ML20084T738
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| ML20084T738 | |
| Person / Time | |
|---|---|
| Site: | Dresden, Indian Point  |
| Issue date: | 10/24/1972 |
| From: | Worden W COMMONWEALTH EDISON CO. |
| To: | Greer B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| Shared Package | |
| ML20084T730 | List: |
| References | |
| NUDOCS 8306240081 | |
| Download: ML20084T738 (1) | |
Similar Documents at Dresden, Indian Point | |
|---|---|
Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER)
MONTHYEARML20149G9861994-11-0404 November 1994
[Table view]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 ML20096H2301992-05-21021 May 1992 Special Rept:On 920504,south Side Lower Electrical Tunnel Detection Sys 8 Taken Out of Svc for Mod to Reposition Detection Sys Run of Conduit.Detection Sys Declared Operable on 920520 After Mod Completed & Sys Retested ML20235V5931989-03-0202 March 1989 Special Rept:During Cycle 6/7 Refueling Outage Scheduled from Feb-May 1989,openings Will Be Made in Plant Penetration Fire Barriers in Order to Install Various Mods. Fire Watches Posted & Fire Detection Tests Completed ML20210L6591986-04-11011 April 1986 Ro:On 860328,diesel Fire Pump Tripped & Would Not Restart During Repair of 860327 Fire Pump Leak.Fire Watches Established.Temporary Bypass Installed.Work Deferred on 860410 & Will Resume Late Apr ML20203P5411986-04-0707 April 1986 Ro:On 860311,fire Pump Taken Out of Svc to Perform Maint on Fire Main Supplied by Pump.Pump Out of Svc Beyond 7-day Limit Permitted by Tech Specs.Pump Will Be Returned to Svc in Approx 45 Days,Upon Completion of Repair Work ML20203P3461986-03-31031 March 1986 Ro:On 860328,diesel Fire Pump Tripped & Could Not Be Restarted.Fire Booster Pumps 11 & 12 Also Out of Svc.Cause Not Stated.Fire Booster Pump 12 & Diesel Fire Pump Returned to Svc ML20151R2921986-01-0303 January 1986 Ro:On 851127,high Pressure Water Protection Sys Fire Pump II Taken Out of Svc in Excess of 7-day Tech Spec Limit.Caused by Maint to Fire Main Supplied by Pump.Pump & Fire Main Returned to Svc on 851220 ML20137Q0251986-01-0202 January 1986 Ro:On 851219,post-maint Test Following Replacement of Fire Detection Alarm Terminal Block for Fan Cooler Unit 21 Not Performed.Caused by Personnel Oversight.Test Performed & Circuitry Repaired & Tested Successfully ML20151R4421985-11-0101 November 1985 Ro:On 850920,Halon Sys Rendered Inoperable in Excess of 14-day Tech Specs Limit.Caused by Closure of Control Bldg Dampers Following Transformer Chart & Actuation of Deluge Sys.Fusible Links Replaced & Dampers Restored on 851030 ML20101A6881984-11-16016 November 1984 Special Rept:On 841017,work Began to Make Openings in Several Penetration Fire Barriers to Execute Various Mods During Scheduled Maint/Insp Outage.Fire Watches Posted When Openings Existed ML20082R5531983-11-30030 November 1983 RO 83-43:two Independent Nonautomatic,Motor Operated Isolation Valves on Containment Spray Pump Discharge Pipes Found Closed & Deenergized Instead of Open & Deenergized,As Required.Caused by Operator Error.Valves Opened ML20082S6021983-10-17017 October 1983 Telecopy RO 50-286/83-006:on 831017,steel Plates Holding Seismic Restraint Collars Discovered Not in Place.Work Request Issued to Correct Condition Prior to Plant Returning to Svc ML20082S5961983-10-12012 October 1983 Telecopy RO 50-286/83-005:on 831011,drain Lines on Accumlators Determined Connected by Manual Valve.Caused by Design Error.Nonseismic Line Could Fail During Earthquake. Procedures Revised to Maintain Valve Closure ML20090H3621983-10-0505 October 1983 Ro:On 831004,138-kV Station Auxiliary Power Supply Lost When Pilot Wire Receiver Relay Tripped.Cause Under Investigation. Supply Reestablished to All 6.9-kV Buses.Also Reported Per Part 21 ML20076G3031983-08-0101 August 1983 Ro:On 830729,review of Log Sheets Determined Isolation Valve Seal Water Sys Violated Tech Specs.Corrective Action Taken to Assure Locally Indicated Pressure on Tank Maintained Per Tech Specs 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 ML20069A7781983-03-0202 March 1983 Ro:On 830301,shaft Matl Found in Square Motor Housing RHR Pump 22 Was Carbon Steel Instead of Stainless Steel.Change Does Not Involve Unreviewed Safety Question Based on Use for Fewer than 24 Calender Months.Equipment Will Be Replaced ML20083Q5091983-02-14014 February 1983 RO 83-003:on 830213,RCS Leakage from Packing on Valve 731 Exceeded Tech Spec Limit.Subsequent Analysis After Hot Shutdown Determined Leakage to Be within Tech Specs.Also Reported Per 10CFR21 ML20066G7691982-11-0909 November 1982 Ro:On 821108,upper End Plug from One Fuel Rod Found Lodged Between Upper End Plugs of Adjacent Fuel Rods within Assembly.Affected Assembly Will Not Be Returned to Core for Cycle 6.Also Reportable Per Part 21 ML20063B6511982-08-18018 August 1982 RO 82-32:on 820817,steam Generator 22 Blowdown Outer Isolation Valve CV1215A Closed.Caused by Failure of 1315A Solenoid Valve.Jumper Installed in Instrument Air Sys to Establish Blowdown.Also Reportable Per Part 21 ML20055B6011982-07-14014 July 1982 Telecopy Message of Ro:On 820713,while in Cold Shutdown During Refueling Outage,Testing of Pressurizer Safety Valves Indicated Setpoints for Pressure Control Valves 466 & 468 Below Tech Spec Limit ML20054L1441982-06-21021 June 1982 Ro:On 820520,Fire Pump 12 Removed from Svc to Repair Leaking Packing Gland.Pump Overhauled & Leaks Repaired.Pump Returned to Svc on 820527 ML20054J2391982-06-10010 June 1982 Ro:During Scheduled Sample Collection for May 1982,Windsor Farms Environ Sampling Station 51 Ceased Commercial Milk Production.Potential Replacement Locations Are Being Investigated ML20054F5441982-06-0909 June 1982 Ro:Provides Addl Info Re 820601 Diver Exposure in Excess of Limits.Review Conducted of Instrumentation Used in Radiation Surveys of Pool Immediately Prior to Exposure.One Alarming Dosimeter Used by Divers Found Inoperable 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 ML20054F5981982-06-0202 June 1982 Ro:On 820601,contractor Employee Experienced Personal Exposure Rate of 8.6 Rem While Working in Spent Fuel Pool. Encl Withheld (Ref 10CFR2.790) ML20052H1801982-05-12012 May 1982 Telecopy of Ro:On 820415,surveillance Test 3PC-R4 Indicated That Pressure Transmitters PT456,PT457 & PT454 Were Out of Spec Nonconservatively.Cause Not Stated ML20051P5321982-05-0606 May 1982 RO 82-17:on 820505,air Conditioning Sys,Booster Fans for Filter Operation & Cooling Water Supply Declared Inoperable Due to Motor Failures.Also Reported Per Part 21 ML20050C2701982-03-29029 March 1982 Telecopy Message of Ro:On 820327,small Leak Discovered on Shell Side of Steam Generator 32 W/Reactor in Cold Shutdown Constituting Abnormal Degradation in Primary Containment Boundary.Cause Not Stated.Investigation Continuing ML20050A4471982-03-25025 March 1982 Telecopy Version of Ro:On 820324,small Primary to Secondary Leak Developed in Steam Generator 33.Generator Removed from Svc & Unit Proceeding to Cold Shutdown.Total Release to Atmosphere Was Less than 0.5 Ci,W/No Iodine Released ML20042A6641982-03-11011 March 1982 Ro:Operating Procedures Will Be Revised to Require Operability of Safeguards Equipment Necessary to Mitigate Steamline Break Transient Prior to Heating RCS Above 350 F from Cold Shutdown ML20042A5681982-03-0808 March 1982 RO 82-009:on 820305,nitrogen Pressure in Boron Injection Tank Observed Below 90 Psig.Caused by Failure of Two Nitrogen Pressure Regulator Valves.Procedure Changed.Also Reported Per Part 21 ML20041F2641982-02-26026 February 1982 Final Anomalous Measurement Rept Re Liquid Effluent Releases.Over Past Several months,Co-58 & Co-60 Releases Greater than Average.Possibly Caused by Vegetation Differences.Demineralizer Sampling Scheme Initiated ML20010G8311981-09-0808 September 1981 Ro:On 810731,transformer 11EC4 Taken Out of Svc for Repair, Deactivating Bus Section 4 Which Feeds Motor Driven Fire Pump 12.On 810801,temporary Svc Restored to Fire Pump,But W/O Automatic Start.Transformer 11EC4 Back in Svc 810819 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 ML20032B1351977-01-12012 January 1977 RO 76-2-29(A):on 761230,sensing Line Separated at Swagelock Fitting Following Attempt to Clear Obstruction.Leakage of Reactor Coolant from Sys Followed.Caused by Improper Installation of Swagelock Fitting 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 1994-11-04 Category:TEXT-SAFETY REPORT MONTHYEARML20217H8501999-10-14014 October 1999
[Table view]Safety Evaluation Supporting Amend 197 to License DPR-64 ML20249C8491999-09-30030 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 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 ML20209E1291999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Dresden Nuclear Power Station,Units 1,2 & 3.With 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 ML20206U2551999-02-0909 February 1999 Safety Evaluation Supporting Amend 187 to License DPR-64 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 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 ML20199D3261998-12-31031 December 1998 10CFR50.59 SER for 1998-04 Quarter, of Changes,Tests & Experiments.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 ML20237A1341998-08-0707 August 1998 Safety Evaluation Supporting Amend 163 to License DPR-25 ML20236Y1571998-08-0303 August 1998 Part 21 Rept Re ASTM A351,GR. CF8 Matl at Indian Point Being Out of Specifications in Molybdenum & Chromium.Cause & Corrective Actions Are Not Stated ML20237A7161998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Dresden Nuclear Power Station,Units 1,2 & 3 ML20236V4281998-07-13013 July 1998 Safety Evaluation of TRs WCAP-14333P & WCAP-14334NP, PRA of RPS & ESFAS Test Times & Completion Times. Repts Acceptable ML20236T8391998-06-30030 June 1998 Rev 1 to EMF-96-141, Dresden Unit 3 Cycle 15 Reload Analysis Rept ML20236T8331998-06-30030 June 1998 COLR for Dresden Station Unit 3,Cycle 15 ML20236Q5851998-06-30030 June 1998 1998 Second Quarter 10CFR50.59 Rept, for Dresden Nuclear Power Station of Completed Changes,Tests & Experiments ML20236M6041998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Dresden Nuclear Power Station,Units 1,2 & 3 ML20236F8131998-06-30030 June 1998 Rev 0 to Defueled SAR Dresden Nuclear Power Station Unit 1 Commonwealth Edison Co ML20236T5511998-06-24024 June 1998 Consolidated Edison Co of Ny,Indian Point Unit 2,Drill Scenario Number 1998C 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 ML20216C9651998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Dresden Nuclear Power Station,Units 1,2 & 3 ML20216D4411998-03-31031 March 1998 First Quarter Rept of Completed Changes,Tests & Experiments for 10CFR5059 ML20248B2371998-03-31031 March 1998 Revised Monthly Operating Rept for March 1998 for Indian Point Station Unit 2 ML20216E2531998-02-28028 February 1998 Monthly Operating Repts for Feb 1998 for Dresden Nuclear Power Station ML20203H2441998-02-25025 February 1998 Safety Evaluation Supporting Amends 166 & 161 to Licenses DPR-19 & DPR-25,respectively ML20203K5201998-02-25025 February 1998 Safety Evaluation Supporting Amends 165 & 160 to Licenses DPR-19 & DPR-25,respectively 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 1999-09-30 |
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SUBJECT DPR-25 DESDEN NUCLEAR POWER STATION UNIT 3 l
THIS WILL CONFIRM A CONVERS ATION WITH MR H D ANCE OF YOUR OFFICE l
AT 1100 HOURS THIS D ATE CONCERNING NO. 10FF GAS MONITOR BEING OUT OF C ALIBRATION ON 10-20-72 THE INSTRUMENT MECH ANICS WHILE MAKING A MONTHLY SURV ALANCE C ALIBRATION ON UNIT 3 0FF GAS l
MONITOR FOUND THE TRIP SETTING ON ONE MONITOR GREATER TH AN
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SPEC IFID) IN THE TECHNIC AL SPECIFIC ATIONS SECTIONS 3. 2.D. A 0F THE I
TECHNIC AL SPECIFICATION STATE THAT THE TRIP SETTING FOR SF.1201 (RS69)
MONITOR SHALL BE SET AT A V ALUE NOT TO EXCEED THE EQUIVIL ANT OF l
STACK RD. EASE LIMIT SPECIFIED IN SPECIFICATION 3. 8 THE STACK RELEASE LIMIT UNDER OPERATING CONDITIONS AT THE TIME WAS 0.7 CI/2ND 1EE TRIP SETTING ON NO. 10FF G AS MONITOR W AS FOUND TO BE 1.0CI/2ND THESE MONITORS DO NOT H AVE A HISTORY OF PREVIOUS FAILURES THE STATION WILL REVIEW THE PRESENT TRIP SETTING TO DETERMINE OF A LOWER LIMIT C AN BE USED W. P. UORD EN SUPT DRESDEN NUCLEAR POWER STATION COL DPR-2 5 3 1100 1 10-20-72 3 3. 2.D.1 3. 8 0. 7 CI/2ND 1 1.0CI/2ND s
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REGULATORY OPERATIONS, REGION III Indicent Notification By:
Coc:monwealth Edison Co. (Dresden 3) 50-249 Transmittal Date:
October 27, 1972 Distribution:
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