|
---|
Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER)
MONTHYEARML20149G9861994-11-0404 November 1994 Special Rept:On 941006,Unit 1 Fuel Storage Pool Conductivity Exceeded 10 Micro/Mho/Cm TS Limit & Returned to within TS on 941010.Caused by Decomposition of Biological micro-organisms in Fuel Storage Pool.Temporary Demineralizer Restarted ML20069E5351983-03-15015 March 1983 RO 83-014:on 830219,contaminated Demineralized Water Released Into Condenser,Allowing 0.7 Mci to Steam Out of Vent.Caused by Personnel Error.Operator Opened Valve MO-3-1301-10 Instead of Valve MO-3-4399-74 ML20069A3561983-03-0909 March 1983 RO 83-016:on 830207,contaminated Water from Drain & Refill of 2/3A Heating Boiler Inadvertently Released to Storm Sewer Sys.Caused by Operator Not Realizing Floor Drain Led to Storm Sewer Sys,Not Radwaste Sys.Tech Specs Not Violated ML20054F7971982-06-0909 June 1982 RO 82-027:on 820511,excessive Radioactive Contamination Identified in Two Areas of Offsite Dump.Caused by Inadequate Control of Dump Access & Failure to Survey Large Loads of Matl Thoroughly.Area Cleaned Up & Procedure 12-5 Revised ML20084R9011977-03-23023 March 1977 Telecopy Ro:On 770322,while Completing Operability Surveillance Following Maint on Sys Air Compressors,Diesel Generator Field Failed to Flash & Diesel Generator 2/3 Failed to Start on First Attempt.Cause Unknown ML20084A0611976-12-20020 December 1976 Telecopy Message of Ro:On 761220,empty Spent Fuel Cask Areas Found W/Removable Contamination ML20084L7821976-12-15015 December 1976 RO 50-237/1974-27A update.Three-yr Study of Use of phosphorus-bronze in Place of Teflon as Bushing Matl in torus-to-drywell Vacuum Breakers Provides No Justification for Replacement of Teflon Bushings ML20084A0991976-12-15015 December 1976 Telecopy Message of Ro:On 761215,4% Reduction Made in Allowable Maplhgr.Caused by Error in GE ECCS Analysis ML20084A2151976-12-13013 December 1976 RO 50-237/76-66:on 761113,HPCI Sys Injection Valve 2-2301-8 Failed.Valve Repairs to Be Completed at Next Outage ML20084A1391976-12-0606 December 1976 Telecopy Message of Ro:Empty Spent Fuel Shipping Cask Received W/Areas of Removable Surface Contamination ML20084A1811976-12-0202 December 1976 Telecopy Message of Ro:On 761202,empty Spent Fuel Shipping Cask Received W/Areas of Removable Surface Contamination ML20084R9111976-11-19019 November 1976 Telecopy Ro:On 761119,potential HPCI Design Error Discovered Which Could Cause Failure of HPCI Valve MO3-2301-8 During Certain Postulated Conditions.Caused by Design Wiring Problem.Valve Placed out-of-svc in Open Position ML20084R9181976-09-20020 September 1976 Telecopy Ro:On 760914,during Reactor Power Operation, Primary Containment Oxygen Content Found Greater than 4%. Caused by Terminated Unit Shutdown After Sys Min Load Problems Developed ML20084R5841976-06-15015 June 1976 Suppl Rept to ROs 50-249/75-10A,11A & 33A:motors Replaced on Valves 3-1402-4A & 3-1501-5A & Original Motors Sent to Manufacturer for Evaluation.Valve Trips Occurred Due to Undersized Overload Heaters.Mods Initiated ML20090E3751976-03-25025 March 1976 Telecopy Ro:On 760325,through-wall Crack Indication Found on HPCI Steam Supply Line safe-end.Cause Not Stated ML20084S0111976-03-0303 March 1976 Telecopy Ro:On 760303,emergency Electrical Feed to 2/3 Standby Gas Treatment Sys B Unavailable While Sys a out-of- Svc for Filter Replacement.Caused by Diesel Generator out- of-svc Due to Loose Connection in Manual Control Circuit ML20084R9381976-02-18018 February 1976 Follow-up RO 50-249/74-29A:on 740924,through-wall Crack Discovered on Torus/Drywell Purge Line.Probably Caused by Slight Preloading,Resulting in Strain on Piping.Pipe Examined for Other Cracks & Repair Program Initiated ML20084N6301975-12-0808 December 1975 Telecopy Ro:On 751208,Bergen-Patterson Piping Restraint on Cleanup Sys 8-inch Supply Line Inside Drywell Failed Due to Loss of Hydraulic Fluid.Caused by Faulty Zirc Fitting.Zirc Fitting Replaced ML20084N6411975-12-0404 December 1975 Telecopy Ro:On 751204,intermediate Range Monitor 12 Instrument Setpoint Drifted Above Tech Spec Limit.Setpoint Corrected ML20084N6641975-12-0202 December 1975 Telecopy Ro:On 751201,offgas Activities Increased During Steady State Operations.Probably Caused by Fuel Degradation. Testing in Progress ML20090E4351975-11-17017 November 1975 Telecopy Ro:On 751116,quarterly Closure Time of IC MSIV Found Below Tech Spec Limit.Valve Repaired ML20090E4381975-11-0303 November 1975 Telecopy Ro:On 751103,torus Level Exceeded Tech Spec Limits. Caused by Water Being Pumped from Storage Tank to Torus During HPCI Surveillance Check ML20084N6691975-10-17017 October 1975 Ro:On 751008,portable Fuel Loading Chamber Containing 2 G SNM Declared Lost.Caused by Lack of Proper Storage.Rev of Nuclear Procedures Will Be Initiated ML20084N6791975-09-29029 September 1975 Telecopy Ro:On 750928,leak Discovered in Feedwater Heater 3D3 Normal Drain Line at Weld Attachment to 4 Inch Pipe Support.Caused by Undercut Weld During Original Installation ML20090E4551975-09-29029 September 1975 Telecopy Ro:On 750929,pressurizing 21-2 D/W Went to 3 Psig. Caused by Excess Nitrogen Added Through Normally Closed Manual Bypass Valve ML20090E4521975-09-29029 September 1975 Telecopy Ro:On 750929,HPCI Turbine Failed to Shut Down. Caused by Damaged Trip Solenoid Coil ML20090E4721975-09-11011 September 1975 Telecopy Ro:On 750911,diesel Generator Cooling Water Pump Breaker on Bus 28-3 Tripped ML20084N7031975-09-0808 September 1975 Telecopy Ro:On 750908,five of Eight Intermediate Range Monitoring Instrument Channels Failed to Respond During Reactor Startup.Caused by Open Cables Due to Personnel Contact ML20090E4951975-09-0202 September 1975 Telecopy Ro:On 750830,diesel Generator Tripped,Following Generator Cooling Water Pump Failure.Investigation Continuing ML20084N8591975-08-28028 August 1975 Telecopy Ro:On 750828,scram Bypass Switches PS3-263-51A & 51B Showed Instrument Drift Above Allowable Limit.Probably Caused by Inactivity Due to Refueling Outage ML20084N8611975-08-28028 August 1975 Telecopy Ro:On 750826,pressure Switches PS3-263-53A,53B & 53C Drifted Above Tech Spec Limit.Probably Caused by Inactivity Due to Refueling Outage ML20084N8531975-08-28028 August 1975 Telecopy Ro:On 750826,isolation Condenser Pressure Switches PS3-263-53A,53B & 53C Setpoints Above Tech Spec Limit. Probably Caused by Setpoint Drift Due to Inactivity During Refuel Outage ML20084N7411975-08-28028 August 1975 Telecopy Ro:On 750828,reactor Pressure Scram Bypass Switches PS3-263-51A & 51B Drifted Above Tech Spec Limit.Caused by Inactivity of Switches During Refueling Outage ML20084N9011975-08-27027 August 1975 RO 50-249/75-33:on 750728,suction Valve for LPCI Pump MO-3-1501-5A Tripped Twice on Thermal Overload.Caused by Defective Motor.Motor Replaced ML20084N8021975-08-25025 August 1975 Telecopy Ro:On 750824,during Instrument Surveillance,Scram Switches PS3-263-55A,B & C Found to Have Drifted.Apparently Caused by Inactivity ML20084N8741975-08-21021 August 1975 Telecopy Ro:On 750821,main Feed Breaker to Bus 34-1 Failed to Trip During Trip Testing.Cause Not Stated.Investigation Underway ML20084N8901975-08-0808 August 1975 Telecopy Ro:On 750808,isolation Condenser Condensate High Flow Switches 3-1349A & 3-1349B Failed to Trip within Tech Spec Limit.Apparently Caused by Instrument Setpoint Drift. Switches Reset ML20084N9111975-07-22022 July 1975 Telecopy Ro:On 750722,location of Broken Tack Welds on Jet Pump Restrainer Clamp Bolt Keepers Determined During Tv Exam of Jet Pumps 6 & 17.Cause Not Stated.Tack Welds Will Be Rewelded Under Water ML20084N9471975-06-27027 June 1975 Telecopy Ro:On 750627,during Overhaul Operations,Cracks Found on Collet Housing Portion of Control Rod Drive Housing Outer Tube.Cause Not Stated.Control Rod Drive Manufacturer Contacted to Determine Extent of Problems ML20084N9841975-06-0505 June 1975 Telecopy Ro:On 750605,actuation of Standby Liquid Control Sys Pump Discharge Release Valve Below Tech Spec Limit. Caused by Procedural Inadequacy ML20084P8051975-06-0202 June 1975 Telecopy of Ro:On 750330,during Refueling Outage Surveillance,Excessive Leakage Through Primary Containment Feedwater Isolation Check Valves 3-220-58B & 3-220-62B Observed.Caused by Failed Valve Disc Seal ML20084D3501975-05-16016 May 1975 Telecopy Ro:From 750421-23,personnel Were within Line of Sight of Core During Rod Withdrawal.Caused by Personnel Error.Operation Terminated When Violation Became Known ML20084D3921975-05-0808 May 1975 Ro:On 750507,control Rod Drive Return Line Check Valve Failed to Pass Local Leak Rate Test.Valve to Be Repaired Prior to Startup ML20084R4041975-04-29029 April 1975 Telecopy Ro:On 750429,HPCI High Temp Isolation Switches Drifted During Operations Exceeding Tech Spec Limit.Caused by Drift of 12 Sensors Found During Refueling Outage.Sensors Will Be Replaced W/Capillary Type Switches ML20084R4061975-04-28028 April 1975 Telecopy Ro:On 750428,HPCI High Temp Isolation Switches Drifted During Operations,Exceeding Tech Spec Limit.Caused by Drift of 12 Sensors Found During Refueling Outage. Switches Will Be Replaced W/Capillary Type Switches ML20085J9881975-04-23023 April 1975 Telecopy Ro:On 750423,during Refuel Outage Surveillance, Feedwater Check Valves 3-220-58A & 62A & Feedwater Line 3A Failed to Pass Leak Rate Test.Cause Not Stated ML20084R4431975-04-17017 April 1975 Telecopy Ro:On 750417,main Steam Line D Drywell Penetration X105D Failed to Pass Containment Local Leak Rate Tests. Caused by Broken Testline Which Penetrates Bellows Type Penetration Between Primary & Secondary Bellows ML20084T0331975-04-0404 April 1975 RO 50-249/75-18:on 750324,during Surveillance Testing,Core Spray Valve 3-1402-4A Failed to Close Electrically.Caused by Fault in Motor Operator.Valve Closed Manually ML20084R5631975-04-0303 April 1975 ROs 50-249/75-18,17 & 16:on 750304,LPCI Valve 3-1501-5A Experienced Thermal Trip After Going Closed.Cause Unknown. Valve Returned to Open Position ML20084E0571975-03-21021 March 1975 Telecopy Ro:On 750319,field Failed to Flash on Diesel Generator While Trying to Return Generator to Svc.Cause Not Stated.Investigation in Progress 1994-11-04
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20249C8491999-09-30030 September 1999 1999 Third Quarter Rept of Completed Changes,Tests & Experiments Evaluated,Per 10CFR50.59(b)(2), for Dresden Nuclear Power Station. 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 ML20210R6081999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Dresden Nuclear Power,Units 1,2 & 3.With ML20209E1291999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Dresden Nuclear Power Station,Units 1,2 & 3.With ML20209J3481999-06-30030 June 1999 1999 Second Quarter Rept of Completed Changes,Tests & Experiments, Per 10CFR50.59.With ML20210D3071999-06-30030 June 1999 Corrected Page 8 to MOR for June 1999 for DNPS Unit 3 ML20195G6381999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Dresden Nuclear Power Station,Units 1,2 & 3.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 ML20206N2821999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Dresden Nuclear Power Station,Units 1,2 & 3.With ML20206B1901999-03-31031 March 1999 First Quarter Rept of Completed Changes,Tests & Experiments Per 10CFR50.59 for Dresden Nuclear Power Station. with ML20205N7491999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Dresden Nuclear Power Station,Units 1,2 & 3.With ML20207M6921999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Dresden Nuclear Power Station,Units 1,2 & 3.With ML20207E9311999-02-26026 February 1999 Part 21 Rept Re Sprague Model TE1302 Aluminum Electrolytic Capacitors with Date Code of 9322H.Caused by Aluminum Electrolytic Capacitors.Affected Capacitors Replaced ML20199M0891999-01-22022 January 1999 Part 21 Rept Re Failure of Square Root Converters.Caused by Failed Aluminum Electrolytic Capacitory Spargue Electric Co (Model Number TE1302 with Mfg Date Code 9322H).Sent Square Root Converters Back to Mfg,Barker Microfarads,Inc ML20199D3261998-12-31031 December 1998 10CFR50.59 SER for 1998-04 Quarter, of Changes,Tests & Experiments.With ML20199C8951998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Dnps,Units 1,2 & 3 ML20205M7061998-12-31031 December 1998 Unicom Corp 1998 Summary Annual Rept. with ML20197G8591998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Dresden Nuclear Power Station.With ML20196A4191998-11-19019 November 1998 Safety Evaluation Accepting QA TR CE-1-A,Rev 66 Re Changes in Independent & Onsite Review Organization by Creating NSRB ML20196J0061998-11-19019 November 1998 Rev 66 to Topical Rept CE-1-A, QA Program ML20195D2861998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Dresden Nuclear Power Station.With ML20154L3681998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Dresden Nuclear Power Station,Units 1,2 & 3.With ML20154N4131998-09-30030 September 1998 1998 Third Quarter 10CFR50.59 Rept, for Dresden Nuclear Power Station of Completed Changes,Tests & Experiments ML20153C5061998-09-21021 September 1998 SER Accepting Qualified Unit 1 Supervisor Initial & Continuing Training Program for Dresden Nuclear Power Station,Unit 1 ML20151Y2711998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Dresden Nuclear Power Station,Units 1,2 & 3.With ML20237E2331998-08-21021 August 1998 Revised Pages of Section 20 of Rev 66 to CE-1-A, QA Topical Rept ML20237A7161998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Dresden Nuclear Power Station,Units 1,2 & 3 ML20236Q5851998-06-30030 June 1998 1998 Second Quarter 10CFR50.59 Rept, for Dresden Nuclear Power Station of Completed Changes,Tests & Experiments ML20236F8131998-06-30030 June 1998 Rev 0 to Defueled SAR Dresden Nuclear Power Station Unit 1 Commonwealth Edison Co ML20236T8331998-06-30030 June 1998 COLR for Dresden Station Unit 3,Cycle 15 ML20236T8391998-06-30030 June 1998 Rev 1 to EMF-96-141, Dresden Unit 3 Cycle 15 Reload Analysis Rept ML20236M6041998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Dresden Nuclear Power Station,Units 1,2 & 3 ML20248M3021998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Dresden Nuclear Power Station,Units 1,2 & 3 ML20248F3531998-05-21021 May 1998 Part 21 Rept Re Electronic Equipment Repaired or Reworked by Integrated Resources,Inc from Approx 930101-980501.Caused by 1 Capacitor in Each Unit Being Installed W/Reverse Polarity. Policy of Second Checking All Capacitors Is Being Adopted ML20247F3391998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Dresden Nuclear Power Station,Units 1,2 & 3 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 ML20216D4411998-03-31031 March 1998 First Quarter Rept of Completed Changes,Tests & Experiments for 10CFR5059 ML20216C9651998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Dresden Nuclear Power Station,Units 1,2 & 3 ML20216E2531998-02-28028 February 1998 Monthly Operating Repts for Feb 1998 for Dresden Nuclear Power Station ML20202F7831998-01-31031 January 1998 Monthly Operating Repts for Jan 1998 for Dresden Nuclear Power Station ML20199K1651998-01-23023 January 1998 Rev 65h to Topical Rept CE-1-A, Comm Ed QA Tr ML20198P5321997-12-31031 December 1997 Monthly Operating Repts for Dec 1997 for Dresden Nuclear Power Station ML20198P7021997-12-31031 December 1997 Fourth Quarter Rept of Completed Changes,Tests & Experiments Per 10CFR50.59 ML20216D3611997-12-31031 December 1997 Unicom Corp 1997 Summary Annual Rept ML20203F8781997-11-30030 November 1997 Monthly Operating Repts for Nov 1997 for Dresden Nuclear Power Station ML20199B0701997-10-31031 October 1997 Monthly Operating Repts for Oct 1997 for Dresden Nuclear Power Station ML20217H7201997-09-30030 September 1997 Monthly Operating Repts for Sept 1997 for Dresden Nuclear Power Station,Units 1,2 & 3 ML20210V2401997-09-19019 September 1997 Rev 65g to Topical Rept CE-1-A, Comm Ed QA Manual ML20216J3781997-08-31031 August 1997 Monthly Operating Repts for Aug 1997 for DNPS ML20210H5511997-07-31031 July 1997 Monthly Operating Repts for July 1997 for DNPS IAW RG 1.16 & GL 97-02 1999-09-30
[Table view] |
Text
- p m Com Figrs. e lth Edison E'
, p , l, One .tiorul Plata. Chictgo, Ilknoy_s 'w/
/ Addr;ss R: ply to: Pnst Offica Box 767
- Chicago Illinois 60690 50 249
'BBS LTR #699-75 Dresden Nuclear Power Station R. R 61 Morris, Illinois. 60450 October 17, 1975
/o Mr. James G. Keppler, Regional Director [;
Directorate of Regulatory Operation-Region III (./
, U. S. Nuclear Regulatory Cor:nission, , fy 799 Roosevelt Road Glen Ellyn, Illinois 60137
SUBJECT:
REPORT OF LOSS OF SPECIAL NUCLEAR IMTERIAL IN ACCORDU!CE WITE 10CFR 70.52
References:
- 1) Title 10 of Code of Federal Regulations part 70 section 70 52 (a)
- 2) Notification of Region III of U. S. Nuclear Regulatory Comission Oral: Vr. P. Johnson, 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br /> on October 8, 1975 Report Date: October 17, 1975 Occurrence Date: October 8, 1975 Facility: Dresden Nuclear Power Station, Morris, Illinois IDENTIFICATION OF OCCURRECE On October 8,1975, a portable Fuel Loading Chamber (FLC) containing two grams of Special Nuclear Material (Sh"4) was declared lost. W.e SNM was 93 355 enriched uranium - 235 CONDITIONS PRIOR TO CCCURRE!CE Unit-3 was operating at a power level of 770 MWe following the unit's third partial refueling outage.
DESCRIPTION OF OCCURREJCE On April 18, 1975, five FI4's were sent from Quad Cities Nuclear Fower Station to Dresden. The FIf's were packaged in the following manner:
Three clean FLC's were loaded into one 55-gallon drum; two contaminated FLC's were loaded in a second 55-callon drum. Two FLC's in each drum were sent with 8306080418 751017
- PDR ADOCK 05000249 S PDR COPY SENT REGION - ,
h/
.- p m p
3
. U V associated cables attached to then. The fifth FIE (a clean spare) was put into a plastic bag, wrapped in rags, and placed in the bottom of the drun containing the other two clean' FIC's. Both drums were bolted closed.
The FLC's were received at Dresden on April 18, 1975 On April 19 the two drums Were transferred to the refueling floor of the reactor building and stored on top of the Unit 2/3 new fuel vault until April 27, 1975 On April 27, two instrument mechanics (IM's) opened the drums containing the FIC's and inspected the dru=s' contents. The IM's noted the presence of the four FIC's with cables and the fifth FIE wrapped in rags before leaving the area.
On April 28, three IM's were sent to inspect the FID's prior to installation in the reactor. The IM's unloaded the four FIE's with cables attached but did not look for a fifth FIE. After the four FIE's had been removed, the two 55-gallon
, drums were stored on the south wall of th,e Unit-3 refueling floor, between the reactor head storage area and the Unit-3 fuel pool.
From April 27 to August 6,1975, major activities on the refueling floor included out-of-core sipping, feedwater sparger replacement, and local power range monitor replacement.
On August 6,1975, as preparations for fuel reloading of Unit-3 were being made, the spare FIE was noted to be missing by the fuel handling foreacn. The nuclear materials custodian and assistant superintendent were notified, and a search was made of the reactor building, with negative results. Further searching was postponed until after completion of the Unit-3 fuel loading since fuel handlers were conducting the search.
Extensive searches of the Unit 2/3 reactor building were conducted from August 26 to September 1, again without success. The refueling of Unit-1 in addition to fuel handler personnel radiation exposure problems necessitated delays in the searching schedule. During these delays, drum movements out of the reactor building were restricted.
On October 7 and 8 a complete and thorough search was made of the ' reactor building, again with negative results. On Cetober 8 at 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br />, the missing FIL was declared lost. Notifications of the loss, i*ncluding an oral report to NRC Region III Inspector P. Johnson who was on-site, were made immediately. -
DESIGNATION OF APPARET CAUSE OF OCCURRENCE The primary cause of the occurrence was the lack of proper storage for the FIE's.
Although there is a special storage area set aside for nuclear fuel, special storage is not provided for components which contain small but reportable amounts of uranium. A lack of administrative controls for the packaging, movement, and storage of FID's was a contributing cause of this occurrence. Commonwealth Edison Nuclear Procedures do not address the problem of handling small, reportable amounts of Special Nuclear Materials.
ANALYSTS OF OCCURRENCE During the period from April 27 to August 6, the only operation involving the use of a cut:stantial number of 55-gallon drums was the feedwater sparger replacement job. The dru.'is were used'for the disposal.of' dry active. waste (DAW) resulting from
r
$~ 1
, the job, and for stor:gn of contaminated toolo. Drums containing DAW were sent to the Un.t 2/3 radwaste barreling area and were eventually transported to Sheffield, Illinois for burial. Drums used for tool storage were thoroughly inspected without success; however, one of the two FIL shipnent drums was discovered during this inspection.
Therefore, it is cons'idered highly probable that either the missing FIf is buried with waste at Sheffield, or it is still on-site at some unknown location. In either case, the consequences to the safety of plant personnel or the public are minimal. This conclusion is based on the following considerations:
a) the amount of uranium involved was small (2 grams); b) the uranium had not
- been irradiated and consequently had minimal activity (less than one millicurie and a dose rate of less than O.T milli-Rem / hour at contact); and c) the uranium was in a solid form, encapsulated in an air-tight container.
Finally, the possibility and significance of illegal diversion of nuclear material in the FI4 was exardned and ruled out for these reasons: 1. The amount of uranium was small, and the material was in a form which would not concern public safety as a result of illegal diversion (the uranium is coated on a capsuie which is then sealed within another capsule) 2. Only a very few management personnel of known reliability were aware that these instruments contained SGI 3 The security of Dresden station is adequate to ensure that the FIf could not easily be taken off-site in an'; form'other than radwaste 4 During the entire investigation of this occurrence, there was no hint of any conscious diversion of the FIf.
CORRECTIVE ACTICN Corrective actions to prevent a similar occurrence are listed below:
- 1. In the future, Dresde'n will ship FLC's only if they are properly packaged, including foam rubber for protection from jolts to the container.
- 2. The FIf's will be stored in the . Unit-1 fuel vault upon receipt, unless dose rates are unacceptably high; in that case, FLC's will be stored in a fuel pcol.
3 Movement of FIf's on-site will be accomplished under the same types of admin-istrative controls that govern movement of fuel assemblics.
4 FIL inventories will be made on a monthly basis.
5 A revision to CF':o nuclear proceda es will be initiated; the revision will deal with components containing small but reportable amounts of SNM.
^
, m 1
/
/ r s .
B. .
' dfg6 phenoon i
i Superi tendent j BBS:JMD:smp i File /NRC i
t e
j