Letter Sequence Other |
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Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance...
- Supplement, Supplement, Supplement, Supplement
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
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MONTHYEARNRC Generic Letter 1985-061985-04-16016 April 1985 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 ML20235V7111987-10-0808 October 1987 Informs That Final Design Review/Quality Revalidation Program & Remaining Responses to NRC 840131 Request Will Be Submitted by 871211.Delay in Submitting Response Due to Vibration Problems Project stage: Request 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
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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20155D4801998-10-27027 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 ML20217D3271997-07-30030 July 1997 Update of 1995 Decommissioning Evaluation for Rancho Seco Nuclear Generating Station ML20137W8151997-03-20020 March 1997 Amend 1 to Post Shutdown Decommissioning Activities Rept ML20217A5711990-08-28028 August 1990 Final Engineering Rept,Assessment of Spent Fuel Pool Liner Leakage ML20058B6521990-05-0404 May 1990 Rev 0 to ERPT-M0216, Property Loss Study for Rancho Seco Nuclear Generating Station in Long Term Defueled Mode ML20246F6301989-02-28028 February 1989 Auxiliary Feedwater Sys Overpressurization Event Engineering Evaluation Rept,Feb 1989 ML20154K8571988-08-24024 August 1988 Evaluation of Double Steam Line Break at Rancho Seco ML20151U4851988-07-31031 July 1988 Power Ascension Mid-Term Assessment of Plant Operations & Maint & Scheduling Activities ML20154M7381988-05-31031 May 1988 Assessment of Control Room Habitability Given Postulated Onsite Release of 20 Weight Percent Aqueous Ammonia ML20147E5361988-03-0707 March 1988 Control Room/Technical Support Ctr Habitability Study, Aqueous Ammonia Concentrations ML20147C3751988-03-0101 March 1988 Procurement Engineering Assessment Plan,Interim Rept ML20147E5201988-02-29029 February 1988 Control Room/Technical Support Ctr Habitability Study, Radiological Dose Assessment ML20147E4991988-02-29029 February 1988 Methodology for Revised Control Room X/Q Determination for Rancho Seco Nuclear Station ML20151U0241988-02-29029 February 1988 Rev 5 to Final Wire & Cable Program Rept for Rancho Seco Nuclear Generating Station ML20148C7641988-02-24024 February 1988 Rev 1 to Future Plant Capacity Factor Engineering Assessment ML20147G4881988-02-11011 February 1988 Preliminary Rept Rancho Seco Piping Vibration Tdi Diesels a & B 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 ML20148G2861988-01-31031 January 1988 Radioactive Liquid Effluent Sys Evaluation Using Program Liquid Effluent Based Operating Guides Rev II ML20149D3981988-01-19019 January 1988 Motor-Operated Valve Common Mode Failures During Plant Transients Due to Improper Switch Settings, Final Rept ML20148T1551987-12-31031 December 1987 Rev 4 to Wire & Cable Program Rept ML20147D3401987-12-31031 December 1987 Proposed Alarm Sys Mods NFPA 72D Compliance ML20234D8161987-12-0404 December 1987 Rev 0 to Resolution of Audit Findings Pertaining to Fire Pumps 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 ML20236U1321987-11-17017 November 1987 Review of Smud Emergency Operating Procedures ML20236B0101987-10-12012 October 1987 Expanded Augmented Sys Review & Test Program (Expanded Asrtp) Evaluation of Nuclear Svcs Electrical Bldg Essential & Normal HVAC Sys ML20236B0051987-10-0707 October 1987 Expanded Augmented Sys Review & Test Program (Expanded Asrtp) Evaluation of Component Cooling Water (CCW) & Turbine Plant Cooling Water (Tcw) Sys ML20236B0021987-10-0707 October 1987 Expanded Augmented Sys Review & Test Program (Expanded Asrtp) Evaluation of Auxiliary Feedwater Sys ML20236A9981987-10-0707 October 1987 Expanded Augmented Sys Review & Test Program (Expanded Asrtp) Evaluation of 480-Volt AC Distribution Sys ML20236A9921987-10-0707 October 1987 Expanded Augmented Sys Review & Test Program (Expanded Asrtp) Evaluation of Rcs ML20236A9891987-10-0707 October 1987 Expanded Augmented Sys Review & Test Program (Expanded Asrtp) Evaluation of Safety Features Actuation Sys ML20235V7951987-09-30030 September 1987 Response to NRC Questions on Geologic & Seismologic Conditions. W/Five Oversize Drawings Encl ML20235Y8891987-09-28028 September 1987 Rev 0 to Rept on Response to NRC IE Circular 79-02, Engineering Rept ML20235Q7301987-09-15015 September 1987 Pressurizer Heater Incident,Task 852 ML20239A0301987-09-0303 September 1987 Twelve Sys Assessment of Expanded Augmented Sys Review & Test Program Rept ML20239A1071987-08-31031 August 1987 Expanded Augmented Sys Review & Test Program (Expanded Asrtp) Evaluation of Radiation Monitoring Sys Sys ML20235Y6651987-08-31031 August 1987 Rereview of Plant Instrumentation & Control for IE Bulletin 79-27 ML20239A1041987-08-27027 August 1987 Expanded Augmented Sys Review & Test Program (Expanded Asrtp) Evaluation of Seal Injection & Makeup Sys ML20239A0891987-08-27027 August 1987 Expanded Augmented Sys Review & Test Program (Expanded Asrtp) Evaluation of Non-Nuclear Instrumentation Sys ML20239A0841987-08-27027 August 1987 Expanded Augmented Sys Review & Test Program (Expanded Asrtp) Evaluation of Nuclear Svc Cooling Water Sys ML20239A0821987-08-27027 August 1987 Expanded Augmented Sys Review & Test Program (Expanded Asrtp) Evaluation of 120 Volt AC Vital Power Sys Sys ML20239A0751987-08-27027 August 1987 Expanded Augmented Sys Review & Test Program (Expanded Asrtp) Evaluation of Main Feedwater Sys ML20239A0661987-08-18018 August 1987 Expanded Augmented Sys Review & Test Program (Expanded Asrtp) Evaluation of Main Steam Sys ML20239A0531987-08-18018 August 1987 Expanded Augmented Sys Review & Test Program (Expanded Asrtp) Evaluation of Nuclear Raw Water Sys ML20239A0461987-08-18018 August 1987 Expanded Augmented Sys Review & Test Program (Expanded Asrtp) Evaluation of Emergency Diesel Generator Sys ML20239A0431987-08-18018 August 1987 Expanded Augmented Sys Review & Test Program (Expanded Asrtp) Evaluation of Control Room/Technical Support Ctr Essential Hvac ML20239A0381987-08-18018 August 1987 Expanded Augmented Sys Review & Test Program (Expanded Asrtp) Evaluation of DHR Sys ML20239A0341987-08-18018 August 1987 Expanded Augmented Sys Review & Test Program (Expanded Asrtp) Evaluation of Integrated Control Sys ML20237J4241987-08-0505 August 1987 Evaluation of Integrated Control Sys ML20237J3871987-08-0404 August 1987 Evaluation of DHR Sys ML20237J3841987-08-0404 August 1987 Evaluation of Control Room/Technical Support Ctr Essential HVAC Sys 1998-10-27
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20211H7921999-08-13013 August 1999 Safety Evaluation Supporting Amend 126 to License DPR-54 ML20195D1901999-05-0606 May 1999 Annual Rept ML20195H8571998-12-31031 December 1998 1998 Annual Rept for Smud. 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 ML20248C4301998-05-0606 May 1998 Annual Rept, Covering Period 970507-980506 ML20249A7831997-12-31031 December 1997 1997 Smud Annual Rept ML20198G8271997-08-22022 August 1997 Safety Evaluation Supporting Amend 125 to License DPR-54 ML20217D3271997-07-30030 July 1997 Update of 1995 Decommissioning Evaluation for Rancho Seco Nuclear Generating Station ML20140A6371997-05-0606 May 1997 Annual Rept, Covering Period 960507-970506 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 ML20137W8151997-03-20020 March 1997 Amend 1 to Post Shutdown Decommissioning Activities Rept ML20141J2711996-12-31031 December 1996 Smud 1996 Annual Rept ML20138L1231996-11-13013 November 1996 Smud Rancho Seco Incremental Decommissioning Action Plan, Rev 0,961113 ML20129E7151996-10-14014 October 1996 Defueled SAR for Rancho Seco ML20059H6821994-01-17017 January 1994 Revised Rancho Seco Quality Manual 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 ML20056E5171993-08-31031 August 1993 Technical Review Rept, Tardy Licensee Actions ML20059K1981993-05-0606 May 1993 Annual Rept, Covering Period from 920501- 930506,consisting of Shutdown Statistics,Narrative Summary of Shutdown Experience & Tabulations of Facility Changes, Tests & Experiments,Per 10CFR50.59(b) ML20128C9641993-02-0202 February 1993 Informs Commission of Status of Open Issues & Progress of Specified Facilities Toward Decommissioning 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 ML20126E6771992-08-0303 August 1992 Rev 7 to Rancho Seco Quality Manual NL-90-451, Monthly Operating Rept for Oct 1990 for Rancho Seco Nuclear Generating Station1990-10-31031 October 1990 Monthly Operating Rept for Oct 1990 for Rancho Seco Nuclear Generating Station ML17348B5061990-10-0909 October 1990 Part 21 Rept Re Zener Diode VR2 on Power Supply Board 9 1682 00 106 Possibly Being Installed Backwards ML20059G9621990-09-10010 September 1990 Safety Evaluation Supporting Amend 115 to License DPR-54 NL-90-443, Monthly Operating Rept for Aug 1990 for Rancho Seco1990-08-31031 August 1990 Monthly Operating Rept for Aug 1990 for Rancho Seco ML20217A5711990-08-28028 August 1990 Final Engineering Rept,Assessment of Spent Fuel Pool Liner Leakage NL-90-439, Monthly Operating Rept for Jul 1990 for Rancho Seco Nuclear Generating Station1990-07-31031 July 1990 Monthly Operating Rept for Jul 1990 for Rancho Seco Nuclear Generating Station ML20055F8591990-07-16016 July 1990 Special Rept 90-11:on 900613,06,25,18,21 & 28,fire Barriers Breached More than 7 Days & Not Made Operable in 14 Days. Corrective Actions:Operability of Fire Detectors Verified on One Side of Breached Barriers NL-90-423, Monthly Operating Rept for June 1990 for Rancho Seco Nuclear Generating Station1990-06-30030 June 1990 Monthly Operating Rept for June 1990 for Rancho Seco Nuclear Generating Station ML20055C6291990-05-21021 May 1990 Special Rept 90-08:on 900419,fire Pump Batteries Inoperable When Surveillance Procedure SP.206 Not Performed by Due Date.Caused by Test Frequency Incorrectly Changed from Weekly to Monthly.Surveillance Schedule Revised ML20055C6301990-05-21021 May 1990 Special Rept 90-09:on 900424,25,30,31 & 0502,fire Barriers Inoperable for More than 7 Days,Per Tech Spec 3.14.6.2 Requirement.Hourly Fire Watches Established & Penetrations & Doors Returned to Operable Status ML20058B6521990-05-0404 May 1990 Rev 0 to ERPT-M0216, Property Loss Study for Rancho Seco Nuclear Generating Station in Long Term Defueled Mode 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 NL-89-634, Monthly Operating Rept for Aug 1989 for Rancho Seco Nuclear Generating Station1989-08-31031 August 1989 Monthly Operating Rept for Aug 1989 for Rancho Seco Nuclear Generating Station NL-89-598, Monthly Operating Rept for Jul 1989 for Rancho Seco Nuclear Generating Station1989-07-31031 July 1989 Monthly Operating Rept for Jul 1989 for Rancho Seco Nuclear Generating Station ML20247B3611989-07-17017 July 1989 Safety Evaluation Supporting Amend 112 to License DPR-54 NL-89-556, Monthly Operating Rept for June 1989 for Rancho Seco Nuclear Station1989-06-30030 June 1989 Monthly Operating Rept for June 1989 for Rancho Seco Nuclear Station ML20245E1161989-06-20020 June 1989 Safety Evaluation Supporting Amend 111 to License DPR-54 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 ML20245A1991989-06-0909 June 1989 Safety Evaluation Supporting Amend 110 to License DPR-54 ML20248B9361989-06-0505 June 1989 Safety Evaluation Supporting Amend 107 to License DPR-54 ML20248B6321989-06-0505 June 1989 Safety Evaluation Supporting Amend 108 to License DPR-54 ML20248B9621989-06-0505 June 1989 Safety Evaluation Supporting Amend 109 to License DPR-54 NL-89-517, Monthly Operating Rept for May 1989 for Rancho Seco Nuclear Generating Station1989-05-31031 May 1989 Monthly Operating Rept for May 1989 for Rancho Seco Nuclear Generating Station ML20247P1761989-05-30030 May 1989 Safety Evaluation Accepting Generic Ltr 83-28,Item 4.5.2 Re on-line Testing of Reactor Trip Sys ML20247N7491989-05-30030 May 1989 Special Rept 89-13:on 890328-29,specific Activity of Primary Sys Exceeded Limits in Administrative Procedure & Chemistry Control Commitment.Possibly Caused by Power Reduction.Isotopic Analysis Continued ML20247K7261989-05-23023 May 1989 Safety Evaluation Supporting Amend 105 to License DPR-54 1999-08-13
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Text
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'T ' E R PT. M OORG
. Report NO. 14850.35-AV3 JAN. 1987 i
CRANKSHAFT TORSIONAL VIBRATION MEASUREMENTS EMERGENCY DIESEL GENERATOR- 'A' RANCHO SECO NUCLEAR POWER PLANT PREPARED FOR SACRAMENTO MUNICIPAL UTILITY DISTRICT PREPARED BY E. BERCEL VIBRATION ENGINEERING l
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STONE & WEBSTER ENGINEERING CORPORATION BOSTON, MASSACHUSETTS 8801070121 DR 871229 g ADOCK 05000312 PDR l i
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TABLE OF CONTENTS
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J Section Title Page l
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SUMMARY
AND CONCLUSIONS ............... 3 1.0 OBJECTIVES ...................... ..... 4 2.0 TEST' EQUIPMENT ..................... .. 4 2.1 Diesel Generator Data ............ . 4 2.2 Instrumentation .................... 4 2.3 Calibration ........................ 5 3.0 MEASUREMENT AND TEST PROCEDURE ........ 5 3.1 Measurement Techniques . ........... 5 3.2 Test Procedure ..................... 5 Variable Speed Test .......... ..... 5 Variable Load Test ...... .......... 6 Transient Tests .................... 6 3.3 Data Reduction ..................... 6 4.0 TEST RESULTS .......................... 7 4.1 Variable Speed-No-Load Test ........ 7 4.2 Rated Speed, Variable Load Test .... 7 4.3 Transient Tests ................ ... 8 APPENDIX .............................. 9 Table 1 Instrumentation Frequency Response Data, :
Table 2 Torsional Vibration Data Variable Speed Test Table 3 Torsional Vibration Data Variable Load Test Figure 1 Instrumentation Schematic Figure 2 Variable Speed Data Plot Figure 3 Frequency Spectrum 440 rpm Figures 4-8 Variable Load Data Time Domain Figures 9-13 Variable Load Data Frequency Domain Figure 14 Variable Load Data Plot Figures 15-17 Fast Starts
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SUMMARY
AND CONCLUSIONS On November 15 1986 crankshaft torsional vibration measurements were performed on the Emergency Diesel Generator 'A' at the Rancho Seco Nuclear Plant. A careful review of the results indicate that the measurements are consistent and reliable.
At all load levels the 4.0 order (the firing frequency) was the dominant frequency component. All orders and the overall torsional vibration increased linearly with engine load. Both of those observations are normal for the type of engine involved.
The torsional vibration amplitudes at 100 and 110 per cent rated load were 1.2 and 1.3 degrees p p respectively. Those values are considerably lower , nan than the corresponding torsional vibration levels observed on two identical engines with identical crankshafts at the Shorehem and River Bend stations.
The crankshaft . stresses calculated for those engines were below DEMA's allowable stress values for both the single order and combined responses at all loads. Since the crankshaft of the three engines are identical, it may be concluded that the torsional vibration levels of the crankshaft of the Rancho Seco engine are acceptable.
The first natural frequency of the torsional system was found to be 38.3 Hz. This is in good agreement with TDI's Holzer calculations. The crankshaft resonance was excited in all fast starts. The largest response measured during a fast start was 2.9 degrees peak-to-peak. This value is close to what was ,
measured en an identical engine at River Bend. j 1
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L .,
9 3.
1.0 OBJECTIVES The objective of. the tests was to measure and record the torsional vibrations of the free end of the crankshaft under variable speed and variable load conditions. The torsional vibration data were to be reduced and presented in order to provide input for the stress analysis of the crankshaft.
2.0 TEST EQUIPMENT ..
1 i
Diesel Generator Data 2.1 Engine Manufacturer Transamerica Delaval Type DSR-48 Serial No. 81015-3057 Rated Output 3500 kW Bore & Stroke 17" x 21" L Engine speed 450 rpm l Firing Order 1,4,7,3,8,5,2,6 Generator Generator Output 3500 kW, 3-phase .
4375 kVA 607.2 Amps.
Service Factor 1.0 2.2 Instrumentation The following instrumentation was used during the test and in subsequent data analysis.
Description Make Model Serial No.
Torsional vibration transducer HBM BD 720 Carrier amplifier for above HBM KWS 3073 91215 Preamplifier Trig-Tek 205A 103 Top-dead-center indicator SWEC PE 3 Magnetic tape recorder (FM) TEAC R-71 160362 Dual-channel spectrum analyzer Nicolet 660B 5620079006 System control computer HP 9826 2205A04469 4
(. - - - - - - - _ _ _ _ _ _ _ _
- l. - .- 1 e r
- ke The instrumentation system used in the measurements and data
}y analysis ,c) illustrated in block-diagram form in Figure 1. The ,
e frequenc;iresponse characteristics of the individual components !
and that of the' system are tabulated in Table 1. l 1
a 2.3 Cal'ihration
, s to The tdreional vibration measurement system was calibrated end to end. With tae transducer mounted on the free end of the crankshaft a static input was applied to the transducer by deflecting th6 internal seismic mass with a magnet. The internal e
arrangement of the transducer, specified by the manufacturer, provides a + /* 3. 0 3 degree movement of the seismic mass between two precisely spLced stops. The resulting output of the system was reccrded on magnetic tape. ""e overall measurement accuracy ,
based on the above calibration is estimated to be +/- 0.008 degree.
h s
3.0 MEASUREMENT, ' REST AND ANALYSIS PROCEDURE 3.1 Measurement Techniques The torsional vibration transducer was mounted on the forward end of the-crankshaft and the vibration. signal was transmitted to the recording' equipment through~a set of slip-rings integral with the transducer. The reference signal that indicated the top-dead-center position of piston No. 7 was obtained as follows. The flywheel was painted black over one half of its perimeter and white over the other half. A photoelectric' sensor was positioned in place of the. flywheel pointer in such a way that the passing of .the black to white transition below the sensor was coincidental with the TDC position of the No. 7 piston within 0.15 degrees. The circuitry associated with the sensor generated a zero based square wave whose falling edge was coincident in time with the reference TDC position.
3.2 Test Procedure p
Variable Speed Test l
l The engine was started up and allowed to operate for 15 minutes I at rated speed-no-load. Using the mechanical governor, the speed was varied trom 400 rpm to 470 rpm in ten steps. The engine was allowed to stabili=e for three to five minutes at each speed and then a two-minute tape recording of the torsional vibration and q 5 L -_ - - - - _ - - - - - - - - - - - _ - - - - _ - - - - - _ _
~ .
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the top-dead-center reference signals was taken. Negligible speed variation was observed during data recording.
Variable Load Test After completion of the variable-speed tests the engine was brought to synchronous speed and synchronized on the external I grid. The generator load was then increased to full rated load in steps of 25 per cent, and then further increased to 110 per cent rated load. At each load level the system was allowed to stabilize for three to five minutes after which a two minute tape recording of the torsional vibration and the top-dead-center reference signals was taken.
Transient Tests The fast-start of the engine was recorded three times. Torsional' vibration and the TDC reference signals were recorded. The signal from the torsional vibration transducer represented the crankshaft acceleration with the torsional oscillations superimposed on it.
3.3 Data Reduction The tape recorded data were analyzed as follows. The torsional vibration signal was processed in the frequency domain to determine the frequency content corresponding to the engine orders and half orders. The analysis was performed in the 0-50 Hz range covering 6.5 engine orders. The ensemble average of 16 instantaneous spectra was obtained for each operating condition.
In order to measure the time averaged peak-to-peak amplitude of the torsional oscillations of the free end of the crankshaft ;
synchronous time averaging of the signal was performed. The TDC l reference signal served as the synchronizing trigger for this analysis. This assured that each time window was positioned at precisely the same point in the engine cycle. The number of samples averaged was 32. Since each sample contained 1.5 engine cycles the resulting average represented 48 engine cycles. All overall peak-to peak torsional vibration measurements were based on the above described synchronous time average.
The transient events were captured in the time domain on the signal analyzer and plotted. The feature of the torsional vibration transducer that its output at low frequencies is proportional to angular acceleration was utilized to obtain a crankshaft speed vs time plot during the start-up.
6
- - - _ _ _ - - - _ _ _ _ _9
e
. J 4.0 TEST RESULTS 4.1 Variable Speed-No-Load Test Traditionally, the variable speed test is performed to determine l the first torsional resonant frequency of the crankshaft. The i spectral content of the torsional vibration measured at the i various engine speeds is tabulated in Table 2. The peaks corresponding to the first twelve engine half-orders are given.
The values shown were obtained from frequency spectra not presented in this report. The peak-to-peak overall vibration amplitudes obtained from the synchronously time averaged data are also presented.
The overall torsional vibration and its frequency components corresponding to the 1.5, 2.5, 4.0, 4.5 and 5.5 engine orders have been plotted against engine speed in Figure 2. The first torsional resonance of the crankshaft is evident in the 415 rpm region in the curve corresponding to the 5.5 order component. At that speed the 5.5 order corresponds to 38 Hz. which can serve as an estimate for the frequency of the first torsional resonance.
The resonance is also visible in the vibration spectra in Figures 3 and 8 through 13 measured under various operating conditions.
It is particularly clear in in Figure 3, measured at 440 rpm where it is not obscured by other peaks. The' frequency read from Figure 3 is 38.3 Hz. The resonance is excited by small random disturbances of the system and it is detected readily under most operating conditions. Therefore, it is evident that the variable speed test is not strictly necessary for the determination of the frequency of the first torsional resonance of the crankshaft.
4.2 Rated Speed-Variable Load Test The synchronously averaged time-domain plots of the torsional vibration measured under the various load conditions are presented in Figures 4 through 8. Figures 9 through 13 contain the frequency spectra measured at the same operating conditions.
The vibration amplitudes corresponding to the various engine orders and the overall value of the torsional vibration have been tabulated in Table 3. The overall values were measured in the time-domain plots. The 1.5, 2.5, 4.0, 4.5 and 5.5 orders and the overall peak to peak torsional displacement have been plotted against engine load in Figure 14.
At all load levels the 4.0 order (the firing frequency) is the dominant frequency component. All orders and the overall torsional vibration increased linearly with engine load. Both of those observations are normal for this type of engine. The torsional vibration amplitudes at 100 and 110 per cent rated load were 1.2 and 1.3 degrees p p respectively. Those values are 7
considerably lower than the corresponding torsional vibration levels observed on two identical engines with identical crankshafts at the Shorehem and River Bend stations.
4.3 Transient Tests The torsional vibrations of the crankshaft recorded during three fast-starts of the engine have been plotted in Figures 15 through
- 17. The output of the torsional vibration transducer is proportional to torsional acceleration at frequencies below 3.0 Hz and to torsional displacement at frequencies above that.
Consequently, the steady state value of the trace in the center portion of the plot is the relatively constant angular I acceleration of the crankshaft. The oscillations superimposed on it represent torsional vibration. The bottom trace in each figure is the corresponding time history of the rotational speed of the crankshaft. It was obtained by numerical integration of the acceleration time history. As such it is a close approximation of the actual engine speed vs time curve.
During fast start the various higher engine orders pass through the first resonant frequency of the crankshaft. The strongest response, 2.86 degrees p-p occurred in the second fast start.
That amplitude is very close to the response measured at River Bend.
8
O
e APPENDIX l
l 9
W
.w TABLE 1 RANCHO SECO NUCLEAR POWER STATION BASELINE VIBRATION SURVEY, DG 'A' NOV. 13, 1986
SUMMARY
OF FREQUENCY RESPON2E CHARACTERISTICS Flat Equipment Model Serial No. Frequency Responce, H3 Tors. Transducer HBM BD ., 720 3-1000 Dicpt Cal. due 1/24/87 Signal Conditioner HBM KWS 3073 91215 0-1000 Cal. due 6/24/87 Preamplifier Trig-Tek 205B 103 0-100,000 Cal. due.7/23/87 Tape Recorder Teae R-71 160362 0-1250 Cal. due 4/16/87 FFT Analyser Nicolet 660B 5620079006. 1-20,000 Cal. due 10/8/86 Overall System Response Acceleration 0-1000 Displacement 3-1000
- h. - _ - _ . _ . . _ - _ . - _ _ . - - _ - - _
+:.'
- s. .
Table 2 TORSIONAL VIDRATION TEST, VARIABLE SPEED RANCHO SECO NUCLEAR POWER STATION, DG 'A' NOVEMBER 1986 Torsional Vibration Data Degrees Engine 400.0 rpm 410.0 rpm 415.0 rpm 420.0 rpm 425.0 rpm Orders p-p pp p-p pp pp.
0.5 0.051 0.050 0.047 0.048 0.016 1.0 0.003 0.005 0.002 0.004 0.004 1.5 0.070 0.069 0.070 0.073 0.070 2.0 0.003 0.003 0.004 0.004 0.001 2.5 0.059 0.062 0.062 0.060 0.062-3.0 0.002- 0.002 0.002 0.003 0.003 3.5 0.023 0.026 0.025 0.027 0.027 4.0 0.121 0.117 0.128 0.132 0.123 4.5 0.020 0.024 0.026 0.027 0.030 5.0 0.002 0.005 0.005 0.009 0.008 S.5 0.135 0.268 0.271 .0.177 0.167 6.0 0.023 0.016 0.014 0.010 0.010 Overall 0.340 0.458 0.468 0.359 0.356 Engine 430.0 rpm 440.0 rpm 450.0 rpm 460.0 rpm 470 0 rpm Ordars p-p p-p p-p p-p pp 0.5 0.052 0.046 0.056 0.043 0.012' I 1.0 0.004 0.004 0.004 0,004 0.005 1.5 0.069 0.071 0.075 0.072 0.070 2.0 0.004 0.005 0.005 0.006 0.007 2.5 0.064 0.064 0.066 0.06b 0.066 3.0 0.002 0.002 0.003 0.003 0.001 3.5 0.025 0.027 0.028 0.027 0.027 4.0 0.128 0.139 0.158 0.167 0.175 i
'4. 5 0.031 0.034 0.038 0.041 0.053 5.0 0.010 0.013 0.020 0.027 0.010 5.5 0.122 0.079 0.058 0.047 0 037 6.0 0.008 0.008 0.006 0.006 0.005 Overall* 0.332 0.317 0.331 0.336 0.344
- Overall p p degrees, determined from !
synchronous time averaging L __ _ _ _ _ :-_1 _ _ _ _ _ _ _ __ _ . _ _ . _ ____ ___ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ . _ _ _ - . _ _ . _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
/
Table 3 j l
TORSIONAL VIBRATION TEST, VARIABLE LOAD RANCHO SECO NUCLEAR POWER STATION, DG 'A' NOVEMBER 1986 Torsional Vibration Dat,a in Degrees Engine Load kW 875 1750 2625 3500 3850 Engine Torsional Vibration Orders p-p p-p pp pp p-p 0.5 0.071 0.053 0.097 0.189 0.217 1.0 0.001 0.002 0.005 0. 00;! 0.00P 1.5 0.121 0.184 0.241 0.308 0.343 2.0 0.005 0.004 0.003 0.001 0.002 2.5 0.099 0.147 0.192 0.244 0.265 3.0 0.001 0.001 0.001 0.003 0.002 3.5 0.043 0.066 0.086 0.104 0.113 4.0 0.254 0.039 0.515 0.633 0.670 4.5 0.053 0.080 0.106 0.128 0.133 5.0 0.038 0.061 0.079 0.092 0.101 5.5 0.085 0.130 0.178 0.221 0.233 6.0 0.007 0.000 0.013 0.015 0.016 Overall* 0.510 0.753 0.979 1.210 1.290
- Overall p p degrees determined from synchronous time averaging l
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