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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
_ _ _, _ _ . _ _ _ . _ _ _ ___ ____ _ _ _ _ _
., .a Com Fiprs.
One Elth Edison Plaza. Chicago. Ilknois
. .ational 4
i Address Reply to: Post Office Box 767 Chicago, !!!inois 60690 50-249 WPW Ltr.d847-73 Dresden Nuclear Power Station .
, R. R. #1 Morris, Illinois 60450 November 15, 1973 .
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6 8 Mr. A. Giambusso 2 kOf ?
Deputy Director for Reactor Projects 9; 4 ,. /S T Directorate of Licensing p,;,,g* g U. S. Atomic Energy C,mnission g 4 g"/ g,7 -
Washington, D. C. 20545 T4
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SUBJECT:
LICENSE DPR-25. DRESDEN NUCLEAR POWER STATION, UNIT #3, Ot SECTION 6.6.B.2 0F THE TECHNICAL SPECIFICATIONS.
MALFUN_ C TION OF CORE SPRAY SYSTEM M.O. VALVE 1402-38A.
Reference:
- 1) Dwgs: P & ID M-358.
4
Dear Mr. Giambus.,
o:
This letter is to report a condition relating to the operation of the unit at about 0300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> en October 16, 1973. At this time, Core Spray System I bypass valve 1402-38A failed to open during a system test.
This malfunction is contrary to section 3.5.A.1 of the Technical Specifications which requires that core spray components shall be operable when irradiated fuel is in the reactor.
PROBLEM Valve 1402-38A is in the minimum flow bypass piping for Core Spray System pump 2A. The function of the valve is to allow adequate pump flow, which prevent pump damage when the core spray system is operating at less than minimum pump flow. This valve is actuated by flow switch DP 1464A. The function of this switch is to monitor core spray flow, and provide an open signal to valve 1402-38A, if flow is less than 300 GPM. When ficw is above this value, the flow switch provides a close signal to the valve. On October 16, 1973 during a test of the Unit 3 Core Spray System, bypass valve 1402-38A failed to open due to the failure of flow switch DP 1464A.
INVESTICATION Flow switch DP 1464A was tested and found to be inoperable.
The switch was recalibrated and then found to operate properly. The switch is a Barton Model 288 and has a history of setpoint drif t in both the increasing and decreasing direction.
4, 0310200355 731115 fj.db PDR ADOCK 05000249 PDR se ep S f /
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Mr. A. Giambu(sJ)o November 15, 1973 On November 1, 1973 the switch was inspected by a Barton field -
representative. The following observations were noted.
- 1. The plunger which actuates the micro switch was very loose.
! 2. The roller on the actuator arm would not roll freely.
- 3. The range of the switch is too large for the setpoint.
During the investigation it was also noted that a procedure revision is needed to provide more exact instructions when calibrating the flow switch .
4 CORRECTIVE ACTION The immediate corrective action was to tighten the plunger screw, free the actuator arm roller, and reset the switch. Future corrective action will be to replace the switch with one having a smaller range, and to develop a program to inspect critical cooponents on Barton switches on I a regular schedule.
^
EVALUATIONS The failure of valve 1402-38A in no way impaired the availability 1
of the Core Spray System. Therefore, it is concluded that the safety of the station personnel and the general public was not compromised as a result of this switch failure.
Investigations into the drifting of instrument setpoints is continuing. Dresden has consulted with instrument manufacturers and is obtaining recommendations for corrective action. Critical instruments with a history of drif ting setpoints are being checked on a more frequent interval. Setpoints have been moved to more conservative value where warranted. These actions have insured continued safe operation of the reactor.
Sincerely, hk S. M W. P. Worden Superintendent
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- Dresden Nuclear Power Station R. R. #1 Forris, Illinois 60450 December 11, 1974 Fr. E. C. Case Directorate of Licensing [ (([ j _
U. S. Ate:nc energy Co::=ission ,g4 p, p Washington, D. C. i ;,
20545
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SUUJDCT: Corrective Action for Barton Instrument Setpoint Drift V !C /
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References:
Letter 176574 to Fr. J. F. O' Leary from Mr. W. P. Worden -
dated January 30, 1974 -
Incident D2-73-1 reported to Mr. Giambasso in letter #41-73 dated January 15, 1973 -
Dear 16. Case:
The above referenced letter outlined a three step program to reduce setpoint drift in 2arton differential pressure switches used at Dresden Station.
This letter is to infom the co=:.ission of the progress of the procram.
Step #1: Analysis of pressure switches by Barten representative to detemine an;r application problemc on Fachmical defects.
Switch application evaluation was perfomed by Fr. Roger Smallwood of Stallings & Co. The following =isapplications were identified.
Switch No. Function Problem 261-34 AECD Jet Pump High Oscillation Riser DP High Range DP 302-52 Drive Water High Oscillation
, Filter DP t
DP 261-35 Recire Pu=p DP High Range
(
1751'A & L Offgas Pressure High Range 1464 A & B Core Spray 111Ch Range High Flow 2352, 53 HPCI Steam Line Low Range High Flow 2ero Center es: ,s' - nn b4d 6 O dh[ /Y 12G87
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r _ _ _
ber 11, 1974 ya . E. D. Ccas ,
Step #2: Factory representative to conduct a maintenance training seminar to assure no proble=s are caused by improper maintenance.
Barton factory representative I'.r. Peter Elderton conducted a one week Maintenance Seminar begining September 1, 1974. All Barton differential pressure switches were inspected during September and October of 1974 using a checklist @ich was developed during the training seminar.
Step #3: Replacement or repair of all pressure switches when deemed necessary by the manufacturer.
Modifications have been initiated for the switches identified in Step #1.
However, the original co=pletion date of January 1,1975 will not be met.
The estimated completion date for Step #3 is June of 1975.
Respectfully, -
, ,s
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NOV f) 1973 H. D. Thornburg, Chief Field Support & Enforcement Branch, RO BARTON 288 PRESSURE SWITQI Attached are two abnormal occurrence reports concerning setpoint drift on the same basic instrument (Barton 288). The letter from Dresden states that the locking device they installed in February did not work. The letter from Browns Ferry says they are going to get and install a locking device, that, if the Dresden experience is correct, will not do them a bit of good. Since these come from dif ferent Regions, I suggest you might alert Region II to this possible waste of effort. /
- 2. Abam R. A. Hartfield i Office of Operations 0E valuation
Attachment:
AOR reports g y9}. y 1 o y y'
yg ,.,,........~..w..,..
. , ng One First fut.onal P:na. Chican, Illinois S V '?7 Address Peo v to. Post Ottce Box 767 / '
U Chicago 6s 60690 (N,!
50-249 i
l WPU Ltr.0797-73 Dresden Nucicar Power Station R. R. #1 Horris, Illinois 60450 "gi m,f October 24, 1973 b l'
Q 0d'6// /.i
- Hr. A. Giambusso l 2-3 Gg 0 Deputy Director for Reactor Projects 4 [ 4 29)*3 e
, (pj[kf4;f %)
Directorate of Licensing 69 U. S. Atomic Energy Conraission Unshington, D. C. 20545 l --- '
SUBJECT:
_L_ICENSE DPR-25, DRESDEN NUCL'AR PO'a*ER STATION, UNIT #3, SECTION 6.6. C.1 C ? ~~.*~ TEC":ICAL SPECITICATIC"S.
i HPCI STEAM LINZ HICH FLC'1 S'.JITCH OUT OF CALIBRATION.
i .
References:
- 1) Dwgs: P&ID H-51. S&L 12E2527
+
Dear Mr. Giambusso:
Thic 1ceter is to report c condition relating to the operation of the unit at about 1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br /> on September 25, 1973. At this ti=e high pressure coolant injection (HPCI) flow switch DPIS 3-2353 was found to have a trip cetpoint of 152.0" H 0. This setpoint is contrary to Tabic 2
3.2.1 of the Technical Specifications which require a setpoint of ,y 150" MgO.
PROBLEM ,
At the ti=e of the occurrence, Unit 3 was operating in a steady state condition with a thermal load of 2295 MWe, Routine surveillance was being performed by the Instru=ent Department when HPCX flow switch DPIS3-2353 was found to have a setpoint of 152" H 20. The switch was ic: mediately reset.to 148" H 2 0.. The function of DPIS-3-2353 is to isolate the HPCI ,
steat:rsupply 'line 'in the event of a brdak 'in the st' am c ' piping.
- INVESTIC,\ TION The subject flow switch is a Barten model 288 differential pressure ,
sensor. This switch has had a tendency to drift in both the EcTEasirifahd' l decreasing direction. A locking device was installed on the switch in February of 1973 fn an attemot to eliminate the~ dHf t tendencyuAt. thT~
_present time, the data from previous curveillances reveals that the_ locking ;
_ device has not solved the drift problem. The overall probicm of instrument i setpoint drift is presently under investigatien. The problem has plagued ;
the station since its beginning, and no adequate corrective action has been determined at this time. '
/ .
h
, EB. Q. CBcmSussa - '
Octcbar 24, 1973 The most recent approach to the problem has been to solicit aid from the manufacturera of the various drif ting sensors. In the case of the Barton model 288, the factory representative has recommended that a field service engineer visit the station and analyse Barton switches with regard to application, factory adjusteents, and calibration technique. The Barton representative has visited the Station and we are now awaiting his recommenda-tions. i I
CORRECTIVE ACTION The immediate ccrrective action was to change the setpoint of DPIS-3-2353 to bring it within-the Technical Specifications. The calibra-tion frequency for this switch will be increased to once per month until such time as this switch has dc=onstrated its reliability. Additional corrective action will be based on reco=mendations made by the Barton field service engineer.
EVALUATION
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Flow switch DPIS-3-2353 is one of two flow switches that isolate the HPCI steem line in the event of a break in the steam piping. The second switch is DPIS-3-2352, and its setpoint at the time of the occurrence was 146" H2 0. Therefore, it is concluded that in the event of a break in the HPCI steam line piping, isolation would have occurred well within the Technical Specifications, and thus the safety of the station personnel and the general public was in no way conpremised. The continued operation of the unit was considered safe.
o Sincerely,
. hb W. P. Worden Superintendent ;
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, . TENNESSEE CHATTANO( VAP]A, TENNESSEEEY AUTHO :
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(: =hn C October 26, 1973
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- 3%.!j i j Mr. .iohn F. O'Icary Directorate of Licensing
,! I. 0073 u. c:m01973>. ng y( i,s Office of Regulation ()A N x.4 gn,j,yg,p If l U.S. Atomic Energy Cc=nission N,:) f, Washington, DC 20545 '
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Dear Mr. O'Imary:
! TEICISSSEE VAll2,Y AUTECRI'IT - BRC'. INS FER3Y I;L'CIIAR PLAIC U LIT 1 -
DoCKsT ::0 50-259 - FACILI'lY OPERATI::G LICE:iSE DPR AB30FMAL l OCCURRE! ICE REPO?Tf BFAO-732TJ The purpose of this report is to provide details concerning t,he l malfunction of recirculation jet punp riser d/p switch PdIS-68-24 in unit 1 at Browns Ferry Iiuclear Plant on October 16, 1973 This occurrence was reported by telegram on Cetober 17 to the Region II Directorate of Regulatcry Operations, Atlanta, Georgia.
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D2scription of the Incident -
l During routine sttrveillance testing on October 16, recirculation jet pump riser d/p sditch PdIS-68-24 was found to operate outside the
- technical specification setpoint of greater than 0 5 but less than 1 5 psid as specified in table 3 2.B. The as-found setpoint was 1.8 psid.
l g Investigation and Corrective Action i '
- Each of the four differential pressure switches operate relays whose contacts are arranged in a one out of two taken tvice logic in the RER injection circuit. The minimum number of channels recuired for each
, trip system is two. The other tuo channels were tested, found to
[ operate satisfactorily, and, if recuired, would have perfonned their l
intended function. The reactor was in the hot standby condition. .
.These switches are Barton model 288 differential _ pressure svitches. h l !
' l The switch nochanisms vere inspected for binding misalign: cat of other
, irregularities. Iione was found. The critches were recall' crated and j then functionally tested several times to ensure repeatability. A l l functional testing frequency of once every 2 vechs has been initiated l l 1 geSq ).
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o-I Mr. John F. O' Leary -
,. October 26, 1973 TEICTESSEE V. LLEY AUTEORITY - ERO'.!:S FERRY !!UCLEAR Fill.f UUlT 1 -
DOCKET IIO. 50-259 - F.".CILITY OPEETII!G LICENSE DPR ABUOMAL OCCURRE:;CE h7Ao-732TJ
'for all four switches and vill be continued until three consecutive tests prove satisfactory performance. At that tiac, the original test schedule of once a month will be recumed. We intend to install,_as j soon as possible upon receipt, nev locking; cuitchp g asser.blics /
recently made available_,gthe_ vendor,grevent_ setpoint drift.___
Very truly yours, * "" T '
TEmiESSES VALLTl NJTEORITY -
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- & E. F. Tho=as i
8 Director of Pcyer Production ,
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CC: Mr. Hornan C. !!oscley, Director Region II Regulatory Cperations Cffice, USAEC -
230 Peachtree Street, IT4 j Atlanta, Georgia 30303 i.
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