Final Deficiency Rept Re Potentially Defective Parts Reported to NRC on 790924.No Identified Parts Have Been Installed in safety-related Applications.All Parts in Storage at Facility Recalled to Avoid Inadvertent UseML19323F345 |
Person / Time |
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Perry ![FirstEnergy icon.png](/w/images/a/ad/FirstEnergy_icon.png) |
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Issue date: |
10/22/1979 |
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From: |
Gold T B-LINE SYSTEMS, INC. |
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ML19323F058 |
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References |
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REF-PT21-79-156-001 NUDOCS 8005280804 |
Download: ML19323F345 (10) |
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Similar Documents at Perry |
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Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML18016A9011999-04-12012 April 1999 Part 21 Rept Re Defect in Component of DSRV-16-4,Enterprise DG Sys.Caused by Potential Problem with Connecting Rod Assemblies Built Since 1986,that Have Been Converted to Use Prestressed Fasteners.Affected Rods Should Be Inspected ML20248F3531998-05-21021 May 1998 Part 21 Rept Re Electronic Equipment Repaired or Reworked by Integrated Resources,Inc from Approx 930101-980501.Caused by 1 Capacitor in Each Unit Being Installed W/Reverse Polarity. Policy of Second Checking All Capacitors Is Being Adopted ML20217D5701998-03-20020 March 1998 Part 21 Rept 40 Re Governor Valve Stems Made of Inconel 718 Matl Which Caused Loss of Governor Control.Control Problems Have Been Traced to Valve Stems Mfg by Bw/Ip.Id of Carbon Spacer Should Be Increased to at Least .5005/.5010 ML20140G4481997-05-0101 May 1997 Part 21 Rept Re Potential Defect in Component of Dsrv & Dsr Enterprise Standby Diesel Generator Sys.Recommends That Springs Be Inspected on Periodic Basis,Such as During Refueling Outages ML20137F3221997-03-26026 March 1997 Part 21 Rept Re Perry Nuclear Power Plant Experiencing False Trip of K600S K-Line Low Voltage Circuit Breaker w/SS-5 Solid State Trip Device.Breaker Removed from Svc & Returned to Abb for Analysis ML20133E8001997-01-0808 January 1997 Deficiency Rept Re Nonconformance Related to Masterflow 713 Grout,Which Master Builders,Inc Has Supplied as Nuclear SR Product to 18 Npps.Cause Unknown.Requests That Listed Info Be Provided to Gain Insight as to Scope & Possible Cause ML20134H3361996-11-0505 November 1996 Part 21 Rept Re Defective Inner Thrust Bearing 1801461-01 Used in PSA 35 Mechanical Shock Arrestor Used as Restraint on Piping Sys for Nuclear Generating Plant.Lot of Defective Parts Located & Isolated to Three Customers ML20115D2001996-07-0909 July 1996 Part 21 Rept Re Mfg Defect of Enterprise DSR-4 & DSRV-4 Edgs,Originally Mfg by Calcon Corp.Amot Control Corp Purchased Calcon Product Line & Maintains Design & Production.Valves Returned to Cooper Energy Svcs on 960131 ML20083R9101995-04-26026 April 1995 Final Part 21 Rept Re Kepco,Inc Model RMX24-D-20804 Power Supplies in Which Transistors Q15 &/Or Q16 Failed to Open & R1 Was Open.Replacement of Transmitters w/XSIS-095 Along W/ Replacement of Electrolytic Capacitors Provides Solution ML20058K3841993-12-0909 December 1993 Part 21 Rept Re Potential Defect in Component of Dsrv & Dsr Enterprise Standby DG Sys,Regarding Potential Problem W/ Subcover Assembled Atop Power Head ML20059A7181993-10-19019 October 1993 Part 21 Rept Re Defective Rocker Arms Supplied to TU & Clei. Rocker Arms Machined & Inspected to Incorrect Print & Discovered at Tu.Defective Rocker Arms Recalled from Nuclear Customers.No Corrective Action Required at Respective Utils ML20056D7071993-07-15015 July 1993 Part 21 Rept Re Reportable defect-75 PSIG Relief Check Valve 1 Npt,Emd 9521844,Kepner 416C-1-75 ML20127H2301993-01-15015 January 1993 Part 21 Rept Re Potential Defeat in Component of Dsrv & Dsr Enterprise Standby DG Sys.Starting Air Distributor Housing Assemblies Installed as Replacement Parts at Listed Sites ML20126B0421992-12-17017 December 1992 Final Part 21 Rept Re Potential Problem W/Steel Cylinder Heads.Initially Reported on 921125.Caused by Inadequate Cast Wall Thickness at 3/4-inch-10 Bolt Hole.Stud at Location Indicated on Encl Sketch Should Be Removed PY-CEI-NRR-1518, Corrected Part 21 Rept Re Defects in MSIV Poppets Supplied by Atwood & Morrill Co,Inc,Originally Submitted Via .Corrects Info in Corrective Action Section to Indicate That Poppet S/N 4 Not S/N 3 Installed at Facility1992-07-0101 July 1992 Corrected Part 21 Rept Re Defects in MSIV Poppets Supplied by Atwood & Morrill Co,Inc,Originally Submitted Via .Corrects Info in Corrective Action Section to Indicate That Poppet S/N 4 Not S/N 3 Installed at Facility ML17289A6971992-06-26026 June 1992 Amend 1 to Part 21 Rept 158 Re gear-wear Induced Failures in engine-driven Jacket Water Pump in DSRV-16-4 Standby DG Sys. Initially Reported on 911029.Grand Gulf Station Observed Wear Characteristics in as Little as 500 Operating Hours ML20102B2071992-06-24024 June 1992 Part 21 Rept Re Cracking of Stellite 21 Hardfacing on Guide Nose of Poppets Supplied as Part of MSIV Leakage Improvement Mod.Initially Reported by Clei on 920522. Recommends That Liquid Penetrant Exam Be Performed ML20101G9211992-06-19019 June 1992 Part 21 Rept Re Rotated Fuel Assemblies Sometimes Inappropriate for Modern Type Fuel Designs.Reevaluation Concluded That Inadvertently Rotated Fuel Assembly for BWR 4/5 C-lattice Plant Could Not Exceed TS Safety Limit MCPR PY-CEI-NRR-1516, Part 21 Rept Re Defects in MSIV Poppets Supplied by Atwood & Morrill Co,Inc.Intially Reported on 920522.Measures Will Be Established to Ensure That Adequate Repair Methods Are Employed During Future Repairs of Modified MSIV Poppets1992-06-19019 June 1992 Part 21 Rept Re Defects in MSIV Poppets Supplied by Atwood & Morrill Co,Inc.Intially Reported on 920522.Measures Will Be Established to Ensure That Adequate Repair Methods Are Employed During Future Repairs of Modified MSIV Poppets ML20097H1531992-05-22022 May 1992 Part 21 Rept Re Defect in MSIV Poppets Supplied to Plant by Atwood & Morrill Co,Inc.Post Weld Heat Treatment Prescribed & Performed for Poppet to Alleviate Concerns Re Residual Stresses Present.Next Rept Will Be Submitted within 30 Days ML20094L1271992-03-13013 March 1992 Amend 1 to Part 21 Rept 159 Re Potential Defect in Power Cylinder Liner.Initially Reported on 920115.Caused by Liner/ Block Fit & Localized Matl Microstructure.All Drawings & Specs Revised to Address Matl Design Requirements ML20081F6091991-04-23023 April 1991 Part 21 Rept Re Edward Controlled Closure Check Valves & Testable Piston Check Valves Dashplate Bolt Failures Due to Rapid Valve Opening or Impulsive Differential Pressure Surge Across Dashplate.Design Changes Recommended PY-CEI-NRR-1303, Part 21 Rept Re Finding That Nitrile Rather than Ethylene Propylene Diene Monomer (Epdm) Used as Seal Matl in Several E-sys Hydraulic Snubbers.Proper Seal Matl (Epdm) Used to Rebuild Snubbers & Leaking Valves Repaired1991-02-0404 February 1991 Part 21 Rept Re Finding That Nitrile Rather than Ethylene Propylene Diene Monomer (Epdm) Used as Seal Matl in Several E-sys Hydraulic Snubbers.Proper Seal Matl (Epdm) Used to Rebuild Snubbers & Leaking Valves Repaired ML20065T1661990-12-19019 December 1990 Part 21 Rept Re Reportable Event Concerning Chilled Water Sys at Plant.Initially Reported on 901030 & 1130.Util Notified of Results of Evaluation & Reported Addl Details, Per 10CFR50.72 PY-CEI-NRR-1281, Part 21 Rept Re Failure of Several Asco Scram Solenoid Pilot Valves.Initially Reported on 901211.Faulty Valves Limited to Single Production Run.Installed Valves from Subj Production Run Replaced1990-12-14014 December 1990 Part 21 Rept Re Failure of Several Asco Scram Solenoid Pilot Valves.Initially Reported on 901211.Faulty Valves Limited to Single Production Run.Installed Valves from Subj Production Run Replaced ML17262A2621990-11-30030 November 1990 Part 21 Rept Re Chilled Water Sys.Initially Reported on 901030.Evaluation of Perry Plant Will Be Sent by 901230 ML20011F5971990-02-22022 February 1990 Part 21 Rept Re Solder Connections in Abb 27/59 Relays Deteriorated Due to Thermal Stress,Causing Bonding of Printed Wiring Pattern to Glass Epoxy Circuit Board.Interim Circuit Board W/Larger Pads & Higher Wattage Will Be Used ML20011F1941990-02-22022 February 1990 Part 21 Rept Re Abb 27/59 Relay Catalog Series 211L.Solder Connections to Printed Wiring Runs on Bottom of Circuit Board Deteriorated Due to Thermal Stress.No Actual Failure Occurred & Relays to Be Changed at Next Outage ML20248E0121989-09-13013 September 1989 Supplemental Part 21 Rept Re Potential Problem W/Six Specific Engine Control Devices in Air Start,Lube Oil, Jacket Water & Crankcase Sys.Initially Reported on 890429. California Controls Co Will Redesign Valve Seating ML20246K7401989-04-26026 April 1989 Part 21 Rept Re Incorrectly Stamped Name Plates on Certain Asco Nuclear Qualified Valves.Vendor Will Contact Each Affected Facility & Furnish Correctly Stamped Plates & in Near Future Discontinue Sale of Rebuild Kits for Valves ML20207P0451988-10-0505 October 1988 Part 21 Rept 146 Re Defect in Left Intercooler Inlet Adapter on Standby Diesel Engine Generator.Recommends Utils Inspect Left Intake Manifold Drain as Part of Operating Plan.Addl Info Expected by 881015 ML20154J4101988-05-12012 May 1988 Addendum 1 to Supplemental Part 21 Rept 145 Re Potential Problem w/F-573-156 Pressure Sensor/Lube Oil Trip.Initially Reported on 880429.Addl 1-1/8-inch Diameter W/Deep Counterbone in Pressure Head Added to Activate Valve 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 ML20153B6191988-04-29029 April 1988 Part 21 Rept Re Potential Defect in Component of Dsr or Dsrv Standby Diesel Generators Supplied to Utils.Recommends Return of Subj Components in Onsite Warehouse Storage & Suggests Surveillance of Devices Already Installed ML20151V8941987-12-22022 December 1987 Part 21 Rept Re Installation of Valve B/M RNU-205 W/ Undersized Motor Operator.Caused by Engineer Failure to Change Sizing from Previously Sized Motor Operator on Computer Program.Existing Operator Replaced ML20216E4721987-05-28028 May 1987 Part 21 Rept 140 Re Potential Defect in Air Pressure Regulators Mfg by Bellofram.Dripwell Gasket May Fail Due to Mismachining of Gasket Seating Surface Causing Loss of Control Air & Starting Air Pressure 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 ML20210F4741986-09-16016 September 1986 Part 21 Rept Re Possible Sticking in Closed or Partially Open Position on Dresser 3050 Diaphragm Valves.Initially Reported on 850118.Disc Caps,Including Chamfers on Outside Diameter,Will Be Modified ML20214M3181986-09-0404 September 1986 Potential Part 21 Rept Re Contromatics Actuator W/Jackscrew/ Handwheel Emergency Override Operator.Jackscrew/Handwheel Should Be Used for Emergency Manual Operation Only.Encl Ltr Also Sent to Listed Utils/Ae Firms ML20205F6141986-08-13013 August 1986 Part 21 Rept Re Connecting Rod Bolts for Dsrv Engines.Listed Procedures Recommended for Next Connecting Rod Insp, Including Replacement of Bolts Due to Cracked Threads & Large Grooves & Galls in Threads ML20207L1831986-07-18018 July 1986 Final Deficiency Rept (Rdc 146(86)) Re Hydraulic Control Units (Hcus) Not Installed Per Equipment Qualification Program.Initially Reported on 860619.Drawings Will Be Changed to Reflect Correct HCU Mounting Bolts Torque Values ML20206U0591986-07-0202 July 1986 Part 21 Rept Re Potential Defect in Component of Dsrv Standby Diesel Generators,Involving Problem W/Fastening of Engine Connecting Rod Assembly Which Could Result in Engine Nonavailability.Procedure Will Be Issued by 860718 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 ML20198E5401986-05-14014 May 1986 Final Part 21 & Deficiency Rept (Rdc 145(86)) Re Kaman Instrument Co High Voltage Power Circuitry.Initially Reported on 860326.Circuit Board Cards Returned to Supplier for Circuitry Mod ML20203N4761986-04-25025 April 1986 Interim Deficiency & Part 21 Rept (Rdc 145(86)) Re Kaman Instrument Co High Voltage Power Supply in Microprocessors. Initially Reported on 860326.Next Rept Expected by 860414 ML20202F4601986-04-0303 April 1986 Interim Part 21 & Deficiency Rept (Rdc 145(86)) Re Kaman Instrumentation Co High Voltage Power Supply (P/N 450447) Found Oscillating Between 240 & 1,030 Volts at 100 Hz. Initially Reported on 860326.Investigation Continuing ML20141A1081986-03-31031 March 1986 Part 21 Rept 134 Re Potential Defect in K-1 Relay in Generator Voltage Regulator.Initially Reported on 860219. Corrective Action Must Take Into Account Equipment Operating Range of 100-137.5-volt Dc ML20154Q3141986-03-10010 March 1986 Final Part 21 Rept Re Possible Defect on Inflatable Door Seals for Personnel Air Locks Used in Plant Reactor Containment Sys.Program to Supply Environmentally Qualified Inflatable Seals Should Be Completed by mid-1986 ML20154N4361986-03-10010 March 1986 Part 21 Rept Re Defect on Inflatable Door Seals for Personnel Air Locks Used in Reactor Containment Sys of Nuclear Power Plants.Initially Reported on 830919.Environ Qualification Testing of New Seal Design Completed 1999-04-12
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217K1231999-10-14014 October 1999 Revised Positions for DBNPS & Pnpp QA Program ML20212J2011999-09-30030 September 1999 Safety Evaluation Supporting Transfer of Dl Ownership Interest in Pnpp to Ceico PY-CEI-NRR-2437, Monthly Operating Rept for Sept 1999 for Pnpp,Unit 1.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Pnpp,Unit 1.With PY-CEI-NRR-2429, Monthly Operating Rept for Aug 1999 for Pnpp,Unit 1.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Pnpp,Unit 1.With NUREG-1482, SE Approving Licensee Relief Requets PR-2,PR-3,PR-6,VR-6, VR-7,VR-10,PR-4,PR-5,VR-4,VR-5,VR-9,VR-1 & VR-3 Related to Inservice Testing Program,Second ten-year Interval for Perry Nuclear Power Plant1999-08-0909 August 1999 SE Approving Licensee Relief Requets PR-2,PR-3,PR-6,VR-6, VR-7,VR-10,PR-4,PR-5,VR-4,VR-5,VR-9,VR-1 & VR-3 Related to Inservice Testing Program,Second ten-year Interval for Perry Nuclear Power Plant PY-CEI-NRR-2424, Monthly Operating Rept for July 1999 for Perry Npp.With1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Perry Npp.With ML20210J3851999-07-28028 July 1999 Pnpp - Unit 1 ISI Summary Rept Results for Outage 7 (1999) First Period,Second Interval PY-CEI-NRR-2416, Monthly Operating Rept for June 1999 for Perry Nuclear Power Plant,Unit 1.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Perry Nuclear Power Plant,Unit 1.With ML20196A1951999-06-17017 June 1999 Instrument Drift Analysis ML20207G2741999-06-0707 June 1999 Safety Evaluation Concluding That Firstenergy Flaw Evaluation Meets Rules of ASME Code & That IGSCC & Thermal Fatigue Crack Growth Need Not Be Considered in Application PY-CEI-NRR-2409, Monthly Operating Rept for May 1999 for Perry Nuclear Power Plant,Unit 1.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Perry Nuclear Power Plant,Unit 1.With PY-CEI-NRR-2393, Special Rept Update:On 990327 Refueling Outage 7 Began & Troubleshooting Efforts Began.Troubleshooting of Affected Calbe Confirmed Fault in Drywell Section of Cable.Determined That Installation of Newer Technology Should Be Explored1999-05-12012 May 1999 Special Rept Update:On 990327 Refueling Outage 7 Began & Troubleshooting Efforts Began.Troubleshooting of Affected Calbe Confirmed Fault in Drywell Section of Cable.Determined That Installation of Newer Technology Should Be Explored ML20206G6451999-05-0303 May 1999 Safety Evaluation Authorizing Requests for Relief IR-032 to IR-035 & IR-037 to IR-040 Re Implementation of Subsections IWE & Iwl of ASME Section XI for Containment Insp PY-CEI-NRR-2399, Monthly Operating Rept for Apr 1999 for Perry Nuclear Power Plant,Unit 1.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Perry Nuclear Power Plant,Unit 1.With ML20206E2261999-04-29029 April 1999 Safety Evaluation Concluding That Proposed Alternatives Will Result in Acceptable Level of Quality & Safety.Authorizes Use of Code Case N-504 for Weld Overlay Repair of FW Nozzle Weld at Pnpp & Use of Table IWB-3514 ML20206D7911999-04-23023 April 1999 Rev 6 to PDB-F0001, COLR for Pnpp Unit 1 Cycle 8,Reload 7 ML20205P4371999-04-15015 April 1999 Safety Evaluation Concluding That Licensee Performed Appropriate Evaluations of Operational Configurations of safety-related power-operated Gate Valves to Identify Valves Susceptible to Pressure Locking or Thermal Binding ML18016A9011999-04-12012 April 1999 Part 21 Rept Re Defect in Component of DSRV-16-4,Enterprise DG Sys.Caused by Potential Problem with Connecting Rod Assemblies Built Since 1986,that Have Been Converted to Use Prestressed Fasteners.Affected Rods Should Be Inspected PY-CEI-NRR-2389, Monthly Operating Rept for Mar 1999 for Perry Nuclear Power Plant,Unit 1.With1999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Perry Nuclear Power Plant,Unit 1.With ML20205G4221999-03-31031 March 1999 Safety Evaluation Accepting Second 10-yr Interval IST Program Releif Requests for Plant,Unit 1 ML20205S0601999-03-31031 March 1999 Rept on Status of Public Petitions Under 10CFR2.206 with Status Change from Previous Update,990331 ML20206D8461999-03-31031 March 1999 Rev 1 to J11-03371SRLR, Supplemental Reload Licensing Rept for Pnpp,Unit 1 Reload 7 Cycle 8 ML20205D3101999-03-26026 March 1999 Safety Evaluation Supporting Amend 103 to License NPF-58 ML20205C3761999-03-26026 March 1999 Safety Evaluation Supporting Request for Proposed Exemption to 10CFR50,app a GDC 19 PY-CEI-NRR-2369, Special Rept:On 990127,PAMI Was Declared Inoperable.Caused by Low Resistance Reading Existing in Circuit That Goes to Drywell.Troubleshooting of Affected Cable Will Commence During RFO on 9902271999-03-0303 March 1999 Special Rept:On 990127,PAMI Was Declared Inoperable.Caused by Low Resistance Reading Existing in Circuit That Goes to Drywell.Troubleshooting of Affected Cable Will Commence During RFO on 990227 PY-CEI-NRR-2372, Monthly Operating Rept for Feb 1999 for Perry Nuclear Power Plant,Unit 1.With1999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Perry Nuclear Power Plant,Unit 1.With ML20203A5961999-02-0202 February 1999 Safety Evaluation Accepting Licensee Proposed Revs to Responsibilities of Plant Operations Review Committee as Described in Chapter 17.2 of USAR ML20203A5211999-01-27027 January 1999 Safety Evaluation Accepting Licensee Calculations Showing That Adequate NPSH Will Be Available for HPCS Pumps ML20198R8921999-01-0707 January 1999 SER Accepting Licensee Proposed Amend to TSs to Delete Reference to NRC Policy Re Plant Staff Working Hours & Require Administrative Controls to Limit Working Hours to Be Acceptable ML20204J6751998-12-31031 December 1998 1998 Annual Rept for Dbnps,Unit 1,PNPP,Unit 1 & BVPS Units 1 & 2 PY-CEI-NRR-2356, Monthly Operating Rept for Dec 1998 for Perry Nuclear Power Plant,Unit 1.With1998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Perry Nuclear Power Plant,Unit 1.With ML20206B0101998-12-31031 December 1998 1998 Annual Rept for Firstenergy Corp, for Perry Nuclear Power Plant & Davis-Besse Nuclear Power Station.Form 10-K Annual Rept to Us Securities & Exchange Commission for Fiscal Yr Ending 981231,encl ML20198J0031998-12-22022 December 1998 SER Accepting Licensee Response to GL 92-08,ampacity Derating Issues for Perry Nuclear Power Plant,Unit 1 PY-CEI-NRR-2346, Monthly Operating Rept for Nov 1998 for Perry Nuclear Power Plant,Unit 1.With1998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Perry Nuclear Power Plant,Unit 1.With ML20195F6891998-11-0505 November 1998 Safety Evaluation Accepting Proposed Reduction in Commitment in Quality Assurance Program to Remove Radiological Assessor Position PY-CEI-NRR-2335, Monthly Operating Rept for Oct 1998 for Perry Nuclear Power Plant,Unit 1.With1998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Perry Nuclear Power Plant,Unit 1.With PY-CEI-NRR-2329, Monthly Operating Rept for Sept 1998 for Perry Nuclear Power Plant,Unit 1.With1998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Perry Nuclear Power Plant,Unit 1.With ML20153B8221998-09-16016 September 1998 Safety Evaluation Accepting Changes to USAR Section 13.4.3, 17.2.1.3.2.2,17.2.1.3.2.2.3 & App 1A PY-CEI-NRR-2323, Monthly Operating Rept for Aug 1998 for Perry Nuclear Power Plant,Unit 1.With1998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Perry Nuclear Power Plant,Unit 1.With PY-CEI-NRR-2313, Monthly Operating Rept for July 1998 for Perry Nuclear Power Plant,Unit 11998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Perry Nuclear Power Plant,Unit 1 PY-CEI-NRR-2306, Monthly Operating Rept for June 1998 for Perry Nuclear Power Plant,Unit 11998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Perry Nuclear Power Plant,Unit 1 ML20249A1891998-06-11011 June 1998 SER on Moderate Energy Line Pipe Break Criteria for Perry Nuclear Power Plant,Unit 1 & Requests Addl Info to Demonstrate That Plant & FSAR in Compliance W/Staff Position & GDC as Discussed in SER ML20248F3531998-05-21021 May 1998 Part 21 Rept Re Electronic Equipment Repaired or Reworked by Integrated Resources,Inc from Approx 930101-980501.Caused by 1 Capacitor in Each Unit Being Installed W/Reverse Polarity. Policy of Second Checking All Capacitors Is Being Adopted PY-CEI-NRR-2282, Monthly Operating Rept for Apr 1998 for Perry Nuclear Power Plant,Unit 11998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Perry Nuclear Power Plant,Unit 1 ML20217D2051998-04-20020 April 1998 SER Authorizing Licensee to Use Code Case N-524 Until Such Time as Code Case Included in Future Rev of RG 1.147 PY-CEI-NRR-2277, Monthly Operating Rept for Mar 1998 for Perry Nuclear Power Plant,Unit 11998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Perry Nuclear Power Plant,Unit 1 ML20217D5701998-03-20020 March 1998 Part 21 Rept 40 Re Governor Valve Stems Made of Inconel 718 Matl Which Caused Loss of Governor Control.Control Problems Have Been Traced to Valve Stems Mfg by Bw/Ip.Id of Carbon Spacer Should Be Increased to at Least .5005/.5010 ML20216G3901998-03-11011 March 1998 SER on Proposed Merger Between Duquesne Light Co & Allegheny Power Sys,Inc ML20216J1401998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Perry Nuclear Power Plant,Unit 1 PY-CEI-NRR-2258, Monthly Operating Rept for Jan 1998 for Perry Nuclear Power Plant,Unit 11998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Perry Nuclear Power Plant,Unit 1 1999-09-30
[Table view] |
Text
Appendix B Q.LINE SYSTEMS INC Page 1 of 1 so9 mst vonroe stree, H.oNano in.no.s 6??d9 U S A S@, M
][T rg 01&6S4 2184 Teten 44 7755 ',} ggg y i world Headouerters
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October 22, 1979 Chicago Regionr1 Office s
Nuclear Regulatory Commission 799 Roosevelt Road, Building 4 Glen Ellyn, Illinois 60137 Attention: Mr. Gaston Fiorelli Centlemen: '
This letter is to advise you that corrective action has been taken {
in regard to the potentially defective parts reported by B-Line .l Systems, Inc. on September 24, 1979. Mr. Fike of Ernst-Comstock has j informed B-Line Systems that none of the parts identified in our letter of September 24, 1979 have been installed in safety related 3 applications at Cleveland Electric Illuminating's Perry Nuclear i Power Station.
B-Line Systems has taken the additional precautionary measure of re-calling all parts which were in storage at the Perry Nuclear Power Station to preclude their inadvertent use in safety related areas.
In light of the facts stated above, B-Line Systems, Inc. considers th( reported potential defects to be satisfactorily r* solved. I Sincerely yours, B-LINE SYSTEMS, INC. / .
9.y;. ,-)p , o" ( .
omas R. Gold, Sr.
President
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8005280f0 : uv
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i sr u E
MANUFACTURERS OF CABLE TRAY AND STRUT SYSTEMS i
Appendix C Page 1 of 3
- B-LINE SYSTEMS, INC. .
. INTEROFFICE MEMORANDUM To: Tom Gold Sr. Date: 9/24/79 Fnn: Charles Hays .' Sebject: Material 7eview Board Ken Radner Investigation of 1/4" Gary Warning Plate Material The following ie,asynopsis of the events and the consequent reccomendations of the MRB regarding possible defects in 1/4" plate material.
9/10/79 During a routine Q. C. inspection, Inspector Gary :.'iarning noticed a hair-line crack on the inside radius of a 3-267 ,
' wing fitting. iiarning procured a hammer and struck the ;
p' art on the outside bend radius opposite the apparent crack. This caused the part to split in two along the bend line. itarning questioned the press foreman to determine what material lot the parts were run from.
The press foreman told hi= that the parts were made' -
from 1/4" plate material pro cured from Jones & Laughlin /
Steel. Warning informed Chuck Hays (the Materials Manager) of this and Hays contacted the mill to arrange for a Metallurgical exacination of the steel. A check of records revealed that the suspect material was received on 5/2/79. Sales was instructed to begin a review of all ~
orders shipped on or after 5/2/79 which required reporting under 10CF7 part 21. A ,Q.C. hold was placed on all parts
- on the shelf which were fabricated from 1/4 plate. A brief meeting was held between the Q.C. Imspector, the Materials Manager, and the Production Manager. It was decided to continue the hammer blow type examination of parts on the shelf to hopefully deter =ine expeditiously which parts were potentially defective.
9/11/79 Hammer testing continued under R.C. supervision.
9/12/79 J & L metallurgist (Mr. J. Schaeffer) arrived and picked up flat samples cut from the suspect J & L material and ~
some B-267 fittings. He promised a report no later than 9/21/79.
9/13/79 Hammer testing continued under Q.C.' supervision. .
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?' 9/14/79 The president of B-Line was advised by B-Line Engineering
. . . - Manager that the hammer test should be stopped since the
r~esults thus far were inconclusive and non-quantifiable.
~~
The president agreed to this and charged B-Line Engineering with beginning a testins program which would yield results i i rr -
' : which could be used to ? deter =ine if the parts were defective.
'1 Samples of a B-144 were sent to St. Louis Testing Labs
' r'for'analysic.
9/17/79 A review of production records had yielded the information
- . that certain parts on the shelf had not been produced af ter
- -~ ~ ~ - ' ' 5/2/79. Chuck Hays sent a memo to Tom Gold releasing these
- ~ ~ ~ - ~ parts for shipment.
- St. Louis Testing Labs reported that chemical tests on the 3-144's were normal for low carbon iC~ ' steel on the first four elements. They further reported laminor type indications on the cross sectioned samples.
~' ' ~'
9/18/79 Encineer1ns testing program was begun. The J & L metal-largist contacted Chuck Hays and reported that his analysis has shown that the J L L material flat sa=ples were to ppecification but that the 3-267 samples contained sign-ificant ammounts of copper and nickel which would be ihdications of a "corten" or ASTM type 606 steel.
9/19/79 Based on the report from J & L samples were taken frou material purchased from Rolled Steel and sent to St. Louis
-Testing for analysis. The receipt date for the Rolled Steel material was determined to,b.e 7/17/79.
9/20/79 The Engineering department reported that the testing had been co=pleted on all parts except for wing type fittings and that as yet, no defective parts had been found.
9/21/79 The sales group reviewing orders for lo0?a21 reporting were instructed to group the orders in two headings. One for all orders shipped on or after 5/2/79, and one for all orders shipped on or after 7/17/79. .
9/24/79 Laboratory report 79P3225 was received from St. Louis Testing Labs. This report confirmed the fact that the ,
Rolled Steel material was,in fact the "corten" type material which the B-267's were made from. Engineering .
completed their testing program and found no failures on any parts made from 1/4" plate. It was determined by the sales group that only the perry Nuclear Project of Cleveland Electric Illu=innting Company had product from 1/4" plate shipped to them since 7/17/79. ,
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Conclusion:
Although the testing program produced no evidence of non-
- confirmance in B-Line parts, the Material 3eview Board-feels that the product made from 1/4" plate shipped to
.the perry Project since 7/17/79 should te recalled and a report filed in accordance with lO".T Part 21. The Peview Board reccomends thic strictly on the basis that "corten" type material in not our standard 1/4" plate material. .
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Ll.o J Ju .3 ~,( DMR NUMBER H-110
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manurocrvatns or casie vna r. srour sysrtus a suctosunts DATE 11/19/19 509 W. MONROE ST.
- P.O. BOX 326 HIGHLAND, ILLINOIS 62249 P%RT NUMBER 1/4 sheet steel PHONE: 618 654 2184 DESCRIPTION 50 x 120 1/2 x 1/4 DEFECTIVE MATERIAL REPORT QUANTITY PURCHASE ORDER NO. 41220 v[ ~l DATE RECEIVED 7/17/79 E Rolled Steel Corp N 6101 West Oakton D Skokie, IL 60076 DATE INSPECT'lD 9/26/79 0
Rl_
j INSPECTED BY_ Garv Warnina LIST O F D E F ECTS
,, ',0.**, a DESCHIPTION Or DEF ECTIVE ITEM .r *;. " ;"*ni'a '*J'.J.'*!, DESCRIPTION OF DEFECT 1 50 x 120 1/2 x 1/4 35,8 hi 3584 4f 35044f Material should be 1008-1010 Sheet steel 84 pcs 84 y cs 84 pcs is corten i
2 Formed Parts 7731f 7731f 77314 Material should be 1008-1010 I
Parts Parts Parts is corten f
DISPOSITION I SAMPLES ENCLOSED BEING RETURNED TO VENDOR FOR: COMMENTS:
X CREDIT R EPLACEMENT REWORK DESIT NO.
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~ , , , , . . . .....a~. .,..m...,..<...... WRITTEN REPLY REQUESTED WITHIN TEN DAYS 7,,,,.,', 'O *.*.*'.J ,*f.78.
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REVIEWED BY-7
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Appendix D
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- j . 2 810 CLARK AVENUE . sT. Louis, MO. 63103
531-8080 Code 314 )
' . Y Chemice! MeteRurgical. Physics!. Non Destructive. Spectrographic, w n _j 4 1n 3 s,g s s, 31 1 Agriculture! Testong and Anstyses hrvestigations. Research and Development. inspection. field Services September 20, 1979 ;
'- )
Lab No. 79P3225 i PO No. 42398 t B-LINE SYSTEMS, INC.
Y i,$09 W. Monroe l
- ' Highland, IL 62249 ,
Attention: Mr. Charles Hays -
REPORT OF TESTS MATERIAL:
1/4 inch by 2 inch by 12 inch HRP & O r.aterial (purchased from Rolled Steel and Feralloy) were delivered to the Laboratory on September 19,1979.
SUBJECT:
Cross section and macroetch to determine whether lamination exists in the material. -
PROCEDURE:
Three (3) sections of the body of the sample were cut through the thickness of the metal. These sections were polished and subjected to a macroetch using a 50 percent hydrochloric acid (approximately 37%) and 50 percent water at a temperature of between 160' and 180*F.
The samples were etched for approximately fifteen (15) minutes.
TEST RESULTS:
The etched sections were visually examined at 5X magnification, with i the following results:
(1) Sample 1 from Rolled Steel is free from any lamination-type indications visible. _
(2) Sample 2 from Feralloy has lamination-type indications visible, which are located at the approximate midpoint of the material.
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4
I* , s( ' Appendix D
- 'A- Page 3 of 5 2' ' c,k ^'*a"*St. Louis Missouri 63 Saint Louis s14/531-sono Testing Laboratories, Inc.
t B-Line Systems Invoice No. 79-5376 Page ,
(at 3X magnification) of the two (2)
The attached photamacrographsmaterial samples are included to p required documentary evidence.
sections.
e
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Respectfully submitted, b
Robert O. Peterson Metallurgist l i
e l
l Enclosures
, ROP /kvh l
l
3.grpmuznw Page 4 of 5 3810 Clark Avenue Scptemb2r 20, 1979, [*
Saint LOdS St. Louis, Missourl 63103 Invoice No. 79-5376 Tcsting 3"/m4oso n.3 No. 79C2676 -
PO No. 42398 Laboratories, Inc.
B-LINE SYSTEMS, INC. .
509 West Monroe Street -
Highland, Illinois 62249 ,
- .. ? Attention: Mr. Chuck Hays
- y'
- ., REPORT OF TESTS
!)- '
MATERIAL SUBMITTED: Two (2) samples identified below TESTS REQUESTED: dilemical Testing .
e f f RESULTS: '. ; ,'
. Sanple Carbon,t' Silicon,% Sulfur,% Manganese,% Phosphorus,% Nickel,4 Chranim,t. Molybdenm ,4 ;
Rolled Steel i -
.023 .36 .013 .12 .07 .02 1 .12 l.! ,*.16 i J /4" x 2" x 12" -
e .
l
,~.[4'f jr Paralloy .020 .48 .009 .11 .06 .02 ,
f 1;/4" x 2" x 12" .08 [4, '.10
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l .. . Respectfully submitted, .
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d W. Dee Trowbridge
' l Assistant Director s.
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Page 5 of 5 An4 St.lsuisTesting taboratories,Inc.
B-LINE SYSTEMS, INC. - ..
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""""'":::". .f.,m 509 W. Monroe --- .
Highland, IL 62249 Report No. 79-s376 Date September 20 19 22.
Attn: Charles Hays PO542398 Lab No. 79P3225 roau e se _
On!GINAI. U ION TIrLD POINT TENSU C STRENOT11 R!!DUCED g Qg, Area Dtarnitu l Area Pu cant Actual Actua l r.r sq. In. taches 5 Dtaanetw l lPerso.In. l z:= = -
, WIDTH THICKNESS AREA .i 1 -
i:
il .517 .249 .1287 5260 40870 7640 59362 .75 37.5 .;
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' ' 5 6 0 0' '44198 7490 59116 .72 36.0
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Yield taken at drop of dial.
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1/4" X 2" X 12" HRP&O' il ,. Rolled steg,1 ;
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. ... C. D.Trowbridge, Director. (/
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\ Appendix E i* - . Page 1 of 1 ,
\
b,o~nh ERNST-COMSTOCK A JOINT VENTURE l
\ opstocx// l Perry N Jelear Power Station P. O. Box 761 Painesville, Ohio 44077 l Phone: (216) 259 - 3755 October 11, 1979 Cleveland Electric Illuminating Co.
P.O. Box 5000 Cleveland, Ohio 44101 Attention: Mr. Stu Tulk Re: B-Line Systems, Inc.
10 CFR 21 letter dated September 24, 1979
Dear Sir:
In regards to the certified letter received by Ernst-Comstock from B-Line Systems, Inc.
(dated 9/24/79, attached) concerning possible defects in certain conduit fitting's, as listed in the attached letter, a thorough review and takeoff (attached) of all conduit SS drawings was performed by the Ernst-Comstock Engineering and Quality Control Depart-ments.
It has been determined from this review that none of the listed fittings are used for cafety-related installations. In addition, fittings, as identified by Mr. J. Hughes, NRC Inspector, (Ref: B-104; B-ll5; B-127; B-238) are not to be used in safety-related installations.
The above referenced conduit fittings, currently in stock in the Ernst-Comstock ware-house are being removed from the shelves and will be exchanged for. acceptable fittings by the manufacturer.
If there are any questions concerning the content of this letter, please feel free to contact the undersigned.
Sincerely yours, l
Thomas W. Packy Quality Control Engineer Te/gse Cc::IRok. No. Q-79-10-1847 RECEWED oc1 11 DD W/ Attachments
- C,fd,SElmN cc: G. King - LKCE T. Woodman - LKC J. Klena - LKC g J. Newsome - LKC F G. Leidich - P/0
.