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Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML20115J3981996-07-22022 July 1996 Interim Part 21 Rept Re 3/4 Schedule 80 Pipe Furnished to Consolidated Power Supply.Investigation Revealed Only One Nuclear Customer Involved in Sale of Matl ML20126J5961992-12-31031 December 1992 Part 21 Rept Re Potential Loss of RHR Cooling During Nozzle Dam Removal.Nozzle Dams May Create Trapped Air Column Behind Cold Leg Nozzle Dam.Mod to Nozzle Dams Currently Underway. Ltrs to Affected Utils Encl ML20113H4871992-07-30030 July 1992 Part 21 Rept Re Surge Line Flooding Which May Occur When Large Pressurizer Vent Used to Support Reduced Rc Inventory Operations.Notification Received from Westinghouse on 920312.Item Not Reportable Per 10CFR21 ML20005G6831990-01-0505 January 1990 Part 21 Rept Re Installation Instructions for Grommet Use Range for Patel Conduit Seal P/N 841206.Conduit Seals in Environ Qualification Applications Inspected for Proper Wire Use Range & Grommets Replaced 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 ML20149J0261987-12-21021 December 1987 Part 21 Rept Re Installation of Relay Part B8002DN in Foxboro 62H Controllers in Facilities.Subj Relay Must Be Replaced by Relay Part N0196ZN.Relay B8002DN Not Used in Any Other Plants ML17261A5301987-06-18018 June 1987 Part 21 Rept Re Potential Util Failure to Comply W/Component Containment Isolation Licensing Commitment If Proposed Mods to Component Cooling Water Sys Instituted.Utils Advised to Evaluate Containment Isolation Sys 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 ML20134Q1741985-08-29029 August 1985 Part 21 Rept Re Potential Maint Issues Associated w/Anker-Holth Snubbers.Owners of Anker-Holth Snubbers Will Be Informed of Problems & Sent Revs to Technical Instruction Manuals to Include Procedures for Seal & Fluid Maint ML20096G9151984-09-0505 September 1984 Final Part 21 Rept Re Certain Bullet & Fire Resistant Protective Doors.Defective Doors Modified & Qualified for Label A.Historical Summary Encl ML20140C2671984-06-0808 June 1984 Part 21 Rept Re Malfunction of DB-50 Undervoltage Trip Attachment.Initially Reported on 840607.Evaluation Indicates Defect Not Generic 1996-07-22
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20140E9181997-06-0707 June 1997 Safety Evaluation Supporting Amend 133 to License DPR-43 ML20115J3981996-07-22022 July 1996 Interim Part 21 Rept Re 3/4 Schedule 80 Pipe Furnished to Consolidated Power Supply.Investigation Revealed Only One Nuclear Customer Involved in Sale of Matl ML20126J5961992-12-31031 December 1992 Part 21 Rept Re Potential Loss of RHR Cooling During Nozzle Dam Removal.Nozzle Dams May Create Trapped Air Column Behind Cold Leg Nozzle Dam.Mod to Nozzle Dams Currently Underway. Ltrs to Affected Utils Encl ML20113H4871992-07-30030 July 1992 Part 21 Rept Re Surge Line Flooding Which May Occur When Large Pressurizer Vent Used to Support Reduced Rc Inventory Operations.Notification Received from Westinghouse on 920312.Item Not Reportable Per 10CFR21 ML20086U0311991-11-30030 November 1991 SG Tube Plugging Criteria for Outside Diameter Stress Corrosion Cracking (ODSCC) at Tube Support Plates ML20077K0831991-06-30030 June 1991 Nonproprietary Technical Justification for Eliminating Pressurizer Surge Line Rupture as Structural Design Basis for Kewaunee Nuclear Plant ML1118102861991-05-31031 May 1991 Handbook on Flaw Evaluation Kewaunee,Unit 1 Steam Generators Upper Shell to Cone Weld. ML20091E3441991-03-31031 March 1991 Nonproprietary Structural Evaluation of Kewaunee Pressurizer Surge Line,Considering Effects of Thermal Stratification ML20066B2101990-12-31031 December 1990 Generator Mid-Cycle Rept,Dec 1990 ML20062A4641990-09-30030 September 1990 Nonproprietary, Reevaluation of U-Bend Tube Fatique for Kewaunee Plant Steam Generators ML20042F3261990-05-0404 May 1990 LER 90-005-00:on 900404,intergranular Attack & IGSCC Results in Both Steam Generators a & B Being Categorized as C-3.All Defective Tubes Plugged & Sludge Lancing & Crevice Flushing conducted.W/900504 Ltr ML1117803551990-04-30030 April 1990 Generator Tubesheet Crevice Indications Return to Power Rept. ML20005G6831990-01-0505 January 1990 Part 21 Rept Re Installation Instructions for Grommet Use Range for Patel Conduit Seal P/N 841206.Conduit Seals in Environ Qualification Applications Inspected for Proper Wire Use Range & Grommets Replaced ML19354D8351989-11-0808 November 1989 Presentation to NRC Re Kewaunee (Wps) SECY-83-472 LOCA Analysis Effort. 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 ML20235J1941988-11-30030 November 1988 Analysis of Capsule P from Wisconsin Public Svc Corp Kewaunee Nuclear Plant Reactor Vessel Radiation Surveillance Program 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 ML20206E9801988-06-30030 June 1988 Rev 2 to Handbook on Flaw Evaluation,Kewaunee Unit 1 Steam Generators Upper Shell to Cone Weld ML20196G5251988-06-15015 June 1988 Technical Review Rept T809, Blocked Thimble Tubes/Stuck Incore Detector ML20154H0391988-04-30030 April 1988 Slide Presentation Matl,Nrc Meeting 880331,Kewaunee Nuclear Power Plant Steam Generator Tube Sleeve Installation ML20196G8881988-03-0303 March 1988 Headquarters Daily Rept for 880303 ML20147B2921987-12-31031 December 1987 Annual Operating Rept for 1987 ML20149J0261987-12-21021 December 1987 Part 21 Rept Re Installation of Relay Part B8002DN in Foxboro 62H Controllers in Facilities.Subj Relay Must Be Replaced by Relay Part N0196ZN.Relay B8002DN Not Used in Any Other Plants ML20236W7341987-11-30030 November 1987 Nonproprietary Kewaunee Steam Generator Sleeving Rept (Mechanical Sleeves) ML20236F3101987-10-31031 October 1987 Nonproprietary WCAP-11620, Addl Technical Bases for Eliminating Large Primary Loop Pipe Rupture as Structural Design Basis for Kewaunee ML20236N3451987-10-31031 October 1987 Monthly Operating Rept for Oct 1987 ML20235V1161987-09-30030 September 1987 Monthly Operating Rept for Sept 1987 ML20238F7541987-08-31031 August 1987 Monthly Operating Rept for Aug 1987 ML20237H6861987-07-31031 July 1987 Monthly Operating Rept for Jul 1987 ML20235J3101987-06-30030 June 1987 Monthly Operating Rept for June 1987 ML17261A5301987-06-18018 June 1987 Part 21 Rept Re Potential Util Failure to Comply W/Component Containment Isolation Licensing Commitment If Proposed Mods to Component Cooling Water Sys Instituted.Utils Advised to Evaluate Containment Isolation Sys ML20215A3211987-05-31031 May 1987 Monthly Operating Rept for May 1987 ML20215L8061987-04-30030 April 1987 Nonproprietary Rev 1 to Technical Bases for Eliminating Large Pipe Rupture as Structural Design Basis for Kewaunee ML20213G4341987-04-30030 April 1987 Monthly Operating Rept for Apr 1987 ML20206H4301987-03-31031 March 1987 Monthly Operating Rept for Mar 1987 ML20207R6091987-02-28028 February 1987 Monthly Operating Rept for Feb 1987 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 ML20211A1761987-01-31031 January 1987 Monthly Operating Rept for Jan 1987 ML20212B9451986-12-31031 December 1986 Reload Safety Evaluation,Kewaunee Cycle 13 ML20207M8271986-12-31031 December 1986 Monthly Operating Rept for Dec 1986 ML20212F4301986-12-31031 December 1986 Annual Operating Rept,1986 ML20212F6581986-12-31031 December 1986 Technical Review Rept, Degradation of Safety Sys Due to Component Misalignment &/Or Mispositioned Control/Selector Switches ML20212D9091986-12-23023 December 1986 Localized Rod Cluster Control Assembly (Rcca) Wear at PWR Plants, Engineering Evaluation Rept ML20211M0441986-11-30030 November 1986 Monthly Operating Rept for Nov 1986 ML20213F2231986-10-31031 October 1986 Monthly Operating Rept for Oct 1986 ML20207F6021986-09-30030 September 1986 Monthly Operating Rept for Sept 1986 ML20210C8931986-08-31031 August 1986 Monthly Operating Rept for Aug 1986 ML20212F5161986-07-31031 July 1986 Monthly Operating Rept for Jul 1986 ML20202G9981986-06-30030 June 1986 Monthly Operating Rept for June 1986 ML20211E1391986-05-31031 May 1986 Monthly Operating Rept for May 1986 1997-06-07
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Westinghouse Water Reactor Ntriear Technology Division Electric Corporation Divisions Box ass Pittsburgh Pennsylvania 15230 t
- June 8, 1984 .
NS-EPR-2928 Mr. Richard C. DeYoung, Director Office of Inspection 6 Enforcement -
U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue ^
Bethesda, Maryland 20814
Subject:
Malfunction of DB-50 Undervoltage Trip Attachment '
Dear Mr. DeYoung:
This is to confirm a conference call on June 7, 1984 with :
Mr. George Lanik of NRC in which Mr. John McAdoo of my' staff i apprised him of an evaluation performed by Westinghouse in response to a component raalfunction reported to us by Wisconsin !
Public Service. Mr. Charles Schrock of Wisconsin Public Service t participated in the same call and reported on the utility's !
evaluation. l Although our evaluation does not indicate the existence of a Substantial Safety Hazard, and we have no knowledge to indicate -
that this is anything other than an isolated incident, we are ,
reporting this to you for your information.
The malfunctioning component was a DB-50 undervoltage trip
~a ttachment (UVTA), supplied by Westinghouse and installed by ,
Wisconsin Public Service as a replacement in one of the reactor trip breakers at Kewaunce. The utility was unable to obtain l proper operation from the device. The nature of the malfunction was such that the reactor could not be taken out of the tripped mode with the faulty UVTA installed. The utility returned the component to Westinghouse for further evaluation of probable ,
cause and any generic implications.
The following findings resulted from that evaluation:
Some parts of the defective UVTA as returned were apparently of an earlier manufacturing vintage than the attachment b
8406190223 840608 O PDR ADOCK 05000305 l
/" Richard C. DeYoung NS-EPR-2928 June 8, 1984 Page 2 itself, based on its nameplate. Moreover, one of the non-conforming parts showed considerable wear, although the component was recently shipped from the supplier and had not been installed prior to the reported malfunction.
Quality records pertaining to the UVTA in question show that the item fully conformed to required inspection criteria when it was examined prior to packaging at the manufacturer's shop, and that storage prior to shipment was controlled in the specified manner. No records authorizing rework were found. The inspectors responsible for these records were interviewed and confirmed no anomalies.
Packages in storage containing the other UVTAs in the same lot which had not been shipped were opened and inspection revealed no abnormalities. Two other UVTAs which were received at the Kewaunee site in the same shipment with the UVTA that malfunctioned also revealed no abnormalities upon examination.
No authorization for rework was requested of Westinghouse by the utility.
Based upon these findings, we have concluded that (a) manufacture, inspection, storage and shipment of UVTAs in the lot containing the UVTA in question were performed according to controlled quality procedures and that.the appropriate records were maintain,ed; (b) the defective UVTA had been reworked utilizing used and out-dated parts; (c) such rework did not occur while the UVTA was in the possession of Westinghouse as manufacturer or supplier. There is no evidence that the defect in this instance is generic nor are we aware of other instances where unauthorized rework of UVTAs has occurred.
If there are further questions concerning this matter, please contact Mr. C. G. Draughon of the Westinghouse Nuclear Safety Department at (412) 374-5761.
Very truly yours, h~
~ Q) W, 4 &
gv- . P. Rahe, Jr., Manager Nuc1 car Safety Department JDM/1 cc: C. E. Rossi, NRC G. P. Lanik, NRC C. A. Schrock, WPS J. S. Moore, W J. L. Gallagher, W