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Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML18016A9011999-04-12012 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 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 HNP-95-087, 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 Replaced1995-09-29029 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 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 ML20045H1071993-07-0909 July 1993 Part 21 Rept (Amend 2 to Enterprise Rept 159) Re Potential Defect in Power Cylinder Liner,Clarifying Recommended Corrective Action Delineated in .Replacement of Loose Fit Liners Will Eliminate Need for Further Insps ML20035E4861993-04-0707 April 1993 Part 21 Rept Re K-400 Circuit Breaker Failed to Meet Certain Rating Requirements Based on ANSI C37.16.Licensees Scheduled Tests on Modified Arc Chutes in Several Different Modes at KEMA-Powertest Lab in Chalfont,Pa ML20034F7031993-02-25025 February 1993 Amend 1 to Enterprise Rept 162 Re Defect on Starting Air Distributor Housing Assembly,As Followup to 930115 Final Rept.Addl Listed Part Numbers Discovered Which Are Higher Level Assemblies of Housing 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 ML13316A1381992-11-25025 November 1992 Part 21 Rept Re Potential Problem W/Cylinder Heads Cast Prior to 840801 in Dsrv & Dsr Enterprise Standby Diesel Generator Sys.Caused by Inadequate Casting Wall Thickness at Tapped Hole.Oil Analysis Should Be Performed Monthly 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 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 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 ML13316A0841992-01-15015 January 1992 Part 21 Rept 159 Re Potential Defect in Power Cylinder Liner in Diesel Engine of DSR-48 & DSRV-16-4 Standby Diesel Generator Sys.Investigation Continuing & Expected to Be Complete on 920301 ML13316A0791991-06-19019 June 1991 Part 21 Rept Re Potential Defect in Component of Dsr or Dsrv Standby Diesel Generator Sys Involving Intake & Exhaust Power Valve Springs Mfg by Associated Spring.Recommends That Springs Be Inspected on Periodic Basis ML13316A0631990-07-19019 July 1990 Part 21 Rept Re Potential Problem W/Starting Air Admission Valve in Starting Air Sys.Caused by Air Start Piston Sticking in Air Start Valve Cap.Recommendations for Corrective Actions Forthcoming ML20006A3611990-01-17017 January 1990 Part 21 Rept 152 Re Potential Defect in Component of Dsr or Dsrv Standby Diesel Generator Sys Supplied to Listed Sites by Cooper Industries.Qualified Replacement Valve in Process of Being Specified.Info Will Be Available by 900215 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 ML13316A0401989-11-28028 November 1989 Part 21 Rept 151 Re Intake Rocker Arm Assembly of Standby Diesel Generator.Deficiency Covers Potential Interface Between Connector Push Rod & End Socket of Rocker Arm. Initially Reported on 891013.Rocker Arm Sketch Encl 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 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 ML16342C3461987-12-0303 December 1987 Followup to Gulf States Utils Part 21 Rept Re Wound Rotor Pole in Generator Unit of Standby Diesel Generator.Generator Mfg by NEI Peebles - Electric Products,Inc & Supplied to Util by Imo Delaval,Inc.Failure Analysis Being Conducted 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 ML20213F8101986-11-10010 November 1986 Interim Deficiency Rept,Item 233,re Electrical Separation. Initially Reported on 860822.Addl Time Necessary to Submit Final Rept.Final Rept Expected on 861210 ML20215K5301986-10-14014 October 1986 Deficiency Rept,Item 234 Re Structural Steel Welds Not Meeting Project Acceptance Criteria.Initially Reported on 860921.Item Not Reportable Per 10CFR50.55(e) & 10CFR21, Confirming 861014 Telcon ML20215K5651986-10-14014 October 1986 Deficiency Rept,Item 231 Re Use of Hylomar Thread Sealant in Stainless Steel Applications.Initially Reported on 860814. Item Not Reportable Per 10CFR50.55(e) Confirming 861014 Telcon ML20215G5351986-10-10010 October 1986 Part 21 Rept Re Vendor Tests of air-operated Diaphragm Valves Revealing Natural Frequencies Less than Required Values of 33 Hz.Initially Reported on 841227.No Adverse Effects Noted During Testing ML20215G6801986-10-10010 October 1986 Part 21 Rept Re Vendor Tests of air-operated Diaphragm Valves Revealing Natural Frequencies Less than Required Values of 33 Hz.Initially Reported on 841227.No Adverse Effects Noted During Testing 1999-04-12
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML18017A9221999-10-19019 October 1999 Safety Evaluation Supporting Amend 92 to License NPF-63 05000400/LER-1999-008-01, :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.With1999-10-0808 October 1999
- 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
ML18017A8971999-10-0404 October 1999 SER Accepting Licensee Responses to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves ML18017A9011999-10-0404 October 1999 Safety Evaluation Accepting Rev 99-1 to Harris Nuclear Plant Eals.Changes Meet Requirements of 10CFR50.47(b)(4) & App E to 10CFR50 HNP-99-151, Monthly Operating Rept for Sept 1999 for Shearon Harris Npp. with1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Shearon Harris Npp. with ML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data ML18017A8801999-09-17017 September 1999 Safety Evaluation Supporting Amend 91 to License NPF-63 ML18017A8741999-09-14014 September 1999 Safety Evaluation Supporting Amend 90 to License NPF-63 05000400/LER-1999-007-02, :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.With1999-09-10010 September 1999
- 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
HNP-99-137, Monthly Operating Rept for Aug 1999 for Harris Nuclear Plant.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Harris Nuclear Plant.With 05000400/LER-1999-006, :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 Revised1999-08-0404 August 1999
- 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
HNP-99-126, Monthly Operating Rept for July 1999 for Shearon Harris Nuclear Power Plant.With1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Shearon Harris Nuclear Power Plant.With HNP-99-110, Monthly Operating Rept for June 1999 for Shearon Harris Npp. with1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Shearon Harris Npp. with ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML18016A9941999-06-18018 June 1999 SER Authorizing Licensee Relief Request 2RG-008,pursuant to 10CFR50.55a(a)(3)(ii) for Second 10-year Interval of Shearon Harris Nuclear Power Plant ISI Program HNP-99-099, Monthly Operating Rept for May 1999 for Shearon Harris Nuclear Plant,Unit 1.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Shearon Harris Nuclear Plant,Unit 1.With ML18017A8981999-05-12012 May 1999 Technical Rept Entitled, Harris Nuclear Plant-Bacteria Detection in Water from C&D Spent Fuel Pool Cooling Lines HNP-99-089, Monthly Operating Rept for Apr 1999 for Shearon Harris Nuclear Plant,Unit 1.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Shearon Harris Nuclear Plant,Unit 1.With 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 05000400/LER-1999-005, :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.With1999-04-12012 April 1999
- 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
ML18016A9001999-04-0808 April 1999 Safety Evaluation Supporting Amend 88 to License NPF-63 05000400/LER-1999-004, :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.With1999-04-0808 April 1999
- 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
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 HNP-99-066, Monthly Operating Rept for Mar 1999 for Shearon Harris Nuclear Power Plant.With1999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Shearon Harris Nuclear Power Plant.With HNP-99-047, Monthly Operating Rept for Feb 1999 for Shearon Harris Npp. with1999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Shearon Harris Npp. with ML18017A8931999-02-28028 February 1999 Risks & Alternative Options Associated with Spent Fuel Storage at Shearon Harris Nuclear Power Plant 05000400/LER-1999-003, :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.With1999-02-22022 February 1999
- 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
ML18016A8531999-02-18018 February 1999 Non-proprietary Rev 3 to HI-971760, Licensing Rept for Expanding Storage Capacity in Harris SFP C & D 05000400/LER-1999-002, :on 990114,RT Due to Not Removing Temporary Device from Relay Following Calibration Was Noted.Caused by Human Error.Counseled Personnel Involved in Event.With1999-02-12012 February 1999
- 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
05000400/LER-1999-001, :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.With1999-02-0505 February 1999
- 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
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 HNP-99-020, Monthly Operating Rept for Jan 1999 for Shearon Harris Nuclear Power Plant.With1999-01-31031 January 1999 Monthly Operating Rept for Jan 1999 for Shearon Harris Nuclear Power Plant.With 05000400/LER-1998-004, :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 Vendor1999-01-29029 January 1999
- 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
HNP-99-003, Monthly Operating Rept for Dec 1998 for Shearon Harris Npp. with1998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Shearon Harris Npp. with HNP-98-181, Monthly Operating Rept for Nov 1998 for Shnpp,Unit 1.With1998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Shnpp,Unit 1.With HNP-99-086, Changes,Tests & Experiments, for Harris Nuclear Plant.Rept Provides Brief Description of Changes to Facility & Summary & of SE for Each Item That Was Implemented Under 10CFR50.59 Between 970608-981128.With1998-11-28028 November 1998 Changes,Tests & Experiments, for Harris Nuclear Plant.Rept Provides Brief Description of Changes to Facility & Summary & of SE for Each Item That Was Implemented Under 10CFR50.59 Between 970608-981128.With ML18016A8351998-11-28028 November 1998 ISI Summary 8th Refueling Outage for Shearon Harris Power Plant,Unit 1 ML18016A7411998-11-25025 November 1998 Rev 1 to Shnpp Cycle 9 Colr 05000400/LER-1998-007, :on 981023,turbine Control Anomaly Caused Manual Rt.Caused by Failure to Incorporate Verbal Vendor Guidance in Operating Procedures.Addl Vendor Guidance Will Be Verified & Added to Procedures.With1998-11-17017 November 1998
- on 981023,turbine Control Anomaly Caused Manual Rt.Caused by Failure to Incorporate Verbal Vendor Guidance in Operating Procedures.Addl Vendor Guidance Will Be Verified & Added to Procedures.With
ML18016A7181998-11-0606 November 1998 SER Approving Alternative Method to ASME Code in Regards to Surface Exam of Weld Repairs for Canopy Seals for Shearon Harris Nuclear Power Plant,Unit 1 ML18016A6721998-11-0404 November 1998 Safety Evaluation Authorizing Relief for Requests 2RG-009 & 2R1-010,per 10CFR50.55a(a)(3)(i) ML18016A7071998-11-0303 November 1998 Rev 0 to Harris Unit 1 Cycle 9 Colr HNP-98-164, Monthly Operating Rept for Oct 1998 for Shearon Harris Nuclear Power Plant.With1998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Shearon Harris Nuclear Power Plant.With ML18016A6161998-10-0707 October 1998 Safety Evaluation Supporting Amend 83 to License NPF-63 ML20154F8701998-10-0606 October 1998 Safety Evaluation Authorizing Proposed Alternative to Requirements of OMa-1988,Part 10,Section 4.2.2.3 for 21 Category a Reactor Coolant Sys Pressure Isolation Valves HNP-98-148, Monthly Operating Rept for Sept 1998 for Harris Nuclear Power Plant.With1998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Harris Nuclear Power Plant.With ML18016A5971998-09-21021 September 1998 Rev 1 to Harris Unit 1 Cycle 8 Colr ML18016A5831998-09-11011 September 1998 Safety Evaluation Supporting Amend 82 to License NPF-63 1999-09-30
[Table view] |
Text
REGULATOR INFORMATION DIS TRI ACCESSION NBR: 6011200386 DOC ~ DATE; 80/11/1 FACIL;50-000 Shearon Harris Nuclear Power Pl 50-001 Shearon Harris Nuclear Power Pl 50-403 Shearon Harris Nuclear Power Pl AUTH BYNAME AUTHOR AFF11LtiATION CHIANGI < N, J.
Cv r o 1 ti na P owe r 8 Light Co.
RECIP NAME RECAP IEN'T AFFILIATION O'REILLYPJ,P
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NOTARIZED:
NO anti Unit ii Carolina antR Unit 2i Carolina anti Unit 4i Carolina 0 Nl'T 3, (p~ i i m~
of the Director DOCKET" N OSOOOLIOO 05000001 05000403 a~%>
SUBJECT:
Inter1im deficiency rept re omission of>> protective'coating 8
existence of damaged coating on containment lineriinitially reported on 600917
~ Application of final coat of paint w/repairs to damaged areas 8 final rept expected by 610301,,
DISTRIBUTION CODE':
B0100 COPIES RECEIVED:LiTR + ENCLt Q SIZE:
TITLE; Construction Def ici ency Report (10CFRSO,SSEI)
NOTES:
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. James P. O'Reil.ly United States Huclear Regulatory Commission Region II 101 Marietta Street, Northwest Atlanta, Georgia 30303 SHEARON HARRIS NUCLEAR POWER PLAUDIT UNITS 1, 2 ~ 3, AND 4 DOCKET NOS. 50-400, 50-401, 50-402, AND 50-403 OMISSIOH OP PROTECTIVE COATING AND EXISTENCE OP DAMAGED COATING ON THE UNIT 1 CONTAINMENT LINER - INTERIM REPORT Dear Mr. O'Reillyt On September 17, 1980, the NRC (Mr. J. K. Rausch) was notified of the subject deficiency as being a potentially reportable item per the provisions of 10CPR50.55(e).
On October 17, 1980, the NRC (Mr. J. K. Rausch) was informed that the sub5ect deficiency was considered reportable per the provisions of 10CFR50.55(e).
The deficiency in question pertains to a section of the Unit 1 Containment Liner Plate, adjacent to the refueling canal slab (a two inch gap exists in this area) not having received the final coat of paint, and in some cases, areas of damaged coating not having been repaired.
The section in question is approximately five (5) feet in height and sixteen (16) feet long.
The intent of this letter is to inform you that corrective action has not been initiated to date since the formwork in this area has not been completely removed, and.
hence, accessibility is restricted.
It is now anticipated that all corrective action willbe completed by March 1, 1981, at which time the final 10CPR50.55(e) report willbe submitted.
When corrective action is implemented, it will consist of application of the final coat of paint and repairs to the damaged areas.
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Yours very truly, Original Signed Bp N. 3. Chiangi N. J. ChMgi - Manager Engineering 6 Construction Quality Assurance cc:
Mr. G. Haxwell Mr. V. Stello (2)v'
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