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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
[Table view] |
LER-2088-001, 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 Upgraded |
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2542088001R00 - NRC Website |
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$ LICENSEE EvtNT REPCRT (I.ER) 1 Facility came (1) , Occket Number (2) _han f 31 OJAD-f!Titi NUCLEAR POWER staff 0N. UNIT ONE 01 El 01 01 01 21 El 4 1 lofl0 $
Title (4) TWO CONTRACTOR PERSONNEL OvtRExP01URES IN THE FOURTH QUARTER OF 1980 OUE TO DOS! METER INACCURACY R t Date (1) Ltt Number (6) Renart Date (7) Other Facilities Involved (R)
Month Day Year Year //
,p/p sequential /// Revision Month Day Year Facility Namat Docket Numberft)
/// Number g/// Number 01 El O! 01 Ol l l
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Ill 213 elo Alt 01 0 ll 0 l0 0l 1 218 Bla of El dl 01 0! l 1 THIS REPORT !$ $UeMITTED PUR$UANT TO THE REQUIREMENTS OF 10CFR
(. Check one er more of the followino) f11) 20.402(b) _ 20.40$(c) 50.73(a)(2)(iv) 73.71(b)
POWER _X., 20.405(a)(1)(1) 50.36(c)(1) _, 50.73(a)(2)(v) _ 73.71(c)
LEvtl _. 20.405(a)(1)(11) 50.36(c)(2) ,_ 50.73(a)(2)(v11) .,_._ Cther (Specify f101 0!0 ! _0 __ _ _ _ 20.405(a)(1)(111) ., 50.73(a)(2)(1) 50.73(a)(2)(vtti)(A) in Abstract below
/,/,//,///////////////,/////// 20.405(4)(1)(tv) _ 50.73(a)(2)(ii) 50.73(a)(2)(vitt)(B) and in Text)
'/',/'////////////////'
j/ , , /////// .,, 20.405(a)(1)(v) _, 50.73(a)(2)(tit) __ 50.73(a)(2)(x)
LIfthift CONTACT F0P THit LER (12)
Name TELt? HONE NUMBER AREA CODE Randall Tank. Desimetry Records coordinator Ext. 2741 3 1019 611141-l212 l COMPLETE ONE LINE FOR EACH COMP T FAILURE DESCRIRtc IN THIS REPORT f13)
CAU$E SYSTEM COMPONENT MANUFAC- REPORTA8LE / CAU$E SYSTEM COMP 0NENT MANUFAC. REPORTABLE TURER 70 NPROS TURER 70 MPRDS X fIL l MI of M Vl1 11 11 N X I IL IM 10 IN X10 11 11 4 X fIL l MI of N LI 01 61 E N l l l 1 l l }
tuPPLEMENTAL REPORT EXPECTto f14) Expected Month l Day I Year cubmission lyet fif yet. conolate EXPicito sORMIi110N DATE) x l NO
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l ll l A31 TRACT (Limit to 1400 spaces i.e. approximately ftfteen single-space typewritten lines) (16)
On January 14, 1988 it was determined fiom a records review that two apparent overexposures of contractor personnel occurred during the fourth quarter of 1980.
Since adequate information does not exist today relative to the 1980 cases, these could not be disproved. This identification of apparent overexposures was the result of a special computer program that produced a list of all individuals that had been documented as being overexposed at Commonwealth Edison (CECO) sites. One individual received 3190 mrem / quarter and the second individual received 3180 trem/ quarter based on documented film badge readings. This is in excess of 10CFR20 exposure limits and is reportable per 10CFR20.405(a)(1)(1).
The cause for the apparent overexposure was the inaccuracy of the secondary and/or primary dosimetry in use. Since this event, significant improvements have been made in both secondary and primary dosimetry systems and discrepancies of this magnitude do not occur. In addition, there are improved administrative controls to track individual doses and to provide for immediate recognition of anyone approaching th6 limits.
8803010023 000128 c;d PDR ADOCK 05000254 S PDR
- l 1174H/03922 i
I LICE 4itt EVENT REPORT fLER) TEXT CONTINUATION FACILITY 4AME (1) 00CKE? CUM 8tR (2) _ ttR MuMa[R f61 pu , (3)
Year // sequential Restston p/pp/
// Number /pp////p/ Number _
oeud citiat unit one 0lEl 0 1 0 1 0 ! fl El 4 8l 8 . O I0I1 - 0 10 012 0F 011
, TEXT PLANT AND SYSTEM IDENTIFICATION:
General Electric - Bolling Water Reactor - 2511 MWt rated core thermal power. Energy Industry Identification System (E:IS) codes are identified in the text as (XX).
EVENT IDENTIFICATION: Two contractor personnel were overexposed in the fourth quarter of 1980.
A. CONDITIONS PRIOR TO EVENT:
Unit: One Event Date: November 23, 1980 Event Time: NA Reactor Mode: NA Mode Name: NA Power Level: 007.
This report was initiated by Deviation Report 0-4-1-88-006 B. DESCRIPTION OF EVENT:
Ouring the fourth quarter of 1980, two contractors were apparently exposed to radiation in excess of the 10CFR20 exposure limits. Respective amounts of exposure are: Individual A - 3190 mrem / quarter and Individual 8 - 3180 mrem / quarter (See Attachment A and B). This occurrence was not recognized until recently when a special computer program was run to identify personnel overexposures to radiation. .
The following is a chronological history of what apparently transpired. Please note that dates are approximate as records do not exist for many of these actions.
September 15, 1980- The two individuals began their employment at Quad Cities Station. The main source of exposure to these individuals was
. the inboard Hain Steam : solation Valves (SB, ISV) which they were working on. Dose rates were between 100 mR/ hour and 400 mR/ hour. They worked in this particular area intermittently for six weeks.
November 23, 1980 - The two individuals terminated their employment at Quad Cities Stttion. The computer update of their radiation exposure had tht 4 listed as:
Individual A - 2754 mremiquarter consisting of film badge readings of 1240 mrem and 1130 mrem, and secondary dostmetry readings of 384 mrem.
Individual B - 2734 mrem / quarter consisting of film badge
- readings of 1100 mrem and 1090 mrem, and secondary dostmetry readings of 544 mrem.
November 29, 1980 - Film badge readings were substituted for secondary readings for the pertoo ending November 23, 1980. As a result:
820 mrem replaced 384 mrem for Individual A, resulting in an exposure of 3190 mrer for the quarter.
l 990 mrem replaced 544 mrem for Individual B, resulting in an exposure of 3180 mrem for the quarter.
1174H/0392Z E
I se _ _ _
L!cENiff EVENT REPORT fLER) TEXT coNTINUAftoN FAc!LITY NAME (1) 00CLit NUMett (2) _ LER NLMER (6)
Year Pieefn _
, /j// sequential /// Revision
/ Number Number ouas cities unit one o I i l o i o I o i 21 11 4. sIa itxT oIoi1 . oIe ol3 or els, Personnel who are terminated are no longer issued film badges.
The computer update lists only individuals who are currently badged.
Since these individuals were no longer badged, they were not listed on the computer update and the overexposure was not recognized.
December 29, 1980 - Termination letters (10CFR20.408) were produced and sent to the individuals and the NRC. Although all letters are reviewed prior to being sent, apparently these overexposures were missed.
August 15, 1986 -
A special computer program, to list all individuals that were overexposed to radiation at all CECO sites, from 1972 to the present, produced a list of 25 individuals. Ten of these occurrences were immediately recognized as being valid but had already been reported to the NRC. The remaining 15 occurrences were not considered to be valid.
March 25, 1987 -
CECO Corporate Health Physics sent a request to the stations asking that these individuals' overexposures be investigated.
Quad Cities Station was responsible for investigating five of the fifteen occurrences.
November 1, 1987 - A review of Quad Cities personnel records revealed that there was a problem with two individuals. Personnel records reviewed included Form-5 microfiche, microfilmed records of badge and dostmeter records, Radiation 00simetry Reports from CECO's film badge contractor, Radiation Occurrence Reports, Investigation Sheets, and termination letters. The apparent overerposures of these two individuals could not be disproved as could the other three individuals' overexposures. An in-depth review of all related records was initiated. Related records included microf timed records- of Exposure Time Worksheets, badge and dosimeter records for co-workers, Radiation Oostmetry Reports for co-workers and Exposure Time Worksheets for co-workers.
December 22, 1987 - CECO's film badge contractor re-read the film badges for these two individuals and reiterated that the original readings were correct.
January 14, 1988 - The apparent overexposures of these two individuals could not be disproved. On this date, this event was determined to be reportable and the NRC was notified by Corporate Health Physics.
C. APPARENT CAUSE OF EVENT:
These overexposures are reportable under 10CFR20.405 "Reports of Overexposures and Excessive t.evels and Concentrations."
The intermediate cause of the event was the substitution of the individuals' secondary dostmetry readings with their substantially higher film badge readings.
The root cause was inaccurate secondary and/or primary (film) dosimetry.
Il74H/Os922
LICENitt (VENT etPdRT fLER) fttf CONTINUAffah FAc!LifY NAMC (1) 00CKET NUNGER (2)
- LtR NUMatt f61 Pace (1) 3 Year //
p/p/p/ ,//
sequential / Rev151on
/ Number /// Number auaa etties unit one oi1IoIofa 1 21 11 4 aia . oIoi1 - a1o 014 or als_
.itz" The cause for the inability to recognize this situation promptly was a deficiency in the system utilized in 1980 to monitor and track radiation exposure.
D. SAFETY ANALYSIS OF EVENT:
There were minimal safety consequences associated with this event because the overexposures were small in magnitude.
E. CORRECTIVE ACTION:
During the years since this event, both secondary and primary dosimetry systems have been upgraded. Secondary dosimetry at the time of this event consisted of indirect reading pocket ton chambers (Victoreen model 362) and mechanical electronic desimeters (Xetex model 415). These have been replaced by better quality direct reading pocket ion chambers (Stephens model 907-862 and DCA model 862) and state of the art electronic dosimeters (Merlin-Gerin model DM-61), Film badges (R.S.
Landauer Jr. and Co. X, gamma and beta badges) have been replaced with thermo-luminescent dostmeters (TLD) (Panasonic model UD 802). Both replacement systems are considered to be much more accurate than the systems in use at the time of the event. Olscrepancies of this magnitude between primary and secondary dastmetry systems no longer occur due to the use of this state of the art equipment.
In addition, there are improved administrative controls to track individual doses and to provide for immediate recogattion of anyone approaching the limits.
Spectfically, the computer program reports used to track doses provide warning flags as individuals approach station administrative and legal limits.
Several reports are currently in use to allow an immediate recognition of a similar occurrence. The first of these is automatically generated when primary readings replace secondary readings and lists all individuals who exceed any administrative or legal limit. Another report compares primary readings with secondary readings for all individuals and lists the individual if the readings are discrepant.
Individuals A and B would have appeared on both of these reports if they had been in place at the time. Both of these reports include individuals who are no longer badged and thus an occurrer.ce of this type would be immediately recognized.
Letters concerning these apparent overexposures have been sent to the two individuals involved.
F. PREVIOUS EVENTS:
Previous events of this type are documented in Quad Cities Station Deviation Reports 0 6-1-76-25 (Mechanical Maintenance Foreman received quarterly whole body dose overexposure) and 0-4-1-76-53 (Two 18 year old contractor personnel received exposures exceeding 10CFR20 limits). These events were reported in letter
' NJK-76-167 dated April 29, 1976 and letter NJK-76-393 dated October 29, 1976.
1174H/03922
c-Litthitt EVENT'2tPott fLE!) ftXT CoNTINUATIoM FACILITY NAMC (1) DOCKET NUMe(R (2)* LER NUMBER f61 Paan (1)
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G. COMPONENT FAILURE DATA:
The following is provided to indicate what dostmetry was in use at the time this event occurred.
Manufacturer Nomenclature Model Number Victoreen Indirect reading lon chamber 362 Xetex Mechanical electronic dosimeter 415 R.S. Landauer, Jr. Film badge X, gamma, beta sensitive and Company l
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, 1174H/0392Z
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4 PURSUANT TO 10CFR20.405(b). THE-FOLLOWING TWO PAGES, IDENTIFIED AS ATTACHMENTS A AND 8. ARE SEING PROVIDED TO NRC UNDER THIS SEPARATE COVER.
i 1174H
6 Commonwealth Edison owad Cities Nuclear Power Station 22710 206 Avenue North Corcova, ininois 61242 Telephone 309/654 2241 RLB-88-29 January 28, 1988 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 please find Licensee Event Report (LER)88-001, Revision 00, for Quad-Cities Nuclear Power Station.
This report is submitted in accordance with th3 requirements of the Code of Federal Regulations, Title 10, Dart 20.405(a)(1)(1), which recuires the reporting of exposures of individuals to radiation in excess of t*,e applicable limits in 10CFR20.101 or 20.104(a). Pursuant to 10CFR20.405(b), Attachments A and B are provided to detail the information required.
Respectfully, COMMONHEALTH EDISON TANY QUAD-CITIE NUC P,OHER STATION
/ /
C. ,
R. L. Bax
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Station Manager RLB/MSK/cir Enclosure cc: I. Johnson R. Higgins INP0 Records Center NRC Regien III 0370H/0183Z
.