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Category:ABNORMAL OCCURRENCE REPORTS (SEE ALSO LER & RO)
MONTHYEARML19343C2181975-12-23023 December 1975 AO 50-219/75-33:on 751212,during 6-month Load Test on Station a batteries,125 Volt Dc Distribution Ctr de-energized.Caused by Personnel Error in Following Procedure.Distribution Ctr re-energized ML20090C9991975-12-12012 December 1975 AO 75-33:on 751212,125-volt Dc Distribution Ctr of Station a Battery Inadvertently de-energized.Caused by Failure to Establish Proper Breaker Lineup Preparation for Conducting Battery Load Test.Procedure changed.W/751219 Memo ML19343C2191975-12-11011 December 1975 AO 50-219/75-32:on 751203,during Testing,Emergency Diesel Generator 1 Failed to Start When Simulated Loss of Power Condition Applied to Fast Start Logic Circuit.Caused by Failure of Relay to Operate Due to Varnish on Armature ML20126E8281975-12-0303 December 1975 AO 50-219/75-31:on 751124,during Operability Test of Torus to Drywell Vacuum Breakers,Alarm Sys 2 Failed to Annunciate in Control Room When V-26-4 Opened.Caused by Failure of Relay Due to Contacts Being Detective.Relay Replaced ML20090D0071975-11-25025 November 1975 AO 75-31:on 751124,drywell Vacuum Breaker Alarm Sys II Failed to Annunciate When Vacuum Breaker V-26-4 Opened. Caused by Component Failure.Corrective Action Under Investigation ML20090D0161975-11-0707 November 1975 AO 75-30:on 751106,low Reactor Pressure Core Spray Valve Permissive Pressure Switches Re 17 a & C Tripped at Pressure Less than Min Required Value.Caused by Switch Repeatability.Pressure Switches Recalibr ML20090D0601975-11-0606 November 1975 AO 75-29:on 751027,torus Drywell Vacuum Breakers Alarm Sys II Failed to Annunciate When Vacuum Breaker V-26-8 Opened. Caused by Sticking Microswitch ML20090D0761975-10-28028 October 1975 AO 75-29:on 751027,torus to Drywell Vacuum Breaker Alarm Sys II Failed to Annunciate When Vacuum Breaker V-26-8 Opened.Caused by Component Failure.Corrective Action Under Investigation ML20090D0941975-10-24024 October 1975 AO 75-28:on 751015,standby Gas Treatment Sys 1 Inoperable. Caused by Air Solenoid Valve Coil Failure.Defective Solenoid Coil Replaced ML20090D1141975-10-17017 October 1975 AO 75-27:on 751008,low Reactor Pressure Core Spray Valve Permissive Pressure Switches RE17B & D Tripped at Pressure Less than Min Required Value.Caused by Switch Repeatability. Pressure Switches Recalibr ML20090D1041975-10-16016 October 1975 AO 75-28:on 751015,standby Gas Treatment Sys 1 Inoperable. Caused by Air Solenoid Valve Coil Failure.Defective Solenoid Coil replaced.W/751016 ML20090D1341975-10-0808 October 1975 AO 75-27:on 751008,low Reactor Pressure Core Spray Valve Permissive Pressure Switches RE17B & D Tripped at Pressures Less than Min Required Value.Caused by Switch Repeatability. Pressure Switches Recalibr ML20090D1501975-09-23023 September 1975 AO 75-26:on 750923,emergency Svc Water Pump 52C Failed to Start Automatically During Routine Surveillance Test of Containment Spray Sys Ii.Caused by Failure of Contact Switch in Time Delay Relay 16 K4B.Relay Replaced ML20090D2071975-09-0808 September 1975 AO 75-24:on 750829,electromatic Relief Valve Pressure Switches 1A83C & 1A83D Tripped at Pressures in Excess of Max Allowable Value.Caused by Instrument Setpoint Repeatability. Switches Reset ML19291C2641975-09-0808 September 1975 AO 73-19:when Closing Signal Was Applied to Breaker S1A,loss of Power Occurred at 4160-volt Ac Bus 1A Causing Trip of Various Pumps.Caused by Incorrect Setting of Current Transformer Ratio Matching Taps.Taps Set Properly ML20090D1941975-09-0808 September 1975 AO 75-25:on 750829,stack Gas Sample Sys Failed to Monitor Stack Releases Continuously While Reactor Was in Unisolated Condition.Caused by Malfunctioning Pump Lubricator.Thermal Overload Protection Reset ML20090D2151975-09-0202 September 1975 AO 75-24:on 750829,electromatic Relief Valve Pressure Switches 1A83C & 1A83D Tripped at Pressures in Excess of Max Allowable Value.Caused by Instrument Setpoint Repeatability. Switches Reset ML20090D2011975-09-0202 September 1975 AO 75-25:on 750829,stack Gas Sample Sys Failed to Monitor Stack Releases Continuously While Reactor Was in Unisolated Condition.Caused by Malfunctioning Pump Lubricator.Thermal Overload Protection Reset ML20090D2241975-08-21021 August 1975 AO 75-23:on 750817-20,stack Effluent for Iodine & Particulates Not Monitored.Caused by Personnel Error.Filter Installed in Operating Stack Gas Sampling Train ML20090D2261975-08-11011 August 1975 Preliminary AO-50-219/75-22:on 750810,stack Gas Sample Line Low Flow Alarm Received.Caused by Stack Gas Sample Pump a Not Running.Thermal Overload Protection Reset ML20090D2471975-08-0404 August 1975 Preliminary AO-50-219/75-21:on 750801,during Routine Surveillance on B Isolation Condensor Sys,Steam Line Valve V-14-32 Failed to Close on Simulation of Steam Line High Flow.Caused by Low Torque Switch Setting.Torque Increased ML20090D2521975-07-17017 July 1975 AO 50-219/75-19:on 750708,during Monthly Surveillance Test on Reactor High Pressure Scram Sensors,Re 03A,B,C & D, A,B & D Tripped Above Normal Trip Points.Caused by Switch Repeatability.Sensors Recalibr ML20090D2561975-07-0909 July 1975 Preliminary AO 50-219/75-19:on 750708,during Monthly Surveillance Test on Reactor High Pressure Scram Sensors,Re 03A,B,C & D,A,B & D Tripped Above Normal Trip Points.Caused by Switch Repeatability.Sensors Recalibr ML20084E1151975-07-0101 July 1975 RO 50-219/75-18:on 750623,two 8-1/2 Inch Handhole Covers in Standby Gas Treatment Filter Train Not in Place.Cause Unknown.Handhole Covers Repositioned & Secured ML20090D2741975-06-27027 June 1975 AO 50-219/75-17:on 750619,during Surveillance Test,Core Spray Sys Parallel Isolation Valve V-20-15 Failed to Demonstrate Operability.Caused by Broken Tab on B Phase of Valve Motor Breaker Stab.Stab Replaced ML20090D2661975-06-24024 June 1975 Preliminary AO 50-219/75-18:on 750623,handhole Covers in Standby Gas Treatment Filter Train 1-1 Not in Place.Cause Under Investigation.Covers Repositioned & Secured ML20090D2781975-06-24024 June 1975 AO 50-219/75-16:on 750614,electromatic Relief Valve Pressure Switches 1A83P & E Tripped at Pressures Exceeding Tech Spec Limit.Caused by Instrument Setpoint Drift.Switches Reset ML20090D2731975-06-19019 June 1975 Preliminary AO 50-219/75-17:on 750619,during Surveillance Test,Core Spray Sys Parallel Isolation Valve V-20-15 Failed to Demonstrate Operability.Caused by Broken Tab on B Phase of Valve Motor Breaker Stab.Stab Replaced ML20090D2901975-06-16016 June 1975 Preliminary AO 50-219/75-16:on 750614,electromatic Relief Valve Pressure Switches 1A83B & E Tripped at Pressure Exceeding Tech Spec Limit.Caused by Instrument Setpoint Drift.Switches Reset ML20090D6561975-06-0606 June 1975 AO-50-219/75-14:on 750529,during Surveillance Test of Containment Spray Pump Operability,Essential Svc Water Pump 1-2 Failed to Develop Sufficient Discharge Pressure.Caused by Dirt in Check Valve V-3-68.Valve Cleaned & Repaired ML20090D2971975-06-0606 June 1975 AO 50-219/75-15:on 750530,calculations of TIP Traces Indicated Total Peaking Factor in One Core Location in Excess of Value of Pf Given in Tech Specs.Caused by Lack of Operating Experience W/New Core Loading ML20090D2981975-06-0202 June 1975 Preliminary AO 50-219/75-15:on 750530,calculations of TIP Traces Indicated Total Peaking Factor in One Core Location in Excess of Value of Pf Given in Tech Specs.Caused by Lack of Operating Experience W/New Core Loading ML20090D6581975-05-30030 May 1975 Preliminary AO-50-219/75-14:on 750529,during Surveillance Test of Containment Spray Pump Operability,Essential Svc Water Pump 1-2 Failed to Develop Sufficient Discharge Pressure.Caused by Dirt in Check Valve V-3-68.Valve Cleaned ML20090D6611975-05-14014 May 1975 AO-50-219/75-13:on 750507,during Surveillance Test,Time Delay Relay 6Kll Failed to de-energize within 15 After Pressure Sensor RE-15C Tripped.Caused by Component Failure.Relay 6Kll Replaced ML20090D6641975-05-0707 May 1975 Preliminary AO-50-219/75-13:on 750507,during Surveillance Test,Time Delay Relay 6Kll Failed to de-energize within 15 After Pressure Sensor RE-15C Tripped.Caused by Component Failure.Relay 6Kll Replaced ML20090D6531975-05-0606 May 1975 AO-50-219/75-12:on 750426,low Reactor Pressure Core Spray Valve Permissive Pressure Switches Re 17B & C Found to Trip at Pressure Less than Tech Spec Value.Caused by Switch Repeatablilty.Switches Recalibr ML20090D6701975-04-28028 April 1975 Preliminary AO-50-219/75-12:on 750426,low Reactor Pressure Core Spray Valve Permissive Pressure Switches Re 178 & C Found to Trip at Pressure Less than Tech Spec Value.Caused by Switch Repeatability.Switches Recalibr ML20090D6751975-04-18018 April 1975 AO-50-219/75-11:on 750410,leakage of Main Line Drain & Bypass Line Exceeded Tech Spec Rate.Caused by Failure of Packing on Valve V-1-110.Valve to Be Repacked ML20090D7001975-04-14014 April 1975 AO-50-219/75-10:on 750404,reactor Bldg to Torus Vacuum Breaker Valves V-26-16 & 18 Leak Rates Exceeded Tech Spec Limits.Caused by Component Failure.Valves Adjusted &/Or Repaired ML20090D6811975-04-11011 April 1975 Preliminary AO-50-219/75-11:on 750410,leakage of Main Line Drain & Bypass Line Exceeded Tech Spec Rate.Caused by Failure of Packing on Valve V-1-110.Valve to Be Repacked ML20090D7131975-04-0808 April 1975 AO-50-219/75-09:on 750329,breaker 1C Tripped Resulting in Fault on Bus 1C.Caused by Fault on Cable 86-25.Cables Replaced ML20090D7061975-04-0707 April 1975 Preliminary AO-50-219/75-10:on 750404,reactor Bldg to Torus Vacuum Breaker Valves V-26-16 & 18 Leak Rates Exceeded Tech Spec Limits.Caused by Component Failure. Valves Adjusted &/Or Repaired ML20090D7271975-04-0303 April 1975 AO-50-219/75-08:on 750325,power Operation Continued W/ Average Linear Heat Generation Rate of Fuel Assemblies in Excess of Max Linear Heat Generation Rate.Caused by Failure to Properly Monitor Reactor Core.Rate Reduced ML20090D7211975-03-31031 March 1975 Preliminary AO-50-219/75-09:on 750329,breaker 1C Tripped Due to Fault on Bus 1C.Caused by Fault on Cable 86-25.Cables Replaced ML20090D7651975-03-27027 March 1975 AO-50-219/75-07:on 750319,during Standby Gas Treatment Sys (SGTS) Test,Dehumidifying Heater EHC-1-5 in SGTS 1 Failed to Energize.Caused by Plugged Orifice in Air Supply to Controller.New Type of Differential Relay Installed ML20090D7361975-03-26026 March 1975 Preliminary AO-50-219/75-08:on 750325,power Operation Continued W/Average Linear Heat Generation Rate of Fuel Assemblies in Excess of Max Linear Heat Generation Rate. Caused by Improper Reactor Core Monitoring.Rate Reduced ML20090D7761975-03-20020 March 1975 Preliminary AO-50-219/75-07:on 750319,during Stanby Gas Treatment Sys (SGTS) Test,Dehumidifying Heater EHC-1-5 in SGTS 1 Failed to Energize.Caused by Plugged Orifice in Air Supply to Controller.New Type of Relay Installed ML20090D7801975-03-19019 March 1975 AO-50-219/75-06:on 750310,stack Gas Sample Sys Failed to Continuously Monitor Stack Releases While Reactor in Unisolated Condition.Caused by Circuit Design.Request to Modify Circuit for Stack Gas Sample Pumps Submitted ML20090D7901975-03-13013 March 1975 AO-50-219/75-05:on 750306,during Monthly Surveillance Test, Containment Spray Pump 51A Failed to Start When Subjected to Simulated Signals.Caused by Breaker Trip Bar Failing to Reset After Previous Breaker Trip.Trip Bar Bushings Cleaned ML20090D7811975-03-11011 March 1975 Preliminary AO-50-219/75-06:on 750310,stack Gas Sample Sys Failed to Monitor Stack Releases While Reactor in Unisolated Condition.Caused by faulty-circuit Design 1975-09-08
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217K4451999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Oyster Creek Nuclear Generating Station.With ML20211P6731999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Oyster Creek Nuclear Generating Station.With ML20211A7051999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Oyster Creek Nuclear Station.With ML20209G0631999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Oyster Creek Nuclear Generating Station.With ML20212H5491999-06-18018 June 1999 Non-proprietary Rev 4 to HI-981983, Licensing Rept for Storage Capacity Expansion of Oyster Creek Spent Fuel Pool ML20195E7961999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Oyster Creek Nuclear Generating Station.With ML20206N7431999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Oyster Creek Nuclear Generating Station.With ML20205P5401999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Oyster Creek Nuclear Generating Station.With ML20204C8201999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Oyster Creek Nuclear Generating Station.With ML20199E4671998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Oyster Creek Nuclear Generating Station.With ML20195E8321998-12-31031 December 1998 10CFR50.59(b) Rept of Changes to Oyster Creek Sys & Procedures, for Period of June 1997 to Dec 1998.With ML20198D2091998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Oyster Creek Nuclear Generating Station.With ML20195J8591998-11-12012 November 1998 Rev 11 to 1000-PLN-7200.01, Gpu Nuclear Operational QA Plan ML20195C4271998-11-0606 November 1998 Safety Evaluation Supporting Proposed Ocnpp Mod to Install Core Support Plate Wedges to Structurally Replace Lateral Resistance Provided by Rim Hold Down Bolts for One Operating Cycle ML20155J3021998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Oyster Creek Nuclear Generating Station.With ML20154R4981998-10-20020 October 1998 Core Spray Sys Insp Program - 17R ML20154L3051998-10-14014 October 1998 Safety Evaluation Accepting Licensee Request to Defer Insp of 79 Welds from One Fuel Cycle at 17R Outage ML20154Q3371998-09-30030 September 1998 Rev 8 to Oyster Creek Cycle 17,COLR ML20154L5571998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Oyster Creek Nuclear Generating Station.With ML20151V6311998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Oyster Creek Nuclear Generating Station.With ML20237D5691998-08-31031 August 1998 Rev 0 to MPR-1957, Design Submittal for Oyster Creek Core Plate Wedge Modification ML20237D5711998-08-18018 August 1998 Rev 0 to SE-000222-002, Core Plate Wedge Installation ML20237B0131998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Oyster Creek Nuclear Generating Station ML20236R0511998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Oyster Creek Nuclear Generating Station ML20249B2981998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Oyster Creek Nuclear Station 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 ML20247F1891998-05-0505 May 1998 Risk Evaluation of Post-LOCA Containment Overpressure Request ML20247G0581998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Oyster Creek Nuclear Generating Station ML20216K0341998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Oyster Creek Nuclear Generating Station ML20151Y4651998-03-31031 March 1998 Non-proprietary Version of Rev 1 to GENE-E21-00143, ECCS Suction Strainer Hydraulic Sizing Rept ML20217A4631998-03-23023 March 1998 Safety Evaluation Accepting Use of Three Heats/Lots of Hot Rolled XM-19 Matl in Core Shroud Repair Assemblies Re Licenses DPR-16 & DPR-59,respectively ML20212E2291998-03-0404 March 1998 Rev 11 to 1000-PLN-7200,01, Gpu Nuclear Operational QAP, Consisting of Revised Pages & Pages for Which Pagination Affected ML20216J0841998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Oyster Creek Nuclear Generating Station ML20203B2781998-02-16016 February 1998 10CFR50.59(b) Rept of Changes to Oyster Creek Systems & Procedures ML20203A3801998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Oyster Creek Nuclear Generation Station ML20198P1791997-12-31031 December 1997 Monthly Operating Rept for Dec 1997 for Oyster Creek Nuclear Station ML20217C7591997-12-31031 December 1997 1997 Annual Environmental Operating Rept for Oyster Creek Nuclear Generating Station ML20197E9131997-11-30030 November 1997 Monthly Operating Rept for Nov 1997 for Oyster Creek Nuclear Station ML20199E4561997-11-13013 November 1997 Safety Evaluation Accepting Ampacity Derating Analysis in Response to NRC RAI Re GL-92-08, Thermo-Lag 330-1 Fire Barriers, for Plant ML20199D4381997-10-31031 October 1997 Monthly Operating Rept for Oct 1997 for Oyster Creek Nuclear Station ML20202E8511997-10-21021 October 1997 Rev 0 to Scenario 47, Gpu Nuclear Oyster Creek Nuclear Generating Station Emergency Preparedness (Nrc/Fema Evaluated) 1997 Biennial Exercise. Pages 49 & 59 of Incoming Submittal Were Not Included ML20211M9481997-10-0303 October 1997 Supplemental Part 21 Rept Re Condition Effected Emergency Svc Water Pumps Supplied by Bw/Ip Intl Inc to Gpu Nuclear, Oyster Creek Nuclear Generation Station.No Other Nuclear Generating Stations Effected by Notification ML20198J7361997-09-30030 September 1997 Monthly Operating Rept for Sept 1997 for Oyster Creek Nuclear Generating Station ML20211B7461997-09-24024 September 1997 Part 21 Rept Re Failure of Emergency Service Water Pump Due to Threaded Flange Attaching Column to Top Series Case Failure.Caused by Dissimilar Metals.Pumps in High Ion Svc Will Be Upgraded to 316 Stainless Steel Matl ML20210V0181997-08-31031 August 1997 Monthly Operating Rept for Aug 1997 for Oyster Creek Nuclear Generating Station ML20210L2961997-07-31031 July 1997 Monthly Operating Rept for Jul 1997 for Oyster Creek Nuclear Station ML20149F9961997-07-18018 July 1997 Safety Evaluation Re Gpu Nuclear Operational Quality Assurance Plan,Rev 10 for Three Mile Island Nuclear Generating Station,Unit 1 & Oyster Creek Nuclear Generating Station ML20196H0111997-07-11011 July 1997 Special Rept 97-001:on 970620,removed High Range Radioactive Noble Gas Effluent Monitor (Stack Ragems) from Service to Allow Secondary Calibr IAW Master Surveillance Schedule. Completed Calibr on 970628 & Returned Stack Ragems to Svc ML20210L3081997-06-30030 June 1997 Corrected Page to MOR for June 1997 for Oyster Creek Nuclear Generating Station ML20141H2051997-06-30030 June 1997 Monthly Operating Rept for June 1997 for Oyster Creek Nuclear Station 1999-09-30
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M ADISoN AVENUE AT PUNCH DoWL Ho AD e MoRRisToWN. N.J. 07960 e 539-6111 August 31, 1973 Oh f
Mr. A. Giambusso S A +
Deputy Director for Reactor Projects R E C EI V E.ggD Directorate of Licensing - SEP4 1973 ;
United States Atomic Energy Commission 9- U.S. A % g Washington, D. C. 20545 Commia;on /g Regulatory
Dear Mr. Giambusso:
% Maul Sectibn y
4 to
Subject:
Oyster Creek Station Docket No. 50-219 Outside Tank Activity The purpose of this letter is to report a violation of the Technical Specification, Paragraph 3.6.C.; whereas, the maximum amount of radioactivity, excluding tritium, neble gases, and isotopes with t ., <3 days contained in the radwaste storage tanks external to the radwaste bui kding, exceeded 10 curies.
This event is considered to be an abnormal occurrence as defined in the Technical Specifications, Paragraph 1.15.B. Notification of this event, as required by the Technical S})ecifications, Paragraph 6.6.2.a. , was made to the AEC Region I, Directorate of Regulatory Operations, on Thursday, August 23, 1973.
A routine analysis of the activity contained in the outside radwaste tanks was made and indicated the total activity to be 11.82 curies with 11.28 curies being contained in the waste surge tank. In reviewing the outside tank activity status sheets and the radwaste logs, an assumption can be made that the activity has been in excess of 10 curies since Friday morning, August 17. The apparent reason for this activity not being detected in samples taken Friday morning, Saturday morning, and Monday morning, was a failure to recirculate the tank for a sufficient period of time to clininate any stratification which nay have been present. This conclusio.1 was reached after a review by the chenical supervisor of Nedra sday morning's sample, when he noted that the octivity con-cent)ation of the water in the waste surce t ank was decreasing with no change in tank volume.
- Due to an apparent plugging of the waste concentrator tube aundle which became evident Wednesday, August J5, plans ucre initiated to replace the element. Coincident with thit event , some n ry Joa p!I hater from the uake-up syste. floot d r ains was ci rculated through t he radwaste floor drain processin" sysi c and essentir.!!y " acid cleaned" the piping. 1hc waste surge tank, which hmJ been drained, w , used t o accomadale waste input into the radwaste systens Uhili the concealto; Gr has being wintained. In subser[uent radiechemical analysee 8305100066 730031 PDR ADOCK 05000219 g PDR y, [d( gg7g
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Mr. Giambusso August 31, 1973 of the water added to the tank starting on Thursday, August 16, at 2:00 p.m.,
the activity in the tank was found to be primarily as a result of particulate [
f matter in suspension. A quantity of partictrlate material had been known to be in the tank from a prior inspection and plans made to have an outside concern i clean the tank and dispose of the waste. Due to the length of time required {
for this job, though, the tank had not yet been. made available for cleaning. I Iloweve r, in adding tat er to the tank on August 16 and 17, it can be shown by comparisoa of previous analyses of the tank contents, thht a quantity of solid or particulate material was added with the water and, consequently, caused a signifi cant increase in the total curie content of thp",# tank. The major con-Fri- .
stituents in the solids activity are 60Co, 58Co, and Pa. By 10:37 a.m., 8 day, August 17, approximately 33,000 gallons of water had been transferred to ,
the tank. No additional water has been added to the tank since that time.
With the return of the waste concentrator to service late Saturday night, August IS, overall water inventory in the various radwaste systems has slowly beca decreasing. As sufficient roo a is made in the tanks internal to the building, waste water from the surge tank will be transferred to reduce the over- >
all activity. The area surrounding the tank has been re-surveyed and reposted accordingly to encure proper radiation protection, lie will keep the regional compliance office advised as to the date the outside tank activity is reduced be-low 10 curies. Iloth operators and chemistry technicians have been advised that, in t he future, recirculation of the contents of the surge tank should be conducted f or a sut heient pericci of time to insure that proper representative sanples and subsequent analysis may he corapleted.
As noted in the .Techni cal Specifications , limiting the activity stored in the outside tanks to less than 10 curies, assures that in the extremely un-likely crent of c rupture of the tanks, the resulting activity discharged to the bay would not he greater than the maximun activity recomended as the li miting condition for operatioa for the annual total quentity released in effluents gi.ven in the proposed App s lix 1 to 10Ci:P50. Duc, in this case, to the activity being primarily as a result of parti cu lat e mat ter in suspension , it is not felt that the material vould be deposited in the bay, but rather would be in the surrounding soil, never to reach the bay, should the tant rupture. This event has not proJoced . hn: ard t o the publi c since no rele se of activity has occurred.
In o r.iei to uinimize the reoccurrei ce of this situat ion, we intend t o eleen out seditent f rc i the waste surge tank as soan e , conditions permit. Further, the eq my i s p repu i ny, for sub.?i.ttal to th: AE', shor t ly , a des cript ion of
- i r.n t fi c
- .n t . J:ficaticy t o t he easting Oy s ter Creek radwast e f aci li ty.
!lc are enelt ;ing for:y copie: e this report,
\'ery t ruly yours ,
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Subject:
t N>norn.n1 Occurrenco Rapv2 t. 33.)q___.
Tiso f011v.cing i:: a prc]irdn:try separt. lucing cu1nt.itt.ct) in complianco vif h the Tcchnica1 Specificationu parograph G.f.2. l a
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i SUD.]I:CT Violation f tha TcchnicAL Spec 1Eication, Caragrarh 1.G.c, h I
i uhcrcas the .nximum demunt at radlaactivi ty , cxcluding tritiuu, g
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nch10 gaso?,, and inatopit:= Wills L s.7 <3 daria containod in tho rad-wa :tc storaye tanhe external to the raduanta building exceeded 10 curies.
This event le considcccd to bc .1n abnorttal occurrence a3 defined in the Tedulical Spect t'ic.3 t.f.on , paragraph 1,153. 110t1[ication l
l l af thin event, as regulied by the Technical Spccificaticas, paracjraph 6.6.7.a, wan nada to Asc scgion 1, Directorate of Requ'atorij oparationn, by telephone on 0ednesday, August 2:1, l973r at 11 sC.I a.m. , and by telecopier at 4:15 p,cl.
S1TUATECI: A roulin analtjnin of thc nctivity contained in the outside radda.uth tanks sta3 mada .1nd indicated the total activity to be i
LL.R2 curins with 11,28 curies helby contained in the Tlast6 Surga l l
Tank. In reviening the outside tan l< activity statun shoctn and l the radwaste in]n, an annucptian can ha made that the activitt) -
E has been in cxccan cE 10 curies since t'riday t1'rning, AU'JU3t 17 l E
The apparent roancn for thi activity not helny detected in h fj L
sa; pics t.>kon Friday morning, Saturday morning, and Handay rarningi jl
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was a [ allure lo r circulata thn tank iar a nufficient Scried E
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of tiae to ellednate alv) =tratification which t ay have been pieeenL. lr
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FAvsH: cuc to an appar .t plugging of.the wasta conca ator tubc hundle which becain evident IIedn0]d.19, Augn5C 15, plans wara initiated Lu revluce lhe elesent. The vanle Surge Tank, which hdd cosentidllt) b&&n drnincd, yaR unCd to occQCDdatc Wastc input into tho radwasta syntc=. In suh=cejacnt rad 10 chemical analysc= uf the water added to the tank atarting on 'rhursday, Augu=t 16 1 at 2:00 p.m. Llw not1Vlty in the tanx van found to be primrlisj ng n result of pnticulato mattor in suspcnnian.
1 a quantity u[ p. Articulate tuterial had been known ta ha in tha tank Eram d Priat indt:Bullon eand a purchase ordOr has bccn AB80ed to an outelde concern to clean tha tank and dinporc cf tha wartc. Due to the length OE titM .t quixed Ecr this job, though, the tank had not yat been trade availabic Ear c1 caning. HowcVer, in adding Water to tha tank on Augn.3c !6 and 17, it can he Ghcun by comparinan of previcu= analyne: .of the tank contents, titat a quantity of solid or particulate saaterial Was ddded v.ith the Water. . It vis this additional ;
matcrial that caused a significant increase in the total curle i content of tha tank, Ry.10:37 a.m., Fridays August 17, apyrcxl-cutaly JJ,000 gallon: of water had been trans[ erred to the tank.
No additionni Water has b:en added to tha tank sincc that time, Kr:tsDLAL Acr1C:t; With the return of the flaste Concentrator to service late Saculday night, August 18, overall Water inventory in the vatloud rat.~'asta stistnmn han slculy bacn accccasing. As sufficient roact is mde in the tanks internal to the building, vaste vater from
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.' the Surge Ta ill bc tran=Eetied LQ roduce overall activity.
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The aton narrounding the tcou; has been to-survcyod and rc-panted uccordingly. nach arcritors ad chem 13try technician = hava hacn ddVlded thdl in tha 1Utura racirculdblon C[ th9 cCntent8 Ot' thc Sut00 Tank should be conduc! -! Eor Bufficiant poricd of tice to in?ura proper reprc=entet1Ve ennplen and nubacquant analysis twy be completed.
CA.ttrY nTm?rricr cn; A3 notod in tha Technical Syccification3, litrdting the activity 8 Cored in tho autside tanks to <10 curies assuro= that in the evant af a rupture of the t=rJ:s, the resulling activity nin - I charged to the bay would not bc greater then the ms::imum activity 1
recxmnded as tho limiting candition for operallon for the j armual LOLn1 quantity rc1casca in effluents efiven in the propc=cd i i
App ndix ! to 10CER50s Lue, in this ca3e, to tho activity being {
i primArily 4 2 a ranu).C of particulate t.uctet in eueten81cn, it.13 .b r
nut felt that the tuterial would bc dcposited in the bay, but i y
I rather uculd be in the surrounding 301.1, never to reach the bay, ?
should tha tank rupturc. !
Consequently, the algni.ficanca of thi: E l
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cvent is ninitral. E I
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Prepared beji __ { l- k .- b...'a- w. [nte f_ 23 73 7 .. . .~nm r .mmv~-- :-- -~- -
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Licensec: Jersey Cent % Power & Light Company I -
50-219 V ~
i,
!!. D. Thornburg, oAst Docket No.-
Chief, FSt.EB ,'
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i Abnormal occurrence: A0-73-18
- To (Name end wa.i; init: Ats a ria Amas RO:llQ (5)
DR Central Files (1) caTt The attached report from the subject licensee is Regulatory Standards (3) -
Dir. of Licensing (13j foruarded in accordance with RO Mnnual chnnter 1 P' 10 (Na me and w'*i/ SNIIIALS AEMAAK5 no Files v Central Ma'il & Files The action taken by the li_censee is considered mt appropriato. Followup will be performed durin?
the next innocction n's annron ~ite. Confee of l' fdoti (N ame .nJ we.O ptM ARAS i ,
- j. - , the report have been foruarded to the PDR, Local
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[ T; 1o , i PDR, NSIC, DTIE and State representatives. The
,ncility Operations < ~
__._I1 ra n ch licensec vill submit a 10 day written report to Pnwtsc CATE -
8/29/73 Licensing.
USE OTHER Saf t FOR ADDITIO*eaL REMARKS , g,y t d 1 0 -4en-o.
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