ML19330B289
| ML19330B289 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek, Callaway, Sterling  |
| Issue date: | 06/30/1980 |
| From: | Petrick N STANDARDIZED NUCLEAR UNIT POWER PLANT SYSTEM |
| To: | |
| Shared Package | |
| ML19330B286 | List: |
| References | |
| SLNRC-80-32, NUDOCS 8007310302 | |
| Download: ML19330B289 (1) | |
Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML20132C0751996-12-13013 December 1996
[Table view]Part 21 Rept Re Testing of Six HFD3045 & HFD3060 Molded Case Circuit Breakers w/125 Volt DC Shunt Trip Devices.Identified Incorrectly Installed DC Shunt Trip Units & Are in Process of Being Returned to Vendor ML20112G3871996-06-0404 June 1996 Potential Part 21 Rept Re Capscrews W/Trace Code of K7 Mfg by Cardinal Industries (Now Known as Accutech) & Distributed by Energy & Process Corp for Plant CP S/N 0194012.Pump/motor Would Remain Operational Throughout Worse Case Scenario 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 ML20125C7161992-12-0707 December 1992 Part 21 Rept Re Possibility for Malfunction of Declutching Mechanisms in SMB/SB-000 & SMB/SB/SBD-00 Actuators. Malfunction Only Occurs During Seismic Event.Balanced Levers May Be Purchased from Vendor.List of Affected Utils Encl ML20127P5861992-11-23023 November 1992 Followup to 921005 Part 21 Rept Re Potential Defect in SB/SBD-1 Housing Cover Screws.Procedure Re Replacement of SBD-1 Spring Cover Bolts Encl.All Fasteners Should Be Loosened & Removed.List of Affected Utils Encl ML20086G2931991-11-21021 November 1991 Part 21 Rept Re Failure of Model 763 & 763A Static Pressure Transmitters.Caused by Short Circuit in Connector Pin to Adjacent Mounting Screw.Engineering Drawings & Mfg Work Instructions Changed & Stock Purged of Subj Transmitters ML20070A6861991-01-17017 January 1991 Part 21 Rept Re Failure of 4.16 Kv vertical-lift Switchgear Cell Mounted,Auxiliary Contacts to Operate on Demand During Testing of Auxiliary Standby Switchgear at Facility. Initially Reported on 901101.New Test Link Sent to Facility ML20062D9351990-11-0101 November 1990 Part 21 Rept Re Failure of 4.16 Kv Vertical Lift Switchgear, cell-mounted Auxiliary Contacts to Operate on Command During Testing of Standby Switchgear at Plant.Caused When Maladjusted Test Link Inserted Between Breaker & Switch ML20059N5191990-10-16016 October 1990 Part 21 Rept Re Rod & Bearing Assembly Failures Noted by Wolf Creek Nuclear Operating Corp During Testing.Rept Will Be Issued Outlining Root Cause & Corrective Actions to Prevent Recurrence ML17223A7451990-01-26026 January 1990 Part 21 Rept Re Backup Rings Furnished in Spare Parts Seal Kits & in 25 Gpm 4 Way Valves as Part of Actuators Made of Incorrect Matl.Rings Should Be Viton & Have Been Identified as Buna N ML20246J0631989-08-29029 August 1989 Part 21 Rept Re Namco Refusal to Certify Design & Matls for Replacement Namco Limit Switches Supplied by Masoneilan. Initially Reported on 890825.Switches Put on QC Hold Until Final Disposition of Switches Determined ML20244D2901989-06-0101 June 1989 Part 21 Rept Re Buchanan 724 Terminal Blocks Supplied by Limitorque Corp,Rather than Correct Buchanan 524 Terminal Blocks.Caused by Error in Order Processing.Training Held to Ensure That Procedures Followed Correctly ML20246N7911989-05-10010 May 1989 Part 21 Rept Re Room Cooler Vents & Drains Mfg by Carrier Corp Per Bechtel Specs,W/Galvanic Corrosion at Interface w/90-10 copper-nickel Room Cooler Supply & Return Headers. Vents & Drains Will Be Modified During Current Outage ML20235Y4811989-03-0303 March 1989 Part 21 Rept Re Cracked Welds Discovered on Striker Plates of GE Circuit Breakers.Initially Reported on 890130.GE Advised Util That Striker Plates Subj to Impact Loading Only When Breaker in Racked Out & Operated in Test Position ML20195F6191988-11-18018 November 1988 Part 21 Rept Re GE Magne-Blast Circuit Breakers.Initially Reported on 881116.Welds on All safety-related Breakers Will Be Repaired Prior to Entry Into Hot Shutdown ML20151W7841988-08-16016 August 1988 Part 21 Rept Re Cracking of Slides Used in Four Way Valves Furnished on Actuators for MSIVs Due to Brazing/Heat Treating of Slide Matl.All Sites Using Actuators Will Be Formally Notified by 880826.List Encl ML20151B4291988-04-0101 April 1988 Part 21 Rept Re Inconsistencies in Gould,Inc Certificate of Compliance Received W/Class 1E Fuses Procured from Planned Maint Sys Due to Fuses Not Being Qualified for Certain Specs.Initially Reported on 880329.Fuses Remain on Hold ML20234C7351987-06-23023 June 1987 Supplemental Part 21 Rept Re Silicone Foam Seal Anomolies at Wolf Creek Generating Station 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 ML20153D8861986-02-17017 February 1986 Part 21 Rept Re Failure of Penetration & Conduit Seal Configurations During Fire Tests.Initially Reported on 860214.Evaluation of Number & Location of Defective Seals in Progress.Nrc Assistance Requested ML20151Y8141986-02-0404 February 1986 Part 21 Rept Re Colt-Pielstick Engine Tripping Out on High Speed When Started for Test Purposes at Seabrook.Caused by Source of Air Pressure Staying On.Engines Will Be Modified to Positively Vent Air from Rack Boost Cylinder ML20137W2611985-09-30030 September 1985 Update to Part 21 Rept Re Insp for Cracked Welds Discovered in Generator Brackets.Insp for Callaway Unit 1 Postponed Until Next Refueling Outage (Probably Apr 1986).No Cracks Discovered During Insp at Wolf Creek ML20135E1161985-09-0505 September 1985 Part 21 Rept Re Use of Connectron non-IEEE Qualified Matl in Spare Part Terminal Blocks Supplied to Facilities. Appropriate Customers Notified.Terminal Blocks Should Be Reviewed to Identify Defective Matl ML20135G0651985-08-28028 August 1985 Supplemental Part 21 & Deficiency Rept U-70 Re Failures of Crane-Deming Keepwarm Lube Oil Pumps.Initially Reported on 840328.Permanent ASME Section III Equivalent Pumps Will Be Installed on Engine Skid by First Refueling ML20135D4481985-08-15015 August 1985 Part 21 Rept Re Raychem auto-trace 20PTV1 self-regulating Electric Heat Tracers & Associated Derivatives.Licensees Advised of Problem & Procedures to Determine Any Effect on Operation ML20210G9921985-08-13013 August 1985 Part 21 Rept Re Failure of Isolated Worm Shaft Gear When Certain Critical Speeds Combined W/Repetitive Transfer of Actuator Clutch Mechanism from Manual (Handwheel) to Motor Drive Mode.Two Possible Solutions Noted ML20129J7381985-06-24024 June 1985 Part 21 Rept Re Auto-Trace 20PTV1,self-regulating Electric Heat Trace,W/Lower than Specified Power Output.Deficiency Could Result in Lower Maint Temp in Electric Pipe Heating Sys.Affected Licensees Identified ML20117B8141985-05-0101 May 1985 Part 21 Rept Re Ruskin Fire Dampers Installed at Facility. Initially Reported on 850426.Fire Dampers Found in Discrepant Condition Will Be Reworked in Order to Assure Integrity & Proper Functioning ML20116E8481985-04-23023 April 1985 Part 21 Rept Forwarding Rev 1 to Insp Procedure for Investigating Emergency Diesel Generators for Fractured Welds on Air Deflectors.Rev Will Be Forwarded to Each Facility ML20116D3201985-04-22022 April 1985 Part 21 Rept Re Ruskin Mfg Co Welds Used to Join Damper to Damper & Damper Section to Mullion Plates.Welds Not in Accordance W/Approved Design Drawings.Drawing 5415 Revised to Indicate Weld Spacing.Drawing of Weld Spacing Encl ML20115J1361985-04-15015 April 1985 Forwards Insp Procedure for Investigating Emergency Diesel Generators for Fractured or Cracked Welds to Determine If Part 21 Problem Exists,Per Jg Borman ML20100E0651985-03-29029 March 1985 Part 21 Rept Re Series of Cracked Welds Discovered in Generators.Welds Occurred in Conical Baffle Section of Coil Guards.All Units Will Be Inspected.Affected Plants Listed NRC-85-3024, Part 21 Rept Re Possible Undetectable Failures in ESF Actuation Sys.Initially Reported on 791107.Possibility of Undetectable Failures Remain Under Certain Circumstances Despite Change in Hardware1985-03-22022 March 1985 Part 21 Rept Re Possible Undetectable Failures in ESF Actuation Sys.Initially Reported on 791107.Possibility of Undetectable Failures Remain Under Certain Circumstances Despite Change in Hardware ML20102B9531985-02-13013 February 1985 Supplemental Final Deficiency Rept (53564-K159) Re Concrete Coatings Inside Containment.Initially Reported on 841213. Coated Concrete Surfaces Inside Containment Will Perform Satisfactorily Under DBA Conditions ML20107B6931985-02-0707 February 1985 Final Deficiency Rept (53564-K161) Re Uncertainties in Resistance Temp Detectors Calibr.Westinghouse Evaluation Demonstrated That Revised Resistance Temp Detectors Uncertainty Acceptable ML20101T1211985-01-25025 January 1985 Final Deficiency Rept (53564-K159) Re Concrete Coatings Inside Containment.Initially Reported on 841213.Destructive Adhesion Tests Performed on Locations Selected by Sampling Plan to Verify Acceptability of Coatings ML20104B1471985-01-18018 January 1985 Final Deficiency Rept Re Insp of Structural Steel Welds. Initially Reported on 840918.Structural Concerns Identified & Corrective Action Repts Issued to Have Shims Less than 1/4 Inch Thick Placed Flush W/Mounting Frame ML20114C7981985-01-13013 January 1985 Final Deficiency Rept Re Removal & Replacement of ASME Components in Support of Cleaning & Flushing Activities. Initially Reported on 840711.Investigation Into Handling & Storage of ASME Components Removed from Sys Conducted ML20114C9141985-01-13013 January 1985 Final Deficiency Rept (53546-K158) Re ASME Hangers & Component Supports.Initially Reported on 841212.Insulation Contractors Revised Procedures & Retrained Personnel to Preclude Further Tampering of Supports ML20114C8441985-01-13013 January 1985 Final Deficiency Rept Re Microbiologically Induced Corrosion in Hxs.Initially Reported on 840601.All HXs Utilizing Lake Water for Cooling Medium Eddy Current Inspected for Microbiologically Induced Corrosion ML20114D1081985-01-13013 January 1985 Final Deficiency Rept (53564-K118) Re safety-related Field Procurement by Constructor.Initially Reported on 840103. Complete Review of Constructor safety-related Purchase Orders Completed.All Nonconformance Repts Resolved ML20104B9241985-01-13013 January 1985 Final Deficiency Rept Re Water Damaged Limitorque Motor Operators.Initially Reported on 840203.Caused by Leakage During Sys Flushing & Hydrostatic Testing Activities.Seals Added Inside Conduit & T-drains Installed in Operator ML20104A8671985-01-13013 January 1985 Final Deficiency Rept Re Standby Diesel Generator B Left Bank Turbocharger.Initially Reported on 840504.Caused by Loose Lock Nut on Left Bank Turbocharger Lubricating Oil Pump Centrifuge.Damaged Turbocharger Repaired & Inspected ML20104A8171985-01-13013 January 1985 Final Deficiency Rept Re Subcooling Core Monitor Alarm & Caution Relays.Initially Reported on 840821.Interposing Relays & Diodes Added to Sys to Minimize Potential for & Suppress Effects of Any Arcs Generated ML20113A4291985-01-11011 January 1985 Part 21 Rept Re Incorrect Insulating Tape.Instructions Governing Handling of Incoming Matls Fully Adequate & If Followed,Would Have Prevented Error ML20112D8061985-01-0404 January 1985 Final Deficiency Rept Re MSIV Lockwashers.Initially Reported on 841207.Lockwashers Installed Via Startup Field Rept I-SU-122 & Will Be Completed Prior to Fuel Load ML20112F5421985-01-0303 January 1985 Forwards Dec 1984 Status Rept Re 10CFR50.55(e)/Part 21 Open Items RBG-19-803, Final Deficiency Rept DR-234 Re Short Cap Screws,Shallow Bolt Holes,Damaged Dowel Pins & Damaged or Missing Lock Devices for Hanger Block Bolts in Check Valves Supplied by Velan Engineering,Ltd.Initially Reported on 8411281984-12-28028 December 1984 Final Deficiency Rept DR-234 Re Short Cap Screws,Shallow Bolt Holes,Damaged Dowel Pins & Damaged or Missing Lock Devices for Hanger Block Bolts in Check Valves Supplied by Velan Engineering,Ltd.Initially Reported on 841128 ML20101N0481984-12-0707 December 1984 Final Deficiency Rept Re RCS Resistance Temp Detector Calibr Data.Initially Reported on 840801.Manufacturer Calibr Procedures Revised to Allow Recalibr at Facility.All Resistance Temp Detectors Will Be Replaced or Refurbished ML20101N1871984-12-0707 December 1984 Final Deficiency Rept Re Heat Numbers W/More than One Pipe Schedule.Initially Reported on 831213.Two Piping Spool Pieces Replaced W/Correct Schedule of Pipe.Exam of All Installations of Subj Heats Revised to Prevent Recurrences 1996-06-04 Category:TEXT-SAFETY REPORT MONTHYEAR05000482/LER-1999-002, :on 990312,testing of Phase a (Cisa) Ctnt Isolation Valves Was Performed in Wrong Mode.Caused by Sp Not Being Properly Developed.Revised Applicable Procedures1999-10-15015 October 1999
[Table view]
1999-09-07 |
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SNUPPS Standardized Nuclear Unit y, Powcr Plant System 5 Choke Cherry Road Nicholas A. Petrick Rockvine, Marytend 20850 Executive Director (301) 869 8010 June 30, 1980 SLNRC 80- 32 FILE: 0491.10.2 SUBJ: Postulated Feedwater Line Piping Break Mr. Boyce Grier Director, Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prut.sia, Pennsylvania 19406 Docket Nos. STN 50-452, STN 50-483, STN-485, STN 50-486
Dear Mr. Grier:
On June 2, 1980, SNUPPS informed the Nuclear Regulatory Commission, Region I Office of Inspection and Enforcement, of a potential deficiency involving excessive pressures in feedwater lines following a postulated high energy line break. The inforraation was communicated by telephone to Mr. Richard McGaughy of your staff pursuant to 10CFR50.55(e).
For a postulated feedwater line break in the turbine building of a SNUPPS plent, Bechtel has calculated a peak pressure of approximately 4000 psi in the feedwater lines between the steam generator and the feedwater check valve, following closure of the check valves which' are located just outside containment. This pressure has been evaluated to be unacceptably high. The peak pressure in the feedwater lines for this transient can be reduced by relocating the feedwater check valves inside containment, closer to the steam generators. This change is being evaluated by SNUPPS, Bechtel, and Westinghouse.
The excessive pressure described above was discovered hring the high energy line break analysis which is performed late in the design process after exact piping layout and support have been determined. It is considered part of nor-mal design evolution that potential problems such as this one are discovered and corrected. Therefore SNUPPS does not consider this matter to be report-able under 10CFR50.55(e). Any design, description, or analysis change that is required because of this feedwater line break consideration will be re-flected in a revision to the SNUPPS FSAR.
Ver truly yours, l
l E%c Nicholas A. Petrick RLS/dck/Bla3 cc: Mr. James G. Keppler, Director, Region III, USNRC Mr. Karl V. Seyfrit, Director, Recion IV, USNRC Mr. Victor Stello, Jr., Director, Office of I&E, USNRC S40 7310 N1