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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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NRC-92-100 WPSC l4141431 1 LOG .
TELLCOP ER (4141433 5544 iA$vufA (GED G93 Glic5EbiGideGc~srnvici}Q@
wo tmn em e o o re 1 ace . caen en m basannom July 30,1992 U. S. Nuclear Regulatory Commission A'ITN: Document Control Desk Washington, D.C. 2055$
Gentlemen:
Docket 50-305 Operating License DPR-43 Kewuu.iec Nucicar Power Plant Siligtlitltfleo. ding
References:
- 1) Ixiter from C. A. Schrock (WPSC) to NRC Document Control Desk dated hiay 11,1992.
- 2) NRC wneric Letter 88-17, "less of Decay 11 eat Removal," dated October 17, 1988.
Wisconsin Publ' Service Corporation (WPSC) received noti 0 cation of a possible 10 CFR Pan 21 (part 21) defect from Westinghouse Electric Corporation on hlarch 12, 1992. The subject of the Westinghouse letter is a phenomenon tenned surge line flooding which may occur when a large pressurizer vent is used to suppon reduced reactor coolant inventory operations. Due to the complexity of this issue WPSC was not able to detennine if surge line flooding represented a substantial safety hazani within the 60 day period allowed for in pan 21.
Therefore, an interim report was submitted (reference 1) in order to infonn the NRC of the actions WPSC was taking to detennine the safety significance of surge line Gooding. WPSC stated that Westinghouse was perfonning an analysis for WPSC to detennine the impact, if any, on the analyses that they performed for WPSC in response to Generic lxtter 88-17 (reference 2). This analysis has been perfonned and the results indicate that surge line Gooding can occur at the Kewaunee Nuclear Power Plant (KNPP)if core cooling is lost and boiling occurs. There are however, administrative controls that maintain physical barriers and a hot leg vent path which would prevent an inventory loss through a cold leg opening as described in the t 9200040037 920730 ADOCK 05000305 PDR S PDR ,
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f e Docuinent Control Desk Jiily 30,1992 Page 2 Westinghouse potential part 21 letter Therefore, WPSC has detennined that this phenoinenon does not constitute a substantial safety hazard requiring pan 21 notification.
As a result of the identification of this phenoinenon and the new Westinghouse analysis, WPSC will revise the operating procedures for reduced inventory conditions prior to the next scheduled refueling outage at the KNPP (htarch 1993). In addition, a coruplete evaluation of the ability of the steam generator nonle dams to serve as a hot leg to cold leg barrier during refueling conditions will be perfonned. In the interim, a copy of this letter and the new Westinghouse analysis will be routed to all operations personnel as required reading. If you have any questions please contact a member of my staff.
Sincerely, e a.J<LA C. A. Schrock hianager - Nuclear Engineering Ph1P/jac cc - US NRC - Region III hir. Patrick Castleman, US NRC urmc.carnwr 7
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