|
---|
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
--
~s O
Ccmm :lth Edis n onal PtagChicago, lHinois Q
@ One First Address Reply to: Post Office Sox 767 Chicago. lifinois 60690 Dresden Nuclear Power Station R. .R. #1 -
Morris, Illinois 60450 - .?x sy
,[f ,p I N>k WFW Ltr. #559-73 August 7, 1973 'I; i l (' W l
,./ Q U; '
.q~
\ . 4:. O. C Mr. A. Giambusso Deputy Director for Reactor Projects j[v$
- g Directorate of Licensing Al "' hA-U. S. Atecic Energy Cassission Washingten, D.C. 20545 SUBJET: LTCETSE DF'4-25. DRFSDni !mCIEAR P(MR STATION tntIT #3.
SECTICN 6.6.C.107 W5 T3""ICAL SPECIFICATICHS.
FAST C105t3E CF FSIV 3-203-13,
References:
- 1) Ietter frec W. P. Uorden to Mr. Giambusso dated December 8, 1972, concerning Fast Closure Time on lB" ISIV.
- 2) Notification of Region III of AEC Regulatory Operations.
Telephone: F. !! aura,1030 on July 30, 1973 Telegram: B. Grier, 1250 on July 30, 1973
- 3) Dv:gs: P + ID M-345
Dear !!r. Gia=busso:
This is to report a cendition relating to the operation of the unit, den during surveillance testing, rain steam isolation valve (!SIV) 3-203-1B was fcund to have a closure ti=a of 2.6 secs, dich is cutside the limits specified in the Technical Specifications (Table 3.7.1). These limits are 15 sees and a 3 secs.
PROBIm ATTD ItiVESTIGATIOPi At 0050, July 29, 1973, with the reactor at a power level of 50 MWe, quarterly ISIV ticing survenhnce was being conducted.
During these tests, it was discovered that IEIV 3-203-1B hcd a closure time of 2.6 seccnds, faster than the 3 second to 5 second limits specifiai in the Technical Specifications (Table 3.7.1). Both valves in the B" steam line were prenptly closed in accordance with section 3.7.2 of the Technical Specifications, and was naintained in that cc:xlition until a subsecuent shutdown. The ESlV's en the other three steam lines had closure times 'within the 3 second to 5 seccexi limits. -
a y/'4[ yy n ,
$$ MoSUo s
y M COPY SI2U REGION G100
, , Mr. A. Giambuseo August 7,1973 The limits specified on fast closure of the HSIV's are intended to prevent a rapid reactor isolation, and subsequent rapid reactor pressuri-sation and resulting relief valve operation. Closure of one }EIV in 2.6 seconds instead of 3 seconds does not significantly increase the pressure spike or the potential for relief valve operation. Additionally, any pressure transient free the fast clesure of one ISIV wouM be " softened" by the slower }SIV closure on the other three lines. Consequently, it is concluded that the fast closure of the 3-203-1B F3IV was of no safety significance to the public or plant personnel.
CCRREunvs ACTIC4 At present, Unit 3 is in the shutdown cotulition. Inspection of "lB" MSIV speed centrol will not be performed prior to letter issuance but will be made before unit startup.
A followup report will be issued to specify the results of the investigatien, the corrective actien taken, the resulting MSIV travel time, armi the date on which "B" steam line is returned to service.
Sincerely,
& ~ . b h s.s .
W. P. Wortien Superinterelent Dresden Station WPW:ID:jw ec: Pile /AECCorr. Cat.I
A Comm mith Edison l 50-237/249
'( *
,k} One First Nynal P1323. Crucago, tilinois p[\ Q' Address Reply to: Post Office Box 767 i Chicago Ilknois 60690 '
WPW Ltr.f572-73 Dresden Nuclear Power Station R. R. #1 , ,
JN Morris, Illinois 60450 g -h N' August 10, 1973 . .M, -
/4 4 U.N ?.b &
IG ~t.
AUG151973P QF Mr. A. Giambusso Deputy Director for Reactor Projects jg N ',> ..
"~?
h O/
, Director of Licensing n'j ,,qg U. S. Atomic Energy Co:: mission N '~7a Washington. D. C.
~
20545
SUBJECT:
LICENSE DPR-19/25, DRESDEN ?PJCLEAR PO'JER STATION, UNIT d2/3.
_ SECTIO:I 3.8.D OF Til?. TECit'iIC\L SPECIFICATIONS.
HIGH ACTIVITY 113 ABOVE GROUND TANK "B" FLOOR DRAIN SAMPLE TANK.
References:
- 1. Notification of Region III of AEC Regulatory Operations Telephone: G. Fiore111, 1400 hours0.0162 days <br />0.389 hours <br />0.00231 weeks <br />5.327e-4 months <br />, on 8-2-73.
Telegram: B. Crier, 15G0 hours, on 8-2-73.
- 2. Dwgs: P & ID M-44.
Dear Mr. Giambusso:
This letter is to reporr a condition relating to the operation of Unit 2/3 Radwaste at about 0820 hours0.00949 days <br />0.228 hours <br />0.00136 weeks <br />3.1201e-4 months <br />, August 2,1973. At this time the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> peried for reprocessing above ground tanks with radioactivity concentrations above 0.7 curies allowed by the Technical Specifications (Section 3.8.D) was exceeded by 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
PROBLEM At 0820 hours0.00949 days <br />0.228 hours <br />0.00136 weeks <br />3.1201e-4 months <br /> on August 1,1973 the processing of water to "B" Floor Drain Sample Tank from the Floor Drain Collector was completed and the B.F.D.S.T. was placed on recirculation for sampling. The sample results indicated the beta-gamma radioactivity to be 1.3x107 pCi/1. This concen-tration combined with a tank level of 82% resulted in a total curie content of 0.89 curies in the "B" Floor Drain Sample Tank.
Although the tank was promptly analyzed, there was a misunderstanding between laboratory and operational personnel concerning the radioactivity reporting. Therefore, action on reprocessing the water was delayed until the morning of August 2,1973 when another shif t foreman verified that "B" Floor Drain Sample Tank radioactivity was 1.3x107 pCi/1.(0215Aours).
I g
)f(lf b' ~
0,Ac+c Q
m7 - r - a gl
..<~rm COPY SEhT REGION $ ' W "7
[Z3D ..
u O O u, Mr. A. Giambusco August 10, 1973 In order to reduce the radioactivity of the water in the "B" Floor Drain Sample Tank to within Technical Specifications limits, at 1105 hours0.0128 days <br />0.307 hours <br />0.00183 weeks <br />4.204525e-4 months <br /> on August 2,1973, the "B" F.D.S.T. was partially transferred to the "B" Neutralizer Tank. At 1135 the concentration of 1.3x107 pCi/1 at a tank level of approximately 637. resulted in a curie content of 0.68 curies in the "B" F.D.S.T.
Before water could be transferred from the "B" Floor Drain Sample Tank to the "B" Neutralizer Tank, the "B" Neutralizer Tank had to be emptied. The Floor Drain Collector,which had filled up again, was transferred to the "B" Neutralizer Tank next. At 1105, August 2, the conditions existed that allowed the transferring of the "B" Floor Drain Sample Tank to the "B" Neutralizer Tark.
INVESTICATION A review was made of the procedures applicable to the incident.
It was determined that in following one operating procedure, the step requiring beta-gacca analysis of the Floor Drain Collector prior to processing was omitted. The delay in reprocessing the water in the "B" Floor Drain Sample Tank was caused by a misunderstanding between laboratory and operational personnel about the radioactivity reporting units.
CORRECTIVE ACTION Enough water in the "B" Floor Drain Sample Tank was transferred to the "B" Neutralizer Tank to reduce the curie content in the "B" F.D.S.T.
to within Technical Specifications.
A review of the appropriate procedures has been made with the personnel involved. In addition, a revision of the operating procedure, 2000-XX, paragraph B, has been ef fected to clarify the section requiring radioactivity analysis of the Floor Drain Collector prior to processing to the Floor Drain Sample Tanks.
EVA1UATION _
The presence of 0.89 curies in th.e "B" Floor Drain Sample Tank did not produce a hazard to the public since it was not released to the river and the tank beta-gamma radioactivity was reduced to below Technical Specifications 26 hours3.009259e-4 days <br />0.00722 hours <br />4.298942e-5 weeks <br />9.893e-6 months <br /> af ter the co11cetion of the first samples. If a failure of the "B" Floor Drain Sample Tank had occurred as described in Amendment #9,Section V.C.1 of the S.A.R., and the radioactivity contained in the tank had been released to the aquatic environment, the limits as I
specified in CFR 20.106 would not have been exceeded when averaged over one year.
i Sincerely, W. F. Worden Superintendent WFW:do
' ec: 4 File-AEC ' Corr. )