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Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML20217A1691999-09-22022 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 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 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 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 ML20210E3591997-03-27027 March 1997 Part 21 Rept Re Sorrento Electronics Inc Has Determined Operation & Maint Manual May Not Adequately Define Requirements for Performing Periodic Surveillance of SR Applications.Caused by Hardware Failures.Revised RM-23A ML20059L9861993-11-11011 November 1993 Part 21 Rept Re Deviation Wherein Fully Open Butterfly Valve Located 15 Pipe Diameters Upstream of Sensors Was Disturbing Flow Profile Enough to Cause Ultrasonic Meter to Indicate 3 to 4% Low.Customers Notified & Valve Removed ML20059G3041993-10-22022 October 1993 Part 21 Rept Re Defective Dual Plate Check Valves W/Viton Seats Supplied by C & Valve Co Since 900928.Immediate Corrective Action Taken to Identify Locations of Defective Valves & Conduct Periodic Surveillance of Ccsw Pressure ML20127K6261993-01-12012 January 1993 Part 21 Rept Re Model Std 130 Differential Pressure Transmitters Manufactured by Honeywell in Accordance W/ Requirements of 10CFR21.21(a)(2) ML20247D3011989-07-12012 July 1989 Part 21 Rept 10CFR21-0047 Re Control Wiring Insulation of Inner Jacket Used on General Motors Diesel Generator Sets Identified as 999 or MP Series.Encl List of Owners of Units Notified ML20207N4641988-10-12012 October 1988 Part 21 Rept Re Potential Problem W/Emd 20-645E4,Type 999 Excitation Sys Circuit Breaker & Wiring.Potential for Field Circuit Breaker to Trip Due to Combined Air Temps & Field Current Exists at All Plants W/Model 999 Sys ML20153G0111988-05-0606 May 1988 Part 21 Rept Re Potential Defect in Bussman Buss KTK-R Fuse Blocks W/Part Numbers 2078,2079 & 2080.Purchasing Records Reviewed to Identify If Any Parts Were Actually Used or Shipped to Customers.Results Listed ML20211P7211987-02-23023 February 1987 Part 21 Rept Re Rockbestos Coaxial Cable Used in Sorrento Electronics Digital & Analog high-range Radiation Monitor. Insulation Resistance at High Temp Not High Enough for Ion Chamber & Associated Electronics to Operate Properly ML20215D2371986-12-0909 December 1986 Part 21 Rept Re Environ Qualification of AMP Butt Splices in GE Drywell Penetrations.Splices Retested by Simulating Postulated LOCA & Failed Due to Excessive Leakage.Ge Contacted Re Repair of Splices ML20214M3181986-09-0404 September 1986 Potential Part 21 Rept Re Contromatics Actuator W/Jackscrew/ Handwheel Emergency Override Operator.Jackscrew/Handwheel Should Be Used for Emergency Manual Operation Only.Encl Ltr Also Sent to Listed Utils/Ae Firms ML20141D8051986-04-0101 April 1986 Part 21 Rept Re Model 402 Series Level Control Used for safety-related Application Shipped W/O Torque Check. Customers Will Be Notified by 860428 & Requested to Perform Torque Check.List of Plants Using Component Encl ML20154K3611986-03-0505 March 1986 Part 21 Rept Re Possible Wiring Defect in Fabricated Primer Chamber Assemblies for Standby Liquid Control Valves. Initially Reported on 860214.Listed Corrective Actions Will Be Completed by 860328 ML20133N4691985-08-0505 August 1985 Part 21 Rept Re Raychem Wcsf Shrink Sleeving for Sensor/ Connecting Assembly of Safety Relief Valve Monitoring Sys. Testing & Retesting in Progress.Sensor Installation Utilizing Shrink Sleeving Recommended ML20128G5101985-05-24024 May 1985 Part 21 Rept Re Heat Numbers to Be Added & Deleted from Sublist Sheet A,Based on Review of NRC ML20117L5891985-05-14014 May 1985 Part 21 Rept Re Hatch Transfer Starters & Transfer Starter Assemblies.Evaluation of Implementation of QA Program Performed on 850429-0503.Results of Evaluation Verified Seismic Adequacy of Equipment ML20127N0621985-05-13013 May 1985 Part 21 Rept Re Incorrect Short Time Delay Band Lever Inadequately Installed in Low Voltage K-line Circuit Breaker Electromechanical Overcurrent Trip Device.Visual Insp to Determine If Correct Lever Installed Recommended ML20111C5431985-03-0404 March 1985 Part 21 Rept Re Degradation of 125-volt Dc Battery.Thirty Cells on Battery Show Corrosion Around Weld Between Plates & Internal Bus Bar.Gnb Batteries,Inc 58 Cell NCT-1344 Lead Calcium Battery Purchased to Replace Existing Battery ML20072N9891983-07-0808 July 1983 Interim Part 21 Rept Confirming 830705 Telcon Re Anomalies in Artificially Aged Apparatus (Using Ahrrenius Methodology W/Elevated Temp Aging).Deficiency Found During Qualification Testing for IEEE 323-1974.Draft Notices Encl ML20085K0671974-01-0404 January 1974 Final Deficiency Rept Re Control Logic of HPCI & RCIC Sys. Initially Reported on 731110.Four Addl Qualified High Reactor Water Level Switches Will Be Installed 1999-09-22
[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
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- mmtnw:alth Edisen m ) 1400 opus Place Downers Grove, Illinois 60515 January 12,1993 Dr. Thomas E. Murley, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulator Washington, DC 2055y . Commission Attn: Document Control Desk
Subject:
Commonwealth Edison Company Honeywell Smart Transmitters 10 CFR Part 21 Interim Report
Dear Dr. Murley:
The aurpose of this letter is to notify the NRC Staff of concerns by Commonwealt.1 Edison Company (CECO) toward Mocel STD 130 differential pressure transmitters manufactured by Honeywell.
Dresden Station is the only CECO station which installed Honeywell Model STD 130 differential pressure transmitters. The potential for miscalculation of reactor power and improper calibration of reactor protection system through use of the Feedwater System flow differential pressure transmitters, as described in the attachment, provides the need for a 10 CFR Part 21 review. At this point, the results of the CECO review indicate it is not likely to be a safety hazard. However, further review which is expected to demonstrate no safety significance is scheduled to be completed by March 12,1993.
Provided as an attachment to this letter is CECO's interim report in accordance with the requirements of 10 CFR Part 21, Section 21.21(a)(2).
If there are any questions regarding this notification, please rSrect them to Linda M. Taylor at (708)515-6641.
Respectfully, 220023 -
7M homas J. Kovach j (Nuclear Licensing Manager i
-3 k 1
Attachment:
10 CFR 21 Interim Report Honeywell Smart Transmitters
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- y. 10 CFR Part 21 Interim Report IIoneywell Smart Transmitters Applicability This notification is submitted in accordance with the requirements of 10 CFR Part 21, section 21.21(a)(2).
Identification of Facility and Component This interim report concerns Model STD 130 differential pressure transmitters manufactured by Honeywell which were utilized to determine Feedwater System now at Dresden nuclear power plant.
Identi6 cation of Component ManufaclutcI Honeywell Incorporated Industrial Automation Systems Division 621 Route 83 Bensenville, Illinois Tel. (708 ) 860 3861 Nature of Defect The three transmitters in the Feedwater System at Dresden Station Unit 3 experienced static pressure calibration drift outside of the vendor specification (0.2% of span per 1000 psi). A worst case value of + 0.95% of span at 1400 psi was experienced. No aspect of installation, maintenance, or calibration were found to explain the significant drifts that occurred.
Safety Significance Dresden Station was the only CECO station which had the Honeywell Model STD 130 differential pressure transmitters installed. The instrument's data is also utilized as input for reactor power determination. The potential for miscalculation of reactor power and improper calibration of reactor protection system through use of the Feedwater System flov/
differential pressure transmitters, provides the need for a 10 CFR Part 21 review. The Honeywell Model STD 130 instruments have subsequently been replaced with Rosemount Model 1152 trarsmitters which are successfully used at other stations.
The results of the CECO review indicate it was not likely to be a safety hazard.
Hov/ever, further review which is expected to demonstrate no safety significance is scheduled to be completed by March 12, 1993 . Because these transmitters have been replaced, no further corrective actions are required.
Contacts l
Questions pertaining to this notification should be addressed to :
Linda Taylor '
Engineering and Construction Regulatory Assurance Commonwealth Edison Company 1400 Opus Place, Suite 500 Downers Grove, IL 60515 (708) 663-6641