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Category:LICENSEE EVENT REPORT (SEE ALSO AO RO)
MONTHYEAR05000285/LER-1998-003, Re Individual Leaving High Radiation Area (HRA) Door Unlocked & Uncontrolled While in Hra. LER 98-003-00 Retracted1998-06-23023 June 1998 Re Individual Leaving High Radiation Area (HRA) Door Unlocked & Uncontrolled While in Hra. LER 98-003-00 Retracted 05000285/LER-1990-0071990-08-0101 August 1990 LER 90-007-02:on 900228,determined That Main Feedwater & Main Steam Piping Outside Design Basis.Caused by Design Deficiency & Failure of Engineer to Consider Loads Induced on Piping.Piping Supports modified.W/900801 Ltr 05000285/LER-1990-0101990-07-0303 July 1990 LER 90-010-01:on 900327,unplanned Attempted Start of Emergency Diesel Generator Occurred While Plant in Refueling Shutdown.Caused by Low Air Pressure in Diesel Start Sys. Instructions Re auto-start Signals changed.W/900703 Ltr ML20071G3271978-12-22022 December 1978 /03L-0 on 781124:during Shutdown Cooling Interlock Test Noted That PC-105B Was Not Operating.Caused by Valve Closing Relay 94-347/348 Not Being Wired to PC-105B; Inadvertently Disconnected in 1977 ML20071G2671978-12-22022 December 1978 /03L-0 on 781204:during Inspec of Discharged Fuel Assemblies,A Single Fuel Pin Was Observed to Have Failed, Assoc W/Manufacture & Exposure of Present Day Nuc Fuel ML20071G2381978-12-21021 December 1978 /03X-1 on 780918:during Refueling Outage,D Channel Hot Leg Temp Indication Was Investigated to Determine Cause of 780918 Failure.Failure Caused by Rosemount Model 104VC RTD Having Water in the Pothead ML20071G2201978-12-20020 December 1978 /03L-0 on 781122:noted That Level Transmiter for C Channel (C/LT-901) for Steam Generator RC-2A Level Instrumentation Not W/In Specs.Caused by Calibr Drift of Ge/Mac Model 555 Transmitter ML20071G2791978-12-19019 December 1978 /03L-0 on 781214:during 1978 Refueling Outage, Certain Surveillance Tests Req by Tech Specs Could Not Be Performed Because of Shutdown Condition.Facil Lic Change 77-11 Submitted to NRC on 781109 to Delete Requirements ML20071G0701978-12-12012 December 1978 /03L-0 on 781113:during Test of Ventilation Isolation Actuation Signal,Lockout 86B1/VIAS Did Not Trip. Cause Unidentified,Since Relay Retested & Found to Be Operating Normally.Relays Will Continue to Be Tested ML20071G0851978-12-0808 December 1978 /01T-0 on 781127:Diesel Generator 2 Failed to Auto Close Onto the Bus;Breaker Mode Switch Contracts 27-27c Failed to Make Contact.Caused by Contact Failure ML20071G1011978-12-0505 December 1978 /03L-0 on 781116:during Refueling,All Limitorque Valves Were Inspec for Proper Staking of the Lock Nut on the Motor operator.30 of 65 Valves Exhibited Unstaked Lock Nuts.Lock Nuts Were Staked IAW Manufacturer'S Instructions ML20071F9281978-11-27027 November 1978 /03L-0 on 781101:auxiliary Feedwater Check Valve FW-164 Found to Be Oriented in Wrong Position.Caused by Missing Valve Disk Plate Which Was Subsequently Located & Recovered ML20071F9061978-11-25025 November 1978 /03L-0 on 781026:repeated Tripping of Stack Particulate Process Monitor.Caused by Trip Set in Accordance W/Tech Specs Table 2-1 at 9.6x10-2,rather than More Conservative Release Rates 2x10-3 ML20071F8541978-11-0202 November 1978 /03L-0 on 781014:Reactor Coolant Cold Leg Temp Indicator B/122C Failed High Off Scale Because of an Open Circuited Rosemount Model 104VC Rtd.The RTD Will Be Replaced During Present Refueling Outage ML20071F4821978-10-0606 October 1978 /03L-0 on 780908:Inadvertent Radioactive Gas Release to Atmosphere Caused by Leakage Past Check Valve CH-284,HG-100 & Relief Valve HG-105.Valves Will Be Inspected & Replaced or Repaired During Next Refueling Outage ML20147B1901978-10-0303 October 1978 /01T-0 on 781003:During Oper Check on Auxiliary Steam Driven Feed Pump,The Steam Inlet Valve YCV-1045 Did Not Open Due to Closed Air Supply ML20071F4671978-09-27027 September 1978 /03L-0 on 780831:failure of Tri-x Weather Tower'S 100 Meter Delta-T Sensor Sys to Rept Stability Class Info. Calibrations Revised to Ensure Instruments Detect Subsequent Sensor Sys Failures ML20071F4881978-09-15015 September 1978 /03L-1 on 780830:Bchannel RPS Variable Overpwr Trip Reset Demand Alarm Actuated & Would Not Reset.Then,Hi Pwr & Thermal Margin/Low Pressure Trip Units Failed,Both Due to Failure of Devar19-601A,18volt Pwr Supply 05000285/LER-1976-005, Suppl 1 to LER 76-05/03L:on 770210,recirculation Actuation Pressure Switches Found Out of Tolerance.Cause Not Stated. Switch Will Be Calibr Monthly Until New Switches Installed1977-02-10010 February 1977 Suppl 1 to LER 76-05/03L:on 770210,recirculation Actuation Pressure Switches Found Out of Tolerance.Cause Not Stated. Switch Will Be Calibr Monthly Until New Switches Installed 05000285/LER-1976-019, Suppl 1 to LER 76-19/03L:on 761001,five of 10 Valve Setpoints Drifted from Tech Spec Tolerance of Plus or Minus 1%.Caused by Change in Environ Condition.Valves Will Be Inspected During Refueling Outage1976-10-14014 October 1976 Suppl 1 to LER 76-19/03L:on 761001,five of 10 Valve Setpoints Drifted from Tech Spec Tolerance of Plus or Minus 1%.Caused by Change in Environ Condition.Valves Will Be Inspected During Refueling Outage 05000285/LER-1976-021, Suppl 1 to LER 76-21/03L:on 760802,timer Relays for SI-3A, AC-3B & SI-3B Failed to Time Out at Set Times.Caused by Binding Operating Mechanisms.Timers Tested Twice Weekly to Verify Operability Until Replacements Received1976-08-0909 August 1976 Suppl 1 to LER 76-21/03L:on 760802,timer Relays for SI-3A, AC-3B & SI-3B Failed to Time Out at Set Times.Caused by Binding Operating Mechanisms.Timers Tested Twice Weekly to Verify Operability Until Replacements Received 05000285/LER-1976-010, Suppl to LER 76-10/03L:on 760401,high Power Margin to Trip Meter B Drifted from 4.2% to 6% Power.Caused by Drift of Feed Back Limiter Module 19-317-2X.Module Calibr & Operated Satisfactorily1976-04-0808 April 1976 Suppl to LER 76-10/03L:on 760401,high Power Margin to Trip Meter B Drifted from 4.2% to 6% Power.Caused by Drift of Feed Back Limiter Module 19-317-2X.Module Calibr & Operated Satisfactorily 1998-06-23
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217B5401999-10-0606 October 1999 Safety Evaluation Supporting Amend 193 to License DPR-40 ML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data LIC-99-0096, Monthly Operating Rept for Sept 1999 for Fcs,Unit 1.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Fcs,Unit 1.With ML20211J9321999-09-0202 September 1999 Safety Evaluation Concluding That Licensee Proposed Alternatives Provide Acceptable Level of Quality & Safety. Proposed Alternatives Authorized for Remainder of Third ten- Yr ISI Interval for Fort Calhoun Station,Unit 1 LIC-99-0084, Monthly Operating Rept for Aug 1999 for Fort Calhoun Station.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Fort Calhoun Station.With ML20216E6431999-08-26026 August 1999 Rev 19 to TDB-VI, COLR for FCS Unit 1 ML20210R1961999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Fcs,Unit 1 ML20210G2181999-07-27027 July 1999 Safety Evaluation Supporting Amend 192 to License DPR-40 ML20210D9951999-07-22022 July 1999 Safety Evaluation Supporting Amend 191 to License DPR-40 ML20216E6361999-07-21021 July 1999 Rev 18 to TDB-VI, COLR for FCS Unit 1 ML20210R2081999-06-30030 June 1999 Revised Monthly Operating Rept for June 1999 for Fcs,Unit 1 LIC-99-0065, Monthly Operating Rept for June 1999 for Fort Calhoun Station,Unit 1.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Fort Calhoun Station,Unit 1.With ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML20210P5461999-06-0808 June 1999 Rev 0,Vols 1-5 of Fort Calhoun Station 1999 Emergency Preparedness Exercise Manual, to Be Conducted on 990810. Pages 2-20 & 2-40 in Vol 2 & Page 4-1 in Vol 4 of Incoming Submittal Not Included ML20195B4581999-05-31031 May 1999 Rev 3 to CE NPSD-683, Development of RCS Pressure & Temp Limits Rept for Removal of P-T Limits & LTOP Requirements from Ts ML20207H7401999-05-31031 May 1999 Performance Indicators Rept for May 1999 LIC-99-0053, Monthly Operating Rept for May 1999 for Fort Calhoun Station,Unit 11999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Fort Calhoun Station,Unit 1 ML20195B4521999-05-17017 May 1999 Technical Data Book TDB-IX, RCS Pressure - Temp Limits Rept (Ptlr) ML20206L4241999-05-10010 May 1999 Safety Evaluation Supporting Corrective Actions to Ensure That Valves Are Capable of Performing Intended Safety Functions & OPPD Adequately Addressed Requested Actions Discussed in GL 95-07 ML20206M2601999-05-0606 May 1999 SER Concluding That Licensee IPEEE Complete Re Info Requested by Suppl 4 to GL 88-20 & IPEEE Results Reasonable Given FCS Design,Operation & History LIC-99-0047, Monthly Operating Rept for Apr 1999 for Fort Calhoun Station Unit 1.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Fort Calhoun Station Unit 1.With ML20195E8621999-04-30030 April 1999 Performance Indicators, for Apr 1999 ML20205Q5831999-04-15015 April 1999 Safety Evaluation Supporting Amend 190 to License DPR-40 ML20210J4331999-03-31031 March 1999 Changes,Tests, & Experiments Carried Out Without Prior Commission Approval for Period 981101-990331.With USAR Changes Other than Those Resulting from 10CFR50.59 ML20206G2641999-03-31031 March 1999 Performance Indicators Rept for Mar 1999 LIC-99-0034, Monthly Operating Rept for Mar 1999 for Fcs,Unit 1.With1999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Fcs,Unit 1.With ML20205J8181999-02-28028 February 1999 Performance Indicators, for Feb 1999 LIC-99-0025, Monthly Operating Rept for Feb 1999 for Fort Calhoun Station,Unit 1.With1999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Fort Calhoun Station,Unit 1.With ML20207F3291999-01-31031 January 1999 FCS Performance Indicators for Jan 1999 ML20203B0991998-12-31031 December 1998 Performance Indicators for Dec 1998 LIC-99-0026, 1998 Omaha Public Power District Annual Rept. with1998-12-31031 December 1998 1998 Omaha Public Power District Annual Rept. with LIC-99-0003, Monthly Operating Rept for Dec 1998 for Fort Calhoun Station.With1998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Fort Calhoun Station.With ML20198S3771998-12-31031 December 1998 Safety Evaluation Supporting Amend 189 to License DPR-40 ML20198S4831998-12-31031 December 1998 Safety Evaluation Supporting Amend 188 to License DPR-40 ML20196G2251998-12-18018 December 1998 Rev 2 to EA-FC-90-082, Potential Over-Pressurization of Containment Penetration Piping Following Main Steam Line Break in Containment ML20198M3141998-11-30030 November 1998 Performance Indicators Rept for Nov 1998 LIC-98-0172, Monthly Operating Rept for Nov 1998 for Fort Calhoun Station,Unit 1.With1998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Fort Calhoun Station,Unit 1.With LIC-98-0160, Special Rept:On 981113,MSL RM RM-064 Was Declared Inoperable Due to Leakage Past Isolation Valve HCV-922.Troubleshooting Has Indicated That Leakage Has Stopped & Cause of Leak Continues to Be Investigated1998-11-25025 November 1998 Special Rept:On 981113,MSL RM RM-064 Was Declared Inoperable Due to Leakage Past Isolation Valve HCV-922.Troubleshooting Has Indicated That Leakage Has Stopped & Cause of Leak Continues to Be Investigated ML20203B0721998-11-16016 November 1998 Rev 6 to HI-92828, Licensing Rept for Spent Fuel Storage Capacity Expansion ML20196E4981998-10-31031 October 1998 Performance Indicators Rept for Oct 1998 ML20196G2441998-10-31031 October 1998 Changes,Tests & Experiments Carried Out Without Prior Commission Approval. with USAR Changes Other than Those Resulting from 10CFR50.59 LIC-98-0154, Monthly Operating Rept for Oct 1998 for Fort Calhoun Station,Unit 1.With1998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Fort Calhoun Station,Unit 1.With ML20154M4881998-10-19019 October 1998 Safety Evaluation Supporting Amend 186 to License DPR-40 ML20154N2411998-10-19019 October 1998 Safety Evaluation Supporting Amend 187 to License DPR-40 LIC-98-0136, Monthly Operating Rept for Sept 1998 for Fort Calhoun Station,Unit 1.With1998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Fort Calhoun Station,Unit 1.With ML20155G4261998-09-30030 September 1998 Performance Indicators for Sept 1998 ML20154A1251998-08-31031 August 1998 Performance Indicators, Rept for Aug 1998 LIC-98-0122, Monthly Operating Rept for Aug 1998 for Fort Calhoun Station Unit 1.With1998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Fort Calhoun Station Unit 1.With ML20238F7231998-08-17017 August 1998 Owner'S Rept for Isis ML18066A2771998-08-13013 August 1998 Part 21 Rept Re Deficiency in CE Current Screening Methodology for Determining Limiting Fuel Assembly for Detailed PWR thermal-hydraulic Sa.Evaluations Were Performed for Affected Plants to Determine Effect of Deficiency 1999-09-30
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Omaha Public Power Disttiet 444 South 16th Street Mall Omaha, Nebraska 68102-2247 ~
402/636-2000
= July 3, 1990 LIC-90-0480 U. S. Nuclear Regulatory Commission-
-Attn: Document Control Desk Mail Station P1-137 Washington,' DC 20555 l l
Reference:
-(1)DocketNo.50-285 l' (2)LicenseeEventReport90-10, April 26,1990(LIC-90-0304)
' Gentlemen:
l:
Subject:
Licen:;ee Event Report 90-10, Revision 1 for the Fort Calhoun I
. Station L Please find attached Licensee Event Report 90-10, Revision 1 dated July L 3, 1990. :An. inapplicable procedure number was inadvertently included in i the correctiveiactions of the: original version of this report. This ;
revision )rovides corrected and updated information identified.by a !
vertical )ar in-the margin. This report is being submitted pursuant to '
10 CFR 50.73(a)(2)(iv).
If you should have any questions, please contact me.
Sincerely, f Aj.M ,
W. G.-Gates.
Division Manager Nuclear Operations -i WGG/tcm Attachment i
- c:, R.'D. Martin, NRC Regional Administrator.
' 4' A. Bournia, NRC Project Manager
,' P. H. Harrell, NRC Senior Resident Inspector -
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O?"tAPa" Won"an"l#E?C?"aca'k M'Ci OF MANAGEMENT AND BUDGET, WASHINGTON, DC 206031 8 ACILITV NAAff Hi . DOCKET NUMSER {3) PAGE G3 Fort Calhoun Station Unit No. 1 o ls l o l o l o 121815 1 loFl013 TITLE ter Unplanned Attempted Start of Emergency Diesel Generator fiftNT DAtt (El LIR NuesstR f61 REPORT DATE 171 OTHER F ACILITit$ INVOLVED tel MONT H DAY YlAR YEAR l at AL MONTM QAY \ TAR F ACokITV Naval DQCKE T NUMBERtBI l
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On March 27, 1990, at 1428, an unplanned attempted start of Emergency Diesel Generator D-1 occurred while the plant was in refueling shutdown. Operations personnel were performing an electrical checklist as part of )ost-maintenance testing prior to returning the diesel generator to service. T1e diesel -
attem)ted to start when the mode selector switch was taken to " Emergency Stand)y", per the procedure, and the start circuitry sensed a low voltage on a '
associated non-vital bus. The non-vital bus had been tagged out and de-energized for scheduled maintenance. The diesel failed to start due to low air pressure in the diesel air start system, which had not yet been completely pressurized.
An unplanned start of an emergency diesel generator is considered an actuation of a Emergency Safeguards Feature. The unsuccessful start in this event was considered to meet the reportability criteria. A four-hour notification to i the NRC was made at 1632, in accordance with 10 CFR 50.72(b)(2)(ii).
l l- Corrective actions included changes to the operating instructions to provide I l
additional guidance prior to realigning the diesel for nc,rmal operation or testing. The revision included a list of the auto-start signals that will initiate a diesel start. As an interim measure, appropriate caution tags were placed on the mode selector switches.
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,n TEXT CONTINUATION C 'o'"4"4'3,1Snn"cias'.MUC#,'!R?,".'f,$$fi P A E RWO RE UC ION ROJ 3 0 i IC r OF MANAGEMtNT AND 9000tT.WASHINQTDN, DC 20603.
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0l1 0l2 0F 0 l3 ftXT f# passe ausse e soewegal asse aduissaar #AC #wiss Mail 171 L On March 27, 1990, Fort Calhoun Station Unit No. I was in a refueling outage (Mode'5). The 4160V Bus 1A1 was de-energized and tagged out for scheduled Emergency Diesel Generator D-1 had also been out of service for maintenance.
maintenance. The maintenance on D-1 had been completed and work was in-progress to return the system to service. Surveillance test lH-ST-DG-0001 was
- the procedure controlling the inspection and testing of D-1. The test l required that D-1 be started following inspection. In preparation for starting the diesel, operations personnel were performing procedure 01-DG-1, >
Normal Operation Diesel' Generator No. 1". Operations personnel started the compressors for the diesel starting air system as required by 01-DG-1. The
- procedure also required that checklists DG-1-CL-A through E be completed. In L checklist DG-1-CL-E, " Normal Operation Electrical Checklist No. 1 Diesel L Generator" an operator is required to place the 43-1/01 Diesel Mode Selector L Switch in the " Emergency Standby" position.
At 1428, Diesel Generator D-1 attempted to auto-start when a control room operator turned the diesel mode selector switch to the " Emergency Standby" position from the "Off Auto" position. The diesel failed to start because of low air pressure in the diesel air start system. The compressors for the starting air system did not have sufficient time to build up system pressure due to being placed in service only a short time earlier. The control room operator performing the switch lineup realized that the diesel was attempting to start and repositioned the diesel mode selector switch back to "Off Auto",
reset the diesel auto start lockout relays and depressed the diesel stop pushbuttons. 4 Investigation following the incident revealed that when the 43-1/01 Diesel Mode Selector Switch was placed in the " Emergency Standby" position, the diesel generator idle start circuitry sensed a low voltage on the associated non-vital 4160V bus IA1. As designed, the undervoltage condition on bus 1A1 tripped the diesel auto start lockout relays (86A/D1 and 86B/01) and initiated an idle start of the diesel, when the mode selector switch was placed in the
" Emergency Standby" position.
Immediately following the incident the Shift Supervisor placed a caution tag on the mode selector switch with instruction that the switch remain in the "Off Auto" position. This was to ensure that another operating crew did not reposition the switch while the diesel auto-start signal was present.
An unplanned start of an emergency diesel generator is an actuation of a Emergency Safeguards Feature. A conservative interpretation was made that this event met the reportability criteria, even though the diesel was out of service and not required to be operable. It did not actually start, and would not have performed its safety function. The NRC Resident Inspector was notified and a four-hour notification to the NRC was made at 1632, in L
accordancewith10CFR50.72(b)(2)(ii). This LER is submitted pursuant to 10 CFR50.73(a)(2)(iv).
i tKC Form assA (649)
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LICENSEE EVENT REPORT (LER) ',"#W,%',$fREMM's fo*i'n' .oC f7.7 ig"JR'!
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PAPE RWO RE itON J l'3 60 IC OF MANAGEMsNT AND $UDGET, WASHINGTON.DC 70603 9ACILITV NAMI HD DOCKET NUsetR 12) - Lim NUMeth Mi PAOS Q1 "aa -" t=. t'JJ.7 Fort Calhoun Station Unit No. -1 o ls jo j o Io l 2l8 l 5 9l0 -
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Q1 Q3 oF 0l 3 rirrin - . . ,= - o ,amm on The safety significance associated with this event was minimal. At the time 1 oftheeventtheplantwasinrefuelingshutdown(Mode 5)andallfuelhad been removed from the reactor. In this mode and plant condition the diesel 1 generators are not required to be operable to be in compliance with !
Technical Specifications. At the time of the event, plant loads were supplied from 161KV off-site power, and 345KV off-site power was available as a backup power supply if needed. Diesel generator D-2 was operable and available for use. Based on the condition and operating mode of the plant during this event, it can be concluded that nuclear safety was not adversely affected.
The primary cause of this event was insufficient guidance in 01-DG-1. The procedure failed to provide instructions for the operator to ensure that no l auto-start signals were 3 resent prior to-performing realignment for normal u o>eration or' testing. T1e procedure also failed to caution the operator I t1at starting air pressure must be adequate before placing the mode switch in " Auto". The same deficiencies existed in the corresponding 3rocedure (01-DG-2)forDieselGeneratorD-2. A contributing cause was t1e failure of operations personnel to recognize existing plant conditions and their effect on-the diesel. auto-start circuitry.
The following corrective actions are associated with this event:
(1) Operating Instructions 01-DG-1 and 01-DG-2 have been revised to include l a precaution statement for the operator to ensure a diesel auto-start signal is not present before realigning the diesel for normal operation or testing. The revision includes a list of the auto-start signals that will initiate a diesel start. A precaution has been added to ensure the operator verifies that starting air pressure is adequate prior to placing the mode selector switch in " Emergency Standby".
(2) Surveillance Test MM-ST-DG-0001 has been revised to include a step to ensure that applicable sections of 01-DG-1 and 01-DG-2 are performed prior to starting the affected diesels.
(3) As an interim measure, caution tags were put on the mode selector i switches as reminders to verify conditions which initiate an auto-start of the emergency diesel generators did not exist prior to moving the switches from "Off-Auto" position. These caution tags have been '
cleared.
This is the fourth LER associated with an inadvertent start of a Emergency Diesel Generator at Fort Calhoun Station. The others are reported in LER's 88-07, 88-14, and 88-24.
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05000285/LER-1990-007 | LER 90-007-02:on 900228,determined That Main Feedwater & Main Steam Piping Outside Design Basis.Caused by Design Deficiency & Failure of Engineer to Consider Loads Induced on Piping.Piping Supports modified.W/900801 Ltr | | 05000285/LER-1990-010 | LER 90-010-01:on 900327,unplanned Attempted Start of Emergency Diesel Generator Occurred While Plant in Refueling Shutdown.Caused by Low Air Pressure in Diesel Start Sys. Instructions Re auto-start Signals changed.W/900703 Ltr | | 05000285/LER-1990-020, Forwards LER 90-020,Rev 1,updating Status of Corrective Actions & Including Other Minor Editorial Changes.Mod Request Initiated to Replace or Upgrade DG Voltage Regulator Due to Lack of Spare Parts Availability Not Required | Forwards LER 90-020,Rev 1,updating Status of Corrective Actions & Including Other Minor Editorial Changes.Mod Request Initiated to Replace or Upgrade DG Voltage Regulator Due to Lack of Spare Parts Availability Not Required | | 05000285/LER-1990-022, Advises That Fire Barrier Penetration Seal Walkdowns Complete,Per 890202 & 900831 Commitments.Drawing & Procedure Change Program Ongoing & Will Be Addressed as Part of Actions to LER-90-022 | Advises That Fire Barrier Penetration Seal Walkdowns Complete,Per 890202 & 900831 Commitments.Drawing & Procedure Change Program Ongoing & Will Be Addressed as Part of Actions to LER-90-022 | |
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