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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 ML20207M9231999-03-12012 March 1999 Amended Part 21 Rept Re Cooper-Bessemer Ksv EDG Power Piston Failure.Total of 198 or More Pistons Have Been Measured at Seven Different Sites.All Potentially Defective Pistons Have Been Removed from Svc Based on Encl Results 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 ML20133E8001997-01-0808 January 1997 Deficiency Rept Re Nonconformance Related to Masterflow 713 Grout,Which Master Builders,Inc Has Supplied as Nuclear SR Product to 18 Npps.Cause Unknown.Requests That Listed Info Be Provided to Gain Insight as to Scope & Possible Cause 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 ML20085J6591995-06-15015 June 1995 Potential Part 21 Rept Re Failure of Air Cylinder Mfg by Bellofram Corp at Ggns.Failure Discussed W/Mfg & Judged to Be Isolated Incident W/No Further C/A Required at Affected Utils or Cooper-Bessemer ML18038A8971994-09-0707 September 1994 Part 21 Rept Re Defect in Latching Mechanism of Potter & Brumfield Relay on C&D High Voltage Shut Down Alarm Assembly Printed Circuit Boards.Pull Test on Relay Reset Button Incorporated Into Receiving Insp Procedures 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 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 ML20101G9211992-06-19019 June 1992 Part 21 Rept Re Rotated Fuel Assemblies Sometimes Inappropriate for Modern Type Fuel Designs.Reevaluation Concluded That Inadvertently Rotated Fuel Assembly for BWR 4/5 C-lattice Plant Could Not Exceed TS Safety Limit MCPR ML20090L8801992-03-18018 March 1992 Part 21 Re Cracked Piston Castings Received from Acme Foundry,Fairbanks Morse & General Casting.Magnetic Particle Insp of All Pistons Will Be Performed.List of Affected Plants Encl AECM-90-0196, Final Part 21 Rept Re Automatic Switch Co MSIVs Failing to Close Upon Demand from Automatic & Remote Manual Actuation Signals.Initially Reported on 890914.Dual Solenoid Valves Replaced W/Two Single Solenoid Valves1990-11-21021 November 1990 Final Part 21 Rept Re Automatic Switch Co MSIVs Failing to Close Upon Demand from Automatic & Remote Manual Actuation Signals.Initially Reported on 890914.Dual Solenoid Valves Replaced W/Two Single Solenoid Valves ML20043F3431990-06-0808 June 1990 Part 21 Rept Re Circumferential Grove of Varying Depth Up to 0.200 Inches on Inside Surface of Journal Above Attachment Weld to Impeller.Failure of Journal Could Result in Major Damage to Pump.Disassembly Scheduled Over Next 18 Months ML20043G7641990-05-22022 May 1990 Part 21 Rept Re Potential Defect W/Speed Transmitter in Diesel Engine Control Panel of Dsrv Standby Diesel Generator.Estimate of Completion of Corrective Actions Not Possible,Since Correction Made by Other Companies 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 ML19332E2971989-11-22022 November 1989 Revised Part 21 Rept Re MSIV Failure to Close Due to Disk Matl for Dual Solenoid Valve Extruding Into Exhaust Port of Valve.Initially Reported on 890914.Dual Solenoid Valve Replaced or Refurbished Prior to Restart AECM-89-175, Part 21 Rept Re Failure of MSIV to Close Due to Malfunction of Valve.Initially Reported on 890914.Dual Solenoid Valves on All MSIVs Replaced or Refurbished Prior to Restart.Update to Be Submitted by Startup from Fourth Refueling Outage1989-09-18018 September 1989 Part 21 Rept Re Failure of MSIV to Close Due to Malfunction of Valve.Initially Reported on 890914.Dual Solenoid Valves on All MSIVs Replaced or Refurbished Prior to Restart.Update to Be Submitted by Startup from Fourth Refueling Outage AECM-89-0175, Part 21 Rept Re Failure of MSIV to Close Due to Malfunction of Valve.Initially Reported on 890914.Dual Solenoid Valves on All MSIVs Replaced or Refurbished Prior to Restart.Update to Be Submitted by Startup from Fourth Refueling Outage1989-09-18018 September 1989 Part 21 Rept Re Failure of MSIV to Close Due to Malfunction of Valve.Initially Reported on 890914.Dual Solenoid Valves on All MSIVs Replaced or Refurbished Prior to Restart.Update to Be Submitted by Startup from Fourth Refueling Outage 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 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 AECM-88-0190, Part 21 Rept Re Diesel Generator Left Bank Intercooler Tubes,Mfg by Imo Delaval.Leaks Initiated When Tubes Ruptured by Diffuser Plate in Inlet Adaptor.Initially Reported on 880930.Intercooler Replaced1988-09-30030 September 1988 Part 21 Rept Re Diesel Generator Left Bank Intercooler Tubes,Mfg by Imo Delaval.Leaks Initiated When Tubes Ruptured by Diffuser Plate in Inlet Adaptor.Initially Reported on 880930.Intercooler Replaced 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 ML20215G2441987-06-16016 June 1987 Part 21 Rept Re Failure of Load Sequencing Equipment Supplied in Aug 1977 During Scheduled Testing.Caused by Open Electrical Connection on One Crimp Lug.Since 1978,insulated Lugs Used on All Equipment 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 AECM-86-0409, Informs That Testing Program for Final Reportability Determination on as-found Conditions of Sealed Splices Delayed Until Feb 1987,per 861212 Telcon.Program Includes Raychem Tube Configurations Found in BWR & PWR Applications1986-12-19019 December 1986 Informs That Testing Program for Final Reportability Determination on as-found Conditions of Sealed Splices Delayed Until Feb 1987,per 861212 Telcon.Program Includes Raychem Tube Configurations Found in BWR & PWR Applications AECM-86-0400, Deficiency Rept Re Wiring in Environmentally Qualified Actuators on air-operated Valves.Initially Reported on 861117.Matl Analysis of Wiring Samples Underway. Reportability Determination Will Be Completed in Jan 19871986-12-18018 December 1986 Deficiency Rept Re Wiring in Environmentally Qualified Actuators on air-operated Valves.Initially Reported on 861117.Matl Analysis of Wiring Samples Underway. Reportability Determination Will Be Completed in Jan 1987 AECM-86-0376, Final Deficiency & Part 21 Rept 4 Re Low Flow Condition Through Standby Svc Water (SSW) Pump A.Initially Reported on 820415.Procedures to Ensure That Min Pump Flow Provided When SSW Sys Automatically Started,Issued1986-11-25025 November 1986 Final Deficiency & Part 21 Rept 4 Re Low Flow Condition Through Standby Svc Water (SSW) Pump A.Initially Reported on 820415.Procedures to Ensure That Min Pump Flow Provided When SSW Sys Automatically Started,Issued ML20206S0841986-06-30030 June 1986 Part 21 Rept Re Possible Cut Wires in Wire Harness of Bbc Brown Boveri K600/K800 Circuit Breakers.Initially Reported on 860509.Safety Implications Listed.Gear Guard Designed to Prevent Cut Wires ML20195D2171986-05-27027 May 1986 Rev 1 to Part 21 Rept Re Dowel Displacement on Connecting Rod Bearings Purchased During Nov 1985 - Apr 1986.Initially Reported on 860421.Rod Bearings Will Be Inspected Dimensionally.Further Info Forthcoming ML20203A0431986-04-0707 April 1986 Part 21 Rept Re Problem Which May Affect Operation of Model C Deluge Valve for Fire Protection Sys.Ie Info Notice 84-16 Issued on 840302 to Describe Failure of Valves to Operate. All Shipments of Model C Valves Stopped ML20154Q3141986-03-10010 March 1986 Final Part 21 Rept Re Possible Defect on Inflatable Door Seals for Personnel Air Locks Used in Plant Reactor Containment Sys.Program to Supply Environmentally Qualified Inflatable Seals Should Be Completed by mid-1986 ML20154N4361986-03-10010 March 1986 Part 21 Rept Re Defect on Inflatable Door Seals for Personnel Air Locks Used in Reactor Containment Sys of Nuclear Power Plants.Initially Reported on 830919.Environ Qualification Testing of New Seal Design Completed ML20154N3431986-03-10010 March 1986 Initial Part 21 Rept 135 Re Potential Problem W/Lube Oil Sump Tank Foot Valve of Dsrv Standby Diesel Generator for Facilities.Cause Not Determined.Recommends Utils Inspect Condition of Foot Valve Liners & Notify Tdi of Findings 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 AECM-86-0050, Final Part 21 & Deficiency Rept RD-85/04 Re Inadequate Cooling in Tdi Diesel Generator Control Panels.Initially Reported on 850429.Linear Reactors on Panels Replaced & Cooling Air Supply Installed1986-02-14014 February 1986 Final Part 21 & Deficiency Rept RD-85/04 Re Inadequate Cooling in Tdi Diesel Generator Control Panels.Initially Reported on 850429.Linear Reactors on Panels Replaced & Cooling Air Supply Installed ML20138A7391985-11-27027 November 1985 Interim Deficiency Rept PRD-83/12 Re Failure of Agastat GP Series Relays to Switch.Initially Reported on 830906. Requests Further Update Be Delayed Until Const Restart ML20198C4981985-11-0606 November 1985 Part 21 Rept Re Potential Defect in Dsr or Dsrv Standby Diesel Generator Intake & Exhaust Valve Springs Mfg by Betts Spring Co.Users Recommended to Inspect Engines for Broken Springs & Identify Original Mfg ML20135H7751985-09-17017 September 1985 Part 21 Rept,Correcting Final Deviation Disposition Request Status Re Unqualified Test Switch.No Changes Planned Since Emergency Buses Found to Have Adequate Separation ML20132B0261985-09-0303 September 1985 Part 21 Rept Re Possibility of Engine Ingestion of Unwelded Part in American Air Filter Standby Diesel Generator Intake Silencer.Immediate Hold Should Be Placed on Diesel Engines/Intake Silencers Not Yet in Svc ML20127E6261985-06-17017 June 1985 Part 21 Rept Re Failure to Follow Design Control Procedures Resulting in Misapplication of Switch CR2940 on Standby Liquid Control Sys Which May Cause Failure of Class 1E Equipment.Design Drawing Change in Progress ML20140G0901985-06-13013 June 1985 Part 21 & Final Deficiency Rept PRD-84/04 Re Failure of Automatic Sprinkler Corp of America Deluge Valves to Open. Condition Not Reportable Under 10CFR50.55(e) or Part 21 ML20127H5411985-05-17017 May 1985 Part 21 Rept Re Potential Defect in Engine Generator Control Panels of Dsr or DSRV-16 Standby Diesel Generator.Review of Generator Control Panel Installation by Each Facility Recommended AECM-85-0142, Part 21 & Second Interim Deficiency Rept RD-85/03 Re MSIV Failure to Remain Closed Due to Failure of Automatic Switch Co Dual Solenoid to Transfer When Deenergized.Initially Reported on 850321.Next Rept by 8506301985-04-30030 April 1985 Part 21 & Second Interim Deficiency Rept RD-85/03 Re MSIV Failure to Remain Closed Due to Failure of Automatic Switch Co Dual Solenoid to Transfer When Deenergized.Initially Reported on 850321.Next Rept by 850630 AECM-85-0133, Part 21 & Final Deficiency Rept 85-02 Re Tdi Diesel Generator Air Start Header Check Valve Failure.Design Change Initiated to Replace Eight Existing Check Valves on Div I & II W/Appropriate Check Valves Suitable for Design1985-04-26026 April 1985 Part 21 & Final Deficiency Rept 85-02 Re Tdi Diesel Generator Air Start Header Check Valve Failure.Design Change Initiated to Replace Eight Existing Check Valves on Div I & II W/Appropriate Check Valves Suitable for Design 1999-04-12
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217F9921999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Grand Gulf Nuclear Station,Unit 1.With ML20212F5641999-09-23023 September 1999 SER Concluding That All of ampacity-related Concerns Have Been Resolved & Licensee Provided Adequate Technical Basis to Assure That All of Thermo-Lag Fire Barrier Encl Cables Operating within Acceptable Ampacity Limits ML20211Q3171999-09-0909 September 1999 Safety Evaluation Accepting BWROG Rept, Prediction of Onset of Fission Gas Release from Fuel in Generic BWR, Dtd July 1996 ML20216E4881999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Grand Gulf Nuclear Station.With ML20211A6921999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Grand Gulf Nuclear Station,Unit 1.With ML20209J1961999-07-12012 July 1999 Special Rept 99-001:on 990528,smoke Detectors Failed to Alarm During Performance of Routine Channel Functional Testing.Applicable TRM Interim Compensatory Measure of Establishing Roving Hourly Fire Patrol Was Implemented ML20196K4981999-07-0101 July 1999 Safety Evaluation Authorizing PRR-E12-01,PRR-E21-01, PRR-P75-01,PRR-P81-01,VRR-B21-01,VRR-B21-02,VRR-E38-01 & VRR-E51-01.Concludes That Alternatives Proposed by EOI Acceptable ML20209G0691999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Grand Gulf Nuclear Station,Unit 1.With ML20196A1161999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Grand Gulf Nuclear Station.With ML20206Q4831999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Grand Gulf Nuclear Station Unit 1.With ML20206J1201999-04-30030 April 1999 Redacted ME-98-001-00, Pressure Locking & Thermal Binding Test Program on Two Gate Valves with Limitorque Actuators 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 ML20205P8771999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Grand Gulf Nuclear Station,Unit 1.With ML20207M9231999-03-12012 March 1999 Amended Part 21 Rept Re Cooper-Bessemer Ksv EDG Power Piston Failure.Total of 198 or More Pistons Have Been Measured at Seven Different Sites.All Potentially Defective Pistons Have Been Removed from Svc Based on Encl Results ML20207K5141999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Grand Gulf Nuclear Station,Unit 1.With ML20206T7991999-01-31031 January 1999 Iodine Revolatizitation in Grand Gulf Loca ML20207A8301998-12-31031 December 1998 1998 Annual Operating Rept for Ggns,Unit 1 ML20206R9501998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Grand Gulf Nuclear Station,Unit 1.With ML20206D7721998-12-31031 December 1998 South Mississippi Electric Power Association 1998 Annual Rept ML20198E2481998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Grand Gulf Nuclear Station,Unit 1.With ML20195F4121998-11-13013 November 1998 Rev 16 to GGNS-TOP-1A, Operational QA Manual (Oqam) ML20195C4841998-11-0606 November 1998 SER Accepting QA Program Change to Consolidate Four Existing QA Programs for Arkansas Nuclear One,Grand Gulf Nuclear Station,River Bend Station & Waterford 3 Steam Electric Station Into Single QA Program ML20195C2791998-11-0505 November 1998 BWR Feedwater Nozzle Inservice Insp Summary Rept for GGNS, NUREG-0619-00006 ML20195F4801998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Grand Gulf Nuclear Station,Unit 1.With ML20155C1351998-10-26026 October 1998 Rev B to Entergy QA Program Manual ML20154K2391998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Grand Gulf Nuclear Station Unit 1.With ML20155F1961998-09-0101 September 1998 Engineering Rept for Evaluation of BWR CR Drive Mounting Flange Cap Screw ML20153B2161998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Grand Gulf Nuclear Station,Unit 1.With ML20237B6661998-07-31031 July 1998 Monthly Operating Rept for Jul 1998 for Grand Gulf Nuclear Station,Unit 1 ML20236R0231998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Grand Gulf Nuclear Station,Unit 1 ML20155J0811998-05-31031 May 1998 10CFR50.59 SE for Period Jan 1997 - May 1998 ML20249B1251998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Grand Gulf Nuclear Station,Unit 1 ML20248B6261998-05-11011 May 1998 Rev 6 to Grand Gulf Nuclear Station COLR Safety-Related ML20217Q6701998-05-0606 May 1998 SER Approving Proposed Postponement of Beginning Augmented Exam Requirements of 10CFR50.55a(g)(6)(ii)(A)(2) at Grand Gulf for Circumferential Shell Welds for Two Operating Cycles ML20206J1271998-04-30030 April 1998 Pressure Locking Thrust Evaluation Methodology for Flexible Wedge Gate Valves ML20247F3591998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Grand Gulf Nuclear Plant,Unit 1 ML20217M8951998-04-30030 April 1998 QA Program Manual ML20217P8281998-04-0707 April 1998 Safety Evaluation Accepting Relief Authorization for Alternative to Requirements of ASME Section Xi,Subarticle IWA-5250 Bolting Exam for Plants,Per 10CFR50.55a(a)(3)(i) ML20217P0381998-04-0606 April 1998 Safety Evaluation Supporting Amend 135 to License NPF-29 ML20217A0291998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Grand Gulf Nuclear Sation,Unit 1 ML20216J4211998-03-18018 March 1998 SER Approving Alternative to Insp of Reactor Pressure Vessel Circumferential Welds for Grand Gulf Nuclear Station ML20216J2021998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Grand Gulf Nuclear Station,Unit 1 ML20203A2891998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Grand Gulf Nuclear Station ML20247B4111997-12-31031 December 1997 1997 Annual Financial Rept for South Mississippi Electric Power Association ML20203H9741997-12-31031 December 1997 1997 Annual Operating Rept, for Ggns,Unit 1 ML20198P1121997-12-31031 December 1997 Monthly Operating Rept for Dec 1997 for Grand Gulf Nuclear Station,Unit 1 ML20203B5581997-12-0404 December 1997 Special Rept 97-003:on 971111,valid Failure of Div 2 EDG Occurred,Due to Jacket Water Leak.Failure Reported,Per Plant Technical Requirements Manual Section 7.7.2.2 ML20203K4031997-11-30030 November 1997 Monthly Operating Rept for Nov 1997 for Grand Gulf Nuclear Station,Unit 1 ML20199H3711997-11-19019 November 1997 SER Accepting Approving Request Relief from Requirements of Section XI, Rule for Inservice Insp of NPP Components, of ASME for Current or New 10-year Inservice Insp Interval IAW 50.55(a)(3)(i) of 10CFR50 ML20199F3431997-11-18018 November 1997 SER Accepting Rev 15 of Operational Quality Assurance Manual for Grand Gulf Nuclear Station,Unit 1 1999-09-09
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MISSISSIPPI POWER & LIGHT COMPANY Helping Build Mississippi --
P. O . B O X 16 4 0, J A C K S O N , M I S S I S S I P P I 3 9 2 0,5
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JAMES P. McGAUGHY, JR. March 26,1982 y AS$1STANT VICE PRESIDENT Office of Inspection & Enforcement #
U. S. Nuclear Regulatory Commission -
Region II 101 Marietta Street, N.W.
Suite 3100 y-Atlanta, Georgia 30303 Attention: Mr. J. P. O'Reilly, Regional Administrator
Dear Mr. O'Reilly:
s
SUBJECT:
Grand Gulf Nuclear Station d ""
a&D _g Units 1 and 2 Op7 .
Docke t Nos. 50-416/417
- File 0260/15525/15526 s[i
'\ r:tr j' / PRD-82/07, Interim Report #1,
/ '- Unqualified NAMCO Limit CS^ Switches 7]T[h AECM-82/108 On February 25, 1982, Mississippi Power & Light Company notified Mr. R.
Butcher, of your of fice, of a Potentially Reportable Deficiency (PRD) at the Grand Gulf Nuclear Station (GCNS) construction site. The deficiency conccens unqualified NAMCO limit switches.
Bechtel Power Corporation and MP&L have both determined that this deficiency is a substantial safety hazard and meets the reporting requirements of 10CFR21 for both Bechtel and MP&L. Mr. F. S. Cantrell was notified by phone of this determination on March 23, 1982.
Our original notification stated that Models EA740 and EA180 may not be qualified for their intended safety functions. At this time, only the model EA740 switches, none of the model EA180 switches, have been identified as being safety-related. However, investigations are continuing by MP&L.
Bechtel's Part 21 report is included as Attachment B to this letter.
MP&L's Interim Report is included as Attachment A. We expect to submit our Final Report by April 19, 1982.
Yours truly, F204080346 G20326 k
PDR ADOCK 05000416 . P. cGaughy, Jr.
S KDS :dr PDR fr/
~
OFFICIAL COPY __ .
cc: See page 2 lb dy Member Middle South Utilities System /
I' ,I
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- Mr. J. P. 0'Reilly
. AECM-82/108 NRC Page 2 cc: .Mr. N. L. Stampley <
Mr. R. B. McGehee
. Mr. T. B. Conner Mr. Richard C. DeYoung, Director Office of Inspectfon & Enforcement U. S. Nuclear Regulatory Commission Washington, D.C. 2055s
Mr. G. B. Taylor-South Miss.-Electric Power Association P. O. Box 1589 -
Hattiesburg, MS 39401 L
f
Attac' amsnt "A" to AECH-82/108 Pagn 1 of.3 INTERIM REPORT NO. 1 FOR PRD-82/07
- 1. Name and address of the individual . . . informing the commission:
J. P. McGaughy, Jr.
Assistant Vice-President, Nuclear Production P.O. Box 1640 Jackson, Mississippi 39205 Notification of Part 21 applicability made to Mr. F. S. Cantrell, NRC, Region II by phone on March 23, 1982.
- 2. Identification of the facility ... which ... contains a deficiency:
Grand Gulf Nuclear Station (CGNS) Unit 1 Port Gibson, Mississippi 39150 Investigations are underway to determine if this deficiency applies to Unit 2.'
- 3. Identification of the firm ... supplying the basic component which ...
contains a deficiency:
Supplied to Grand Gulf by Bechtel Power Corporation, Gaithersburg, Maryland. Investigations are underway to see if any unqualified safety-related NAMCO switches were supplied by General Electric in the NSSS Scope of Supply.
- 4. Nature of the deficiency .. . and the safety hazard which . .. could be created by such a deficiency ...:
A. Description of the Deficiency According to NAMCO's test report " Qualification of NAMCO Control Limit Switches Model EA740", Revision 1, 2/22/79 Model EA740 and EA180 limit switches were qualified for - '. lear containment service.- However, it was later discov- that the applicability of the report depends upon the materials unca in construction of the limit switches. The materials can be identified by certain manufacturing codes stamped on each limit switch. The absence of the proper code on any limit switch indicates that it is unqualified since the materials used in the construction of the switch cannot be l identified.
Uncoded switches at GGNS on Unit 1 are known to be on valves in the following systems: Suppression Pool Cleanup (P60), Domestic Water (P66), Floor and Equipment Drains (P45), Residual Heat Removal I (E12), Reactor Water Cleanup Filter /Demineralizer (G36), Containment '
Cooling (M41), Condensate / Refueling Water (Pil)' and Standby Liquid Control (C41)
Attachannt "A" to AECH-82/108 Pags 2 of 3 During the investigation of NUREG-0588 requirements, EA740 limit switches on Main Steam Isolation Valves in the Nuclear Boiler System
. (B12) were also determined to be unqualified because of the manufac-turing date. These have previously been reported by MP&L under PRD-81/42.
' Applicability of the deficiency to Unit 2 and to the NSSS vendor is currently under investigation.
B. Analysis of Safety Implications The majority of the valves identified are used for containment and auxiliary building isolation. The limit switches are used to indicate the position (open/close) of safety-related valves. Failure of the limit switches during degraded plant conditions could cause erroneous indications of the status of the building isolation. This could further degrade plant conditions if inappropriate corrective actions were taken utilizing the erroneoue indications. This is a substantial safety hazard and reportable under the provisions of 10CFR21.
- 5. The date on which the information of such daficiency ... was obtained.
Mississippi Power and Light received information of the deficiency on Februa ry 24, 1982. We reported the deficiency to Mr. R. Butcher, of your office, as a Potentially Reportable Deficiency under 10CFR50.55(e) on that date. .We notified Mr. F. Cantrell of your office on March 23, 1982, that this deficiency was also reportabl3 under the provisions of 10CFR21 for Bechtel Power Corporation and Mississippi Power & Light. The MP&L-
" Responsible Officer," Mr. J. P. McGaughy, Jr. , will be notified of the Part 21 reporting requirement when he returns to his office.
- 6. In the case of the basic component ... the number and location of all such components.
- A total of ninety three (93) NAMCO type EA740 limit switches that perform a safety function have been identified on Unit 1 in eight (8) systems.
Two (2) type EA180 limit switches have been identified on Unit 1 but these do not perform a safety' function. Investigations are currently underway to locate any additional affected switches on Unit 2.
We do not have knowledge of the location of defective equipment located other than at GGNS. i 1
-7. The corrective action which has been taken . . . the name of the individual '
... reponsible for the action; and the length of time that has been ...
taken to complete the action.
A. Corrective Actions Taken -l l
All unqualified switches that perform a safety related function will
. be replaced with correct switches that have the necessary '
qualifications for nuclear service. '
w Atttchannt "A" to AECM-82/108 Pags 3 of 3 B. . Responsible Individual G. B. Rogers, Jr.
Site Manager Mississippi. Power and Light Company C. - Length of Time to Complete Actions Since it is not positively known at this time if all affected switches-have been located, a definite date cannot be determined for completion of. corrective actions.
- 8. Any advice related to the deficiency ... that has been, is being, or will be given to purchasers or licensees:
hi the deficiency did not originate with MP&L, we have no advice to offer.
i i
-r f w t +- - .an. .- a
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bec: Dr. D. C. Gibbs Mr. J. N. Ward .
Mr. J. P. McGaughy, Jr.
Mr. J. D. Hbaton Mr. R. S. Trickovic Mr. J. W. Yelverton
'Mr. L. F. Dale Mr. C. K. McCoy Mr. T. H. Cloninger Mr. R. A. Ambrosino Mr. J ". Pinto Mr. G. T Rogers
- Mr- '.
, H. Hobbs Mr. L. E. Ruhland Mr. C. C. Hayes Mr. A. G. Wagner Mr. R. F. Phares PRD File Manual File File-
-Mr. D. M. Houston
- U. S. Nuclear Regulatory Commission Division of Licensing Washington, D.' C. 20555 s
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. Attachment "B" to AECM-82/108 Page 1 of 4 ATIACF2ET "A" 'IO PRD 82/07 (I* CAR-132)
NAFCO LI!!IT SNI'lGES PARr 21 REPORP
- 1. Name and address of the individmis ... infonning the ccmnission:
J. R. Valdez Quality Assurance Supervisor Bechtel Power Corporation Post Office Eox 41 Port Gibson, Mississippi 39150 K. D. Shelton -
Quality Assurance Mississippi Power & Light Capany City Center North 210 South Lamar Street suite 320 Jackson, Mississippi 39201 Per telephone call on March 23, 1982 with !!r. F. Cantrell, Region II, NBC, it was confirmed that the 10 CFR 50.55 (e) tia2 requirements for the written report could be applied and, as such, MP&L was requested to include this report with their 50.55(e) report. -
- 2. Identification of the facility ... which contains a defect:
Grand Gulf Nuclear Station (GGNS)
Unit I and Unit II Port Gibson,flississippi 39150
- 3. Identification of the firm constructing the facility ... contains a defect:
Installed at the CGIS by:
Bechtel Power Corporation 15740 Shady Grove Pcad Gaithersburg,11aryland 20S77 m
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' Atitachment "B" to AECM-82/103
.Page 2 of 4
- 14. . Nature of the defect ... and the safety hazard which could be created by such defect:
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- a. NXX) Controls letter to Bechtel dated August 27, 1982,. stated that all EA180 and EA740 limit switches listed in its attachment were qualified for nuclear containment service.
Based an this infortration, Bechtel Project Engineering for I
GGNS utilized the W ICO Controls test report " Qualification of
' MICO Controls Linit Switches, Model EA740, Revision 1, dated February 22, 1979" for justifying the use of 200 limit switches EA180 and EA740 on the safety related valves in Unit i I. However, subsequent discussions with NANCO Controls revealed that the applicability of this test report depends upon the caterials used in the construction of limit switches.
L These mate. rials can be identified by certain manufacturing
,! codes stanped on each limit switch, as explained in NAtro
' letter to Bechtel, dated December 15, 1981. Limit switches which do not have the proper codes may have materials which are indeterminate and, therefore, they cannot be covered by the above referenced test report. It should be noted that the nodel numbers remained unchanged even thcugh materials of construction are different.
- b.
' The ambiguity in the NMKD letter dated August 27, 1981, resulted in this deficiency. Since the materials are indeterminate, there is a possibility that these limit switches may fail during normal operation or under post-ICCA conditions. These limit switches are used to-indicate the-position (open/close) of safety related valves. Failure of the limit switches could result'in erroneous indications.
This could confuse the operator, as the operator is required 4 to verify the position of sane of these valves (e.g., --
containment isolation valves) under the Off tbrreal Event Procedure. This confusion could cause.the operator to take improper corrective action..
The failure of the limit switches could also cause erroneous control signals to be generated which could initiate further T
indeterminate plant conditi6ns.
- 5. -
The date on which the information of such a defect was obtained.
4 An evaluation of.the applicability under the provisions of 10 CFR 21 was made on !! arch 23, 1982 by Bechtel Pcwer Corporatien.
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-Attachment "B" to AECM-82/108 to: v. Page 3 of 4
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In the case of basic cwguent ... the number and location of all such.ccraponents:
The letter frcm NM 00 Controls, dated August 27, 1981, to Bechtel Grand Gulf Project Engineering resulted in the incorrect use of the subject test re:crt for the qualification of limit switch Models
.EA740 and FA180 at GGNS.
Note that for GGNS Unit I, none of the Model FA180 switches are
. utilized in a mode that could create a substantial hazard. I A total of ninety-three (93) Mcdel FA740 limit switches without proper identification code were found on various safety related valves located in the Containment and Auxiliary Buildings.
NAt00 Controls is being notified that Bechtel Project Engineering has filed a Part 21 Report. NM00 Controls is also being requested to be~ aware of the potential error that can occur in use of the test report " Qualification of NMKD Controls Limit Switches, Model EA740, Revision 1, dated February 22, 1979," as this report does not refer to any manufacturing codes.
'Information concerning this defect is being furnished to the other Bechtel Power Corporation divisions for review. should it be determined that basic canponents which contain this defect are in use at, have been supplied for, or are being supplied for one or more other Bechtel projects, this will be reported by the cognizant division directly to the cognizant director (s) of the NBC Pegicnal Office of Inspection and Enforcement.
7.
The corrective action which has been taken ... the name of the "
organization responsible for the action, and the length of time that has been ... or will be taken to ccznplete the action:
For Unit I, all the affected lbnit switch Models EA740 and EA180 en safety related valves have been physically inspected for the-manutacturing codes.
It has been determined that the lirit switches on certain valves do not'have proper manufacturing ccdes.
'Ihey are, therefore, not covered by the subject test report. .
Bechtel Field Engineering has placed an order for procurement of new limit switches which are qualified for nuclear service.
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Attachment "B" to AECM-82/108 l e
, Page 4 of 4 I 1
Mississippi Power & Light Ccmpany has been notified of the deficiency by Bechtel letter dated February 5, 1982. The replacement of the switches will be scheduled by MP&L.
For Unit II, there is a possibility that a similar deficiency may exist in the limit switches Modals FA180 and EA740 installed on the safety related valves of Urit II. These limit switches will be physically inspected, end all those models which do not meet the criteria of the manufacturing ccdes will be replaced with new switches. These actions will be ccrcpleted, by Bechtel, prior to fuel load of Unit II.
- 8. Any advice related to the defect that has been, is being, or will be given to purchasers of licensees.
None e-t 9
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