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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER)
MONTHYEARML20195F5911998-09-11011 September 1998 Special Rept:On 980812,addl Unseated Wires Were Discovered. Cause Is Unknown at Present Time.Util Evaluated Number of Unseated/Ineffective Wires & Determined Effect on Containment Structural Integrity.Commitments,Encl ML20247F7711998-05-0808 May 1998 Special Rept:On 980403 & 980503 Seismic Monitoring Sys Was Declared Inoperable.Caused by 5-volt Power Supply & Regulator Card Failure.Imd & Sys Engineering Are Continuing to Identify & Resolve Problems So Sys Can Be Operable ML20217D5131997-09-26026 September 1997 Special Rept:On 970918,moisture Content in Grease Samples Exceeded Maximum 10% by Weight.Caused by Ground Water Intrusion.Engineering Evaluation Performed & Insp of Tendons for Water Will Be Done on Annual Basis ML20149H7271997-07-18018 July 1997 Special Rept:On 970711,abnormal Containment of Tendon Degradation Was Noted.Cause Indeterminate.Will Perform Addl Inspections of Tendon H4ED to Monitor Apparent Addl Degradation.Calculation Re Subj Tendon Encl ML20135F3321997-03-0404 March 1997 Special Rept:On 970303,Braidwood Auxiliary Bldg Vent Stack Wide Range Gas Monitor Was Inoperable for Greater than Seven Days.Caused by Removing Monitoring from Operation to Perform 18-month Channel Calibr.Calibr Was Completed ML20129C8191996-10-0808 October 1996 Special Rept:On 960826,Unit 1 Began Receiving Loose Parts Alarm in Mcr.Caused by C Loop Cold Leg Loop Stop Isolation Valve.Se Performed by Westinghouse ML20057F3961993-10-0808 October 1993 Ro:On 930928,Train B DG Valid Failure Occurred,Causing Annunciators 2-22-C8 & 2-22-D6 to Alarm Simultaneously Due to Blown Fuses 27 & 29.Caused by Relay W/Shorted Circuit. Relay W/Shorted Circuit Replaced W/Bench Tested Relay ML20118B5361992-09-25025 September 1992 Special Rept:On 920913,auxiliary Bldg Vent Stack wide-range Gas Monitor Declared Inoperable.Caused by Need to Perform Instrument Maint Surveillance Procedure.Nuclear Work Request Generated to Replace Failed Printed Circuit Board ML20099K2941992-08-18018 August 1992 Ro:On 920807,auxiliary Bldg Vent Stack wide-range Noble Gas Monitor Declared Inoperable Due to Inability to Pass Source Check.Caused by Failure of High Voltage Power Supply. Original Detector Reinstalled After Addl Failure ML20102B1431992-07-14014 July 1992 Special Rept:On 920610,DG 2A Output Breaker Closed, Resulting in Parallel Operation of DG 2A to Sys Grid & Causing DG Trip.Caused by Reverse Power Condition Due to Operator Error.Surveillance Successfully Completed ML20094K1251992-03-11011 March 1992 Ro:On 920212,diesel Generator 1A Failed to Attain Rated Speed & Voltage within 10 & Declared Inoperable.Caused by Air Leak in Air Control Sys Which Positions Fuel Racks in Full Fuel Position.Test Frequency Increased ML20086A2371991-11-12012 November 1991 Special Rept:On 911026,auxiliary Bldg Vent Stack wide-range Noble Gas Monitor Declared Inoperable & Removed from Svc for More than 7 Days.Caused by Need to Perform 18-month Channel Calibr.Channel Returned to Operable Status on 911107 ML20077B5751991-04-30030 April 1991 Special Rept:On 890724,seismic Monitoring Sys Declared Inoperable to Facilitate Relocation of Free Field Monitor. Efforts to Troubleshoot & Repair Sys Unsuccessful.Schedule for Restoration of Sys Listed ML20066F7191990-12-24024 December 1990 Special Rept:On 901102,sensor Channel Malfunctioned.Cause Unknown.Sensor Channel Will Be Repaired by Next Refueling Outage (Mar 1991) ML20065R8211990-12-13013 December 1990 RO:901114,during Performance of Monthly Operability Surveillance of Diesel Generator 2A,noted That Voltage Indication on Panel Appeared to Be Erroneous.Caused by Failure of Fuse.Fuse Replaced ML20245A8611989-04-14014 April 1989 Ro:On 890215,diesel Generator 1DG01KB Started in Performance of Monthly Operability Surveillance.Generator Came Up to Speed But Immediately Voltage & Frequency Indications Malfunctioned.Caused by Short in Strip Chart Recorder ML20245D8721989-04-14014 April 1989 Ro:On 890215,diesel Generator Voltage & Frequency Indications Malfunctioned.Caused by Blown Fuse in Strip Chart Recorder.Generator Run Manually Terminated & Fuse Replaced ML20196E2341988-11-29029 November 1988 Special Rept:On 881020,discovered That Sensor Channels LM001 & LM009 Were in Low Alarm.Caused by Fraying of Insulated Fibre Jacket of Microdot Connector Cable.Sensor Channels Replaced ML20154E8931988-09-0909 September 1988 Ro:On 880803,diesel Generator 2A Began Losing Speed Upon Entering Test Mode During Monthly Operability Surveillance. Caused by Abnormally High Resistance in Normally Closed Test Mode Contacts of 4EX3 Relay ML20235G8841987-07-0101 July 1987 Special Rept:On 870614,wide Range Gas Monitor (WRGM) Failed Automatic Check Source Test on High Range detector,1PC330. Check Source Damaged During Repairs.Parts & Installation of New Check Sorce Expected to Be Completed by 870715 ML20212K4601987-02-0303 February 1987 Special Rept:On 870106,PORV 1RY455A Lifted for 2 S.Caused by Rapid Increase of RCS Temp When Reactor Cooling Pump 1C Started.Opening PORV Terminated Pressure Transient.On 870112,bubble Formed in Pressurizer to Prevent Recurrence ML20212H3511987-02-0303 February 1987 Ro:On 861209,diesel Generator 1DG01KB Output Breaker Did Not Close on Signal from Control Room.Breaker Circuitry & Linkages Inspected.Following Successful Surveillance Run, Diesel Generator Declared Operable on 861210 1998-09-11
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217G9961999-10-14014 October 1999 SER Accepting First 10-year Interval Inservice Insp Requests for Relief for Plant,Units 1 & BW990066, Monthly Operating Repts for Sept 1999 for Braidwood Station, Units 1 & 2.With1999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Braidwood Station, Units 1 & 2.With ML20217P6351999-09-29029 September 1999 Non-proprietary Rev 6 to HI-982083, Licensing Rept for Spent Fuel Rack Installation at Byron & Braidwood Nuclear Stations ML20217A1691999-09-22022 September 1999 Part 21 Rept Re Engine Sys,Inc Controllers,Manufactured Between Dec 1997 & May 1999,that May Have Questionable Soldering Workmanship.Caused by Inadequate Personnel Training.Sent Rept to All Nuclear Customers ML20212A7441999-09-10010 September 1999 Safety Evaluation Concluding That Alternatives Contained in Relief Request 12R-07 Provide Acceptable Level of Quality & Safety BW990056, Monthly Operating Repts for Aug 1999 for Braidwood Station, Units 1 & 2.With1999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Braidwood Station, Units 1 & 2.With ML20210R6421999-08-13013 August 1999 ISI Outage Rept for A2R07 ML20210U8111999-08-0404 August 1999 SER Granting Licensee Relief Requests VR-1,VR-3 & Portion of VR-2 Pursuant to 10CFR50.55a(a)(3)(ii).Relief Request VR-4 Does Not Require Explicit NRC Approval Because Relief Applies to Valves Not Required by 10CFR50.55a BW990048, Monthly Operating Repts for Jul 1999 for Braidwood Station, Units 1 & 2.With1999-07-31031 July 1999 Monthly Operating Repts for Jul 1999 for Braidwood Station, Units 1 & 2.With ML20210K9861999-07-30030 July 1999 Safety Evaluation Accepting Licensee 60-day Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs ML20216D3841999-07-12012 July 1999 Revised NFM9900022, Braidwood Unit 2 Cycle 8 COLR in ITS Format & W(Z) Function M990002, Revised NFM9900022, Braidwood Unit 2 Cycle 8 COLR in ITS Format & W(Z) Function1999-07-12012 July 1999 Revised NFM9900022, Braidwood Unit 2 Cycle 8 COLR in ITS Format & W(Z) Function BW990038, Monthly Operating Repts for June 1999 for Braidwood Station, Units 1 & 2.With1999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Braidwood Station, Units 1 & 2.With BW990029, Monthly Operating Repts for May 1999 for Braidwood Stations, Units 1 & 2.With1999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Braidwood Stations, Units 1 & 2.With ML20209H7481999-05-31031 May 1999 Revised Monthly Operating Repts for May 1999 for Braidwood Station,Units 1 & 2 ML20207B6481999-05-25025 May 1999 SER Accepting Revised SGTR Analysis for Byron & Braidwood Stations.Revised Analysis Was Submitted to Support SG Replacement at Unit 1 of Each Station ML20195B2591999-05-19019 May 1999 Rev 66a to CE-1-A,consisting of Proposed Changes to QAP for Dnps,Qcs,Znps,Lcs,Byron & Braidwood Stations BW990021, Monthly Operating Repts for Apr 1999 for Braidwood Station, Units 1 & 2.With1999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Braidwood Station, Units 1 & 2.With BW990016, Monthly Operating Repts for Mar 1999 for Braidwood Generating Station,Units 1 & 2.With1999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Braidwood Generating Station,Units 1 & 2.With ML20205C5101999-03-21021 March 1999 Revised Safety Evaluation Supporting Improved TS Amends Issued by NRC on 981222 to FOLs NPF-37,NPF-66,NPF-72 & NPF-77.Revised Pages Include Editorial Corrections ML20196A0721999-03-16016 March 1999 Cycle 8 COLR in ITS Format & W(Z) Function ML20207J4371999-03-0808 March 1999 ISI Outage Rept for A1R07 ML20204H9941999-03-0303 March 1999 Non-proprietary Rev 4 to HI-982083, Licensing Rept for Spent Fuel Rack Installation at Byron & Braidwood Nuclear Stations BW990010, Monthly Operating Repts for Feb 1999 for Braidwood Generating Station,Units 1 & 2.With1999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Braidwood Generating Station,Units 1 & 2.With ML20206U9011999-02-15015 February 1999 COLR for Braidwood Unit 2 Cycle 7. Page 1 0f 13 of Incoming Submittal Was Not Included BW990004, Monthly Operating Repts for Jan 1999 for Braidwood Generating Station,Units 1 & 2.With1999-01-31031 January 1999 Monthly Operating Repts for Jan 1999 for Braidwood Generating Station,Units 1 & 2.With ML20205M7061998-12-31031 December 1998 Unicom Corp 1998 Summary Annual Rept. with BW990001, Monthly Operating Repts for Dec 1998 for Braidwood Generating Station,Units 1 & 2.With1998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Braidwood Generating Station,Units 1 & 2.With ML20206B4001998-12-31031 December 1998 Annual & 30-Day Rept of ECCS Evaluation Model Changes & Errors for Byron & Braidwood Stations ML20206U9081998-12-17017 December 1998 Cycle 8 COLR in ITS Format & W(Z) Function BW980076, Monthly Operating Repts for Nov 1998 for Braidwood Generating Station,Units 1 & 2.With1998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Braidwood Generating Station,Units 1 & 2.With ML20196A4191998-11-19019 November 1998 Safety Evaluation Accepting QA TR CE-1-A,Rev 66 Re Changes in Independent & Onsite Review Organization by Creating NSRB ML20195D3561998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Braidwood Generating Station,Units 1 & 2.With ML20155B6711998-10-26026 October 1998 Safety Evaluation Accepting Requests for Relief Associated with Second 10-yr Interval ISI Program Plan ML20207H7671998-10-0505 October 1998 Rv Weld Chemistry & Initial Rt Ndt ML20154D4401998-10-0202 October 1998 Safety Evaluation Authorizing Second 10-yr Interval ISI Program Request for Relief 12R-30 for Plant,Units 1 & 2 ML20155C2601998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Braidwood Generating Station,Units 1 & 2 ML20195F5911998-09-11011 September 1998 Special Rept:On 980812,addl Unseated Wires Were Discovered. Cause Is Unknown at Present Time.Util Evaluated Number of Unseated/Ineffective Wires & Determined Effect on Containment Structural Integrity.Commitments,Encl ML20196B3711998-09-0808 September 1998 Cycle 8 Operating Limits Rept (Olr) ML20151X6671998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Braidwood Generating Station,Units 1 & 2.With ML20238F3281998-08-31031 August 1998 SER Approving Second 10-year Interval Inservice Insp Program Request for Relief 12R-14 for Braidwood Station,Units 1 & 2 ML20237E2331998-08-21021 August 1998 Revised Pages of Section 20 of Rev 66 to CE-1-A, QA Topical Rept ML20237A1091998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Braidwood Generating Station,Unit 1 & 2 ML20236N7001998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Braidwood Generating Station,Units 1 & 2 ML20198A0151998-06-18018 June 1998 10CFR50.59 Summary Rept 960619 Through 980618, Vols I & Ii,Consisting of Descriptions & SE Summaries for Changes to Procedural UFSAR Changes,Tests & Experiments & FP Rept.Without Fp,Rept ML20249A5451998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Braidwood Generating Station Units 1 & 2 ML20247F7711998-05-0808 May 1998 Special Rept:On 980403 & 980503 Seismic Monitoring Sys Was Declared Inoperable.Caused by 5-volt Power Supply & Regulator Card Failure.Imd & Sys Engineering Are Continuing to Identify & Resolve Problems So Sys Can Be Operable ML20247L7591998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Braidwood Generating Station,Units 1 & 2 ML20217K6331998-04-20020 April 1998 Safety Evaluation Accepting Methodology & Criteria Used in Generating Flaw Evaluation Charts for RPV of Braidwood IAW Section XI of ASME Code ML20216C6621998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Braidwood Generating Station,Units 1 & 2 1999-09-30
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. ..
, . Commonwealth I:dison Company p liraidwust Generating Station
, Route *l. !kix H 4 liracesille, 11.60107 % 19 Tel H 15-iS8 2H01 October 8,19%
United States Nuclear F.egulatory Commission Attention: Document C ontrol Desk Washington, D. C. 205f 5-0001
Subject:
Braidwood Station Unit I loose Parts Monitoring System Special Report, Docket No. STN 50-456
References:
(a) NUREG-1276, Technical Specifications, Braidwood Station, Unit Nos. I and 2 (b) Regulatory Guide 1.133, Loose-Part Detection Program for the Primary System of Light-Water-Cooled Reactors, Rev.1, May 1981 Braidwood Station Technical Specification 3.3.3.8 Action (a) requires that with one or more Loose-Part Detection System channels inoperable for more than 30 days, a Special Report shall be prepared and aubmitted to the Commission within the next 10 days. In accordance with Specification 6.9.3, the cause of the malfunction and plans for restoring the channel (s) to operable status must be outlined. Pursuant to these Specifications, the enclosure provides a report regarding th: inoperability of a Loose Part Detection System initiated on September 13, i 1996.
Please direct any questions regarding this submittal to Doug Houston, Braidwood Station l Licensing Coordinator, extension 2511.
l 1
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. Tulon
/ tation Manager Braidwood Nuclear Station Attachment cc: A. B. Beach, Regional Administrator - Region III ' l R. R. Assa, Braidwood Project Manager - NRR 4 ,.
l C. Phillips, Senior Resident Inspector - Braidwood // -
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9610240125 961008 PDR ADOCK 05000456 S PDR 5
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Braidwood Station Unit 1 Loose Part Detection System Inoperable for greater than 30 days
Description:
At 1335 hours0.0155 days <br />0.371 hours <br />0.00221 weeks <br />5.079675e-4 months <br /> on August 26,1996, Unit I began receiving Loose Parts alarms.in the Main Control Room. After a two-week investigation period, which included taking ;
Unit 1 offline on September 6,1996, Comed concluded that the most probable source of the metal-to-metal impacts causing the Loose Parts alarms was the C Loop Cold Leg Loop Stop Isolation Valve (LSIV). A 50.59 Safety Evaluation was performed by Westinghouse and a Braidwood On-Site Review was conducted that approved restart ,
of Unit 1 on September 9,1996. The low level impacts within the LSIV are causing l repetitive Main Control Room loose parts alarms. This will continue until the source j of the impacts can be eliminated. Braidwood Station recognizes that the nature of the I repetitive alarms may result in control room personnel becoming desensitized to the alarming condition. Comed has taken actions to prevent this from occurring, and also ,
to be able to detect another loose part, if one actually exists. Therefore, the existing 1 in-plant system has been realigned and a portable Loose Parts Monitoring system has ;
been installed in Unit 1.
]
Actions Taken:
The Loose Part Monitoring (LPM) detectors are currently aligned to the following sensors:
IVE-LM003 Reactor Vessel Bottom 1VE-LM006 1 A SG Cold Side IVE-LM007 IB SG Hot Side IVE-LM009 1C SG Hot Side IVE-LM016 ID RCP SealInjection IVE-LM020 1 A SG Upper Level Tap IVE-LM021 ID SG Lower Tap i 1 VE-LM024 ID SG Upper Tap This alignment eliminates the repetitive alarms associated with the LSIV and it is '
expected to detect another loose part, if one actually existed. While the Loose Parts Monitoring system has been declared inoperable due to the above stated alignment (Reactor Top not aligned), the system is still fully functional. Thus, a valid impact resulting in an alarming condition will be detected in the Main Control room to allow operators to take the appropriate actions. The in-plant system is also being checked shiftly by operating personnel for additional assurance that no other conditions exist that would prevent a valid impact from going undetected.
. ._ . .-. =- .. .- .-- - - - - ~ _ - . - _ -
r I
4 The currently installed portable LPM system is monitoring the alarming channels,
- which include the reactor top, to ensure the " constrained" part within the C Loop Cold Leg LSIV has not moved. The portable LPM system is not connected to the j annunciation system in the Main Control room and thus, the repetitive alarms do not become a distraction to the operators.
Plans and Schedule for Restoring the Loose Part System to Operable status:
Currently, plans are being developed to address inspecting the C Loop Cold Leg LSIV. It is expected that the next refueling outage, which is scheduled to begin I
- March 29,1997, will provide an opportunity to inspect the LSIV and to correct the l cause of the impacts. Also during this outage, all sensors will be calibrated and
!' repaired if necessary, and the routine 18-month surveillance will be performed to ensure the Loose Parts Monitoring System is functioning properly. In the interim, the
- LPM sensors will be aligned for optimum detection of a potential loose part and to 4 continue to monitor the existing condition in the C Loop Cold Leg LSIV. l J