ML20236N713: Difference between revisions
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| document type = DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21), TEXT-SAFETY REPORT | | document type = DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21), TEXT-SAFETY REPORT | ||
| page count = 3 | | page count = 3 | ||
| project = TAC:63030 | |||
| stage = Other | |||
}} | }} | ||
Latest revision as of 02:05, 20 March 2021
Letter Sequence Other | |
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TAC:63030, (Approved, Closed) | |
Initiation
Administration Questions
Results Other: A11745, Evaluation of DSR-48 Emergency Diesel Generator Crankshafts at Rancho Seco Nuclear Generating Station, ML20126J866, ML20126J973, ML20135E867, ML20149D631, ML20149F003, ML20196E677, ML20196E697, ML20206H162, ML20212B420, ML20214K863, ML20215G661, ML20234C529, ML20234C558, ML20234D524, ML20234D615, ML20234D649, ML20235M565, ML20235Q511, ML20236L543, ML20236N639, ML20236N713, ML20236S088, ML20237B265, ML20237B279 | |
MONTHYEARNRC Generic Letter 1985-061985-04-16016 April 1985
[Table View]NRC Generic Letter 1985-006: Quality Assurance Guidance for ATWS Equipment That Is Not Safety-Related Project stage: Request ML20126J9731985-06-0404 June 1985 Notice of Denial of Amend to License DPR-54 & Opportunity for Hearing Re Proposed Tech Spec Establishing Operability Requirements for Essential HVAC Sys Project stage: Other ML20126J8901985-06-0404 June 1985 Safety Evaluation Supporting Amend 68 to License DPR-54 Project stage: Approval ML20126J8661985-06-0404 June 1985 Amend 68 to License DPR-54,defining Operability & Surveillance Requirements for Plant Essential Electrical Sys & Operability Requirements for Components of Fire Protection Sys Project stage: Other ML20135E8721985-09-0909 September 1985 Safety Evaluation Supporting Amend 74 to License DPR-54 Project stage: Approval ML20135E8671985-09-0909 September 1985 Amend 74 to License DPR-54,revising Tech Specs to Define Testing Requirements for Pressurizer Heaters Powered from Class 1E Power Sources Project stage: Other ML20135E8571985-09-0909 September 1985 Forwards Amend 74 to License DPR-54 & Safety Evaluation. Amend Revises Tech Specs to Define Testing Requirements for Pressurizer Heaters Powered from Class 1E Power Sources Project stage: Approval ML20215C9951986-10-0202 October 1986 Forwards Replacement Pages Inadvertently Omitted from 860723 Amend 4 to Updated FSAR Re Reactor Vessel & Steam Generator Design Data Project stage: Request ML20212B3781986-12-19019 December 1986 Application for Amend to License DPR-54,consisting of Rev 1 to Proposed Amend 147,changing Electrical Distribution Sys. Design Basis Repts,Response to NRC Question from 861125 Telcon & Summary of Changes Encl Project stage: Request ML20212B4201986-12-19019 December 1986 Proposed Tech Specs Reflecting Changes to Electrical Distribution Sys & Mods to Inverter Power Supply Sys & Undervoltage/Overvoltage Protection Sys.W/Five Oversize Diagrams Project stage: Other ML20234D5241986-12-31031 December 1986 Baseline Vibration Survey Emergency Diesel Generator 'A' Rancho Seco Nuclear Power Plant Project stage: Other ML20234D6151986-12-31031 December 1986 Pipe Vibration Survey Emergency Diesel Generator 'A' Rancho Seco Nuclear Power Plant Project stage: Other ML20234D6491987-01-31031 January 1987 Crankshaft Torsional Vibration Measurements Emergency Diesel Generator 'A' Rancho Seco Nuclear Power Plant Project stage: Other A11745, Evaluation of DSR-48 Emergency Diesel Generator Crankshafts at Rancho Seco Nuclear Generating Station1987-02-28028 February 1987 Evaluation of DSR-48 Emergency Diesel Generator Crankshafts at Rancho Seco Nuclear Generating Station Project stage: Other ML20206H1281987-04-0101 April 1987 Application for Amend to License DPR-54,revising &/Or Adding Addl Sections to Tech Specs & Addressing Safety Impact of Bringing Tdi Diesel Generators Into Svc. Description of Proposed Changes Encl Project stage: Request IR 05000312/19870081987-04-0101 April 1987 Insp Rept 50-312/87-08 on 870209-0306.No Violations Noted. Major Areas Inspected:Licensee Program for Environ Qualified Electrical splices,follow-up of Insp Open Items,Ie Bulletins & Info Notices,Unresolved Items & LERs Project stage: Request ML20206E0561987-04-0101 April 1987 Commits to Broadening Scope of 870226 Upgrade of Meteorological Sys to Include Installation of fixed-width Guyed Tower Approx 120 Yards Southwest of Existing Tower,Per 870211 Meeting.Schedule Will Be Submitted within 30 Days Project stage: Meeting ML20206H1621987-04-0101 April 1987 Proposed Tech Specs Re Safety Impact of Bringing Tdi Diesel Generators on Line Project stage: Other ML20215G6611987-04-13013 April 1987 Informs That Seismic Qualification of Either of Listed Options Re Resolution of Issue of Class 1 Indication of Tdi Diesel Generator Status in Control Room Will Be Based on Generic Ltr 87-02,per 870401 Commitment Project stage: Other ML20214K8631987-05-18018 May 1987 Informs That Validations Re Tdi Diesel Generator Insps Completed & Phase I Rept Progressing Well.Some Difficulties Prevented Completion of Test Program & Rept to Support 870515 Submittal Date.Interim Rept Expected by 870630 Project stage: Other ML20234C5581987-06-10010 June 1987 Rev 0 to Rept on Conformance of Nuclear Svc Electrical Bldg & Diesel Generator Bldg Electrical Installation to Reg Guide 1.75 Project stage: Other ML20234C5291987-06-26026 June 1987 Forwards Rev 0 to ERPT-E0220, Rept on Conformance of Nuclear Svc Electrical Bldg & Diesel Generator Bldg Electrical Installation to Reg Guide 1.75, Per Discussions on 870602 & 03 Re Rev 2 to Proposed Amend 147 to License Project stage: Other ML20235M5651987-07-0808 July 1987 Forwards Design Review/Quality Revalidation (Dr/Qr) Program for Rancho Seco Tdi Diesel Generators, Final Engineering Summary Rept.Preliminary Turbocharger Final Rept Will Be Submitted by 871001 Project stage: Other ML20236N7131987-08-0505 August 1987 Part 21 Rept Re Potential Problem W/Vibration in Lube Oil & Jacket Water Sys.At Rancho Seco Site,Fatigue Cracks Found in Welds of Support Members in Lubricating Oil Sys.Cracks Due to Vibration in Lube Oil Sys.Addl Preventive Action Taken Project stage: Other ML20235F5251987-09-22022 September 1987 Forwards Supplemental Info Re Previous Submittal of Proposed Amend 147,Rev 2 Re Electrical Sys Tech Specs.Info Reflects More Restrictive Limiting Condition of Operation for Diesel Generators to Be out-of-svc Project stage: Supplement ML20235F5301987-09-22022 September 1987 Proposed Tech Specs Consisting of Supplemental Info to Proposed Amend 147,Rev 2 Re Diesel Generator Outages Project stage: Supplement ML20235Q4781987-10-0101 October 1987 Application for Proposed Amend 164 to License DPR-54, Consisting of Enhancements to Tech Specs to Resolve Certain Comments Resulting from NRC Region V Feb & Mar 1987 Contracted Comparison of Plant Tech Specs to Sts.Fee Paid Project stage: Request ML20235Q5111987-10-0101 October 1987 Proposed Tech Specs Re Comparison of Plant Tech Specs to STS Project stage: Other NL-87-1295, Forwards Supplemental Emergency Diesel Generator Info,Per NRC Request.W/One Oversize Drawing Change Notice1987-10-0808 October 1987 Forwards Supplemental Emergency Diesel Generator Info,Per NRC Request.W/One Oversize Drawing Change Notice Project stage: Supplement ML20236E9361987-10-26026 October 1987 Forwards Response to 871008 Request for Clarification & Info Re Emergency Diesel Generator Review Project stage: Request ML20236L5431987-10-30030 October 1987 Forwards Requested Addl Info Re Proposed Amend 147 to License DPR-54 & Plant Electrical Distribution Sys.Single Failure at Switch 52-4B202 Has No Safety Impact Project stage: Other ML20236N3211987-11-0909 November 1987 Forwards Three Pages Inadvertently Omitted from Util 871030 Response to NRC Request for Addl Info Re Proposed Amend 147 to License DPR-54 Project stage: Request ML20236N6391987-11-0909 November 1987 Confirms That 15% Damping Value Used During Design of Cable Tray Supports in Tdi Diesel Generator Bldg,In Response to Request Project stage: Other ML20236Q2381987-11-10010 November 1987 Forwards Safety Evaluation Supporting Plant Electrical Distribution Sys Design (Ref Tdi Diesel Generators).Approval of Design Required Before Performance of Loss of Offsite Power Test Project stage: Approval ML20236Q2461987-11-10010 November 1987 Safety Evaluation Supporting Util & Related Submittals Re Design Mods to Emergency Electrical Distribution Sys (Ref Tdi Diesel Generators) Project stage: Approval ML20236S0821987-11-17017 November 1987 Supplemental Application for Amend to License DPR-54, Consisting of Suppl 2 to Rev 2 to Proposed Amend 147, Concerning Diesel Generators Project stage: Supplement ML20236S0881987-11-17017 November 1987 Proposed Tech Specs,Consisting of Suppl 2 to Rev 2 to Proposed Amend 147,concerning Diesel Generators Project stage: Other ML20237B2791987-12-0101 December 1987 Rev 2 to Rept on Conformance of Nuclear Svc Electrical Bldg & Diesel Generator Bldg Electrical Installation to Reg Guide 1.75 Project stage: Other ML20237B2651987-12-0808 December 1987 Forwards Rev 2 to ERPT-E0220, Rept on Conformance of Nuclear Svc Electrical Bldg & Diesel Generator Electrical Installation to Reg Guide 1.75, Per Class 1 & 2 Cable Trays & Raceways Described in NUREG-1286,Section 4.7.3.2 a 1 & 2 Project stage: Other ML20234D5061987-12-29029 December 1987 Forwards Listed S&W & Failure Analysis Assoc Repts Re Vibration on Tdi Emergency Diesel Engines,In Response to M Hartzman 871215 Request for Addl Info Project stage: Request ML20149D6311988-01-0404 January 1988 Forwards Engineering Summary Repts for 16 Tdi Phase I Diesel Generator Components,Containing Detailed Info on Design Review/Quality Revalidation Program.Vibration Problems W/Turbocharger Support Bracket Resolved Project stage: Other ML20149F0031988-02-0101 February 1988 Informs of Intent to Submit Formal Rept Re Vibration Surveillance Program for Tdi Diesel Generators.Actions to Be Taken in Future to Monitor Diesels for Vibration Listed Project stage: Other ML20196E6971988-02-0505 February 1988 Rev 3 to Rept on Conformance of Nuclear Svc Electrical Bldg & Diesel Generator Bldg Electrical Installation to Reg Guide 1.75 Project stage: Other ML20149L2391988-02-0909 February 1988 Forwards Amend 94 to License DPR-54 & Safety Evaluation. Amend Changes Tech Specs to Reflect Addition of Two Diesel Generators & Associated Mods to Facility Emergency Electrical Distribution Sys Project stage: Approval ML20196E6771988-02-22022 February 1988 Forwards Rev 3 to ERPT-E0220, Rept on Conformance of Nuclear Svc Electrical Bldg & Diesel Generator Bldg Electrical Installation to Reg Guide 1.75, Presenting Clarification for Actual Configuration at Facility Project stage: Other 1987-12-29 |
ML20236N713 | |
Person / Time | |
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Site: | River Bend, Rancho Seco, 05000000, Shoreham |
Issue date: | 08/05/1987 |
From: | Guntrum B IMO DELAVAL, INC. |
To: | NRC |
References | |
REF-PT21-87, REF-PT21-87-156-000 141, PT21-87-156, PT21-87-156-000, TAC-63030, NUDOCS 8708120074 | |
Download: ML20236N713 (3) | |
Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML20154E2171998-09-28028 September 1998
[Table view]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 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 ML20203H9891997-12-12012 December 1997 Part 21 Rept Re Potential Manufacturing Defect of Enterprise DSR-4 & DSRV-4 Edgs.Cooper Energy Svcs Supplied 1A-7840 Adjusting Screw to Affected Utils & Sites.River Bend Station Replaced W/Acceptable Assemblies 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 ML20135D8011996-11-26026 November 1996 Part 21 Rept Re Two Safety Related Valves Supplied by Velan Valve Corp Were Not in Compliance W/Originally Supplied QA Documentation.Returned Valves to Velan in May 1996 & on 961120 Velan Advised That Valves Had Been Misplaced 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 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 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 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 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 ML20125C7161992-12-0707 December 1992 Part 21 Rept Re Possibility for Malfunction of Declutching Mechanisms in SMB/SB-000 & SMB/SB/SBD-00 Actuators. Malfunction Only Occurs During Seismic Event.Balanced Levers May Be Purchased from Vendor.List of Affected Utils Encl ML20127P5861992-11-23023 November 1992 Followup to 921005 Part 21 Rept Re Potential Defect in SB/SBD-1 Housing Cover Screws.Procedure Re Replacement of SBD-1 Spring Cover Bolts Encl.All Fasteners Should Be Loosened & Removed.List of Affected Utils Encl ML20118B4391992-09-11011 September 1992 Part 21 Rept Re Degradation in Abb Type 27N Undervoltage Relays Used in Electrical Switchgear.Recommends That Users Review Applications Requiring Exposures Greater than 1E03 Rads TID W/Time Delay Function Option ML20101R0641992-07-0808 July 1992 Part 21 Rept Re Defect in Forged Elbow SA234 Wpc.Initially Reported by Util on 920625.Connex Will Audit Quality Sys Prior to Awarding Purchase Orders to Ram Forge to Verify Measurements Taken on Elbow ML20101H5291992-06-25025 June 1992 Part 21 Re Forged Elbow Purchased by Connex Pipe Sys.Elbow Return to Connex to Be Repaired.Elbow Returned to Gulf States Util River Bend Station Unit 1 Along W/Associated Documentation 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 RBG-37042, Deficiency Rept:Employee Informed NRC of Defect in Forged Replacement Elbow Involving Numerous Areas Where Required Code & Design Min Wall Thickness Was Not Maintained.Licensee Returned Forged Elbow to Supplier1992-06-18018 June 1992 Deficiency Rept:Employee Informed NRC of Defect in Forged Replacement Elbow Involving Numerous Areas Where Required Code & Design Min Wall Thickness Was Not Maintained.Licensee Returned Forged Elbow to Supplier 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 ML17348B5061990-10-0909 October 1990 Part 21 Rept Re Zener Diode VR2 on Power Supply Board 9 1682 00 106 Possibly Being Installed Backwards ML20043A6091990-04-27027 April 1990 Part 21 Rept Re Defective Axial Cracks in Pump Shaft in Region Immediately Above Impeller & in Reactor Recirculation Pumps.Probably Caused by Crack Growth as Thermal Fatigue. Technical Advisory Bulletin Will Be Sent to Each Util ML20012A9011990-02-27027 February 1990 Suppls 900213 10CFR21 Rept Re Chilled Water Sys Operation. Evaluation of Crystal River Determined That Postulated High Energy Line Break in Intermediate Bldg May Be Subj to Steam Loads Higher than Normal Loads,Causing Rising Water Temp 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 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 ML18153C1011990-02-0202 February 1990 Part 21 Rept Re Two of Three Pc Cards in GE Type SLV11A1 Over/Undervoltage Relays Failing to Produce Output.Short Between Leads Would Result in Damage to Component 1C5. Sketch of Threshold Detection Board Encl 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 ML20005G6831990-01-0505 January 1990 Part 21 Rept Re Installation Instructions for Grommet Use Range for Patel Conduit Seal P/N 841206.Conduit Seals in Environ Qualification Applications Inspected for Proper Wire Use Range & Grommets Replaced ML19325E7271989-10-20020 October 1989 Part 21 Rept Re Defect in Eight GE Type CR 2940 Control Switches at Plant.Initial Condition Found on 890930.Contacts 3 & 4 for All Switches in Plant Sys Verified to Be in Correct Position for Intended Application ML19325E0861989-10-16016 October 1989 Followup Part 21 Rept Re Class 1E Battery Chargers W/ Transformers Running at Temps Exceeding Those Used in Qualification Rept When Operating at or Near Full Load Rating of Equipment.Listed Corrective Actions Underway RBG-31618, Part 21 Rept Re Defect in Standby Diesel Engine Replacement Rocker Arm Assembly Supplied by Cooper Industries.Caused by Use of Oversized Casting.Rocker Arm Assembly & Corrector Rod Replaced & Exhaust Valve Stems Readjusted1989-10-13013 October 1989 Part 21 Rept Re Defect in Standby Diesel Engine Replacement Rocker Arm Assembly Supplied by Cooper Industries.Caused by Use of Oversized Casting.Rocker Arm Assembly & Corrector Rod Replaced & Exhaust Valve Stems Readjusted ML19351A2941989-10-0909 October 1989 Part 21 Rept Re Potential of Ambient Compensated Molded Case Circuit Breakers to Deviate from Published Info. Instantaneous Trip Check Will Be Instituted on All Class 1E Thermal/Magnetic Ambient Breakers Prior to Shipment RBG-31583, Part 21 Rept Re Slow Closure of One Main Turbine Control Valve.Caused by Turbine Control Valve Assumed to Close Due to Unspecified Failure in Turbine Control Circuit.Standing Order Issued to Change Max Critical Power Ratio Limit1989-10-0202 October 1989 Part 21 Rept Re Slow Closure of One Main Turbine Control Valve.Caused by Turbine Control Valve Assumed to Close Due to Unspecified Failure in Turbine Control Circuit.Standing Order Issued to Change Max Critical Power Ratio Limit ML19325C9521989-09-29029 September 1989 Part 21 Rept Re Potential Common Failure of SMB-000 & SMB-00 Cam Type Torque Switches Supplied Prior to 1981 & 1976. Vendor Recommends That Switch W/Fiber Spacer Be Replaced 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 ML20246P7111989-07-17017 July 1989 Part 21 Rept Re Quench Cracks in Bar of A-SA-193 Grade B7 Component.Quench Cracks Found in One Bar of Matl.Listed Purchasers Informed of Potential Defect.Next Rept Will Be Submitted When Addl Info Becomes Available ML20247D3011989-07-12012 July 1989 Part 21 Rept 10CFR21-0047 Re Control Wiring Insulation of Inner Jacket Used on General Motors Diesel Generator Sets Identified as 999 or MP Series.Encl List of Owners of Units Notified RBG-31189, Supplemental Part 21 Rept Re Defect in safety-related Limitorque Valve Operators.Initially Reported on 880119.List of Limitorque Operators W/Wire Lug Defaults Encl.All Defects Corrected Prior to Restart1989-06-30030 June 1989 Supplemental Part 21 Rept Re Defect in safety-related Limitorque Valve Operators.Initially Reported on 880119.List of Limitorque Operators W/Wire Lug Defaults Encl.All Defects Corrected Prior to Restart ML20245B6651989-06-15015 June 1989 Part 21 Rept 150 Re Potential Defect in Component of Dsr Standby Diesel Generator.Cause of Failure Determined to Be Combination of Insufficient Lubrication to Bushings.Listed Course of Action Recommended at Next Scheduled Engine Maint 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 ML20244D8161989-04-13013 April 1989 Part 21 Rept Re Failure of Rosemount Transmitters.All Failed Transmitters Replaced,Inservice Test Procedure Prepared & Monthly Test of All 12 Transmitters in RCS Throughout Cycle 2 Operation Will Be Performed.Review Continuing 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 ML20207N4641988-10-12012 October 1988 Part 21 Rept Re Potential Problem W/Emd 20-645E4,Type 999 Excitation Sys Circuit Breaker & Wiring.Potential for Field Circuit Breaker to Trip Due to Combined Air Temps & Field Current Exists at All Plants W/Model 999 Sys ML20205F3211988-10-10010 October 1988 Part 21 Rept Re Potential Deviation from Tech Spec Concerning Ry Indicators Due to Operating Temp Effect on Analog Meter Movement.Initially Reported on 881006.Customers Verbally Notified on 881006-07 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 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 ML20245D9541988-09-0606 September 1988 Part 21 Rept Re Condition Involving Inconel 600 Matl Used to Fabricate Steam Generator Tube Plugs & Found to Possess Microstructure Susceptible to Stress Corrosion Cracking CEO-88-113, Part 21 Rept Re Mfg Defect W/Gould Model PD3200 Pressure Transmitters.Three Failed Units Removed from Svc & Returned to Mfg for Analysis.Engineering Action Plan Formulated to Monitor Subj Transmitters & Replace Any Defective Devices1988-08-0808 August 1988 Part 21 Rept Re Mfg Defect W/Gould Model PD3200 Pressure Transmitters.Three Failed Units Removed from Svc & Returned to Mfg for Analysis.Engineering Action Plan Formulated to Monitor Subj Transmitters & Replace Any Defective Devices ML20155C4091988-05-16016 May 1988 Part 21 Rept 88-03 Re Potential Problem W/Gems Sensors Model 63328A Modular Receivers.Modular Receivers Qualified Toggle Switch Installed 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 ML20154A8781988-05-0909 May 1988 Rev 1 to Part 21 & Deficiency Rept 88-02 Re Improper Mounting of Armature Button on Undervoltage Device Armature. CRD Trip Breaker Removed from Svc & Placed in QC Quarantine & Maint Procedure Revised for Armature Defect 1998-09-28 Category:TEXT-SAFETY REPORT MONTHYEARRBG-45144, Monthly Operating Rept for Sept 1999 for River Bend Station. with1999-09-30030 September 1999
[Table view]Monthly Operating Rept for Sept 1999 for River Bend Station. with ML20216G1201999-09-0909 September 1999 Rev 3 to Rbs,Cycle 9 Colr RBG-45110, Monthly Operating Rept for Aug 1999 for River Bend Station, Unit 1.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for River Bend Station, Unit 1.With ML20211H7921999-08-13013 August 1999 Safety Evaluation Supporting Amend 126 to License DPR-54 RBG-45087, Special Rept:On 990510,LPCI a & LPCS Injected Into Rv for Less than Two Minutes.Caused by Electrical Transient in One of ECCS Power Supplies.Operators Verified Reactor Cavity Level & Closed Injection Valves to Stop Injection1999-08-0606 August 1999 Special Rept:On 990510,LPCI a & LPCS Injected Into Rv for Less than Two Minutes.Caused by Electrical Transient in One of ECCS Power Supplies.Operators Verified Reactor Cavity Level & Closed Injection Valves to Stop Injection ML20210K4721999-08-0303 August 1999 SER Accepting Licensee 180-day Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves RBG-45091, Monthly Operating Rept for July 1999 for River Bend Station, Unit 1.With1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for River Bend Station, Unit 1.With ML20210C6391999-07-0202 July 1999 Rev 2 to River Bend Station,Cycle 9 Colr RBG-45055, Monthly Operating Rept for June 1999 for River Bend Station, Unit 1.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for River Bend Station, Unit 1.With ML20196J8031999-06-24024 June 1999 Rev 1 to Rbs,Cycle 9 Colr RBG-45028, Monthly Operating Rept for May 1999 for River Bend Station, Unit 1.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for River Bend Station, Unit 1.With ML20195D1901999-05-0606 May 1999 Annual Rept RBG-45016, Monthly Operating Rept for Apr 1999 for River Bend Station, Unit 1.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for River Bend Station, Unit 1.With ML20206A2111999-04-21021 April 1999 Safety Evaluation Authorizing Pump Relief Request PRR-001 & Valve Relief Request VRR-001 & Denying Valve Relief Request VRR-002 RBG-44969, Monthly Operating Rept for Mar 1999 for River Bend Station, Unit 1.With1999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for River Bend Station, Unit 1.With ML20205S0601999-03-31031 March 1999 Rept on Status of Public Petitions Under 10CFR2.206 with Status Change from Previous Update,990331 ML20205D5481999-03-26026 March 1999 SER Accepting Util Proposed Alternative to Exam Weld AA with Weld Volume Coverage of 62 Percent for First 10-year Insp Interval Pursuant to 10CFR50.55a(a)(3)(ii) & 10CFR50.55a(g)(6)(ii)(A)(5) RBG-44930, Monthly Operating Rept for Feb 1999 for River Bend Station, Unit 1.With1999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for River Bend Station, Unit 1.With RBG-44826, Monthly Operating Rept for Dec 1998 for River Bend Station Unit 1.With1998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for River Bend Station Unit 1.With ML20195H8571998-12-31031 December 1998 1998 Annual Rept for Smud. with ML20198K2701998-12-22022 December 1998 Rev 1 to RBS Cycle 8 Colr RBG-44773, Monthly Operating Rept for Nov 1998 for River Bend Station, Unit 1.With1998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for River Bend Station, Unit 1.With RBG-44727, LER 98-S01-00:on 981021,identified That Contract Employee with Temporary Access Authorization Failed to Disclose Complete Criminal & Employment History.Individual Denied Access to Plants for Five Years.With1998-11-17017 November 1998 LER 98-S01-00:on 981021,identified That Contract Employee with Temporary Access Authorization Failed to Disclose Complete Criminal & Employment History.Individual Denied Access to Plants for Five Years.With ML20195C4841998-11-0606 November 1998 SER Accepting QA Program Change to Consolidate Four Existing QA Programs for Arkansas Nuclear One,Grand Gulf Nuclear Station,River Bend Station & Waterford 3 Steam Electric Station Into Single QA Program ML20155H3491998-11-0303 November 1998 Safety Evaluation Granting Requests for Relief RR2-0001, RR2-0002 & RR2-0003 RBG-44719, Monthly Operating Rept for Oct 1998 for River Bend Station, Unit 1.With1998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for River Bend Station, Unit 1.With ML20155D4801998-10-27027 October 1998 Amend 3 to Rancho Seco DSAR, Representing Updated Licensing Basis for Operation of Permanently Shutdown & Defueled Rancho Seco Nuclear Facility During Permanently Defueled Mode ML20155C1351998-10-26026 October 1998 Rev B to Entergy QA Program Manual RBG-44677, Monthly Operating Rept for Sept 1998 for River Bend Station, Unit 1.With1998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for River Bend Station, Unit 1.With 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 ML20151S5421998-09-0303 September 1998 Safety Evaluation Opposing Licensee Thermal Model as Currently Implemented.Evaluation Recommended to Be Used in Any follow-up Site Insp RBG-44629, Monthly Operating Rept for Aug 1998 for River Bend Station, Unit 1.With1998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for River Bend Station, Unit 1.With 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 RBG-44600, Monthly Operating Rept for July 1998 for River Bend Station1998-07-31031 July 1998 Monthly Operating Rept for July 1998 for River Bend Station RBG-44564, Monthly Operating Rept for June 1998 for River Bend Station, Unit 11998-06-30030 June 1998 Monthly Operating Rept for June 1998 for River Bend Station, Unit 1 ML20249A6431998-06-12012 June 1998 SER Accepting 980427 Request for Change to River Bend QA Manual Program Description,Per 10CFR50.54(a)(3) RBG-44539, Monthly Operating Rept for May 1998 for River Bend Station, Unit 11998-05-31031 May 1998 Monthly Operating Rept for May 1998 for River Bend Station, Unit 1 ML20248C4301998-05-0606 May 1998 Annual Rept, Covering Period 970507-980506 RBG-44501, Monthly Operating Rept for Apr 1998 for River Bend Station, Unit 11998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for River Bend Station, Unit 1 ML20217M8951998-04-30030 April 1998 QA Program Manual ML20217P8281998-04-0707 April 1998 Safety Evaluation Accepting Relief Authorization for Alternative to Requirements of ASME Section Xi,Subarticle IWA-5250 Bolting Exam for Plants,Per 10CFR50.55a(a)(3)(i) RBG-44458, Monthly Operating Rept for Mar 1998 for River Bend Station, Unit 11998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for River Bend Station, Unit 1 RBG-44423, Monthly Operating Rept for Feb 1998 for River Bend Station Unit 11998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for River Bend Station Unit 1 ML20203L6631998-02-11011 February 1998 Rev 0 to River Bend Station,1998 Emergency Preparedness Exercise RBG-44385, Monthly Operating Rept for Jan 1998 for River Bend Station, Unit 11998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for River Bend Station, Unit 1 RBG-44460, Forwards Annual Radiological Environmental Operating Rept, for Period Jan-Dec 19971997-12-31031 December 1997 Forwards Annual Radiological Environmental Operating Rept, for Period Jan-Dec 1997 RBG-44353, Monthly Operating Rept for Dec 1997 for River Bend Station, Unit 11997-12-31031 December 1997 Monthly Operating Rept for Dec 1997 for River Bend Station, Unit 1 ML20249A7831997-12-31031 December 1997 1997 Smud Annual Rept ML20203H9891997-12-12012 December 1997 Part 21 Rept Re Potential Manufacturing Defect of Enterprise DSR-4 & DSRV-4 Edgs.Cooper Energy Svcs Supplied 1A-7840 Adjusting Screw to Affected Utils & Sites.River Bend Station Replaced W/Acceptable Assemblies ML20202E9941997-12-0101 December 1997 ISI Plan Second Ten-Yr Interval (Dec 1,1997-Nov 30,2007) 1999-09-09 |
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Imo Delaval Inc.
Enterprise Engine Division Enterprise Way and Mth Avenue I D Oakland, CA 94621 P. O ikix 2161 415 577-7400 August 5, 198/
Director, Office of Inspection and Enforcement US Nuclear Regulatory Commission Washington, DC 205S3 Report #141 i
Dear Sir,
in accorance with the requirements of Title 10, Chapter 10, Code of Federal Regulations, Part 21, IMO Delaval Inc.
hereby notifies the Commission of a potential defect in a component of a DSR engines Standby Diesel Generatbr. There exists a potential problem with vibration in the lube oil and jacket water systems.
IMO Delaval has supplied DSR with this potential defect to tne f ollowing sites:
MIILill M11b 9tM1AL NO. MOpEL LlLCO Shoreham 74010-12 DSR-48 GULF STATES Hiver Band 740J9-40 DSR-48 SMUD Rancho Seco 81015-16 DSH-48 At tne Rancho Seco site, fatigue cracks have been found in the welds of support members in the lubricating oil system.
Tnese cracks are due to vibration in the lube oil system believed to be induced by the on-engine lube oil pump. These cracks nave occured in supports and welded joints resulting in minor lube oil leakage. It is reasonable to postulate, however, that left uncorrected the lube oil piping could ultimately fail causing a sufficient loss of lube oil to render tne diesel engine inoperable. ;
Vibration in the jacket water system at the same site has resulted in a minor violation of the pressure boundary.
Again, left uncorrected this crack could propagate to the point wnere a major failure could occur rendering the diesel engine Inoperative. In this case, probable cause has not been determined, requiring further investigation.
In neither case, is there concern of an immediate failure.
There are alarms in the systems to alert the operators of a pressure boundary failure. Additionally, the potential problems are of a progressive nature, not susceptible to an immediate catastrophic failure mode.
8708120074 G70805 ,
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Page 2 August 5, 1987 US Nuclear Regulatory Commission Corrective action is being taken at the Rancho Seco site with additional preventive action being investigated. Wnile the other listed sites have similar system and component designs, neither excessive vibration nor reiated failures of piping or supports have been reported. It is recommended, however, that these sites monitor the subject syste=s and report any excessive vibration levels to IMO Delaval Customer Services.
A copy of tnis ietter will be sent to all of the sites referenced in Paragraph 2 of this letter as indicated by the carbon copy iist.
Our evaluation of this matter was concluded on August 3, 1987.
Very truly yours,
, w=
3 e_ , 4 I
Bruce C. Guntrum Manager, Quality Assurance BCG/dfa
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Page 3 August 5, 1987 US Nuclear Hegulatory Commission c.c. Long Island Lighting Company Shoreham Nuclear Power Station North Country Road Wading River, New York 11791 Attn: Mgr. Nuclear Operations Support Dept.
Gulf States Utilities Company Stone & Weoster Engineering Company Cherry Hill Operations Center 3 Executive Campus P.O. Box 5200 Cherry Hill, New Jersey 08034 Attn: Project Manager (J.O. #12210)
Gult States Pro.iect Sacramento Municipal Utility District P.O. Box 16830 Sacramento, CA 95813 Attn: Mr. Cranston Nuclear Engineering Dept. M.S. 208 Judy R. Beal Purchasing Dept. M.S. 50 1
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