ML19347D856
ML19347D856 | |
Person / Time | |
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Site: | Perry |
Issue date: | 04/03/1981 |
From: | Davidson D CLEVELAND ELECTRIC ILLUMINATING CO. |
To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
References | |
10CFR-050.55E, 10CFR-50.55E, NUDOCS 8104140337 | |
Download: ML19347D856 (2) | |
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Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML18016A9011999-04-12012 April 1999
[Table view]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. 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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 ML20034F7031993-02-25025 February 1993 Amend 1 to Enterprise Rept 162 Re Defect on Starting Air Distributor Housing Assembly,As Followup to 930115 Final Rept.Addl Listed Part Numbers Discovered Which Are Higher Level Assemblies of Housing 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 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 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 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 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 ML20006A3611990-01-17017 January 1990 Part 21 Rept 152 Re Potential Defect in Component of Dsr or Dsrv Standby Diesel Generator Sys Supplied to Listed Sites by Cooper Industries.Qualified Replacement Valve in Process of Being Specified.Info Will Be Available by 900215 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. 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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 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 Category:TEXT-SAFETY REPORT MONTHYEAR05000440/LER-1999-004, :on 990916,loss of Safety Function Resulted in TS 3.0.3 Entry.Caused by Design Deficiency in Control Complex Architectural Walls.Revised Storm Contingencies Instructions.With1999-10-18018 October 1999
[Table view]
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 1999-09-30 |
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Dear Mr. Keppler:
Perry Nuclear Power Plant Final.P.eport on Safety Relief Valve Control System This letter serves as the final report as required by 10CFR50.55(e) con-cerning the safety relief valve control system supplied by General Elec-tric. This item was first reported by Mr. R. G. Schuerger of the Cleve-land Electric Illuminating Company to Mr. D. Hayes of your office on October 6, 1977. The Interim Report was written on November 2, 1977 as a follow up to this notification.
Description of Deficiency The safety relief valve control system deficiency along with its impact is described in the G.E. report attached to the Interim Report transmitted to you. 'Ihis report identifies that more than one safety relief valve may reopen after the initial pressure trans-ient isolation event instead of the single valve predicted.
Corrective Action In order to correct the system deficiency, we will implement the low-low set relief lo;,ic on Perry as described and submitted by G.E. to the NRC in the January 31, 1978 letter from G. Sherwood to E. Case. The Perry design is exactly the same as the generic design which has been extensively discussed with the NRC through G.E. 's standard plant submittals. This modification is described in the Perry FSAR Section 5.2.2.2.3.2 which incorporates the 30/f G.E. generic design.
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j Mr. James G. Keppler April 3, 1981 Analysis of Safety Implications We have determined that the resulting modifications will have no effect on plant, safety. The implementation of the low-low set relief logic will be completed prior to plant operation.
Sununary The Perry modification work has presently involved only drawing and specification changes. The field work on this modification will be completed by May 1, 1983.
Very truly yours,7
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)h (@hvC Dalwyn R. Davidsen Vice President System Engineering and Construction DRD: bas cc: Mr. J. Hughes U.S. NRC - Perry Plant Site Mr. Victor Stello Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C.
20555 U.S. Nuclear Regulatory Commission c/o Document Management Branch Washington, D.C.
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