ML20136A939
ML20136A939 | |
Person / Time | |
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Site: | Rancho Seco |
Issue date: | 11/08/1985 |
From: | Reinaldo Rodriguez SACRAMENTO MUNICIPAL UTILITY DISTRICT |
To: | Martin J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
References | |
REF-PT21-85, REF-PT21-85-480-000 PT21-85-480, PT21-85-480-000, RJR-85-546, NUDOCS 8511200086 | |
Download: ML20136A939 (2) | |
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Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML20140G4481997-05-0101 May 1997
[Table view]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 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 ML20034F7031993-02-25025 February 1993 Amend 1 to Enterprise Rept 162 Re Defect on Starting Air Distributor Housing Assembly,As Followup to 930115 Final Rept.Addl Listed Part Numbers Discovered Which Are Higher Level Assemblies of Housing ML20127H2301993-01-15015 January 1993 Part 21 Rept Re Potential Defeat in Component of Dsrv & Dsr Enterprise Standby DG Sys.Starting Air Distributor Housing Assemblies Installed as Replacement Parts at Listed Sites ML20126B0421992-12-17017 December 1992 Final Part 21 Rept Re Potential Problem W/Steel Cylinder Heads.Initially Reported on 921125.Caused by Inadequate Cast Wall Thickness at 3/4-inch-10 Bolt Hole.Stud at Location Indicated on Encl Sketch Should Be Removed ML20125C7161992-12-0707 December 1992 Part 21 Rept Re Possibility for Malfunction of Declutching Mechanisms in SMB/SB-000 & SMB/SB/SBD-00 Actuators. 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CRD Trip Breaker Removed from Svc & Placed in QC Quarantine & Maint Procedure Revised for Armature Defect ML20153B6191988-04-29029 April 1988 Part 21 Rept Re Potential Defect in Component of Dsr or Dsrv Standby Diesel Generators Supplied to Utils.Recommends Return of Subj Components in Onsite Warehouse Storage & Suggests Surveillance of Devices Already Installed ML20151J5001988-04-0707 April 1988 Part 21 & Deficiency Rept 88-02 Re Improper Mounting of Armature Button on Undervoltage Device Armature.Maint Procedure for CRD Trip Breaker Revised to Include Checks for Defects Discovered W/Undervoltage Device ML20196D6281988-02-10010 February 1988 Part 21 Rept Re Potential Defect in Certain Model RTF-480/120-30 Ac Line Regulating Transformers Involving Nuisance Tripping of 100 Ampere Ac Input Circuit Breaker When Initializing Unit.Breaker Should Be Replaced ML20237G5781987-08-0707 August 1987 Part 21 & Deficiency Rept 142 Re Defect in Starting Air Distributor Sys of Dsr Standby Diesel Generator.Drain Sys Will Be Permanently Installed in Start Air Distributor 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 ML20236M9581987-07-20020 July 1987 Part 21 Rept 7 Re Cracks & Chipping Discovered on Bus Bar Insulators Mounted on Power Conversion Products,Inc. 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Insulation Resistance at High Temp Not High Enough for Ion Chamber & Associated Electronics to Operate Properly ML20211M9231987-02-10010 February 1987 Part 21 & Deficiency Rept Re Warped Geared Limit Switch Rotors Supplied by Limitorque Corp.Initially Reported on 870205.Internal Occurrence Description Rept Initiated. Limitorque Corp Will Provide Itemization of Affected Plants ML20215G7591986-10-0101 October 1986 Part 21 Rept Re Deficiencies in Tdi Time Delay Relays. 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Caused by Improper Handling/Storage.Advisory Bulletin Encl. Item Not Reportable Per Part 21 ML20206S0841986-06-30030 June 1986 Part 21 Rept Re Possible Cut Wires in Wire Harness of Bbc Brown Boveri K600/K800 Circuit Breakers.Initially Reported on 860509.Safety Implications Listed.Gear Guard Designed to Prevent Cut Wires ML20211N5951986-06-10010 June 1986 Part 21 Rept Re Cracked Limit Switch Rotors for Motor Operated Valves Supplied by Limitorque.Initially Reported on 860610.White (Melamine) Rotors Found Cracked Will Be Replaced W/Brown (Fibrite) Replacements ML20195D2171986-05-27027 May 1986 Rev 1 to Part 21 Rept Re Dowel Displacement on Connecting Rod Bearings Purchased During Nov 1985 - Apr 1986.Initially Reported on 860421.Rod Bearings Will Be Inspected Dimensionally.Further Info Forthcoming ML20154N3431986-03-10010 March 1986 Initial Part 21 Rept 135 Re Potential Problem W/Lube Oil Sump Tank Foot Valve of Dsrv Standby Diesel Generator for Facilities.Cause Not Determined.Recommends Utils Inspect Condition of Foot Valve Liners & Notify Tdi of Findings ML20140A5281985-12-19019 December 1985 Part 21 Rept Forwarding Ltr Sent to Customers Re Check Valves Missing Lock Welds on Hinge Supports or Hinge Support Capscrews,Per 851121 Request.List of Customers Receiving Ltr Also Encl ML20136B0221985-11-0808 November 1985 Part 21 & Deficiency Rept Re Unreliable Porthole Oil Level Gauge for Auxiliary Feedwater Pumps Supplied by B&W.Metal Insert Behind Sight Glass Trapped Oil Causing False Level Indication.Metal Insert Removed ML20136A9391985-11-0808 November 1985 Part 21 & Deficiency Rept Re Rev B to Rosemont Instruction Manual 4302 Not Addressing Zero Shift Due to Process Pressure in Model 1153 Alphaline Nuclear Pressure Transmitter ML20198C4981985-11-0606 November 1985 Part 21 Rept Re Potential Defect in Dsr or Dsrv Standby Diesel Generator Intake & Exhaust Valve Springs Mfg by Betts Spring Co.Users Recommended to Inspect Engines for Broken Springs & Identify Original Mfg ML20205C6891985-09-17017 September 1985 Part 21 Rept Re Potential Defect in Centerline,Inc Lube Oil Check Valves of Dsr Standby Diesel Generator Which Could Result in Engine Nonavailability.Valve Seat Matl Will Be Changed to Buna N.List of Tdi Part 21 Repts Encl ML20132B0261985-09-0303 September 1985 Part 21 Rept Re Possibility of Engine Ingestion of Unwelded Part in American Air Filter Standby Diesel Generator Intake Silencer.Immediate Hold Should Be Placed on Diesel Engines/Intake Silencers Not Yet in Svc ML20127H5411985-05-17017 May 1985 Part 21 Rept Re Potential Defect in Engine Generator Control Panels of Dsr or DSRV-16 Standby Diesel Generator.Review of Generator Control Panel Installation by Each Facility Recommended ML20024D2961983-07-29029 July 1983 Part 21 Rept Re Small Break Operating Guidelines Not Considering Overcooling Transients Caused by Disregarding Extent or Rate of Cooldown.Instructions Sent to Affected Plants Explaining Potential Misuse of Guidelines ML20024D1971983-07-27027 July 1983 Part 21 Rept Re 8-inch Mfg Splice Detected within Cable Shipped to Ranch Seco 1 During 1979.Caused by Mfg Operator Not Following Procedure.Training Classes Conducted & Cable Returned ML20054J9111982-06-23023 June 1982 Part 21 Rept Re Potential Defect in Couplings Drive Element of Dsrv or Dsr Standby Diesel Generator.Affected Licensees Will Be Notified No Later than 820715 ML20054M4631982-05-10010 May 1982 Part 21 Rept Re Defective Cable Code K2S,initially Reported 820506.Cable Reel Quarantined.Brand Rex Co Investigating ML20010F7911981-08-27027 August 1981 Part 21 Rept Re Effects of Spurious Opening of Turbine Bypass Sys Valves on Nuclear Supply Sys.Potential Single Active Failure Could Result in Possibility of Exceeding DNBR Limits 1997-05-01 Category:TEXT-SAFETY REPORT MONTHYEARML20211H7921999-08-13013 August 1999
[Table view]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 ML20029D3561994-03-31031 March 1994 Update of 1991 Decommissioning Cost for Rancho Seco Nuclear Generating Station 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 ML20045B9051993-06-16016 June 1993 Safety Evaluation Re Order Approving Decommissioning Plan & Authorizing Decommissioning of Rsngs,Unit 1,SMUD.Concludes That Reasonable Assurance That Health & Safety of Public Will Not Be Endangered by Decommissioning Option,Provided 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) ML20034F7031993-02-25025 February 1993 Amend 1 to Enterprise Rept 162 Re Defect on Starting Air Distributor Housing Assembly,As Followup to 930115 Final Rept.Addl Listed Part Numbers Discovered Which Are Higher Level Assemblies of Housing 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 ML20036C0601992-12-31031 December 1992 1992 Annual Rept for Smud 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 ML20029A7511991-02-28028 February 1991 Suppl to Special Rept 90-13:on 901224,25,29 & 910113,listed Meteorological Instrumentation Inoperable for More than 7 Days.Work Request Initiated & Instrumentation Channels Declared Operable on 910116 ML20029B6721991-02-22022 February 1991 Safety Evaluation Supporting Proposed Rev to Emergency Plan & Granting Exemption from 10CFR50-54(q) Requirements 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 05000312/LER-1990-002, :on 900614,Step 6.9.3.1 of Liquid Waste Discharge Permit Checked R-15017A as Inoperable & Two Independent Samples Not Performed.Caused by Personnel Error. Caution Will Be Added to Step 6.9.21990-07-20020 July 1990
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 NL-90-355, Monthly Operating Rept for May 1990 for Rancho Seco Nuclear Plant1990-05-31031 May 1990 Monthly Operating Rept for May 1990 for Rancho Seco Nuclear Plant 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 ML20042E6921990-03-30030 March 1990 Special Rept 90-06:on 900301,06 & 14,listed Fire Barrier Penetrations That Failed Surveillance Test Not Restored to Operable Status within 7 Days as Required by Tech Spec 3.14.6.2.Operability of Fire Detectors Verified ML20042E6931990-03-30030 March 1990 Special Rept 90-07:on 900228,high Temp Detector Circuit for Zone 53 Not Restored to Operable Status within 14 Days When Circuit Failed Surveillance Test SP.345 & Would Not Alarm. Fire Watch Established.Detector Found Operable on 900316 ML20033G6031990-03-30030 March 1990 Rev 1 to Defueling Training Programs for NRC License Candidates ML20033G6011990-03-30030 March 1990 Rev 1 to Defueled Requalification Training Program for NRC Licensed Operators NL-90-054, Monthly Operating Rept for Feb 1990 for Rancho Seco Nuclear Generating Station1990-02-28028 February 1990 Monthly Operating Rept for Feb 1990 for Rancho Seco Nuclear Generating Station ML20006F4181990-02-0909 February 1990 Special Repts 90-1,90-2,90-3 & 90-4:on 900110,16,18,19,30 & 31,fire Barriers Breached for More than 7 Days.All Fire Barrier Penetrations & Fire Doors Returned to Operable Status NL-90-035, Monthly Operating Rept for Jan 1990 for Rancho Seco Nuclear Generating Station1990-01-31031 January 1990 Monthly Operating Rept for Jan 1990 for Rancho Seco Nuclear Generating Station 1999-08-13 |
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g suun SACRAMENTO MUNICIPAL UTILITY DISTRICT C E201 S Street Box 15830. Sacramento California 95M3;(916) 452 3211 eS N.
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G November 8,1985 5
E RJR 85-546 q
E J.B. MARTIN REGION V 0FFICE OF INSPECTION & ENFORCEMENT U.S. NUCLEAR REGULATORY COMMISSION 1450 MARIA LANE, SUITE 210 WALNUT CREEK, CA 95638 10CFR21 NOTIFICATION This is to inform the Nuclear Regulatory Commission, Region V, of the District's decision that the Model 1153, Alphaline Nuclear Pressure Transmitter manufactured by Rosemount Inc. Minneapolis, Minnesota, must be reported as a 10CFR21 deficiency.
The pertinent information required by the regulation is included as attachment No. 1.
(.
.sy R.J. Rodrig Assistant Geh al Manager, Nuclear Attachment V
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10CFR21 REPORT 1.
INFORMANT:
R.J. Rodriguez Assistant General Manager, Nuclear Sacramento Municipal Utility District 6201 S Street Sacramento, CA 96813 2.
FACILITY:
Rancho Seco Nuclear Power Plant Herald, CA BASIC COMPONENT:
Model 1153 Alphaline Nuclear Pressure Transmitter 3.
BASIC COMPONENT SUPPLIER:
Rosemount, Inc.
Post Office Box 35129 Minneapolis, Minnesota 55435 4.
NATURE OF DEFECT:
The Rosemont Instruction Manual,#4302 Rev. B, Revised 7/82, does not address zero shift due to process pressure.
The Rosemont Performance Specification Report does address zero shift due to process pressure. Because information was not in the technical manual received, it was not incorporated in the calibration procedure.
The specific area of concern is High Pressure Injection Flow, the result being that flow indication less than 100 gpm is questionable.
5.
DATE OF INFORMATION:
November 1985 6.
NUMBER AND LOCATION:
a)
Inside Containment Building OTSGLevel, Ten (10)
Core Flood Tank Level, Four (4)
Pressurizer Level, Three (3) b) Outside Containment Building Aux Feedwater Flows, Four (4)
Cond. Storage Tank Level, Two (2) liigh Press. Inject. Flow, Four (4)
Total Seal Inj. Flow, One (1)
Decay Heat Flow, Two (2) 7.
CORRECTIVE ACTION:
The zero shift due to process pressure will be addressed by calibration procedures.
In the case of HPI with various process pressures will be addressed providing instructions to the operators not to rely on readings below 100 gpm.
Also the calibration pressure was selected on the HPI indicators so that the zero error is caused to be always in a minus direction (Indicated flow is less than actual). On the other flow indicators the District corrected the 7;ro shift due to process pressure at zero differential pressure.
/