|
---|
Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML20217N3271999-10-21021 October 1999 Part 21 Rept Re non-linear Oxygen Readings with Two (2) Model 225 CMA-X Containment Monitoring Sys at Bsep.Caused by High Gain Produced by 10K Resistor Across Second Stage Amplifier.Engineering Drawings Will Be Revised ML18016A9011999-04-12012 April 1999 Part 21 Rept Re Defect in Component of DSRV-16-4,Enterprise DG Sys.Caused by Potential Problem with Connecting Rod Assemblies Built Since 1986,that Have Been Converted to Use Prestressed Fasteners.Affected Rods Should Be Inspected ML20140G4481997-05-0101 May 1997 Part 21 Rept Re Potential Defect in Component of Dsrv & Dsr Enterprise Standby Diesel Generator Sys.Recommends That Springs Be Inspected on Periodic Basis,Such as During Refueling Outages ML20134L1081996-10-10010 October 1996 Part 21 Rept Re Defect in Component of Nordberg Model FS1316HSC Sdg.Nak Engineering,Inc Has Established & Adopted Procedures to Assemble Fuel Oil Lines & Climinate Possible Defective Condition ML20116H2031996-08-0505 August 1996 Part 21 Rept Re Potential Defect on Condition in Component of Nordberg Model FS1316HSC Sdg W/Fuel Injection Line Assembly Which Connects Fuel Pump to Injector.Caused by Loose Fuel Line Sleeve ML20115D2001996-07-0909 July 1996 Part 21 Rept Re Mfg Defect of Enterprise DSR-4 & DSRV-4 Edgs,Originally Mfg by Calcon Corp.Amot Control Corp Purchased Calcon Product Line & Maintains Design & Production.Valves Returned to Cooper Energy Svcs on 960131 ML20117G4641996-05-14014 May 1996 Part 21 Rept Re Cooper Bessemer Reciprocating Products,Div of Cooper Cameron Corp,Issued Ltr to Define Utils/Plants Containing Similar Equipment as Supplied on Cooper Bessemer Ksv & Enterprise Dsr EDGs ML20097A5641996-01-31031 January 1996 Final Part 21 Rept Re Ball Valves Supplied by Cardinal Industrial Products Containing Suspect Pressure Boundary Bolting.Valves Containing Suspect Bolts Returned to Canadian Worcester Controls Ltd to Have Bolting Replaced ML18022A9701995-09-29029 September 1995 Part 21 Rept Re Failure of Charging SI Pump Miniflow Check Valves.Caused by Cocking of Piston Towards Valve Outlet Port Due to Large Hydraulic Surge.Valves That Experienced Failures Replaced ML20092H3641995-09-13013 September 1995 Part 21 Rept Re 3/4 Inch ASME Section III Class 2 Ball Valves Supplied by Canadian Worcester Controls Ltd (Cwcl) ML20059H7721994-01-17017 January 1994 Part 21 Rept Re Virginia Power Notifying Fairbands Morse Via Failure Analysis Rept NESML-Q-058 of Defective Air Start Distributor cam,16104412 ML20059F2631994-01-0707 January 1994 Part 21 Rept Re Air Start Distributor Cam Mfg by Fairbanks Morse.Mfg Suggests That Site Referenced in Encl App I Inspect Air Start Distributor Cam as Soon as Practical ML20058K3841993-12-0909 December 1993 Part 21 Rept Re Potential Defect in Component of Dsrv & Dsr Enterprise Standby DG Sys,Regarding Potential Problem W/ Subcover Assembled Atop Power Head ML20127H2301993-01-15015 January 1993 Part 21 Rept Re Potential Defeat in Component of Dsrv & Dsr Enterprise Standby DG Sys.Starting Air Distributor Housing Assemblies Installed as Replacement Parts at Listed Sites 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 ML20126B0421992-12-17017 December 1992 Final Part 21 Rept Re Potential Problem W/Steel Cylinder Heads.Initially Reported on 921125.Caused by Inadequate Cast Wall Thickness at 3/4-inch-10 Bolt Hole.Stud at Location Indicated on Encl Sketch Should Be Removed 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 ML20118B4391992-09-11011 September 1992 Part 21 Rept Re Degradation in Abb Type 27N Undervoltage Relays Used in Electrical Switchgear.Recommends That Users Review Applications Requiring Exposures Greater than 1E03 Rads TID W/Time Delay Function Option ML17289A6971992-06-26026 June 1992 Amend 1 to Part 21 Rept 158 Re gear-wear Induced Failures in engine-driven Jacket Water Pump in DSRV-16-4 Standby DG Sys. Initially Reported on 911029.Grand Gulf Station Observed Wear Characteristics in as Little as 500 Operating Hours ML20095J3061992-04-24024 April 1992 Initial Part 21 Rept Re Defectively Installed Bolting in Emergency Diesel Generator Bldg Internal Wall Seismic Supports.Repairs to Reestablish Seismic Qualification of Walls Continuing & Emergency Buses Declared Inoperable ML18010A5701992-03-23023 March 1992 Initial Part 21 Rept Re Defect in Anchor Darling Supplied Main Feedwater Preheater Bypass Isolation Valves.On 920112, All non-Q Components Replaced W/Suitable Components & Tested Satisfactorily.Next Rept Will Be Submitted by 920214 ML20094L1271992-03-13013 March 1992 Amend 1 to Part 21 Rept 159 Re Potential Defect in Power Cylinder Liner.Initially Reported on 920115.Caused by Liner/ Block Fit & Localized Matl Microstructure.All Drawings & Specs Revised to Address Matl Design Requirements ML18010A5071992-01-16016 January 1992 Initial Part 21 Rept Re Deficiency in Actuator to Main Feedwater Preheater Bypass Isolation Valves.On 920107,2 H Surveillance Interval Was Commenced to Verify Actuator Components Were Functioning Properly ML20079G8921991-08-27027 August 1991 Part 21 Rept Re Failure of Normally Energized Asco Model L206-832 Solenoid Valves Due to Gelling of Lubricant (Dow Corning 550).Initially Reported on 910826 Via Telcon.Ler 2-91-005 Re ESF Actuations Caused by Transient Encl ML20077A4041991-04-29029 April 1991 Deficiency Rept Re Possible Mfg Problems W/Certain Coils Used on Asco Nuclear Qualified Valves.Problems Discussed in NRC Info Notice 86-057.All Purchasers Will Be Notified & Replacement Product Will Be Offered If Item Still in Svc BSEP-91-0191, Part 21 Rept Re Discrepancy Noted Between Torque Indicated by motor-actuator Characterization Sys & Output Torque Measured by Limitorque Actuator Test Stand.Initially Reported on 910426.Vendor Contacted Re Software Problem1991-04-29029 April 1991 Part 21 Rept Re Discrepancy Noted Between Torque Indicated by motor-actuator Characterization Sys & Output Torque Measured by Limitorque Actuator Test Stand.Initially Reported on 910426.Vendor Contacted Re Software Problem ML20043A6091990-04-27027 April 1990 Part 21 Rept Re Defective Axial Cracks in Pump Shaft in Region Immediately Above Impeller & in Reactor Recirculation Pumps.Probably Caused by Crack Growth as Thermal Fatigue. Technical Advisory Bulletin Will Be Sent to Each Util 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 ML20011D4321989-12-15015 December 1989 Suppl to Part 21 Rept Re Completion of Replacement of Unit 1 CR205 Series Auxiliary Contacts w/CR305 Contacts.Initially Reported on 871030.Implementation of Five of Six Auxiliary Contacts Extended Until 900131 ML19325E4571989-10-20020 October 1989 Part 21 Rept Re Potential Inconsistencies in Mac Diagnostic Sys Software.Licensee to Review All Smb,Sb & Sbd Size 3 Mac Torque Test Data Using Mac Software Version 2.96 to Insure That Torque Switch Settings Meet Valve Design Requirements ML20248E0121989-09-13013 September 1989 Supplemental Part 21 Rept Re Potential Problem W/Six Specific Engine Control Devices in Air Start,Lube Oil, Jacket Water & Crankcase Sys.Initially Reported on 890429. California Controls Co Will Redesign Valve Seating ML18005B0321989-08-25025 August 1989 Potential Part 21 Rept Re ITE-Siemens molded-case Circuit Breakers Not Holding Required Load,Resulting in Inoperability.Motor in-rush Current Tests Will Be Performed on S-4 Motor to Determine If Correct Breaker Utilized ML18005B0081989-07-26026 July 1989 Part 21 Rept Re Potential Failure of Main Steam PORVs Supplied by Control Components,Inc.Initially Reported on 890719.Cause of Failure Speculated to Be Dirt or Corrosion Particles Preventing Ring from Sealing.Porv Trim Modified BSEP-89-0342, Part 21 Rept Re Problem in Pump Suction & Discharge Valves of Standby Liquid Control Sys.Initially Reported on 890427. Evaluation Found Defect Consisting of Casting Flaws/Surface Irregularities in Valves1989-05-0101 May 1989 Part 21 Rept Re Problem in Pump Suction & Discharge Valves of Standby Liquid Control Sys.Initially Reported on 890427. Evaluation Found Defect Consisting of Casting Flaws/Surface Irregularities in Valves ML20247P7991989-04-0404 April 1989 Part 21 Rept Re Atmospheric Dump Valves.Cause of Failure Speculative But Result of Piston Ring That Failed to Seal. Resolution to Problem Requires Increasing Pilot Valve Capacity & Reworking of Plug to Enlarge Pilot Flow Area ML20207P0451988-10-0505 October 1988 Part 21 Rept 146 Re Defect in Left Intercooler Inlet Adapter on Standby Diesel Engine Generator.Recommends Utils Inspect Left Intake Manifold Drain as Part of Operating Plan.Addl Info Expected by 881015 ML18005A6551988-09-29029 September 1988 Part 21 Rept Re Deficiency in Control & Power Circuits for Dc motor-operated Valves Due to Lack of Surge Protection. Initially Reported on 880518.Interim Measures Established to Ensure Proper Operation of Valves Until Surge Installed ML18005A4401988-05-18018 May 1988 Part 21 Rept Re Dc Motor Failure on Auxiliary Feedwater Limitorque Operated Valves.Plant Mod Will Be Implemented to Install Surge Protection for Shunt Coil Circuitry of Subject Dc Motors ML20154J4101988-05-12012 May 1988 Addendum 1 to Supplemental Part 21 Rept 145 Re Potential Problem w/F-573-156 Pressure Sensor/Lube Oil Trip.Initially Reported on 880429.Addl 1-1/8-inch Diameter W/Deep Counterbone in Pressure Head Added to Activate Valve ML20153B6191988-04-29029 April 1988 Part 21 Rept Re Potential Defect in Component of Dsr or Dsrv Standby Diesel Generators Supplied to Utils.Recommends Return of Subj Components in Onsite Warehouse Storage & Suggests Surveillance of Devices Already Installed BSEP-87-1205, Part 21 Rept & Deficiency Rept Re Defective GE CR205X Series Auxiliary Contacts.Initially Reported on 871027.Contacts for Loads Listed in Attachment 3 Will Be Replaced on Unit 1 by 880701 & by 881101 on Unit 21987-10-30030 October 1987 Part 21 Rept & Deficiency Rept Re Defective GE CR205X Series Auxiliary Contacts.Initially Reported on 871027.Contacts for Loads Listed in Attachment 3 Will Be Replaced on Unit 1 by 880701 & by 881101 on Unit 2 ML18004B9461987-09-22022 September 1987 Part 21 Rept Re Failure to Postulate Unavailability of Vital Dc Bus in Conjunction W/Auxiliary Feedwater (AFW) Isolation Design.Afw Isolation Logic Modified W/Westinghouse Involvement.Operation Will Resume Upon Completion of Mods ML18004B8701987-07-0101 July 1987 Part 21 & Deficiency Rept Re LOCA Occurring During Modes 3 & 4.Initially Reported on 860815.Completion Date for Item Cannot Be Determined Due to Continued Westinghouse Owners Group Effort ML20234C7351987-06-23023 June 1987 Supplemental Part 21 Rept Re Silicone Foam Seal Anomolies at Wolf Creek Generating Station ML20216E4721987-05-28028 May 1987 Part 21 Rept 140 Re Potential Defect in Air Pressure Regulators Mfg by Bellofram.Dripwell Gasket May Fail Due to Mismachining of Gasket Seating Surface Causing Loss of Control Air & Starting Air Pressure ML20207R7031987-03-11011 March 1987 Part 21 Rept Re Potential Defect in Static Exciter Voltage Regulator (Sevr) Reset Design.Recommends Mod to Control Circuits to Energize Sevr Upon Receipt of Emergency Start Signal.Mods Will Be Completed by 870331 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 ML20210E7901987-02-0404 February 1987 Part 21 Rept Re Incorrect Operation of Hfa Auxiliary Relays, Per 861114 GE Svc Advice Ltr 188.1.Relays Installed in Standby Diesel Generator Sys Af Plant.Svc Ltr Forwarded to Util ML20215F0041986-12-12012 December 1986 Final Deficiency Rept,Item 233 Re Quantity of Electrical Separation Interactions That Remained Undetected After Installation Insp.Initially Reported on 860822.Remaining Separation Interactions Identified,Reworked & Reinspected 1999-04-12
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217N3271999-10-21021 October 1999 Part 21 Rept Re non-linear Oxygen Readings with Two (2) Model 225 CMA-X Containment Monitoring Sys at Bsep.Caused by High Gain Produced by 10K Resistor Across Second Stage Amplifier.Engineering Drawings Will Be Revised ML18017A9181999-10-0808 October 1999 LER 99-008-00:on 991008,CR Emergency Filtration Sys Tech Specs Occurred.Caused by Site Personnel Failed to Recognize That Blocking Open CR Emergency Filtration Sys.Procedures Revised.With 991008 Ltr ML18017A9151999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Shearon Harris Npp. with 991012 Ltr ML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data BSEP-99-0168, Monthly Operating Repts for Sept 1999 for Bsep,Units 1 & 2. with1999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Bsep,Units 1 & 2. with ML18017A8671999-09-10010 September 1999 LER 99-007-00:on 990811,determined That Cvis ARMs High Alarm Setpoints Were Not within TS Limit.Caused by Not Having Procedure to Verify If Cvis ARM High Alarm Setpoints Were within TS Requirements.Revised Procedures.With 990910 Ltr ML20212D0431999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Brunswick Steam Electric Plant,Units 1 & 2 ML18017A8621999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Harris Nuclear Plant.With 990908 Ltr ML20210P9181999-08-10010 August 1999 Safety Evaluation Authorizing Request for Reliefs CIP-01,02, 06,07,08,09,10 & 11 (with Certain Exceptions) & 12-18,for Second 10-year ISI Interval.Request CIP-04 & 05 Would Result in hardship,CIP-03 Not Required & CIP-11 Denied in Part ML20210P9441999-08-10010 August 1999 Safety Evaluation Accepting Licensee Assessment of Impact on Operation of Plant,Unit 1,with Crack Indications of 2.11, 6.36 & 1.74 Inches in Three Separate Jet Pump Risers ML20210N2341999-08-0505 August 1999 SER Accepting Response to NRC GL 87-02, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Unresolved Safety Issues (USI) A-46 ML18016B0481999-08-0404 August 1999 LER 99-006-01:on 981124,noted Failure to Comply with TS 4.0.4 & TS 3/4.6.3, Civs. Caused by post-maint Testing That Did Not Adequately Test Control Circuitry & Verify Isolation Time Following Maint.Procedure Was Revised ML18017A8361999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Shearon Harris Nuclear Power Plant.With 990811 Ltr ML20210R1191999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Bsep,Units 1 & 2 BSEP-99-0118, Monthly Operating Repts for June 1999 for Bsep,Units 1 & 2. with1999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Bsep,Units 1 & 2. with ML18016B0151999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Shearon Harris Npp. with 990713 Ltr ML20210R1311999-06-30030 June 1999 Revised Monthly Operating Rept for June 1999 for Bsep,Unit 2 ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML18016A9801999-06-0404 June 1999 LER 99-006-00:on 981124,failed to Comply with TS 4.0.4 & TS 3/4.6.3, Civ. Caused by post-maint Testing That Did Not Adequately Test Control Circuitry & Verify Isolation Time Following Maint.Procedure Will Be Revised.With 990604 Ltr BSEP-99-0095, Monthly Operating Repts for May 1999 for Brunswick Steam Electric Plant,Units 1 & 2.With1999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Brunswick Steam Electric Plant,Units 1 & 2.With ML18016A9851999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Shearon Harris Nuclear Plant,Unit 1.With 990614 Ltr ML20210M8581999-05-14014 May 1999 B214R1 RPV Hydrotest Bolted Connection Corrective Action Evaluation, Rev 0 ML18017A8981999-05-12012 May 1999 Technical Rept Entitled, Harris Nuclear Plant-Bacteria Detection in Water from C&D Spent Fuel Pool Cooling Lines. ML20211L3711999-05-10010 May 1999 Rev 0 to ESR 98-00333, Unit 2 Invessel Feedwater Sparger Evaluation ML20206G1871999-05-0404 May 1999 Safety Evaluation Approving Third 10-year ISI Program Requests for Relief (RR) RR-08,RR-15 & RR-17 ML18016A9581999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Shearon Harris Nuclear Plant,Unit 1.With 990513 Ltr BSEP-99-0075, Monthly Operating Repts for Apr 1999 for Brunswick Steam Electric Plant,Unit 1 & 2.With1999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Brunswick Steam Electric Plant,Unit 1 & 2.With ML20206N1791999-04-23023 April 1999 Rev 0 to 2B21-0554, Brunswick Unit 2,Cycle 14 Colr ML18016A9011999-04-12012 April 1999 Part 21 Rept Re Defect in Component of DSRV-16-4,Enterprise DG Sys.Caused by Potential Problem with Connecting Rod Assemblies Built Since 1986,that Have Been Converted to Use Prestressed Fasteners.Affected Rods Should Be Inspected ML18016A9111999-04-12012 April 1999 LER 99-005-00:on 990313,plant Exceeded ESFAS TS 3.3.2,Action 21.Caused by Inadequate Procedure Rev Preparation.Licensee Revised Applicable Maint Surveillance Test Procedure (MST-10072) to Identify TS Required Actions.With 990412 Ltr ML18016A8971999-04-0808 April 1999 LER 99-004-00:on 990312,unit Trip Was Noted.Caused by Degraded Condition of SG Water Level Flow Control Valve. Replaced Positioners on All Three FW Regulating Valves.With 990408 Ltr ML18016A8941999-04-0505 April 1999 Revised Pages 20-25 to App 4A of non-proprietary Version of Rev 3 to HI-971760 ML18016A8661999-03-31031 March 1999 Shnpp Operator Training Simulator,Simulator Certification Quadrennial Rept. ML18016A9101999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Shearon Harris Nuclear Power Plant.With 990413 Ltr BSEP-99-0059, Monthly Operating Repts for Mar 1999 for Brunswick Steam Electric Plant,Units 1 & 2.With1999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Brunswick Steam Electric Plant,Units 1 & 2.With ML20205F9031999-03-30030 March 1999 Safety Evaluation Supporting Proposed Rev to BSEP RERP to Licenses DPR-62 & DPR-71,respectively ML18016A8551999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Shearon Harris Npp. with 990312 Ltr BSEP-99-0043, Monthly Operating Repts for Feb 1999 for Brunswick Steam Electric Plant,Units 1 & 2.With1999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Brunswick Steam Electric Plant,Units 1 & 2.With ML20206N1831999-02-28028 February 1999 Rev 0 to Suppl Reload Licensing Rept for Bsep,Unit 2 Reload 13 Cycle 14 ML18017A8931999-02-28028 February 1999 Risks & Alternative Options Associated with Spent Fuel Storage at Shearon Harris Nuclear Power Plant. ML18016A8261999-02-22022 February 1999 LER 99-003-00:on 990123,noted That Plant Was Outside Design Basis Due to Isolation of Fire Protection Containment Sprinkler Sys.Caused by Human Error.Restored Containment Sprinkler Sys to Operable Status.With 990222 Ltr ML18016A8531999-02-18018 February 1999 Non-proprietary Rev 3 to HI-971760, Licensing Rept for Expanding Storage Capacity in Harris SFP 'C' & 'D'. ML18016A8111999-02-12012 February 1999 LER 99-002-00:on 990114,RT Due to Not Removing Temporary Device from Relay Following Calibration Was Noted.Caused by Human Error.Counseled Personnel Involved in Event.With 990212 Ltr ML20203D7061999-02-0909 February 1999 SER Accepting Proposed Alternatives Contained in Relief Requests PRR-04,VRR-04,VRR-13,PRR-01,PRR-03,VRR-01.VRR-07, VRR-08 & VRR-09 Denied ML18016A7971999-02-0505 February 1999 LER 99-001-00:on 990106,SF Pool Water Level Was Not Maintained Greater than 23 Feet Above Stored BWR Fuel Assemblies.Caused by Fasteners Bending Under Specific Circumstances.Increased Water Level.With 990205 Ltr ML18022B0631999-02-0404 February 1999 Rev 0 to Nuclear NDE Manual. with 28 Oversize Uncodable Drawings of Alternative Plan Scope & 4 Oversize Codable Drawings ML20202J1161999-02-0101 February 1999 SER Accepting Relief Requests Associated with Second 10-year Interval Inservice Testing Program ML18016A8041999-01-31031 January 1999 Monthly Operating Rept for Jan 1999 for Shearon Harris Nuclear Power Plant.With 990211 Ltr ML18016A7941999-01-29029 January 1999 LER 98-004-01:on 980313,identified Design Deficiency Re Potential Runout of Tdafwp.Caused by Inadequate Original AFW Sys Design.Operability Evaluation Was Completed on 980313 & Addl Engineering Analysis Was Performed by Vendor ML18016A7801998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Shearon Harris Npp. with 990113 Ltr 1999-09-30
[Table view] |
Text
- -
h' w '
Cp&L Carolina Power & Lig,ht Co,mpany P.O. Box 101, New Hill, N.C. 27562 July 13, 1984 Mr. James P. O'Reilly NRC-238 United States Nuclear Regulatory Commission ._
Region II T 101 Marietta Street, Northwest (Suite 2900)
Atlanta, Georgia 30323 CAROLINA POWER & LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT 1986 - 900,000 KW - UNIT 1 SEISMIC RESTRAINT STRUCTURES, ITEM 160
Dear Mr. O'Reilly:
Attached is our second interim report on the subject item whf ch was deemed reportable per the provisions of 10CFR50.55(e) on March 6, 1984. CP&L is pursuing this matter, and it is currently projected that corrective action and submission of the final report will be accomplished by March 31, 1985.
Thank you for your consideration in this matter.
Yours very truly, gr -k , -
a R. M. Parsons Project General Manager Shearon Harris Nuclear Power Plant RMP/ jam Attachment cc Messrs. G. Maxwall/R Prevatte (NRC-SHNPP)
Mr. R. C. DeYoung (NRC) 8408090018 840713 F.gI F1CI At> COPY PDR ADOCK 05000325 B PDR '-
9 s
.~
-]
CAROLINA POWER & LICHT COMPANY
.SHEARON HARRIS NUCLEAR POWER PLANT UNIT NO. 1 i
SECOND INTERIM REPORT SEISMIC RESTRAINT STRUCTURES ITEM 160 JULY 13, 1984
.i .
REPORTABLE UNDER 10CFR50.55(e) r,
q ll . 's 1
, . n
(
SUBJECT:
10CFR50.55(e) Reportable Item, Shearon Harris Nuclear -
Power Plant. Unit 1. Deficient shop welds on seismic restraint structures received from Pittsburgh Bridge and Iron-(PBI) Industries.
s 5,
.t . ,
ITEM: ' Seismic restraint structures supplied on Purchase Order NY-435196.
1
~^
w SUPPLIED BY: Pittsburgh Bridge and Iron Industries, Rochester, ,
Pennsylvania NATURE OF DEFICIENCY: 1. Undersized welds and missing welds
- 2. Cosmetic weld defects
- 3. Base metal damage
- 4. Incorrect weld symbols and welds not per design
's DATE PROBLEM OCCURRED: Weld defects resulted during the fabrication of these items in 1979. However, the problems were not identified until January 26, 1984 when the frames received an on-site primary inspection of the shop s
weids.
- DATE PROBLEM REPORTED: On March 6, 1984, CP&L (Mr. N. J. Chiangi) notified
(' the NRC (Mr. A. Hardin) that the February 9,1984 potentially reportable item (Item 160) was reportable per the provisions of 10CFR50.55(e).
SCOPE OF PROBLEM: In our first interim report, fifty (50) seismic restraint structures, which were fabricated by PBI Industries for CP&L use on Shearon Harris Nuclear Power Plant, Unit 1, were reported. 'Since that time, further investigation has revealed that the remaining PBI restraint structures are now suspect.
SAFETY IMPLICATIONS: Deficient shop welds could cause a safety-related restraint structure to fail under seismic conditions.
\ As a result. if not. corrected, they could adversely affect the safe operation of this facility.
L
..v ,
) ,
1 REASON DEFICIENCY
.IS REPORTABLE: The number of deficiencies represent a significant' condition which would require extensive evaluation for reportability. The item represents a breakdown in'the PBI and Ebasco QA programs, which allowed structures to
, "be shipped with welds which were not in accordance with design criteria. Therefore, the ,
item is reportable under 10CFR50.55(e).
CORRECTIVE ACTION: QC weld inspection of PBI restraint structure shop welds is being performed to identify those welds which will require disposition. Welds which are found not.to meet the acceptance criteria of Ebasco Drawing CAR-2165-A003 R5 will be reworked or waivered per engineering evaluation.
FINAL REPORT: A final report will be issued once the
. corrective actions described above.have been cowpleted. It is currently projected that the final report.will be submitted by March 31, 1985.
.d I
l
. , __, , . ~ - - . , , , , . _ - , . . ., ,,_, , _ _ .,