05000312/LER-1986-001, :on 860121,diesel Generator G-886B Declared Inoperable Due to Fuel Inlet Pressure Above Limits Specified in Process Stds.Safety Functions Performed.New Spare Parts Ordered for Generator
ML20141M742 | |
Person / Time | |
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Site: | Rancho Seco |
Issue date: | 02/14/1986 |
From: | Colombo R, Reinaldo Rodriguez SACRAMENTO MUNICIPAL UTILITY DISTRICT |
To: | Martin J NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
References | |
LER-86-001, LER-86-1, RJR-86-65, NUDOCS 8602280153 | |
Download: ML20141M742 (3) | |
Similar Documents at Rancho Seco | |
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Category:LICENSEE EVENT REPORT (SEE ALSO AO RO)
MONTHYEAR05000312/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
[Table view]
1990-07-20 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 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
1999-08-13 |
Event date: | |
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Report date: | |
Reporting criterion: | 10 CFR 50.73(a)(2)(v), Loss of Safety Function |
3121986001R00 - NRC Website | |
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EDG "A" AND "B" DECLARED IN0PERABLE DURING COLD SHUTDOWN EVENT DATE 15)
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' AM E A CODE Ron W. Colombo, Regulatory Compliance Superintendent 91116 415121-13121111 COMPLETE ONE LINE FOR EACH CLMIPONENT F AILURE DESCRISED IN THIS REPORT (13)
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During cold shutdown conditions, diesel generator G-886B exhibited a fuel inlet pressure slightly above the limits and precautions specified in the Process Standards and Operating Procedures during the monthly surveillance test. Although all the required technical specification acceptance criteria had been satisfied, the diesel generator was declared inoperable until the fuel inlet pressure condition was investigated.
Con-currently, diesel generator G-886A was considered to be out-of-service due to an air start system pressure control valve which had been rebuilt with parts which lacked complete quality assurance documentation.
The "A" generator had, however, successfully completed its monthly surveillance test.
Both diesel generators were functional, as evidenced by successful surveillance testing, except during the brief period when maint9nanm on the "A" generator was perior med to rectify the air start system pressure control valve concerns.
There was no effect on plant or public safety, particularly since the plant was in cold shutdown and there was no loss of offsite power.
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EXPtRES. 8,31 as FACILITY NAME Elf DOCKET NUMSER L2p LE R NUMSE R 181 PAGE(3)
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During cold shutdown conditions on January 21, 1986, diesel generator G-886B exhibited a fuel inlet pressure slightly above the limits and precautions specified in the Process Standards and Operating Procedures during the monthly surveillance test. Although all the required surveillance test procedures and technical specification acceptance criteria had been satisfied, the diesel generator was declared inoperable until the slightly elevated fuel inlet pressure condition was investigated. Concurrently, diesel generator G-886A, the remaining diesel generator at Rancho Seco, was considered to be out-of-service due to an air start system pressure control valve which had been rebuilt with parts which lacked complete quality assurance documentation.
It should be noted that diesel generator G-886A had successfully completed its monthly surveillance test.
Technical Specification 3.1.1.5 requires the decay heat system to be operable during cold shutdown conditions and the technical specification definition 1.3 of operable requires the system to have available its normal and emergency sources of power.
Although the diesel generators were not technically considered operable, they were avail-able and capable of performing their intended safety function. Therefore, it is a voluntary report since the reporting thresholds of 10 CFR 50.73(a)(2)(v), (vi) or (vii) were not reached.
To prevent a recurrence of this event, the District has taken the following corrective actions:
1.
New spare parts were ordered for diesel generator G-886B.
2.
The diesel generator manufacturer was contacted and a new higher fuel inlet pressure (80 psig) was determined to be an appropriate threshold value for corrective action.
The limits and precautions of the Operating Procedures and Process Standards have been appropriately revised.
3.
The air start system nonconforming part was removed by installation of a new pressure regulating valve for diesel generator G-886A.
4.
An audit of the control and documentation of spare parts in the warehouse has been initiated.
There was no effcct on plant or public safety as a result of this event since both offsite and onsite electric power were available for the decay removal system.
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'$SMUD SACRAMENTO MUNICIPAt. UTILITY OlSTRICT 6201 S Street. P 0 Box 15830. Sacramento CA 95852-1830.1916)452-3211 AN ELEC TRIC SYSTEM SERVING THl: HEAR T OF t'ALIFORNIA RJR 86-65 February 20, 1986 J B MARTIN REGIONAL ADMINISTRATOR REGION V 0FFICE OF INSPECTION AND ENFORCEMENT ATTN DOCUMENT CONTROL DESK U S NUCLEAR REGULATORY COMMISSION WASHINGTON DC 20555 DOCKET NO. 50-312 LICENSE NO. OPR-54 LICENSEE EVENT REPORT NUMBER 86-01 The Sacramento Municipal Utility District hereby submits volontary I.icensee Event Report Number 86-01.
If there are any questions concerning this report please contact Mr. Ron W.
Co16fnbo,at the Rancho Seco Nuclear Generating Station Unit No.1.
7
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PM R. J.
ODRIGUER ASSISTANTGENERAgMANAGER, NUCLEAR Attachment cc: Region V (2)
INPO 4
'fl RANCHO SECO NUCLEAR GENERATING STATION D 14440 Twin Cities Road, Herald, CA 95638 9799;(209) 333-2935