Letter Sequence Other |
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MONTHYEARML20134Q1741985-08-29029 August 1985 Part 21 Rept Re Potential Maint Issues Associated w/Anker-Holth Snubbers.Owners of Anker-Holth Snubbers Will Be Informed of Problems & Sent Revs to Technical Instruction Manuals to Include Procedures for Seal & Fluid Maint Project stage: Other 1985-08-29
[Table View] |
Part 21 Rept Re Potential Maint Issues Associated w/Anker-Holth Snubbers.Owners of Anker-Holth Snubbers Will Be Informed of Problems & Sent Revs to Technical Instruction Manuals to Include Procedures for Seal & Fluid MaintML20134Q174 |
Person / Time |
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Site: |
Monticello, Kewaunee, Point Beach, Arkansas Nuclear, Three Mile Island, Prairie Island, Brunswick, Ginna, 05000000, Trojan |
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Issue date: |
08/29/1985 |
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From: |
Fisher R PAUL-MUNROE HYDRAULICS, INC. |
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To: |
Deyoung R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
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References |
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REF-PT21-85, REF-PT21-85-388-000 PT21-85-388, PT21-85-388-000, TAC-08525, TAC-8525, NUDOCS 8509090198 |
Download: ML20134Q174 (5) |
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Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML20217N3271999-10-21021 October 1999 Part 21 Rept Re non-linear Oxygen Readings with Two (2) Model 225 CMA-X Containment Monitoring Sys at Bsep.Caused by High Gain Produced by 10K Resistor Across Second Stage Amplifier.Engineering Drawings Will Be Revised ML17265A7601999-10-0505 October 1999 Part 21 Rept Re W2 Switch Supplied by W Drawn from Stock, Did Not Operate Properly After Being Installed on 990409. Switch Returned to W on 990514 for Evaluation & Root Cause Analysis ML17265A7531999-09-23023 September 1999 Part 21 Rept Re Corrective Action & Closeout of 10CFR21 Rept of Noncompliance Re Unacceptable Part for 30-4 Connector. Unacceptable Parts Removed from Stock & Scrapped ML20217A1691999-09-22022 September 1999 Part 21 Rept Re Engine Sys,Inc Controllers,Manufactured Between Dec 1997 & May 1999,that May Have Questionable Soldering Workmanship.Caused by Inadequate Personnel Training.Sent Rept to All Nuclear Customers ML17265A7291999-07-29029 July 1999 Interim Part 21 Rept Re safety-related DB-25 Breaker Mechanism Procured from W Did Not Pas Degradatin Checks When Drawn from Stock to Be Installed Into BUS15/03A.Holes Did Not line-up & Tripper Pan Bent ML17265A6761999-06-16016 June 1999 Part 21 Rept Re Defects & noncompliances,10CFR21(d)(3)(ii), Which Requires Written Notification to NRC on Identification of Defect or Failure to Comply. Relays Were Returned to Eaton for Evaluation & Root Cause Analysis ML17265A6651999-05-27027 May 1999 Interim Rept Re W2 Control Switch,Procured from W,Did Not Operate Satisfactorily When Drawn from Stock to Be Installed in Main Control Board for 1C2 Safety Injection Pump. Estimated That Evaluation Will Be Completed by 991001 ML17265A6591999-05-17017 May 1999 Part 21 Rept Re Relay Deficiency Detected During pre-installation Testing.Caused by Incorrectly Wired Relay Coil.Relays Were Returned to Eaton Corp for Investigation. Relays Were Repaired & Retested ML17265A6381999-05-0707 May 1999 Part 21 Rept Re Replacement Turbocharger Exhaust Turbine Side Drain Port Not Functioning as Design Intended.Caused by Manufacturing Deficiency.Turbocharger Was Reaasembled & Reinstalled on B EDG ML17265A6361999-04-23023 April 1999 Part 21 Rept Re Power Supply That Did Not Work Properly When Drawn from Stock & Installed in -25 Vdc Slot.Power Supply Will Be Sent to Vendor to Perform Failure Mode Assessment.Evaluation Will Be Completed by 991001 ML17265A6551999-04-0909 April 1999 Initial Part 21 Rept Re Mfg Deficiency in Replacement Turbocharger for B EDG Supplied by Coltec Industries. Deficiency Consisted of Missing Drain Port in Intermediate Casing.Required Oil Drain Port Machined Open ML20154E2171998-09-28028 September 1998 Follow-up Part 21 Rept Re Defect with 1200AC & 1200BC Recorders Built Under Westronics 10CFR50 App B Program. Westronics Has Notified Bvps,Ano & RBS & Is Currently Making Arrangements to Implement Design Mods ML17265A4151998-09-10010 September 1998 Part 21 Rept Re 980325 Discovery of Missing Tripper Bar Tabs During Troubleshooting of DB-75 Breaker Failure.Caused by Failure to Notify Technician of Revised Procedure to Reinstall Tabs.Inspected All DB-75 Breakers 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 ML17265A4031998-08-12012 August 1998 Part 21 Rept Re W DB-75 Circuit Breakers W/Missing Tripper Bar Tabs.Caused by Intermittent Failure to Close in DB-75 B EDG Supply Circuit Breaker to Bus #16.Licensee Nuclear Engineering Personnel Are Performing Vendor Document Review ML20236X2351998-08-0505 August 1998 Part 21 Rept Re Defect Associated W/Westronics 1200AC & 1200BC Recorders Built Under Westronics 10CFR50,App B Program.Beaver Valley,Arkansas Nuclear One & River Bend Station Notified.Design Mod Is Being Developed ML20236J1051998-06-29029 June 1998 Part 21 30 Day Written Rept Re Refurbished DB-25 Circuit Breaker Returned W/Missing Pin in Operating Mechanism.Spare DB-25 Circuit Breaker Was Inspected,Tested & Installed to Restore B Service Water Pump to Service ML20249B7791998-06-22022 June 1998 Part 21 Rept Re Findings,Resolutions & Conclusions Re Failure of Safety Related Siemens 4KV,350 MVA,1200 a Circuit Breakers to Latch Closed ML17265A3181998-06-0808 June 1998 Part 21 Rept Re Receipt of Refurbished DB-25 Circuit Breaker W/Missing Part from W Replacement Components Svcs on 980608. Spare DB-25 Circuit Breaker Was Inspected,Tested & Installed to Restore B Swp to Svc 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 ML20217C2481998-04-21021 April 1998 Potential Part 21 Rept Re Failure of Siemens Circuit Breaker to Close Latch in Test Position W/Ge Test Flag Installed. Cause Indeterminate.Will Ship Identified Circuit Breakers to Siemens Mfg Facility in Wendell,Nc for Checking Procedure ML17309A6241998-01-15015 January 1998 Deficiency Rept Re Failure of Shunt Trip Coil Plunger to Return to Deenergized Position Resulting in Breaker Tripper Bar Being Maintained in Trip Free Position,Preventing DB-75 Air Circuit Breaker from Closing.Failed Assembly Replaced ML17264B1401997-12-22022 December 1997 Part 21 Rept Re Binding Plunger of Assembly Shunt Trip Coil on 971114.Failed Shunt Trip Coil Was Replaced W/Spare from Stock 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 ML20211M6491997-10-0808 October 1997 Addenda 1 to Part 21 Rept Re Weldments on Opposed Piston & Coltec-Pielstick Emergency stand-by Diesel gen-set lube-oil & Jacket Water Piping Sys.Revised List of Potentially Affected Utils to Include Asterisked Utils,Submitted ML20211H7911997-09-30030 September 1997 Part 21 Rept Re Failure of Weldment Associated w/lube-oil Piping Sys on 970804 at Millstone,Unit 2.Root Cause Is Not Yet Known.Quality of Weldment Is Being Considered.Listed Util Sites Affected ML17309A6211997-09-29029 September 1997 Part 21 Rept Re Final Disposition of Masterflow 713 & Embeco 636 Grout Nonconformance Reported by Master Builders,Inc. Licensee Continuing to Monitor shelf-life of Masterflow 713 & Embeco 636 Grouts Produced at Rancho Cucamonga 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 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 ML20140A4761997-05-27027 May 1997 Provides Addl Info to 970429 Part 21 Rept Re Potential safety-related Problem W/Asco HV 266000-007J Scram Solenoid Pilot Valves.Corrective Actions Also Listed ML20141K7711997-03-10010 March 1997 Preliminary Part 21 Rept Re Parsons Peebles/Electric Products Generators W/Modified Bearing Insulation.Util Implemented Mod to Add Insulation to Outer Spacer Ring ML20134B2301997-01-24024 January 1997 Final Part 21 Rept Re Potential Safety Concern on Matl Used for Fabrication of Permanent Canal Seal Plate.Correpondence W/Fabricator & Matl Supplier Documents Tig Automated Welding Process Used to Fabricate Angle Pieces 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 ML20132D8091996-12-18018 December 1996 Part 21 Rept Re Defect of Welds on Weld Nut Holding Filter Assembly Panel.Failure of Weld or Weld Nut Could Allow Filter Assembly Panel to Break Loose Under Seismic Stress & Cause Damage to Other Components in Charger ML17264A7301996-11-0606 November 1996 Part 21 Rept Re Defective 350 HP,1800 RPM,460 VAC,3 Phase, 5006P Frame,1.15 Sf,Vertical Hollow Shaft Motor Used as Service Water Pump motor.Safety-Relayed Cgiee Revised to Enhance Steps for Exam of Windings & Workmanship ML18065B0111996-10-18018 October 1996 Part 21 Rept Re Application of Certain Aspects of ABB-CE Safety Analysis Methodology ML17264A7331996-10-10010 October 1996 Part 21 Rept Re Defect in 350 HP,1800 RPM,460 VAC,3 Phase, 500GP frame,1.15 Sf Vertical Hollow Shaft Motor for Use as Svc Water Pump Motor.Motor Removed,Disassembled,Inspected, Refurbished,Reinstalled & Satisfactorily Tested ML20134L1081996-10-10010 October 1996 Part 21 Rept Re Defect in Component of Nordberg Model FS1316HSC Sdg.Nak Engineering,Inc Has Established & Adopted Procedures to Assemble Fuel Oil Lines & Climinate Possible Defective Condition ML20116H2031996-08-0505 August 1996 Part 21 Rept Re Potential Defect on Condition in Component of Nordberg Model FS1316HSC Sdg W/Fuel Injection Line Assembly Which Connects Fuel Pump to Injector.Caused by Loose Fuel Line Sleeve ML20115J3981996-07-22022 July 1996 Interim Part 21 Rept Re 3/4 Schedule 80 Pipe Furnished to Consolidated Power Supply.Investigation Revealed Only One Nuclear Customer Involved in Sale of Matl ML20115F2471996-07-0303 July 1996 Part 21 Rept Re Piping (Small Portion of Unmelted Matl Drawn Lengthwise Into Bar During Drawing Process) Defect That Existed in Bar as Received from Mill.Addl Insp Procedure for Raw Matl Instituted 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 ML20101N8441996-04-0505 April 1996 Interim Part 21 Rept Re Potential Safety Concern on Matl for Fabrication of Permanent Canal Seal Plate.Licensee Will Provide Final Rept to NRC in Approx Six Months Upon Completion of Evaluation of Welds ML20097A5641996-01-31031 January 1996 Final Part 21 Rept Re Ball Valves Supplied by Cardinal Industrial Products Containing Suspect Pressure Boundary Bolting.Valves Containing Suspect Bolts Returned to Canadian Worcester Controls Ltd to Have Bolting Replaced ML17264A1701995-09-28028 September 1995 Part 21 Rept Re Fuel Oil Booster Pump post-maint Testing Revealed Fuel Oil Sys Pressure Readings of 32 PSIG in Required Action Low Range.Plant Personnel Installed Rebuilt Fuel Oil Booster Pump on B EDG ML20092H3641995-09-13013 September 1995 Part 21 Rept Re 3/4 Inch ASME Section III Class 2 Ball Valves Supplied by Canadian Worcester Controls Ltd (Cwcl) ML20095K0361995-08-28028 August 1995 Part 21 Rept Re Failure of Diesel Min Operating Fuel Oil Pressure Pump Mfg by Tuthill Corp.Safety Hazard May Be Created If Emergency DG B Not Able to Maintain Design Load Rating.Pump End Play Clearance Adjusted ML20086T1761995-07-19019 July 1995 Part 21 Rept Re Potential Problem W/Type 51's & 87T Relays. Potential Problem Identified as Defective Tap Block. Recommends That Users Identified on Attachment 1 Page Verify Testing Per Instruction Listed on Encl Product Advisory Ltr ML17264A1091995-07-14014 July 1995 Part 21 Rept Re 14 Inch air-operated Butterfly Valve,Used as SW Outlet Valve AOV-4561 Supplied by Fisher Controls Co.On 950418,found That Valve Actuated Opposite from Required Configuration.Actuator Lever Reinstalled 1999-09-23
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217L8931999-10-31031 October 1999 Rev 1 to BAW-10235, Mgt Program for Volumetric Outer Diameter Intergranular Attack in Tubesheets of Once-Through Sgs ML20217N3271999-10-21021 October 1999 Part 21 Rept Re non-linear Oxygen Readings with Two (2) Model 225 CMA-X Containment Monitoring Sys at Bsep.Caused by High Gain Produced by 10K Resistor Across Second Stage Amplifier.Engineering Drawings Will Be Revised ML17265A7601999-10-0505 October 1999 Part 21 Rept Re W2 Switch Supplied by W Drawn from Stock, Did Not Operate Properly After Being Installed on 990409. Switch Returned to W on 990514 for Evaluation & Root Cause Analysis ML20212L1141999-10-0101 October 1999 Safety Evaluation Granting Request for Exemption from Technical Requirements of 10CFR50,App R,Section III.G.2.c ML20217D1261999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Monticello Nuclear Generating Plant.With 0CAN109902, Monthly Operating Repts for Sept 1999 for Arkansas Nuclear One,Units 1 & 2.With1999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Arkansas Nuclear One,Units 1 & 2.With NPL-99-0569, Monthly Operating Repts for Sept 1999 for Pbnp,Units 1 & 2. with1999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Pbnp,Units 1 & 2. with ML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data ML20217G4461999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Pingp.With ML20217K4701999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for TMI-1.With BSEP-99-0168, Monthly Operating Repts for Sept 1999 for Bsep,Units 1 & 2. with1999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Bsep,Units 1 & 2. with ML17265A7621999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Re Ginna Npp.With 991008 Ltr ML20216J6271999-09-27027 September 1999 Rev 0 to CALC-98-R-1020-04, ANO-1 Cycle 16 Colr ML17265A7531999-09-23023 September 1999 Part 21 Rept Re Corrective Action & Closeout of 10CFR21 Rept of Noncompliance Re Unacceptable Part for 30-4 Connector. Unacceptable Parts Removed from Stock & Scrapped ML17265A7541999-09-22022 September 1999 LER 99-011-00:on 990823,small Tears Were Discovered in Flexible Duct Work Connector at Inlet of CR HVAC Sys Return Air Fan (AKF08).Caused by in-leakage Greater than That Assumed.Implemented Temporary Mod 99-029.With 990922 Ltr ML20212F5261999-09-22022 September 1999 SER Approving Request Reliefs 1-98-001 & 1-98-200,parts 1,2 & 3 for Second 10-year ISI Interval at Arkansas Nuclear One, Unit 1 ML20217A1691999-09-22022 September 1999 Part 21 Rept Re Engine Sys,Inc Controllers,Manufactured Between Dec 1997 & May 1999,that May Have Questionable Soldering Workmanship.Caused by Inadequate Personnel Training.Sent Rept to All Nuclear Customers ML20212D5961999-09-15015 September 1999 Safety Evaluation Supporting Licensee IPEEE Process.Plant Has Met Intent of Suppl 4 to GL 88-20 NPL-99-0051, Monthly Operating Repts for Aug 1999 for Pbnp,Units 1 & 2. with1999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Pbnp,Units 1 & 2. with 0CAN099907, Monthly Operating Repts for Aug 1999 for Ano,Units 1 & 2. with1999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Ano,Units 1 & 2. with ML20216E7031999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Monticello Nuclear Generating Plant.With ML20212D0431999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Brunswick Steam Electric Plant,Units 1 & 2 ML17265A7471999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Re Ginna Npp.With 990909 Ltr ML20211H5111999-08-31031 August 1999 Non-proprietary Rev 1 to MPR-1820(NP), TMI Nuclear Generating Station OTSG Kinetic Expansion Insp Criteria Analysis ML20211Q3551999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Tmi,Unit 1.With ML20216E7151999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Pingp,Units 1 & 2. with ML20211F4281999-08-25025 August 1999 Safety Evaluation Concluding That Licensee Provided Acceptable Alternative to Requirements of ASME Code Section XI & That Authorization of Proposed Alternative Would Provide Acceptable Level of Quality & Safety ML20211D3981999-08-24024 August 1999 Safety Evaluation Supporting Requested Actions to Licenses DPR-42 & DPR-60,respectively ML17265A7431999-08-24024 August 1999 LER 99-004-01:on 990412,discovered That Containment Recirculation Fan Chevron Separator Vanes Were Installed Backwards.Caused by Improper Assembly by Mfg.Moisture Separator Vanes Were Dismantled & Correctly re-installed ML20210R4791999-08-13013 August 1999 Update 3 to Post-Defueling Monitored Storage SAR, for TMI-2 ML20210P9181999-08-10010 August 1999 Safety Evaluation Authorizing Request for Reliefs CIP-01,02, 06,07,08,09,10 & 11 (with Certain Exceptions) & 12-18,for Second 10-year ISI Interval.Request CIP-04 & 05 Would Result in hardship,CIP-03 Not Required & CIP-11 Denied in Part ML20210P9441999-08-10010 August 1999 Safety Evaluation Accepting Licensee Assessment of Impact on Operation of Plant,Unit 1,with Crack Indications of 2.11, 6.36 & 1.74 Inches in Three Separate Jet Pump Risers ML20210N2341999-08-0505 August 1999 SER Accepting Response to NRC GL 87-02, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Unresolved Safety Issues (USI) A-46 ML20210Q0521999-08-0404 August 1999 Safety Evaluation Approving Relief Request 10 to License DPR-22 Per 10CFR50.55a(g)(6)(i).Inservice Exam for Relief Request 10,Parts A,B,C,D & E Impractical & Reasonable Assurance of Structural Integrity Provided ML20211C2531999-08-0404 August 1999 Unit 1 ISI Summary Rept Interval 3,Period 2 Refueling Outage Dates 990425-990526 Cycle 19 971212-990526 ML20210Q4891999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Pingp,Units 1 & 2. with ML20211B5971999-07-31031 July 1999 Cycle 20 Voltage-Based Repair Criteria 90-Day Rept ML20210U4791999-07-31031 July 1999 Monthly Operating Rept for July 1999 for TMI-1.With ML20210R1191999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Bsep,Units 1 & 2 ML17265A7341999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Re Ginna Npp.With 990806 Ltr NPL-99-0449, Monthly Operating Repts for July 1999 for Pbnp,Units 1 & 2. with1999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Pbnp,Units 1 & 2. with 0CAN089904, Monthly Operating Repts for July 1999 for Ano,Units 1 & 2. with1999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Ano,Units 1 & 2. with ML20210Q6611999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Monticello Nuclear Generating Plant.With ML20210K8831999-07-29029 July 1999 Non-proprietary Addendum B to BAW-2346P,Rev 0 Re ANO-1 Specific MSLB Leak Rates ML17265A7291999-07-29029 July 1999 Interim Part 21 Rept Re safety-related DB-25 Breaker Mechanism Procured from W Did Not Pas Degradatin Checks When Drawn from Stock to Be Installed Into BUS15/03A.Holes Did Not line-up & Tripper Pan Bent ML17265A7181999-07-23023 July 1999 LER 99-007-01:on 990423,reactor Trip Occurred Due to Instrument & Control Technicians Inadvertently Pulling Fuses from Wrong Nuclear Instrument Channel.Setpoint Adjustments Were Completed by Different Crew of Technicians ML17265A7081999-07-22022 July 1999 LER 98-003-02:on 980904,actuations of CR Emergency Air Treatment Sys Was Noted Due to Invalid Causes.Caused by Various Degraded Components in CR RM Sys.Creats Actuation Signal Was Reset & Normal Ventilation Was Restored ML17265A7131999-07-22022 July 1999 Special Rept:On 990407,radiation Monitor RM-14A Was Declared Inoperable.Caused by Failed Communication Link from TSC to Plant Process Computer Sys.Communication Link Was re-established & RM-14A Was Declaed Operable on 990521 ML20210F8701999-07-22022 July 1999 Rev 1 to PGE-1076, Trojan Reactor Vessel Package Sar ML17265A7031999-07-19019 July 1999 LER 99-S01-00:on 990617,determined That Temporary Unescorted Access Had Been Granted to Contractor Employee.Caused by Incomplete Info Re Circumstances of Individual Military Separation.Individual Access Was Revoked.With 990719 Ltr 1999-09-30
[Table view] |
Text
_ _ _ _ _____-__-- --_______ -_--_--_ -- -
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29 August 1985 Mr. Richard C. DeYoung, Director Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Subject:
Seal and Fluid Maintenance of Anker-Holth equipment snubbers.
Reference:
Letter from R. Fisher of Paul-Munroe to Owners of Anker-Holth Snubbers, dated 29 August 1985.
Dear Mr. DeYoung,
During a recent N.R.C. vendor audit at the Paul-Munroe facility in Orange California, potential maintenance issues with regard to Anker-Holth snubbers were identified. In particular, the Anker-Holth Technical Instruction Manuals do not clearly specify a maintenance program that is, at this time, consistent with current industry standards for snubber seals or fluids. To rectify this situation, Paul-Munroe will first inform the owners of Anker-Holth snubbers that these potential problems exist and then revise the Technical Instruction
, Manuals to include specific procedures for seal and fluid maintenance.
Included with this letter is a copy of the notification which has been transmitted to the owners of Anker-Holth Snubbers.
If there are any questions regarding our action on this matter, please do not hesitate to contact me at (714) 978-9600 Very truly yours, PAUL-MUNROE INCORPORATED Ene Products D v s on 4%s Y 41 Y R rd C. Fisher Director of Engineering cc: Mr. Robert L. Pettis U.S. Nuclear Regulatory Commission 7 ((gb 4
, gt RCF:kcd 8509090198 850829 PDR ADOCK 05000244 lI 0144K S PM AttachmentVFACTURING e COMPONENTS
- SYSTEMS + INSTALLATION . SERVICE
. k "E #e:n Energy Products " ' **&yt!E Teiecopier (7 )9 (714) 978 9600 29 August 1985
Dear Sirs:
This letter is to notify the owners of Anker-Holth snubbers of the possibility that seal and fluid degradation may occur in these snubbers over extended periods of time. The Technical Maintenance Instructions provided by Anker-Hol th at the time of snubber delivery has been determined to be inconsistent with what now appears to be prudent maintenance procedures for seal s and fluids. Paul-Munroe will submit revisions to the Anker-Hol th manuals in the near future. A description of these forthcoming changes is provided below.
Seal Life -
The Anker-Holth Technical Instruction Manuals define the seal service life in terms of cumulative radiation exposure. Experience shows degradation of EPR or Viton A seals occurring faster than the OEM recommended seal service life due to other aging mechanisms such as compression set and temperature. The Anker-Holth Technical Instruction Manuals will be revised to recommend a nominal seal service life of 5 years.
Reservoir Fluid Levels - The Anker-Holth Technical Instruction Manuals provide inconsistent instructions on the checking of reservoir fluid level s. The Anker-Holth Technical :nstruction Manual will be revised to recomend that the reservoir be checked during each refueling outage.
Fluid Quality - The Anker-Holth Technical Instruction Manuals provide no fluid quality guidelines or sampling interval s for Silicone base fluids. The Anker-Holth Technical Instruction Manuals will be revised to recommend the following fluid quality guidelines and sampling intervals:
MANUFACTURING . COMPONENTS . SYSTEMS
29 August 1985 Page 2 o Fluid Cleanliness oo New fluid cleanliness level - SAE Class 4 or better oo Cleanliness level at 5 years - SAE Class 6 or better oo Sample frequency, quantity, and measurement techniques will be specified o Fluid Viscosity oo 150 - 200 centistokes at 750F + 150F o Fluid Water Content oo New fluid water content - less than or equal to 100 ppm oo Water content at specified sampling intervals - less than or equal to 150 ppm oo Water content test method - Karl Fis'1er method o Radiation exposure check - no evidence of coagulation Snubbers that have received the Paul-Munroe Tefzel seal upgrade along with new Technical Instruction Manuals are exempt from the concerns identified above.
If there are any questions regarding this matter, please do not hesitate to contact me at (714) 978-9600.
Very truly yours, PAUL-MUNROE INCORPORATED Energy Products Division i / f
% d '1 %
Richard C. Fisher l Director of Engineering
! cc: Richard C. DeYoung, Director l Office of Inspection and Enforcement, U.S. Nuclear Regulatory Commission l
l Robert L. Pettis, Inspector Office of Inspection and Enforcement, U.S. Nuclear Regulatory Commission l RCF:ked 0145K
. ' Portland General Electric Company 121 S.W. Salmon Street Portland, Oregon 97204 Attention Roger Weihage Portland General Electric Company 121 S.W. Salmon Street Portland, Oregon 97204
- Attention Arlen Wogen Carolina Power & Light H.B. Robinson S.E.G. Plant P.O. Box 790 Hartsville, S.C. 29550 Attention Warren Farmer Inservice Inspection Engineer ,
i GPU Nuclear Corporation 1
TMI Unit 1 i'
P.O. Box 480 Route 441 South i
Middletown, PA 17057 Attention Peter Snyder Preventative Maintenance Engineering GPU Nuclear Corporation TMI Unit 1 P.O. Box 480
- Route 441 South Middletown, PA 17057 Attention John Pearco Site Maintenance Engineering l
Rochester Gas and Elect'ric Co.
Robert E. Ginna Power Station 1503 Lake Road
! Ontario, New York 14519 3
Attention Jerry Schuler
- Maintenance Manager a
j American Electric Power l 1 Riverside Plaza P.O. Box 16631 Columbus, OH 43216-6631
! Attention Kas Santos, Senior Engineer I Mechanical Engineering Division I
Wisconsin Public Service Corp.
P.O. Box 48 Kewaunee, Wisconsin 54216 4
Attention Roger Lange Maintenance Supervisor Wisconsin Public Service Corp.
P.O. Box 48 Kewaunee, Wisconsin 54216 Attention Ken Weinhauer Nuclear Services Supervisor (Downtown)
Florida Power Corporation 3201 34th Street South P.O. Box 14042 St. Petersburg, Florida 33733 Attention Joe Masada Nuclear Project Engineer Wisconsin Electric Power Co.
231 W. Michigan Street P.O. Box 2046 i
Milwaukee, Wisconsin 53201 Attention Bill Herrman Maintenance Supervisor Point Beach Site Northern States Power Prairie Island R.R. #2 Welch, MN 55089 Attention Gerry Gore >
Maintenance Engineer Arkansas Power and Light Co.
, P.O. Box 551 Little Rock, Arkansas 72203 Attention Mark Browning Wisconsin Public Service Corporation 700 North Adams Street i Green Bay, Wisconsin 54301
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