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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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C;mmonw lth Ediz:n O-- Quad Cites Nuclear Power Station 22710 206 Avenue North Cordova. Ilunois 61242-974D Teiephone 309%54 2241
/
s' RLB-93-105 August 6, 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)93-009, Revision 00 for Quad Cities Nuclear Power Station.
This report is submitted in accordance with the requirements of the Code of Federal Regulations, Title 10, Part 50.73 (a)(2)(v)(C). The licensee shall report any event or condition that alone could have prevented fulfillment of (V the safety function of structures or systems that are needed to control the release of radioactive material.
Respectfully, COMMONWEALTH EDISON COMPANY QUAD CITIES NUCLEAR PO ER STATION 4 R. L. Bax
/ Station Manager RLB/TLB/pim Enclosure cc: R. Stols T. Taylor INP0 Records Center NRC Region III O :so m STMGR\lO593.kLB C
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9308100097 930813 ,
PDR ADOCK 05000254 g/
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LICENSEE EVENT REPORT (LER) Fonn Res.2.0 p* Sty Name (1) ,
Ducka Number Gl Page Q) l I -
_lcties t'ait one 0 15 P P P P P H lor l l Title (O SBGT Methyllodide Test Failure Due To Age Of Charteal Event Date (5; LER Number tol Report Date (J) Other lachties la,<dved (El Mouth Day near near Saguentaal Re,auen Mouth Day near l achty DucLa humberts)
Number Number Names Q=dCn= 4
"' T **
0 P P P P P P P l 0 [7 i P W p V p -
O p f -
O p 0 p i p 9 p 0 p p p p l l l OPERATING THIS REPORT IS SUhMTTTED PUR5U ANT 101HE REQUIRutENT5 OF MCFR MODE (9) (Check one or more of the following) (11)
I 20.402(b) 20.405(c) 50.73(a)(2)Ov) 73.71(b) i luw LR 20.405(a)(1)6) 50.36(c)(1) I50.73(a)G)(v) -73.71(c)
LEVEL 20.405(a)(1)6i) 50.36(c)G) 50.73(a)(2)(vii) Other (Specify
- 00) l p 20.405(a)(1)6ii) 50.73(a)C)6) 50.73(a)C)(viii)(A) in Abstract 20.40$(a)(1)6v) 50.73(a)C)6i) 50.73(a)C)(viii)(B) below and in 20.405(a)(1)(v) 50.73(a)C)6ii) 50.73(a)(2)(x) Text)
LICENSEE CONTACT FOR 1H15 LLk (12)
NAME TELEPHONE S UMBEA AREA CODE Rachel Luebbc. Tech staff Engineer. Ext. 2119 3 p p 6 p p l.p p p p COMPLETE ONE LINE FOR EACH COMPONLNT F AILURL DEACR1hED IN T111S REPOkT (13)
CAU5L SYSTIM COMPuNENT MANUf ACTURER kDok1 AMA C AUsE 6h TIAi CosuuNLT'T MANL 3 ACTLKER kuukIANI To NPRDs TO NPRDS n i I I I I I I I I I I I I I l I I I I I ! I I I I I SUPPLD1 ENTAL REPORT LXPLCILD tlO Espcta$1 Mouth Day Year Submission fES (If es, 3 compide EXPECTED St'B%115510N DATE)
K NO Date (15) l l l All5'l RACI (Lamit to 14u0 spaces, i.e., apprvsunately fif teca smgie-space ty peunttens hues) (1 }
ABSTRACT:
On Wednesday, July 14, 1993, Unit one was in cold shutdown and Unit two was in the run mode at 20% of rated core thermal power. On June 29, 1993 the A SBGT train charcoal methyl iodide efficiency was shown to be 75.4% Tech Spec 3.7.B.2.a.3 require a methyl iodide efficiency of 90%. Both SBGT trains charcoal were replaced by July 4th. At 1500 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.7075e-4 months <br /> on July 14th, the results of the old B Standby Gas Treatment (SBGT)[VI] train charcoal showed a methyl iodide efficiency of 72.1%. Therefore, before the charcoal replacement on both trains of SBGT on July 4th, both trains of SBGT were inoperable. A 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Emergency Notification Phone call was made at 1610 hours0.0186 days <br />0.447 hours <br />0.00266 weeks <br />6.12605e-4 months <br /> on July 14, 1993.
The apparent cause of the failed methyl iodide efficiency test is the age of charcoal combined with the more stringent test criteria. ;
One corrective action was to replace the charcoal adsorber [ ADS) in both trains of SBGT upon discovery of the A Train methyl iodide efficiency failure. Followup corrective actions are to ,
install modification M04-0-92-013, which replaces the pneumatic flow switches with electronic ;
% switches. This modification will allow relaxation of the testing criteria. Until the i fication is completed and the Tech Spec revision approved, the station will test the methyl (
iodide efficiency of the charcoal every 6 months. }
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LER254193\004.WPF '
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LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Fons Rev.2.0 FACILITY NAME (1) DOCKET NL3tBER Q) LLR NL}iliER t4 PAGE 0)
Year Sequestaal kernwa
, Number Number Cities Unit One o p l0 p p p p }4 9 p -
O p p a p 2 lOF p l TLXT 1mergy industry Identifscation Systeun LLII5) tooes are identiGad in the text as [XX)
PLANT AND SYSTEM IDENTIFICATION:
Gereral Electric - Boiling Water Reactor - 2511 MWt rated core thermal power.
?
EVENT IDENTIFICATION: SBGT Methyl Iodide Test Failure Due to Age of Charcoal.
i A. CONDITIONS PRIOR TO EVENT Unit: One Event Date: July 14, 1993 Time: 1507 hours0.0174 days <br />0.419 hours <br />0.00249 weeks <br />5.734135e-4 months <br /> Reactor Mode: 1 Mode: Shutdown Power Level: 0%
This report was initiated by Licensee Event Report 254/93-009.
SHUTDOWN (1) - In this pasition, a reactor scram is initiated, power to the control rod l drives is removed, and the reactor protection trip systems have been deenergized for 10 seconds prior to permissive for manual reset.
B. DESCRIPTION OF EVENT 0n Wednesday, July 14, 1993, Unit One was in cold shutdown, and Unit Two was in the run l 0' mode at 20% of rated core thermal power. On Tuesday, June 29, 1993 at 1500 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.7075e-4 months <br /> Nuclear Consulting Services (NUCON) informed the station that_the charcoal sample previously sent from the "A" Standby Gas Treatment (SBGT)[VI) had a methyl iodide removal efficiency of 75.4%. A 90% methyl iodide removal efficiency is required per Technical Specification 3.7.B.2.a.3.
The "A" SBGT train was declared inoperatie and the "B" SBGT train was started to prove ,
operability. On Wednesday, June 30, 1993 the failed charcoal was removed from the A Train of SBGT. On Thursday, July 1,1993 new charcoal trays were installed with a methyl iodide efficiency of 98.94%. After successful completion of the 10 hour1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> operability run the A Train of SBGT was declared operable at 1820 hrs on Friday, July 2, 1993.
On Friday, July 2nd the "B" SBGT was taken out of service for replacement of the charcoal adsorber [ ADS). At that time, a test canister was taken out of the old charcoal for methyl ;
iodide lab analysis. The replacement charcoal has an efficiency of 99.7%. After successful completion of the 10 hour1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> operability run the B Train of SBGT was declared operable on Sunday, July 4th at 1815 hours0.021 days <br />0.504 hours <br />0.003 weeks <br />6.906075e-4 months <br />.
Results of the "B" SBGT old charcoal methyl iodide efficiency were received by the station at 1500 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.7075e-4 months <br /> on Wednesday, July 14th. The results showed an efficiency of 72.1%. A4 hour Emergency Notification Phone call was made on July 14, 1993 at 1610 hours0.0186 days <br />0.447 hours <br />0.00266 weeks <br />6.12605e-4 months <br />.
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LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Form Rev.2.0 l OKILil Y NAME O s DOEKET NUMBER (2; .LER NUMllER (6) PAGE0; l
Year Sequmtaal Rensnun Number Number l
_ Chks Unt ow 0 p p p p p p p 9 p -
O p p -
O p 2 pF p l l 1 EXT lacrgy ladustry ldatifacatu,n System (Lil5p codes are idatified an the test as (XX) i C. APPARENT CAUSE The failure of the charcoal to successfully pass the methyl iodide test is attributed to the age of charcoal and new stringent test criteria. The charcoal for the A train of SBGT was installed in 1990, and was originally ordered in 1988. The charcoal for the B Train was installed in 1987. The last tests for methyl iodide efficiency were done per ASTM D3803-1979 at 30* C and 70% relative humidity. The 70% relative humidity (R.H.) was previously used because SBGT contains a heater which controls the relative humidity.
Since that test, it was discovered that a loss of instrument air would prevent the heater from functioning and reducing the relative humidity in the train. Therefore, the station ;
committed to doing the methyl iodide test for SBGT at 30' C and 95% relative humidity per ;
ASTM D3803-1989 (see LER 254/92-028), because the use of the heater to control humidity 4
could no longer be assumed.
The ASTM D3803-1989 standard states, " Decreasing the relative humidity of the test i generally increases the efficiency of the methyl iodide removal by activated carbon. The :
, water vapor competes with the methyl iodide for adsorption sites on the carbon, ..." !
I Therefore, switching from a 70% relative humidity test to a 95% relative humidity test will '
cause the methyl iodide efficiency of the charcoal to decrease.
l A review of maintenance activities since November 1991, showed no actions that would have
, degraded the charcoal. Painting activities have been controlled by procedure since July 1991; therefore, a painting event in the area of SBGT did not cause the charcoal to degrade. ,
D. SAFETY ANALYSIS l l
This event is being reported in accordance with 10CFR 50.73(a)(2)(v)(C). The licensee .
shall notify the NRC for any event or condition that alone could have prevented the l fulfillment of the safety function of structures or systems that are needed to control the '
j release of radioactive material. i l i
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tousenvo9xrr ,
, _ LICENSEE EVENT REPORT (LER) TT_XT CONTINUATION Form Rev. 2.0 ACILITY NAME (1) DOCKET NDihER Gl LER NDiBER 46) PAGE 0)
Year l maumtmal kersuon iumber Number d Citiem Unit One O p p p p p p p 9 p -
O p p -
O p 2 pF p l pEXT bwrgy industry idesat4 cation 6stesu (Lils codes are idstinesi in the test as IXX]
Based on calculations the safety consequences of this event would have been a reduction in the design basis dose margin from 260% to 257% had a loss of Coolant Accident (LOCA) occurred. The release of radioactive material wou~. not have exceeded Control Room (GDC
- 19) and Off-site Dose (10CFR100) limits had a loss of Coolant Accident (LOCA) occurred.
Methyl iodide makes up about 4% of the iodine source seen during a post-accident situation.
The other 96% are elemental and particulate iodides. Trapping of elemental and particulatt iodides involves physical adsorption only, and the efficiency of activated carbon will
- typically be at least 99%. Trapping of methyl iodides involves a chemical adsorption
. process, which is why the carbon is impregnated with Potassium Iodine (KI). Methyl iodide removal efficiency is intended to gauge the degree of degradation of the impregnation of the carbon and not the actual removal efficiency of the system. Assuming that the removal efficiency of the elemental and particulate iodides are also affected by the degradation of the carbon, the design basis dose would increase by 165%. However, since the removal efficiency of 96% of the iodides was unaffected then the design basis dose would increase by 2.7%
E. RECOMMENDED CORRECTIVE ACTIONS When the test results were received from the A train of SBGT, both train's charcoal adsorbers were replaced with new charcoal tested to the 30' C, 95% R.H.1989 standard.
This work was completed on both trains on July 3, 1993. The new A train charcoal has an O efficiency of 98.9% and the new B train charcoal has an efficiency of 99.7%. These efficiencies are well above the 90% required by Technical Specifications.
Modification M04-0-92-013 to replace the pneumatic flow switches on SBGT will be completed.
Once this modification is completed and the submitted Technical Specification revision is approved, then the station can return to the 30' C and 70% relative humidity methyl iodide test (NTS# 2542009211302). Until that time, the station will test the methyl iodide efficiency of the charcoal every 6 months at 30* C and 95% R.H.1989 standard (NTS# 2541809300901).
F. REVIEW OF PREVIOUS EVENTS l There have been no previous events of the SBGT charcoal failing the methyl iodide efficiency test.
G. COMPONENT FAILURE DATA .
Currently, the Nuclear Plant Reliability Data System (NPRDS) does not cover the SBGT charcoal adsorber. The NPRDS system will be revised to include this component. This and all future failures of the charcoal adsorber will be reported through NPRDS.
O LER254t91MWPF