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Category:LICENSEE EVENT REPORT (SEE ALSO AO RO)
MONTHYEAR05000254/LER-1993-0131993-08-27027 August 1993 LER 93-013-00:on 930729,identified Deviation from TS & Reg Guide 1.52 Requirements for Methyl Iodide Testing of Charcoal Sample Canisters.Caused by Failure to Implement Proper Canister Testing.Canisters Tested by Nucon 05000254/LER-1993-0121993-08-24024 August 1993 LER 93-012-00:on 930726,light Socket Shorted Out When Operator Reset HPCI Logic Power.Caused by Short Circuit in Light Socket.Light Socket & Blown Fuses replaced.W/930824 Ltr 05000254/LER-1993-0101993-08-19019 August 1993 LER 93-010-00:on 930720,HPCI Declared Inoperable & HPCI Outage Rept Qcos 2300-2 Initiated Because IST Flow Rate Fell in IST Required Action Range Due to New Procedure. Surveillance Procedure Will Be revised.W/930819 Ltr 05000254/LER-1993-0111993-08-18018 August 1993 LER 93-011-00:on 930721,discovered That 4kV Breaker 68 Feeding CS 1B Motor Pump Open & Discharged,Resulting in CS 1B Being Declared Inoperable.Wr Written to Investigate & repair.W/930813 Ltr 05000254/LER-1993-0091993-08-13013 August 1993 LER 93-009-00:on 930714,SBGT Methyl Iodide Test Failed Due to Age of Charcoal Combined W/Stringent Test Criteria. Replaced Charcoal Absorber in Both Trains of Sbgt. W/930806 Ltr 05000254/LER-1993-0081993-08-11011 August 1993 LER 93-008-00:on 930709,reactor Bldg Ventilation Radiation Monitor Setpoints Set non-conservatively Four Times in Five Yrs.Caused by Instrument Maint Program Error. New Computer Program developed.W/930805 Ltr 05000265/LER-1988-006, Errata to LER 88-006-02:on 880404,station Notified That Eleven Flued Head Anchors Did Not Meet Design Requirements. Caused by Misinterpretation of Scope & Design Structures.Mod Initiated to Revise Structure1992-06-0404 June 1992 Errata to LER 88-006-02:on 880404,station Notified That Eleven Flued Head Anchors Did Not Meet Design Requirements. Caused by Misinterpretation of Scope & Design Structures.Mod Initiated to Revise Structure 05000254/LER-1990-0131990-07-24024 July 1990 LER 90-013-00:on 900626,annunciators on Both Units & Reactor Recirculation Loop Sample Valve Closed.Caused by Actuation of Primary Containment Isolation Valve When Lightning Struck 345 Kv Line.Valve reopened.W/900724 Ltr 05000254/LER-1988-001, Sanitized Version of LER 88-001-00:on 880114,records Review Found Two Apparent Overexposures of Contractor Personnel During Fourth Quarter 1980.Caused by Inaccurate Secondary &/ or Primary Dosimetry.Dosimetry Sys Upgraded1988-01-28028 January 1988 Sanitized Version of LER 88-001-00:on 880114,records Review Found Two Apparent Overexposures of Contractor Personnel During Fourth Quarter 1980.Caused by Inaccurate Secondary &/ or Primary Dosimetry.Dosimetry Sys Upgraded ML20203L0281986-04-25025 April 1986 Informs of Planned Site Visit to Obtain Info Supporting Implementation of Emergency Response Data Sys,Including Availability of PWR or BWR Parameters in Digital Form & Characterization of Available Data Feed Points 05000254/LER-1984-018, :on 840922 & 24,reactor Bldg Fuel Pool Channel B Area Radiation Monitor 1705-16B Spiked High, Tripping Ventilation.Cause Unknown.Corrective Actions for Both Events Will Be Documented in Suppl to LER 84-0181984-10-11011 October 1984
- on 840922 & 24,reactor Bldg Fuel Pool Channel B Area Radiation Monitor 1705-16B Spiked High, Tripping Ventilation.Cause Unknown.Corrective Actions for Both Events Will Be Documented in Suppl to LER 84-018
05000265/LER-1983-021, Revised LER 83-021/01T-5:on 831028,ultrasonic Exams of Large Bore Stainless Steel Pipe Welds Identified 11 Welds W/Crack Indications.Caused by Intergranular Stress Corrosion Cracking.Weld Overlay Performed1984-02-28028 February 1984 Revised LER 83-021/01T-5:on 831028,ultrasonic Exams of Large Bore Stainless Steel Pipe Welds Identified 11 Welds W/Crack Indications.Caused by Intergranular Stress Corrosion Cracking.Weld Overlay Performed 05000265/LER-1983-018, Revised LER 83-018/01T-1:on 831011,discovered 1-1/4 Inch long,20% through-wall Linear Indication in Weld 12S-S27. Caused by Intergranular Stress Corrosion Cracking.New Welds & Elbow Installed1984-02-0202 February 1984 Revised LER 83-018/01T-1:on 831011,discovered 1-1/4 Inch long,20% through-wall Linear Indication in Weld 12S-S27. Caused by Intergranular Stress Corrosion Cracking.New Welds & Elbow Installed 05000265/LER-1983-020, Revised LER 83-020/01T-1:on 831028,weld 02B-S9,22-inch Pipe to Cap,Weld 02BS-S12,28-inch Elbow to Pipe & Weld 02BS-F14, 28-inch Pipe to Elbow Weld Had Circumferential Linear Indications1983-12-0909 December 1983 Revised LER 83-020/01T-1:on 831028,weld 02B-S9,22-inch Pipe to Cap,Weld 02BS-S12,28-inch Elbow to Pipe & Weld 02BS-F14, 28-inch Pipe to Elbow Weld Had Circumferential Linear Indications 05000265/LER-1982-018, Supplemental LER 82-018/03L-1:on 821006,emergency Diesel Generator Tripped on High Temp After Loading.Caused by Fouling of Diesel Generator Cooling Water Sys.Both HX Replaced1982-12-0101 December 1982 Supplemental LER 82-018/03L-1:on 821006,emergency Diesel Generator Tripped on High Temp After Loading.Caused by Fouling of Diesel Generator Cooling Water Sys.Both HX Replaced 05000254/LER-1982-022, Supplemental LER 82-022/03L-1:on 820816,maint Outage for 1/2B Diesel Fire Pump Exceeded 7-day Limit.Cause Not Stated. Diesel Pump Wear Rings Replaced1982-10-0707 October 1982 Supplemental LER 82-022/03L-1:on 820816,maint Outage for 1/2B Diesel Fire Pump Exceeded 7-day Limit.Cause Not Stated. Diesel Pump Wear Rings Replaced ML20150E1741978-11-20020 November 1978 /03L-0 on 781026:dual Position Indication Was Received for Supression Chamber to Drywell Vacuum Breaker, Valve 1-1601-33E.Caused by Position Indication Problem ML20062E6521978-11-15015 November 1978 /03L-0 on 781025:smoke Detectors Were Removed from Svc in Cable Spreading Room,Elec Equip Room & Control Room for Installation of New Fire Detection/Suppression Sys ML20062D5871978-10-25025 October 1978 /03L-1 on 780420:during Routine Hydraulic Snubber Surveillance Inspec,Snubber Mark 149 Was Found Inoper Due to Empty Fluid Reservoir & Mark 144 Was Found W/Missing Cotter Pin,Due to Component Failure ML20062D5161978-10-19019 October 1978 /03L-0 on 780920:A RHR Room Watertight Door Found Open.Caused by Contractor Personnel Ignorance. Personnel Admonished to Heed Procedures at All Times ML20084Q0021976-12-30030 December 1976 LER 017/03L-0:on 761203,Grinnell Corp Snubber 4755 on RCIC Steam Supply Piping Found to Have Empty Oil Reservoir. Caused by Leakage Through Reservoir End Gap Gaskets.Snubber Repaired & Reservoir Refilled w/oil.W/761230 Forwarding Ltr 05000265/LER-1976-012, Updated LER 76-012/03L-1 Correcting Event Type,Category & Rept type.W/761001 Forwarding Ltr1976-10-0101 October 1976 Updated LER 76-012/03L-1 Correcting Event Type,Category & Rept type.W/761001 Forwarding Ltr ML20084P4791976-08-25025 August 1976 LER 023/03L-0:on 760727,diesel Generator 1/2 Out of Svc for Monthly Insp for 55 Minutes Longer than Tech Spec Limit of 1.5 H.Caused by Maint Personnel Not Being Aware of Time Limit.Procedure to Be Changed ML20084Q0281976-05-27027 May 1976 LER 017/03L-0:on 760427,while Performing Low Reactor Water Level Functional Test,Level Indicating Switch LIS-1-263-58A Tripped,Exceeding Tech Specs.Caused by Instrument Drift. Switch recalibr.W/760527 Forwarding Ltr ML20084Q0511976-04-30030 April 1976 L-0:on 760427,while Performing MSIV Surveillance, Duel Indication Received for Valves AO 1-203-1B & AO 1-203-1D.Caused by Switches Being Out of Alignment.Minor Air Leak repaired.W/760430 Forwarding Ltr 05000254/LER-1976-002, Updated LER 76-002/03L Re Excessive Leakage from Double Gasketed Seal X-4.Initially Reported on 760202.Caused by Equipment Failure & Insufficient Compression.Hatch Bolts Tightened1976-03-0303 March 1976 Updated LER 76-002/03L Re Excessive Leakage from Double Gasketed Seal X-4.Initially Reported on 760202.Caused by Equipment Failure & Insufficient Compression.Hatch Bolts Tightened 1993-08-27
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data SVP-99-204, Monthly Operating Repts for Sept 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With1999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With 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 ML20212J0501999-09-21021 September 1999 Safety Evaluation Re Licensee Implementation Program to Resolve USI A-46 at Plant,Per GL 87-02,Suppl 1 SVP-99-179, Monthly Operating Repts for Aug 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With1999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With ML20210L8661999-08-0202 August 1999 Safety Evaluation Accepting License 60-day Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs SVP-99-155, Monthly Operating Repts for July 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With1999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With SVP-99-148, Monthly Operating Repts for June 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With1999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML20195K1481999-06-16016 June 1999 Safety Evaluation Authorizing Relief Request RV-23A for Duration of Current 10 Yr IST Interval on Basis That Compliance with Code Requirements Would Result in Hardship Without Compensating Increase in Level of Quality & Safety SVP-99-123, Monthly Operating Repts for May 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With1999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With 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 SVP-99-104, Monthly Operating Repts for Apr 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With1999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With SVP-99-102, Summary Rept of Changes,Tests & Experiments Completed, Covering Period 990201-0430. with1999-04-30030 April 1999 Summary Rept of Changes,Tests & Experiments Completed, Covering Period 990201-0430. with ML20205Q5291999-04-16016 April 1999 SER Concluding That Quad Cities Nuclear Power Station,Unit 1,can Be Safely Operated for Next Fuel Cycle with Weld O2BS-F4 in Current Condition Because Structural Integrity of Weld Will Be Maintained ML20205J6011999-04-0707 April 1999 Safety Evaluation Accepting Proposed Merger of Calenergy Co, Inc & Midamerican Holdings Co for Quad Cities Nuclear Power Station,Units 1 & 2 SVP-99-071, Monthly Operating Repts for Mar 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With1999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With ML20205C5671999-03-19019 March 1999 Simulator Four-Yr Certification Rept ML20207D2341999-03-0101 March 1999 Post Outage (90 Day) Summary Rept, for ISI Exams & Repair/Replacement Activities Conducted 981207-1205 ML20204B1571999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Quad Cities,Units 1 & 2.With SVP-99-021, Quarterly Summary SER of Changes,Tests & Experiments Completed, Covering Period of 981101-990131,IAW 10CFR50.59 & 10CFR50.71(e).With1999-01-31031 January 1999 Quarterly Summary SER of Changes,Tests & Experiments Completed, Covering Period of 981101-990131,IAW 10CFR50.59 & 10CFR50.71(e).With ML20205D1311998-12-31031 December 1998 1998 Decommissioning Funding Status Rept for Yr Ending 981231 for Quad Cities Nuclear Power Station,Units 1 & 2 ML20205M7061998-12-31031 December 1998 Unicom Corp 1998 Summary Annual Rept. with SVP-99-007, Monthly Operating Repts for Dec 1998 for Quad Cities Nuclear Power Station,Units 1 & 2,IAW GL 97-02 & TS 6.9.With1998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Quad Cities Nuclear Power Station,Units 1 & 2,IAW GL 97-02 & TS 6.9.With ML20196C8391998-11-30030 November 1998 Rev 0 to GE-NE-B13-01980-030-2, Assessment of Crack Growth Rates Applicable to Induction Heating Stress Improvement (IHSI) Recirculation Piping in Quad Cities Unit 1 SVP-98-364, Monthly Operating Repts for Nov 1998 for Quad Cities Nuclear Power Station,Units 1 & 2.With1998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Quad Cities Nuclear Power Station,Units 1 & 2.With ML20196G1241998-11-30030 November 1998 COLR for Quad Cities Unit 1 Cycle 16 ML20196D9651998-11-30030 November 1998 Safety Evaluation Supporting Relief Requests CR-21 & CR-24, Respectively.Relief Request CR-23,proposed Alternative May Be Authorized,Per 10CFR50.55a & Relief Request CR-22 Was Withdrawn by Licensee ML20196C8731998-11-30030 November 1998 Rev 0 to GE-NE-B13-01980-30-1, Fracture Mechanics Evaluation on Observed Indications at Two Welds in Recirculation Piping of Quad Cities,Unit 1 Station ML20196A9761998-11-20020 November 1998 Safety Evaluation Re Licensee 180-day Response to GL 95-07, Thermal Binding of Safety-Related Power-operated Gate Valves 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 SVP-98-346, Monthly Operating Repts for Oct 1998 for Quad Cities Nuclear Power Station,Units 1 & 2.With1998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Quad Cities Nuclear Power Station,Units 1 & 2.With SVP-98-358, Summary Rept of Changes,Tests & Experiments Completed, Including SEs Covering Period on 980716-1031.With1998-10-31031 October 1998 Summary Rept of Changes,Tests & Experiments Completed, Including SEs Covering Period on 980716-1031.With SVP-98-326, Monthly Operating Repts for Sept 1998 for Quad Cities Nuclear Power Station,Units 1 & 2.With1998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Quad Cities Nuclear Power Station,Units 1 & 2.With ML20153D0191998-09-18018 September 1998 Part 21 Rept Re Defect in Gap Conductance Analyses for co- Resident BWR Fuel.Initially Reported on 980917.Corrective Analyses Performed Demonstrating That Current Operating Limits Bounding from BOC to Cycle Exposure of 8 Gwd/Mtu ML20153C6771998-09-17017 September 1998 Part 21 Rept Re Defect Relative to MCPR Operating Limits as Impacted by Gap Conductance of co-resident BWR Fuel at Facilities.Operating Limit for LaSalle Unit 2 & Quad Cities Unit 2 Will Be Revised as Listed ML20151T2711998-09-0404 September 1998 Safety Evaluation Accepting Licensee Response to NRC Bulletin 95-002 ML20151Y7261998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Quad Cities Nuclear Power Station ML20237E2331998-08-21021 August 1998 Revised Pages of Section 20 of Rev 66 to CE-1-A, QA Topical Rept ML20151Y7301998-07-31031 July 1998 Revised MOR for Jul 1998 for Quad Cities Nuclear Power Station,Units 1 & 2 ML20237A6251998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Quad Cities Nuclear Power Station,Unit 1 & 2 SVP-98-328, Summary Rept of Changes,Tests & Experiments Completed, Including SEs Covering Period of 971001-980715,per 10CFR50.59 & 10CFR50.71(e).With1998-07-15015 July 1998 Summary Rept of Changes,Tests & Experiments Completed, Including SEs Covering Period of 971001-980715,per 10CFR50.59 & 10CFR50.71(e).With SVP-98-249, Monthly Operating Repts for June 1998 for Quad Cities Nuclear Power Station,Units 1 & 21998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Quad Cities Nuclear Power Station,Units 1 & 2 SVP-98-215, Monthly Operating Repts for May 1998 for Quad Cities Nuclear Power Station Units 1 & 21998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Quad Cities Nuclear Power Station Units 1 & 2 ML20247N6281998-05-19019 May 1998 Rev 2 to COLR for Quad Cities Unit 2 Cycle 15 ML20216C0561998-04-30030 April 1998 Safe Shutdown Rept for Quad Cities Station,Units 1 & 2, Vols 1 & 2.W/22 Oversize Figures SVP-98-176, Monthly Operating Repts for Apr 1998 for Quad Cities Nuclear Power Station,Units 1 & 21998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Quad Cities Nuclear Power Station,Units 1 & 2 ML20217D0281998-04-22022 April 1998 Part 21 Rept Re Additive Constants Used in MCPR Determination for Siemens ATRIUM-9B Fuel by Core Monitoring Sys Were Found to Be non-conservative.SPC Personnel Notified All Customers w/ATRIUM-9B Lead Test Assemblies ML20217G3951998-04-0808 April 1998 TS 3/4.8.F Snubber Functional Testing Scope Quad Cities Unit 2 TS (Safety-Related) Snubber Population 129 Snubbers SVP-98-128, Monthly Operating Repts for Mar 1998 for Quad Cities Nuclear Station Units 1 & 21998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Quad Cities Nuclear Station Units 1 & 2 1999-09-30
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text
i Commtnw=lth Edison p
Og' Ouad Cmes Nuclear Power Station 22710 206 Avenue North
. Cordova, I!! nois 61242 9740 Te;ephone 309/654-2241 RLB-93-10B~
August 13, 1993 U.S. Nuclear Regulatory Commission Document Control Desk !
~
Washington, DC 20555
Reference:
Quad Cities Nuclear Power Station Docket Number 50-254, DPR-29, Unit One Enclosed is Licensee Event Report (LER)93-011, Revision 00, for Quad Cities Nuclear Power Station.
This report is submitted in accordance w'th the requirements of the Code of Federal Regulations, Title 10, Part 50.73(a)(2)(1)(B). The licensee shall report any operation or condition prohibited by the plant's Technical Specification.
Respectfully, COMMONWEALTH EDIS0N COMPANY ,
QUAD CITIES NUCLEAR POWER STATION l
R. L. Bax Station Manger RLB/TB/plm Enclosure cc: J. Schrage
T. Taylor
, INPO Records Center NRC Region III ;
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. LICENSEE EVENT REPORT (LER) Form Rev. 2.0 Facahty Narne (1) Docket Number (2) Page (3)
(haod Citica Unit One O p p p p p p p 1 jof p p Title (4)
Unit Or2 A Core Spray System inop Duc To Random Breaker Failure [
Event Date (5) LER Number (6) Repon Date Up Other Facilities involved (6)
Month Day Year Year Sequential Revision Month Day Year f acihty Docket Number (s)
Number Number Names r
o P P P P I I I O l7 2 l1 9 l3 9 p -
O p p -
O p 0 p 1% 9 p 0 p p p p l l l OPf. RATING THIS REPORT 15 $UbMITTED FUR $UANT TO THE kEQUIREMENTS OF 10CIR MODE (9) sCheck one or more of the following) (1I) 4 20.402(b) 20.405(c) 50.73(a)(2)(rv) i
-73.71(b)
POWEk 20.405(a)(1)(i) 50.36(c)(1) 50.73(a)(2)(v) 73.71(c)
LEVEL 20 405(a)(1)6i) 50.36(c)(2) 50.73(s)(2)(vii) Other (Specify (10) [2 p 20.405(a)(1)6ii) T50.73(a)(2)(i) 50.73(a)(2)(viii)(A) in Abstract 20.405(a)(1)6v) 50.73(a)(2)6i) 50.73(a)(2)(viii)(B) below and in l 20.405(a)(1)(v) 50.73(a)(2)6ii) 50.73(a)(2)(x) Text) ,
LICENSEE CONT ACT FOR THIS LER (la) l NAME TELEPHONE NUMLER !
AREA CODE +
Mark L Huhn Ext. 2117 3 p p 6 p l4 lp p p p ,
COMPLET E ONE LINE FOR EACH COMIONENT F ALLURE DESCklBED IN THIS REPORT (13) !
CAUSE SYSTEM COMPONENT MANUFACTURER REFOkTABLE CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE !
TO NPRDS TO NPRDS ,
Y BM lB f lR G p f p Y l l l l l l l l l i I J l l I I I I I SUPPLEMENTAL REPuki EXPECTED (14) Expected Month Day Year Submission lYES Of yea, complete EXPECTED SUBMISSION DATE) 70 Date (15) l l l
%hSTRACI (Lamn to 1400 spaces, s.c., approumately fifteen single-space typewntten imes) (16)
I A. ABSTRACT:
At 0917 hours0.0106 days <br />0.255 hours <br />0.00152 weeks <br />3.489185e-4 months <br /> on July 21, 1993, Unit One was in the RUN mode at 25 percent of rated core thermal power. It was discovered that 4KV breaker [BKR] #68, feeding the 18 Core Spray [BM] Pump Motor, was open and discharged. This resulted in the IB Core Spray loop being declared inoperable. Since the High Pressure Coolant Injection !
System [BJ] (HPCI) was also inoperable at the time, this placed Unit One in a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> I Limiting Condition for Operation (LCO) per Technical Specification section 3.5.C.4. )
The breaker was changed out and the IB Core Spray loop was tested satisfactorily and the LC0 was exited at 1017 on July 21, 1993. Troubleshooting indicated the breaker ,
malfunction was caused by a random component failure of the 52-SM/LS (Spring Monitor !
Limit Switch) switch [33]. This prevented the breaker from recharging because this i switch controls the operation of the charging motor. !
Since this condition was determined to have existed prior to reactor startup, this !
report is being submitted in accordance with 10 CFR 50.73(a)(2)(1)(b) due to l unintentional operation outside of Technical Specification section 3.5.A.1. j LI21254i93\0ll.%T'F ,
. .-. .~ .-
1 4 I
- LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Form Rev. 2.0 FACILITY NAME.(l) DOCKET NUMBER (2) LER NUMBER @) PAGE (3)
Year Sequennal Revision Number Number
)
l Quad Cities Unit one 0 5 0 0 0 2 5 4 9 3 :) I 1 0 0 2 OF 0 TiXT Energy industry idetA16 cation System (Ells) codes are idenu6ed in the text as [XX) l PLANT AND SYSTEM IDENTIFICATION: I General Electric - Boiling Water Reactor - 2511 MWt rated core thermal power.
EVENT IDENTIFICATION: Unit One A Core Spray System inop due to random breaker failure.
A. CONDITIONS PRIOR TO EVENT:
Unit: One Event Date: July 21, 1993 Event Time: 0917 I
Reactor Mode: 4 Mode Name: Run Power Level: 25%
This report was initiated by Licensee Report 254/93-011. I i
RUN (4) - In this position the reactor system pressure is at or above 825 psig, and the !
reactor protection system is energized, with APRM protection and RBM interlocks in service (excluding the 15% high flux scram).
i
)
I I
LER254\93\0ll.%TF l l
e LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Form Rev. 2.0 FhCILrry N AME (1) DOCKET NUMBEJL (2) LEA NUMBEA (6) PAGE (3)
Year $cquennal Revimon Number Nunber ,
Quad Cities Unit one 0 p p p p p p p 9 p -
3 p p -
3 p 2 pF p p TEX'I Energy industry idenu6couon System (Ell 5) codes art idenu6ed in the text as {XX)
PLANT AND SYSTEM IDENTIFICATION: ,
General Electric - Boiling Water Reactor - 2511 MWt rated core thermal power.
EVENT IDENTIFICATION: Unit One A Core Spray System inop due to random breaker failure.
i A. CONDITIONS PRIOR TO EVENT:
Unit: One Event Date: July 21, 1993 Event Time: 0917 .
Reactor Mode: 4 Mode Name: Run Power Level: 25%
This report was initiated by Licensee Report 254/93-011.
RUN (4) - In this position the reactor system pressure is at or above 825 psig, and the reactor protection system is energized, with APRM protection and RBM interlocks in service (excluding the 15% high flux scram).
B. DESCRIPTION OF EVENT: -
On July 21, 1993 at 0917, Unit One was in the RUN mode at 25 percent of rated core thermal power. An operator, while performing rounds, discovered that 4KV breaker
[BKR] #68, feeding the IB Core Spray [BM] Pump Motor, was open and discharged. The normal configuration is open and charged. This condition resulted in tha IB Core ,
Spray system being declared inoperable. Since the High Pressure Coolant Injection i (BJ](HPCI) system was also inoperable at the time, this placed Unit One in a 24 LC0 .
per Technical Specification section 3.5.C.4. !
It was determined that the only time the breaker could have been discharged was following Core Spray system testing at 0245 hours0.00284 days <br />0.0681 hours <br />4.050926e-4 weeks <br />9.32225e-5 months <br /> on July 20, 1993. Unit One reactor startup commenced at 0435 hours0.00503 days <br />0.121 hours <br />7.19246e-4 weeks <br />1.655175e-4 months <br /> on July 20, 1993. Technical Specification section 3.5.A.1 states that, "Both core spray subsystems shall be operable whenever irradiated fuel is in the reactor vessel and prior to reactor startup from a cold condition." Since the unit was started up with one of the Core Spray loops inoperable, this resulted in operation outside of Technical Specification section 3.5.A.1, and this report is being submitted in accordance with 10 CFR 50.73(a)(2)(1)(b).
In order to restore the IB Core Spray system to operability, the Operations department attempted unsuccessfully to recharge the breaker. The Electrical Maintenance (EM) department was contacted to assist in the breaker troubleshooting.
Since Unit Two was in cold shutdown, the breaker for the 2B Core Spray pump cubicle from bus 24-1 was installed in the bus 14-1 cubicle for the IB Core Spray Pump.
Follow'aig breaker replacement, QCOS 1400-4, Monthly Core Spray Pump Operability, was p;rformed satisfactorily to prove operability of the IB core spray system. The LCO was exited at 1017 on July 21, 1993.
LER254\93\011.WPF
i UCENSEE EVENT REFORT (LER) TEXT CONTINUATION Form Rev. 2.o ;
PACluTY NAME (1) DOCKET NUMBER (2) LER hUMBM (6) PAGE (3)
Year Sequennal Revisen l Number Nurnber [
~
( od Citics Unit One 0 p p p p p p p 9 p -
3 p p -
3 p 3 lOF p p TEXT Energy industry idenuficatson System (Ell 5) codes art idenufaed in the text as (XX) }
=
C. APPARENT CAUSE OF EVENT:
1 i The cause for operation outside of Technical Specification section 3.5.A.I. is due to an inadequate procedure. Currently, no requirement exists to inspect the Core Spray '
pump breakers following the performance of operability surveillances. A breaker )
inspection is performed daily by Equipment Operators (E0). This inspection did not occur during the short time between system testing at 0235 hours0.00272 days <br />0.0653 hours <br />3.885582e-4 weeks <br />8.94175e-5 months <br /> and reactor startup at 0445 hours0.00515 days <br />0.124 hours <br />7.357804e-4 weeks <br />1.693225e-4 months <br /> on July 20, 1993. ;
An apparent contributing cause is due to personnel error in the form of lack of attention to detail. The breaker was discovered uncharged at 0917 hours0.0106 days <br />0.255 hours <br />0.00152 weeks <br />3.489185e-4 months <br /> on July 21, '
1993. Operator surveillance sheets for July 20 indicate that this breaker was verified to be charged on shift 3 (1500-2300). Based on the only possible discharge mode available for the breaker charging spring, the system operability test completed i at 0235 on July 20, it appears that the uncharged breaker condition was overlooked by ;
the operator during the shift three rounds on July 20. This event was discussed with the operator who performed the shift three rounds on July 20. He said he inspects both the toggle switch and the breaker status window, and was unable to explain why he did not identify the uncharged breaker.
The cause of the breaker malfunction was due to a random component failure of one of
. the breaker charging motor switches.
D. SAFETY ANALYSIS OF EVENT:
The safety significance of this event was minimal. The A loop of Core Spray was ,
operable throughout the time period that the B loop was considered inoperable. One !
loop of Core Spray is sufficient to accomplish the intended safety function of the 1 Core Spray system. Also, both loops of the Low Pressure Coolant Injection [B0](LPCI) !
system were operable. ,
Since HPCI was also inoperable at the time the . Core Spray loop was determined to I be inoperable, Unit One entered a 24 LC0 per Tet 4 cal Specification section 3.5.C.4.
E. CORRECTIVE ACTIONS:
The immediate corrective action was to declare the IB Core Spray loop inoperable and write a work request to investigate and repair. ]
Currently the breaker sthtus windows, which indicate if the breaker is charged or l uncharged, are not consistent with respect to window color. The " Charged" windows are either yellow or red while the " Uncharged" windows are black. The charged window colors will be standardized in order to make it more apparent when one of the breakers is uncharged. A procedure change will be processed to standardize the window colors as part of the normally scheduled breaker PM program per QCEPM 200-1, Inspection and Maintenance of 4KV Horizontal Circuit Breakers Type 4.76-250 (NTS# 2541809301101).
LIR254\93ND11.WPF 4
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LICENSEE EVENT REPORT (LER) TEU CONTLNUATION Form Rev. 2.0
[ACILTTY NAME 0) DUCKET NUMBEJL C) LER NUMBER (6) PAGE 0)
Year Sequent 6al Revision Number Number t Quod Cities Unit One o p p p p p p p 9 p a p p -
a p 4 pp p TEXT Imergy industry idenufwation System (LUS) codes are idenufsed n the text as [XXj Troubleshooting was performed on the failed breaker under Work request Q08741. The faulty breaker was replaced with the breaker from the 2B Core Spray Pump and the Monthly Core Spray surveillance was performed and the LC0 was exited. During initial inspection, it was determined that the 52-SM/LS (Spring Monitor Limit Switch) switch contacts 1 and 2 were open. This is a normally open switch which is actuated when :
the breaker springs are discharged. Switch contacts 1 and 2 close to supply power to :
the breaker charging motor and open to remove power from the motor when the breaker springs are charged. The failed breaker was manually charged and the switch operated well enough for breaker operation in subsequent attempts. Failure of the breaker to operate is directly attributable to the intermittent operation of the 52-SM/LS contacts 1 and 2. This switch was disassembled and it was found that the contact carrier had melted due to overcurrent. The melted contact carrier caused a l misalignment of the contact points preventing the switch from actuating to supply
~
pcwer to the breaker charging motor. An additional switch in series to the 52-SM/LS switch was inspected and did not show any similar damage leading to a conclusion that this was a random failure of the 52-SM/LS switch.
While this event was considered a random failure, the EM department checked similar switches on this breaker and found three of them to have erratic resistance readings. :
The switches appeared to have a dirt accumulation that would wipe clean with repeated cycling. These switches were replaced with spares. ;
As a result of this event, the EM department will incorporate into QCEPH 200-1, I Inspection and Maintenance of 4KV Horizontal Circuit Breakers Type 4.76-250, a requirement to perform resistance checks on these switches as part of future breaker inspections (NTS# 2541809301102). ;
The failed switch on this breaker was original equipment. Based on this fact and the results of the previous events search for this type of failure, no further corrective ,
actions are necessary at this time. '
Procedure changes will be processed to require the inspection of ECCS Pump breakers ;
following operability testing.
F. PREVIOUS EVENTS:
A TJM search on all items with an "S35 " aquipment code (breakers) did not indicate '
any related failures. The replacement switches had to be obtained from Dresden Station because they had not been stocked at Quad Cities with the required safety l classification since the parts classification program began in 1988, indicating zero !
usage during that period.
A Nuclear Plant Reliability Data System (NPRDS) nationwide search was conducted for l 4KV breaker failures, Model ID no. AMH-4.76-250, dating back to 1988. Two events were identified which were caused by similar switch failures of the charging motor .
1 circuit, neither of which occurred at Quad Cities Station.
An LER previous events search for similar breaker failures revealed no similar ,
events. :
i LDC54i93i0l l .uTF l
l
)
UCENSEE EVENT REFORT (LER) TDCT CONTINUATION Form Rsv. 2.0 ;
b,CL'ITY NAME (1) DOCKET NUMBLR (2) LER NUMBER (6) PAGE (3) ;
- Year Sequenual Revis'e n Number Number Quad Cines Unit one 0 }5 l0 p p p l5 P 9 p -
O p p 0 p 5 pF p l5 TEXT Emergy Induary idend6cauon System (EIIS) codes are odern36ed an the text as (XXj i
i G. COMPONENT FAILURE DATA:
This switch is a model CR29400310 manufactured by General Electric.
h i
l LER254\93\011.%7F I
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