ML20207S698
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| ML20207S698 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 03/05/1987 |
| From: | Haynes J ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | Kirsch D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| References | |
| REF-PT21-87, REF-PT21-87-056-000 023-02104-JGH-D, 23-2104-JGH-D, PT21-87-056-000, PT21-87-56, RER-QSE-87-05, RER-QSE-87-5, NUDOCS 8703200188 | |
| Download: ML20207S698 (2) | |
Similar Documents at Palo Verde | |
|---|---|
Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML20207M9231999-03-12012 March 1999
[Table view]Amended Part 21 Rept Re Cooper-Bessemer Ksv EDG Power Piston Failure.Total of 198 or More Pistons Have Been Measured at Seven Different Sites.All Potentially Defective Pistons Have Been Removed from Svc Based on Encl Results ML18066A2771998-08-13013 August 1998 Part 21 Rept Re Deficiency in CE Current Screening Methodology for Determining Limiting Fuel Assembly for Detailed PWR thermal-hydraulic Sa.Evaluations Were Performed for Affected Plants to Determine Effect of Deficiency LD-97-033, Part 21 Rept Re Defect in Potter & Brumfield Mdr Relays, Models 170-1 & 7032.Extended Problem to Include All Mdr Relay Models W/Date Codes 93XX-95XX.Root Cause Analysis, Written Rept & Recommended Corrective Actions Due by 9712011997-11-20020 November 1997 Part 21 Rept Re Defect in Potter & Brumfield Mdr Relays, Models 170-1 & 7032.Extended Problem to Include All Mdr Relay Models W/Date Codes 93XX-95XX.Root Cause Analysis, Written Rept & Recommended Corrective Actions Due by 971201 LD-97-028, Part 21 Rept Re Contamination of Lubricant Which Has Led to Hardening of Lubricant in Certain Potter & Brumfield Mdr Relay Models 170-1 & 7032.Will Distribute Copy of Rept to Utils Having ABB-CE Designed Nuclear Steam Supply Sys1997-10-13013 October 1997 Part 21 Rept Re Contamination of Lubricant Which Has Led to Hardening of Lubricant in Certain Potter & Brumfield Mdr Relay Models 170-1 & 7032.Will Distribute Copy of Rept to Utils Having ABB-CE Designed Nuclear Steam Supply Sys LD-97-024, Part 21 Rept Re Error in Energy Redistribution Factor Used in LOCA Analysis for Listed Plants for Which ABB-CE Performed Analysis.Issued Recommendations Info Bulletin 97-0041997-08-14014 August 1997 Part 21 Rept Re Error in Energy Redistribution Factor Used in LOCA Analysis for Listed Plants for Which ABB-CE Performed Analysis.Issued Recommendations Info Bulletin 97-004 ML20140A9661997-05-29029 May 1997 Part 21 Rept Re Ksv Emergency Diesel Generator Power Piston Failure.Caused by Jacket Water in Combustion Chamber. Recommends That Users Verify That Crown Thickness at Valve Cutout Be 100 Minimum ML20137G6261997-03-25025 March 1997 Svcs Part 21 Rept Re Emergency Generators Installed at Zion Station Which Developed Significant Drop in Crankcase Lube Oil Level.Caused by Crack in Liner Wall,Allowing Jacket Water to Enter Chamber ML18065B0111996-10-18018 October 1996 Part 21 Rept Re Application of Certain Aspects of ABB-CE Safety Analysis Methodology ML20117G4641996-05-14014 May 1996 Part 21 Rept Re Cooper Bessemer Reciprocating Products,Div of Cooper Cameron Corp,Issued Ltr to Define Utils/Plants Containing Similar Equipment as Supplied on Cooper Bessemer Ksv & Enterprise Dsr EDGs LD-96-009, Part 21 Rept Re Potential Instrumentation Decalibr at Low Power.Affected Utils Should Ensure That Log Power Channels Properly Calibr & cross-correlated to Linear Power Channels at 100% Reactor Power1996-04-15015 April 1996 Part 21 Rept Re Potential Instrumentation Decalibr at Low Power.Affected Utils Should Ensure That Log Power Channels Properly Calibr & cross-correlated to Linear Power Channels at 100% Reactor Power ML20077D3431994-11-29029 November 1994 Part 21 Rept Re Suspect Master Connecting Rods & Contains Info Location in Engine for Rods ML20078G3051994-11-0909 November 1994 Rev to Part 21 Rept Re Potential Problem W/Master Power Connecting Rods.Vendor Recommends Listed Utils Perform Visual Insp of Master Rods to Determine Applicability of Rept LD-93-003, Part 21 Rept Re Defect in Potter & Brumfield Model 170-1 Relay.One of Two Rotor Return Springs Broke & Portion of Spring Lodged Between Rotor & Stator.Rotor Springs Supplied by Lewis Spring Co.Info Bulletin Being Prepared1993-01-13013 January 1993 Part 21 Rept Re Defect in Potter & Brumfield Model 170-1 Relay.One of Two Rotor Return Springs Broke & Portion of Spring Lodged Between Rotor & Stator.Rotor Springs Supplied by Lewis Spring Co.Info Bulletin Being Prepared 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 ML17306B0581992-10-0808 October 1992 Part 21 Rept Advising That Preliminary Evaluation of Rosemount Part 21 Notification Determined That Change in Systematic Static Pressure Span for Pressure Differential Transmitters May Result in Increase in Indicated Power ML17306A3341991-12-13013 December 1991 Followup Part 21 Rept Re Potential for Certain Westinghouse Products,Utilizing Dc Coil Assemblies,To Malfunction.Caused by Epoxy Compound Becoming semi-fluid During Svc.Initially Reported on 910624.Epoxy Check Will Be Incorporated ML20086P1591991-10-31031 October 1991 Part 21 Rept Re Microscopic Cracks in Fuel Nozzle Tip from Mfg Lot D87001.Cracks Perpendicular to Axis of Nozzle & Extend Through Case Hardening & Stop at Core.Interim/Final Report Will Be Forwarded as Further Development Occurs ML17305B6181991-06-24024 June 1991 Part 21 Rept Re Potential for Certain Westinghouse-supplied Products,Utilizing Dc Coil Assemblies,To Malfunction. Initially Reported on 910620.Recommends That All Suspect Devices Be Replaced & Epoxy Compound Probed ML17348A1621990-03-27027 March 1990 Part 21 Rept Re Matls W/Programmatic Defects Supplied by Dubose Steel,Inc.Customers,Purchase Order,Items & Affected Heat Numbers Listed ML17223A7451990-01-26026 January 1990 Part 21 Rept Re Backup Rings Furnished in Spare Parts Seal Kits & in 25 Gpm 4 Way Valves as Part of Actuators Made of Incorrect Matl.Rings Should Be Viton & Have Been Identified as Buna N ML17304B1281989-04-20020 April 1989 Part 21 Rept Re Multiple Control Element Assembly Slip or Drop Events at Unit 1 on 881210.Caused by Intermittent T Grounding of Control Element Drive.Initially Reported on 890419.Stack Assemblies Will Be Replaced ML20247P7991989-04-0404 April 1989 Part 21 Rept Re Atmospheric Dump Valves.Cause of Failure Speculative But Result of Piston Ring That Failed to Seal. Resolution to Problem Requires Increasing Pilot Valve Capacity & Reworking of Plug to Enlarge Pilot Flow Area ML17304B1691989-02-0202 February 1989 Part 21 Rept Re Ruskin Div Supplied Dampers W/Itt Actuators. Div Currently Evaluating Loctite Compound Which May Be Applied,Following Verification of Proper Damper Adjustment, to Threads of Extension Shaft in Place ML17304A9711989-01-18018 January 1989 Part 21 Rept Re Ksv Standby Diesel Generator Rocker Arm Failure.On 890104,exhaust Valve Rocker Arm Installed in KSV-20-T Engine Broke at Plant.Investigation Revealed That Castings Cracked During Mfg.Review Underway ML20207P0151988-10-0404 October 1988 Part 21 Rept Re Fuel Nozzle Tips in Standby Diesel Generator KSV-20-T W/Cracks Permitting Diesel Fuel to Be Sprayed Into Cylinders.Heavy Vapors Observed Emitting from Breathers on Some Cylinder Heads ML20153B2811988-02-22022 February 1988 Part 21 Rept Re Defect in Operation of Gas Monitors Using Fixed Filters.Initially Reported on 880212.Caused by Error in Software for Monitors.Vendor Testing Mod to Software & in Interim Recommends Changing Filters Every 48 H ML17303A6081987-10-0202 October 1987 Part 21 Rept Re Fasteners Installed in motor-operated Valves.Initially Reported on 870930.Valve yoke-to-yoke Adapter Fasteners Replaced to Meet Allowable Stress Limits ML17303A5231987-07-17017 July 1987 Final Part 21 Rept RER-QSE 87-12 Re Improper Application of Agastat Relay.Initially Reported on 870714.Relay Contacts Burnished.Design Change Implemented to Replace Relays W/ Hermetically Sealed Relay W/Bifurcated Contacts ML17300A7791987-04-13013 April 1987 Revised Deficiency Evaluation Repts DER 84-30 & 86-25 Re U-2 Diesel Generator Valves & Kaman Radiation Monitors, Respectively.Changes to Reported Info or Corrective Actions Noted ML20205P7771987-03-19019 March 1987 Rev 3 to Final Part 21 & Deficiency Rept DER 82-46 Re Itt Barton Pressure Transmitters Supplied by C-E That Do Not Meet Overpressure Requirements.Rev Updates & Clarifies Info Re Description of Deficiency & Corrective Actions ML20205P9241987-03-19019 March 1987 Part 21 & Rev 2 to Final Deficiency Rept DER 84-08 Re Itt Barton Model 763 Transmitters Supplied by C-E Having Output Errors of -2 to -3% of Calibr Span.Defects May Affect Monitoring & Alarm Capabilities of Shutdown Cooling Sys ML20207S8341987-03-0606 March 1987 Final Part 21 & Deficiency Rept RER-GSE 86-41 Re Control of Design Change Packages (Dcp).Initially Reported on 861205. Review & Correction of DCPs Will Be Completed by 870101. Conditions Not Reportable Per 10CFR50.55 & Part 21 ML20207S6981987-03-0505 March 1987 Final Part 21 & Deficiency Rept RER-QSE 87-05 Re Travel Limit Switches on HVAC Dampers.Initially Reported on 870217. Condition Not Reportable Per 10CFR21 & 50.55 ML20207S9861987-03-0505 March 1987 Part 21 & Deficiency Rept RER-QSE 87-08 Re Lead Wires on Limitorque Operators.Initially Reported on 870217.Condition Found Not Reportable Under 10CFR50.55(e) & 10CFR21 ML17300A6741987-02-27027 February 1987 Part 21 & Final Deficiency Rept DER 86-29 Re Crack in Letdown HX Nozzle Mfg by Richmond Engineering Co & Supplied by C-E.Initially Reported on 861114.Nozzle Crack Initially Weld Repaired Under Nonconformance Rept Ncr NA-1942 ML20207R0951987-02-23023 February 1987 Deficiency Rept DER 86-29 Re Letdown HX Nozzle Crack. Initially Reported on 861114.Due to Extensive Investigation, Time Extension Requested.Final Rept Expected by 870227 ML20212D8301987-02-12012 February 1987 Deficiency Rept DER 86-29 Re Letdown HX Nozzle Crack. Initially Reported on 861114.Due to Extensive Investigation, More Time Required for Final Rept.Rept Anticipated by 870223 ML20211Q2681987-02-0909 February 1987 Final Part 21 & Deficiency Rept RER-QSE 86-47 Re Failure of Unit 3 B Diesel Generator Engine.Initially Reported on 861223.Units 2 & 3 Cylinder Master Rods Replaced.All Diesel 3A & Remaining 3B Rods Ultrasonically Examined ML20211A2101987-01-29029 January 1987 Final Part 21 & Deficiency Rept DER 86-32 Re Discrepancies Between Pipe Support Designs & Stress Calculations.Initially Reported on 861231.Caused by Personnel Design Errors. Condition Not Reportable Per 10CFR50.55(e) & 10CFR21 ML20211A6951987-01-23023 January 1987 Interim Deficiency Rept DER 86-30 Re Unqualified Fuses, Terminal Blocks & Wires.Initially Reported on 861104.Due to Extensive Investigation & Evaluation Required to Address Issue,Final Rept Expected by 870219 ML20213A0711987-01-20020 January 1987 Final Part 21 & Deficiency Rept RER-QSE 87-01 Re Brown Boveri K600/K800 Circuit Breakers W/Possible Cut Wires on Wire Harness.Initially Reported on 860630.Gear Guards Will Be Installed to Protect Circuit Breakers During Next Outage ML20212Q1231987-01-13013 January 1987 Part 21 & Updated Interim Deficiency Rept RER-QSE 86-47 Re Diesel Engine Generator Failure.Initially Reported on 861223.Iron Plated Rod Previously Identified as 6 Should Be Rod 9.Final Rept Will Be Submitted by 870220 ML20212H5451987-01-12012 January 1987 Part 21 Rept Re Break of Master Power Rod at Fractured Surface.Caused by Fatigue Failure Originating in Rod When Iron Plating in Articulated Rod Pin Bore Failed,Resulting in Engine Inoperability.Rod Replaced ML20212R3301987-01-0909 January 1987 Interim Deficiency Rept DER 86-29 Re Letdown HX Nozzle Crack.Initially Reported on 861114.Due to Extensive Investigation & Evaluation Required to Address Complexity of Issue,Next Rept Delayed Until 870216 ML20212Q1711987-01-0909 January 1987 Part 21 & Interim Deficiency Rept RER-QSE 86-47 Re Diesel Generator Engine Failure.Initially Reported on 861223.Caused by Fatigue Failure of Main Connecting Rod 9 Due to Addition of Iron.Final Rept Will Be Submitted by 870220 ML20210A9191987-01-0707 January 1987 Rev 1 to Final Part 21 & Deficiency Rept DER 85-38 Re QA Audit at Ge.Initially Reported on 851108.Re-audit at GE Identified Addl Purchase Orders Requiring Review for Validity of Proper Certification ML20207M2561987-01-0202 January 1987 Interim Deficiency Rept DER 86-31 Re Loose Windings of Diesel Generator.Initially Reported on 861205.Defective Rotor Removed & Visually Inspected by Vendor.Pole Piece Fasteners re-torqued.Final Rept Delayed Until 870209 ML20207M6541987-01-0202 January 1987 Interim Deficiency Rept RER-QSE 86-41 Re Withdrawal of Limitorque Operators from Warehouse W/O Required Design Changes.Initially Reported on 861205.Operators Located & Procedures Reviewed.Next Rept Delayed Until 870306 ML20207C5661986-12-12012 December 1986 Rev 2 to Deficiency Rept DER 86-04 Re Certain Seals Not Properly Supported & Rev 19 to DER 86-19 Re Modules Returned to Ga/Sorrento Electronics.Summary Description & Evaluation of Impact Encl ML20215E3691986-12-0505 December 1986 Interim Deficiency Rept DER 86-29 Re Letdown HX Nozzle Crack.Initially Reported on 861114.Due to Extensive Investigation & Evaluation,Final Rept Delayed Until 870115 1999-03-12 Category:TEXT-SAFETY REPORT MONTHYEARML17300B3811999-09-30030 September 1999
[Table view]Monthly Operating Repts for Sept 1999 for Pvngs,Units 1,2 & 3.With 991007 Ltr ML17300B3271999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Pvngs,Units 1,2 & 3 ML17313B0751999-08-27027 August 1999 LER 99-002-00:on 990730,test Mode Trip Bypass for EDG Output Breakers Not Surveilled.Cause Under Investigation.Operations Personnel Conservatively Invoked SR 3.0.3 for SR 3.8.1.13. with 990827 Ltr ML17313B0611999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Pvngs,Units 1,2 & 3.With 990810 Ltr ML17313B0191999-07-16016 July 1999 LER 99-005-00:on 990618,RT on Low DNBR Was Noted.Caused by Hardware Induced Calculation Error.Cr Operator Was Taken to Place Reactor in Stable Condition IAW Appropriate Operating Procedure ML17300B3151999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Pvngs,Units 1,2 & 3.With 990714 Ltr ML17313A9921999-06-21021 June 1999 Special Rept:On 990525,RMS mini-computer Was Removed from Service to Implement Yr 2000 Mod & Was OOS Longer than 72 H Allowed.Caused by Planned Y2K Mods.Preplanned Alternate Sampling Program Was Initiated ML17313A9911999-06-18018 June 1999 Special Rept:On 990510,loose-part Detection Sys Channel 2 Was Declared Inoperable.Caused by Malfunction of Mineral Cable Connector to Accelerometer.Licensee Will Implement Modifications Which Will Enhance loose-part Detection Sys ML17313A9731999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Pvngs,Units 1,2 & 3.With 990608 Ltr ML17313A9281999-05-0707 May 1999 LER 99-004-00:on 990408,PSV Lift Pressures Were Outside of TS Limits.Caused by Lift Pressure Setpoint Drift.Psvs Have Been Tested,Disassembled,Inspected,Reassembled & Certified at Wyle Labs ML17313A9201999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Pvngs,Units 1,2 & 3.With 990512 Ltr ML17313A8951999-04-14014 April 1999 LER 99-003-00:on 990317,required Surveillance Requirement Not Completed Due to Deficient Procedure,Was Determined. Caused by Cognitive Personnel Error.St Procedures Revised to Require Chiller to Be Operating & Oil Temperature Checked ML17313A8921999-04-13013 April 1999 LER 98-003-01:on 980902,discovered That MSSV as-found Lift Pressures Were Outside TS Limits.Caused by Bonding of Valve Disc to Nozzle Seat.Affected Valves Were Adjusted,Retested & Returned to Svc ML17313A8891999-04-0909 April 1999 LER 99-001-00:on 990310,RT on High Pressurizer Pressure Was Noted.Caused by Loss of Heat Removal.Cr Supervisor Was Removed from Shift Duties for Diagnostics Skills Training. with 990409 Ltr ML17300B3071999-03-31031 March 1999 Seismic Portion of Submittal-Only Screening Review of Palo Verde Nuclear Generating Station Units Ipeee. ML17313A8801999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Pvngs,Units 1,2 & 3.With 990412 Ltr ML20207M9231999-03-12012 March 1999 Amended Part 21 Rept Re Cooper-Bessemer Ksv EDG Power Piston Failure.Total of 198 or More Pistons Have Been Measured at Seven Different Sites.All Potentially Defective Pistons Have Been Removed from Svc Based on Encl Results ML20207H7471999-03-10010 March 1999 1999 Emergency Preparedness Exercise 99-E-AEV-03003 ML17313A8361999-03-0101 March 1999 LER 99-001-00:on 990103,TS Violation for Power Dependent Insertion Limit Alarm Being Inoperable.Caused by Personnel Error.Revised Procedure to Clarify How Computer Point Is to Be Returned to Scan Mode.With 990302 Ltr ML17313A8501999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Palo Verde Nuclear Generating Station.With 990311 Ltr ML17313A7791999-02-0505 February 1999 Safety Evaluation Accepting Licensee Rev to Emergency Plan That Would Result in Two Less Radiation Protection Positions Immediatelu Available During Emergencies ML17313A8061999-01-31031 January 1999 Monthly Operating Repts for Jan 1999 for Pvngs,Units 1,2 & 3.With 990218 Ltr ML17313A7701999-01-15015 January 1999 LER 96-008-00:on 960507,inadequate Procedure Results in Nuclear Power Channels Not Calibrated During Power Ascension Tests Occurred.Caused by Deficient Procedure.Procedure Revised ML17313A7381998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Palo Verde Nuclear Generating Station,Units 1,2 & 3.With 990113 Ltr ML20206H2101998-12-31031 December 1998 SCE 1998 Annual Rept ML17313A7031998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Pvngs,Unit 1,2 & 3. with 981209 Ltr ML17313A6701998-11-0404 November 1998 Rev 2 to PVNGS Unit 2 Colr. ML17313A6741998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Pvngs,Units 1,2 & 3.With 981109 Ltr ML17313A6611998-10-24024 October 1998 LER 98-008-00:on 980729,EQ of Electrical Connectors Were Not Adequately Demonstrated.Caused Because Test Was Conducted with Only Single Lv Connector & Without Fully Ranged Inputs. Revised EQ Requirements ML17313A6561998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for PVNGS Units 1,2 & 3.With 981007 Ltr ML17313A5961998-09-14014 September 1998 LER 98-002-00:on 980814,B Train H Recombiner Was Noted Inoperable Due to cross-wired Power Receptacle.Cause of Event Is Under investigation.Cross-wired Power Supply Receptacle for B Train H Recombiner Was re-wired ML17313A5761998-09-0808 September 1998 LER 98-003-01:on 980113,discovered That One Channel of RWT Level Sys Had Failed High.Caused by Water Intrusion Into Electrical Termination Pull Box.Weep Holes Were Drilled Into Bottoms of Pull Boxes Nearest Level Transmitters ML17313A5591998-08-28028 August 1998 LER 98-001-00:on 980730,entered TS 3.0.3 Due to Safety Injection Flow Instruments Being Removed from Svc.Caused by Personnel Error.Transmitters Were Unisolated & Returned to svc.W/980828 Ltr ML20151S0941998-08-21021 August 1998 Rev 6 to COLR for PVNGS Unit 3 ML20151S0861998-08-21021 August 1998 Rev 4 to COLR for PVNGS Unit 1 ML20151S0901998-08-21021 August 1998 Rev 1 to COLR for PVNGS Unit 2 ML18066A2771998-08-13013 August 1998 Part 21 Rept Re Deficiency in CE Current Screening Methodology for Determining Limiting Fuel Assembly for Detailed PWR thermal-hydraulic Sa.Evaluations Were Performed for Affected Plants to Determine Effect of Deficiency ML17313A5401998-08-13013 August 1998 Special Rept:On 980715,declared PASS Inoperable.Caused by Failure of Offgas Flush/Purge Control Handswitch HS0101. Handswitch Replaced & Post Maintenance Retesting Was Initiated ML17313A5301998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Pvgns,Units 1,2 & 3.W/980812 Ltr ML17313A5201998-07-30030 July 1998 LER 98-004-00:on 980630,personnel Discovered That Pressure Safety Valve Had Not Received Periodic Set Pressure Test for ASME Class 1 Pressure Safety Valve.Caused by Personnel Error.Pressure Safety Valve reviewed.W/980730 Ltr ML17313A5791998-07-0707 July 1998 to PVNGS SG Tube ISI Results for Seventh Refueling Outage Mar & Apr 1998. ML17313A5001998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Palo Verde Nuclear Generating Station,Units 1,2 & 3.W/980710 Ltr ML17313A4671998-06-19019 June 1998 LER 98-007-00:on 980520,CR Personnel Observed Flow & Pressure Perturbations on Chemical & Vol Control Sys Letdown Sys.Caused by Cyclic Fatigue Due to Dynamic Pressure Transients.Unit Letdown Piping Replaced ML17313A4521998-06-19019 June 1998 Rev 5 to COLR for Pvngs,Unit 3. ML17313A4501998-06-19019 June 1998 Rev 4 to COLR for Pvngs,Unit 3. ML17313A4131998-06-0505 June 1998 LER 98-006-00:on 980507,determined That Plant Was Outside Design Basis Due to SI Discharge Check Valve Reverse Flow. Check Valve Was Disassembled,Examined & Reassembled, Whereupon Valve Met Acceptance Criteria ML17313A4211998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Pvngs,Units 1,2 & 3.W/980609 Ltr ML17313A3951998-05-26026 May 1998 LER 98-005-00:on 980428,noted That Required Response Time Testing Had Not Been Performed.Caused by Personnel Error. Coached I&C Personnel Responsible for Reviewing Work Authorization Documentation ML17313A3691998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for PVNGS.W/980412 Ltr ML17313A3251998-04-0101 April 1998 LER 98-004-00:on 980304,safety Valves as-found Pressures Out of Tolerance.Cause of Event Is Under Investigation.Three Mssv'S & Psv Will Be Replaced W/Refurbished & Recertified Valves During Refueling Outage U1R7 1999-09-30 |
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Arizona Nuclear Power Project P.O. BOX 52034 e PHOENIX, ARIZONA 85072-2034 1397 n>g 4 g /// 0 74 2 2 04 lDffGl0;;l7jq U. S. Nuclear Regulatory Commission Region V 1450 Maria Lane - Suite 210 Walnut Creek, California 94596-5368 Attention: Mr. D. F. Kirsch, Director Division of Reactor Safety & Projects Palo Verde Nuclear Generating Station (PVNGS)
Units 1, 2, 3 Docket No. 50/528, 529, 530
Subject:
Reportability Evaluation Report - RER-QSE 87-05 A 50.55(e) and 10CFR21 Evaluation Relating to Travel Limit Switches on HVAC Dampers File: 87-006-216
Reference:
Telephone conversation between R. C. Sorenson and D. R. Larkin on February 17, 1987 (Initial Notification - RER-QSE 87-05)
Dear Sir:
The NRC was notified of the subject deficiency evaluation in the referenced telephone conversation, with a determination of reportability to be made within thirty (30) days (March 17, 1987).
The deficiency has subsequently been determined to be Not Reportable under the requirements of 10CFR50.55(e) and 10CFR21, therefore no written report is required. Necessary documentation of the evaluation will be maintained in ANPP files.
Very truly yours, fty J. G. Haynes Vice President Nuclear Production JGH/DRL/lks cc: See Page Two I, 0 h
5 8
RER-QSE 87-05 Mr. D. F. Kirsch Director
. March 5, 1987 023-02104-JGH/DRL Page Two cca J. M. Taylor, Director Office of Inspection and Enforcement
'U. S. Nuclear Regulatory Commission Washington, D. C. 20555 A. C. Gehr (4141)
R. P. Zimmerman (6295)
Records Center Institute of Nuclear Power Operations 1100 circle 75 Parkway - Suite 1500 Atlanta, Georgia 30339 L
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