990-07-18018 July 1990 Forwards Corrected Tech Spec Page 3/4 3-5 for License Change Request 89-12 Submitted on 891227 & 900521 ML18095A3591990-07-13013 July 1990 Corrects Typo in 900702 Response to Generic Ltr 90-04 Re Schedule for Completion of Remaining Open Items ML18095A3471990-07-11011 July 1990 Responds to NRC 900611 Ltr Re Violations Noted in Insp Repts 50-272/90-14 & 50-311/90-14.Corrective Actions:Directive from Radiation Protection Mgt to All Radiation Protection Personnel Issued Re Control of Compliance Agreement Sheets ML18095A3451990-07-10010 July 1990 Forwards Addl Info Re License Change Request 89-03 Re Reactor Trip Sys Instrumentation ML18095A3461990-07-10010 July 1990 Responds to NRC 900608 Ltr Re Violations Noted in Insp Repts 50-272/90-12 & 50-311/90-12.Corrective Actions:Assessment of ECCS & Component Performance Undertaken & ECCS Flow Testing Procedure Upgraded to Address Human Factors ML18095A3491990-07-10010 July 1990 Forwards Jn Steinmetz of Westinghouse 900614 Ltr Re Reassessment of Util Response to Bulletin 88-002 ML18095A3481990-07-10010 July 1990 Submits Supplemental Rept Identifying Root Cause of Missed Commitment & Corrective Actions to Assure Future Compliance Re Implementation of Mods to Facility PASS ML18095A3441990-07-0909 July 1990 Provides Written Notification Re Change in Calculated Peak Clad Temp,Per 900606 Verbal Notification ML18095A3281990-07-0202 July 1990 Responds to NRC 900530 Ltr Re Violations Noted in Insp Repts 50-272/90-09 & 50-311/90-09.Corrective Actions:Util Intends to Use Nuclear Shift Supervisor as Procedure Reader & EOP, Rev 2 Under Development ML18095A3301990-07-0202 July 1990 Responds to Generic Ltr 90-04 Re Status of Licensee Implementation of Generic Safety Issues.Table Describing Status of Generic Safety Issue Implementation Encl ML18095A3391990-06-29029 June 1990 Forwards Correction to 890913 License Change Request 88-09, Consisting of Tech Spec Page 3/4 4-13 ML18095A3221990-06-28028 June 1990 Provides Supplemental Info Re 900223 Proposed Revs to Tech Specs for Reactor Vessel Level Instrumentation Sys.Tables 3.3-11a & 3.3-11b Should Be Combined Into Single Table ML18095A3231990-06-28028 June 1990 Responds to NRC 900518 Ltr Re Violations Noted in Insp Repts 50-272/90-10,50-311/90-10 & 50-354/90-07.Two Noncited Violations Disputed.Util fitness-for-duty Program Exceeds Part 26 Requirements for Positive Blood Alcohol Limits ML18095A3241990-06-28028 June 1990 Forwards Retyped Pages to 871224 License Change Request 87-15 & Modified,Per 900620 Ltr ML18095A3211990-06-26026 June 1990 Requests 30-day Extension Until 900730 to Provide Completion Schedule to Resolve Audit Findings Re Station Blackout ML18095A3161990-06-25025 June 1990 Forwards Supplemental Info Re Response to Generic Ltr 88-14. All Committed Actions Complete as of 900613 ML18095A3141990-06-25025 June 1990 Provides Schedule Change for Implementation of Control Room Mods.Schedule Modified to Address Overhead Annunciator Human Engineering Discrepancies During Phase III ML18095A3201990-06-25025 June 1990 Responds to NRC 900524 Ltr Re Violations Noted in Insp Repts 50-272/90-11 & 50-311/90-11.Corrective Actions:All Overdue Operations & Maint Procedure Files Reviewed for Outstanding Rev Requests & Procedure Upgrade Program Initiated ML18095A3001990-06-20020 June 1990 Provides Addl Info Re Application for Amend to Licenses DPR-70 & DPR-75 Concerning Turbine Valve Surveillance Interval,Per 900320 Request.Util Adding Direction to Personnel If Unnacceptable Flaws Found ML20043H6221990-06-20020 June 1990 Provides Supplemental Info Re NRC Bulletin 88-008 for Fifth Refueling Outage.Detailed Test Rept Being Prepared to Document Results of Each Individual Insp Re Insulation, Hangers & High Energy Break Areas ML18095A2991990-06-20020 June 1990 Forwards Westinghouse Affidavit Supporting 900412 Request for Withholding Proprietary Info from Public Disclosure Per 10CFR2.790 ML18095A2721990-06-0808 June 1990 Responds to NRC 900329 Ltr Re Weaknesses Noted in Insp Repts 50-272/90-80 & 50-311/90-80.Corrective Actions:Fire Doors Placed on Blanket Preventive Maint Work Order & Damaged Fire Doors Will Be Repaired Immediately ML18095A2711990-06-0606 June 1990 Submits Info in Support of 900522 Verbal Request for Relief from Requirements of ASME Section XI ML18095A2611990-06-0101 June 1990 Forwards Corrected Operating Data Rept, Page for Apr 1990 Monthly Operating Rept ML18095A2521990-06-0101 June 1990 Forwards Application in Support of Request for Renewal of NJPDES Permit NJ0005622,per Requirements of Subsection 3.2 of Plant Environ Protection Plan,Nonradiological ML18095A2591990-06-0101 June 1990 Forwards Corrected Unit Shutdown & Power Reductions, Page for Apr 1990 Monthly Operating Rept ML18095A2411990-05-30030 May 1990 Submits Special Rept 90-4 Addressing Steam Generator Tube Plugged During Fifth Refueling Outage.Plugging Completed on 900516.Cause of Tube Degradation Attributed to Normal Wear Due to Erosion/Corrosion Factors ML18095A2431990-05-30030 May 1990 Informs of Util Plans Re Facility Cycle 6 Reload Core, Expected to Achieve Burnup of 16600 Mwd/Mtu.All Postulated Events within Allowable Limits Based on Review of Basis of Cycle 6 Reload Analysis & Westinghouse SER ML18095A2531990-05-29029 May 1990 Provides Addl Info Re End of Life Moderator Temp Coefficient.Feedback Used in Steam Line Break Has No Relationship to Full Power Moderator Density Coefficient 1990-09-04
[Table view] |
Text
.; *O PSEG Public Service Electric and Gas Company P.0; Box 236 Hancocks Bridge, New Jersey 08038
' Nuclear Depedment November 17, 1983
, Dr.:Th6 mas Murley LRegional; Administrator U.S. Nuclear Regulatory Commission
-631 Park Avenue King of-Prussia, Pennsylvania 19406
Dear Dr. Murley:
IE BULLETIN 83-06 NONCONFORMING: MATERIALS SUPPLIED BY TUBE-LINE CORPORATION NO. l'AND 2 UNITS SALEM. GENERATING STATION DOCKET NOS. 50-272 AND 50-311
'PSE&G_has performed the following actions in response to the referenced Bulletin.
Item 1 Review the list of purchasing and rece'iving companies given
. in Attachments 2 and 3 and determine if any Tube-Line (T-L) supplied materials have-been furnished for your facility._
Response::
We have reviewed the list of purchasing and receiving companies given in Attachments 2 and 3 to the Bulletin. Additionally, we physically checked the mill test reports of vendors of pipe fittings and components to determine the vendor's source. We have found.that the following principal suppliers have provided material furnished by Tube-Line Corporation: Louis P. Canuso, h Inc., Capitol Pipe _and Steel Company, and Empire Valve and Fitting Company.
Item 2A.
1 i Provide a list of.the T-L supplied materials and identify the systems in which these materials are/will be installed.
Response:-
A listing of the materials furnished by the above suppliers and the systems in which they are installed is provided in Attach-ment 1.
8311280527 831117 PDR ADOCK 05000272 k/
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The Energy People 95 2168(80 % 11 82 m
Dr._ Thomas Murley, Regional Administrator U.S. Nuclear Regulatory Commission 11/17/83 Item 2B Implement a program which provides assurance that received materials comply with ASME Code Section III and applicable procurement specification requirements, or which demon-strates that such materials are suitable for intended service. This program should include specific verifica-tion that received austenitic stainless steels are in a non-sensitized condition.
Response
The materials received through Capitol Pipe and Steel Co. and Louis P. Canuso Inc. (see Attachment 1) were readily rejected _
,and returned to the vendor for nonconformance.
An engineering evaluation was conducted to verify the integ-rity and suitability of those. fittings that are installed in safety-related systems. (See Attachment 2)
To assure that austenitic stainless steel is procured in the non-sensitized condition, we are currently revising our piping specification to include ASTM 262, Practice A - Oxalic Acid Etch Test. This test is for detecting susceptibility to intergranular attack in stainless steel.
Item 2C Replace fittings and flanges with materials which have been manufactured in full compliance with ASME Code Section III and the applicable procurement specification requirements.
Response
-The PSE&G Engineering Evaluation (Attachment 2) concluded that the' material integrity of the subject fittings is well assured. The certified material test report showed chemical and physical properties within ASTM specification. Addition-ally, 100% Radiography (RT) and 100% Magnetic Particle Testing (MT) combined with the tensile testing met Nuclear Class 1 material testing requirements.
Item 3 For ASME' Code materials furnished by T-L which are installed in safety-related systems in operating plants, the following actions are requested: a, b, c.
l
Response
This action is addressed in 2a, 2b, 2c and Attachment 1 and 2.
Dr. Thomas Murley, Regional Administrator U.S~. ' Nuclear Regulatory Commission 11/17/83
.Should you have any questions, please do not hesitate to contact us.
Sincerely,
'A_ .
E. A. Liden Manager - Nuclear Licensing and Regulation Attachment CC: Mr. Donald C. Fischer Licensing Project' Manager Mr. James Linville Senior Resident Inspector
' ~
U ."O 87:Nu'cle a rZ Rsiju 15'E5EfiComisi is ion f DocumentXConte 51 e-DiskM
, Washington, D.C. 20555 I~
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ATTACHMENT'l ,
EUPPLIER ITEM DESCRIPTION PURCHASE SYSTEM IS INSTALLED LOCATION OF DISPOSITION ' RENARKS ORDER NO. SAFETY RELATED INSTALLATION .
Capitol Pipe s Steel 2-8* TEE, SCH.10, ASTM A234 WPB P2-009018 . NA NO MA DR 9 R1-02-83-155 (10/3/8 TO DE RETURNED ** SE not required since .
Co. Tube-Line 7-6* TEE SCH 40 P2-009018 NA NO NA TO THE V9NDOR DISPOSITIONED 10/6/83 this was installed on 1-6* TEE, SCH. 40,(Heat 9 EYPH) P2-009018 NO - TES** NON SR SYSTEM Won-Safety related system.
(Louis P. Canuso 1- 8* E 90* Elbow ASTM- 217979' NA NO NA SEE Rejected and returned to Inc.) A403 TP316L DR9 04-82-091 SCRAPPED vendor Tube-Line 2 10* X 45' Elbow ASTM A403 217979 NA NO NA TP316L (Capitol Pipe a 12- 3/4" rianges P2-002704 NA NO . NA RETURNED TO VENDOR FOR SE Wot REQUIRED Steel Co. ) 12- 1" rianges P2-003077 NA. . NO MA - . _ - - - TE Tube-Line 12. I 1/2* rianges P2-002798 NA NO NA (Louis P. Canuso 4- 4* Cape, Sch. 40, 883865
- SE not required Non-Safety Inc.) ASYM A403 WP 304 . NO 'YES NON SR SYSTEM NO ACTION related systee Tube-Line (Empire Valva 1- 3" x 90* Elbow ASME 21 % 68 NO ***YES NON SR SYSTEM NO ACTION *** SE not required.
Pitting Co.) S A4 20 WPLG, Installed on NSR System Tube-Line Meat Code EOQ 1- 3* X 90* Elbow 219668 YES t YE9 CHILLED WATER MATERIAL ADEQUACY EMAMINED AND VERIFIED. t See Attached Safety ASME SA420 WPLG NO FURTHER ACTION REQUIRED Evaluatione Heat Code EOQ (Louis P. Canso 2-4* I 3' Reducing TECH. SCH.40 891743 YES YES CHILLED WATER See Attached Safety Inc) Tube-Line B.W. ASTM A234 WPB Evaluation.
4-3* X 90* Elbow SCH 40 B.W. 891743 YES YES CHILLED WATER ASTM A234WPB 1-3* E 45' Elbow, SCH 40 B.W. 891743 YES YES CHILLED WATER ASTM A234 WP 2-3* X 2 1/2* COAC. Red. B.W. 891743 YES' YES CHILLED WATER ASTM A234 WPB 1-3* X 90* Elbow, Sch. 40 B.W. 891743 NA NO CHILLED WATER USED FOR DESTRUCTIVE TESTING ASTM A234 WPB
's e
ATTACHMENT 2 Page 1 of 2 Date Oct. 19, 1983 Public Service Electric and Gas Company P.O. Box 236 Hancocks Bndge, New Jersey 08038 Nuc! ear Department TITLE: SAFETY EVALUATION OF NONCONFORMING MATERIALS SUPPLIED BY TUBE-LINE SALpM GENERATING STATION UNIT NO. 2 1.0 PURPOSE The purpose of this Safety Evaluation is to document the review of NRC IE Bulletin No. 83-06 on nonconforming materials supplied by Tube-Line and confirm the adequancy of affected components for intended service.
2.0 SCOPE This safety Evaluation applies to pipe fittings supplied by Tube-Line which are installed in the Chilled Water Piping System, SGS Unit No. 2.
3.0 REFERENCES
a) NRC IE Bulletin No. 83-06 (attached) b) Nondestructive Examination Reports (attached) c) Radiographic Examination Reports (attached) d) Certified Material Test Report HN-894 (attached) e) Certified Material Test Report 34414 P-1 (attached) f) PSE&G Research Corporation RTLR No. 67585 (attached) 4.0 DISCUSSION Responding to NRC IE Bulletin No. 83-06 (Ref. 3.a), our investigation revealed that the following fittings were supplied by Tube-Line.
a) 2 each 4"x3" Reducing Tee, Sch.40, B.W., ASTM A234 WPB b) 5 each 3"x90* L.R. Elbow, Sch.40, B.W., ASTM A234 WPB c) 1 each 3"x45' Elbow, Sch.40, B.W., ASTM A234 WPB d) 2 each 3"x2-1/2" Concentric Reducer, B.W., ASTM A234 WPB e) 1 each 3"x90* L.R. Elbow, Sch.40, B.W., ASTM A420 WPL6 All the above fittings, except one (1) 3"x90* elbow (Item 4.b above), were installed on safety-related piping components of the Chilled Water System.
To verify the material integrity and suitability of these fittings for the intended service, 100% Radiography ( RT) and 100% Magnetic Particle Testing (MT) were performed on three 3" x 90* elbow (Item 4.b), two 3" x 2-1/2" concentric reducer (Item 4.d) and one 3" x 90* elbow (Item 4.e).
E5/7 Th9 Energy ';c; EDD-7 FORM 1 REV 0 10 SEPT 81
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. Pcgo 2 of 2
^* '*I~ D2ts: Oct. 19, 1983 Both RT and MT found these fittings acceptable with no inherent defects (Ref's. 3.b and 3.c). The Certified Material Test Reports (Ref's. 3.d and 3.e) showed chemical and physical properties acceptable to ASTM specification. Additionally, one 3"x90* elbow that has not been installed was sent to PSE&G Energy Lab for testing (Ref. 3.f) and the tensile requirements were found to exceed those in the material specification, ASME/ ASTM A234 WPB.
5.0 CONCLUSION
AND RECOMMENDATION Based on the above discussion and written report of tests performed, the material integrity of the subject fittings is well assured. The total'of seven fittings examined are considered good representatives of the eleven (11) fittings supplied by Tube-Line. The installed ten (10) fittings will not, in any way, degrade the Chilled Water piping system, which is a Nuclear Class 3 system. The non-destructive examinations performed (RT and MT) combined with the tensile testing at the Energy Lab, in fact, exceed Nuclear Class 1 requirements. We recommend that all ten fittings remain in the system.
\
OJN:cbp ES/7 h MGm . Io Zo 83 Origin tor verifier i l
f Manager - Plant Engineering Piping, Materials & Stress Group Head EDD-7 FORM 1 REV 0 10 SEPT 81
.