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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
[Table view] |
Text
. . ._ _.
9" ? EntCrgy i
Operations November 21, 1990 i;!":'f"
. m. Uff'7"'""*'F W. {. Cottle i
U.S. Nuclear Region II Regulatory Commission .
101 Marietta St. '
Atlanta, Georgia, 30323N.W., Suite 2900 Attention:
i Mr. Stewart D. Ebneter, Regional Administrator-
Dear Mr. Ebneter:
SUBJECT:
Grand Unit 1 Gulf Nuclear Station Docket No. 50-416 License No. NTF-29 RD-89/001, Main Steam Isolation Valve Failure to Close Due to Solenoid Valve Malfunction, Final Report AECH-90/0196 On September 14, 1989 Mr. Floyd Cantrell of System Energy Resources, Inc .
SERI) notified Nuclear Station (GGNS)your Unit 1. office of a Reportable Deficien(cy at Grand $11f isolation valve failure to close.The deficiency concerned a main steam
a dual valve. solenoid valve extruding through the exhaust port of theThis The extruded material blocked the exhaust port preventi solanoid valve from exhausting air which resulted inngthe MSIV remaini ng the solenoid open, j
10CFR21 for GGNS Unit I and an September 18, 1989. r the interim provisions ofreport, R0-8 was issued submitted by startup from the fourth refueling outage.The e inter
! GGNS Unit 1.
Attached is the updated
! entirety for continuity. Item 9 has been added to provica f
- actions taken, and final a ons, Inc. -
n report its for E urs raly, _
. n. .., ;
pc f
UG/WTC:be Attachment
- ca (See Next Page) 9011081/SNLICFLR \
\
9104150156 901121 PDFs 11:020 S ADOCK 05000416 PDR
'7 At.LM-WU/0196 Page 2 cc: Mr. D. C. Hintz Mr. R. B. McGehee(t/a) /a Mr. N. S. Reynolds(w(w/a))
Mr. H. L. Thomas (w/o Mr. H. O. Christensen)(w/a)
Mr. L. L. Kintner, Project Manager (w/a)
Office of Nuclear Reactor Regulation '
U.S. Nuclear Regulatory Comission Mail Sten 11021 Washington, D.C.
20555 Director Office of(w/3)
Nuclear Reactor Regulation U.S. Nuclear Regulatory Comission Mail Stop P1-137 Washington, D.C. 20555 Document Control Desk U.S. Nuclear Regulatory (w/a)
Commission Mail Stop P1-137 Washington, D.C. 20555 1
4 i
A9011081/SNLICFLR
=- ,- , -
Attachment to !
,.. e -
AECM 90/0196 FINAL 10CFR21 REPORT
- 1. Name and address of the indi'ddual informing the comission:
l W. T. Cottle .
Vice President, Nuclear Operatiors P. O. Box 469 .
Port Gibson, Mississippi 39150 l
- 2. Identification of the facility ... whien ... contains a deficiency:
Grand Gulf Nuclear Station (GGNS) Unit 1 Port Gibson, Mississippi 39150
- 3. Identification of the fira ... supplying the basic component which ...
contains a deficie m -
l Automatic Swi6h Coinpany Florham Park, N,1. 07932
- 4. Nature of the deficiency ... and the safety hazard which ... could be l created by such a dificiency ...:
A. Description of the Deficiency On August 14, 1989 MainSteamIsolationValve(MSIV)821F0022B failed to close upon demand from automatic and remote manual actuation signals. Several minutes later the MSIV closed on-its .
own. An investigation later revealed that the EPDM disk material for ASCO Model NP8323A20E dual solenoid valve B21SV501B had extruded into the exhaust port of the solenoid valve. When the solenoid valve was de-energized, the disk lifted off the exhaust port and the extruded mater.al in the exhaust port was torn away from the disk material. The extruded disk material blocked the exhaust port preventing the solenoid valve from exhausting air resulting in the MSIV remaining open. The extruded disk material was later blown out hv r rmal air pressure allowing the solenoid valve to exhaust and che ESIV.to close.
! A contributing factor which caused the disk material to be extruded into the exhaust port appears to be related to the elastomer seal
- being forced against the metal seat by the energized dual solenoid.
! pressure-(not spring pressure .
have been separated from rthe )emaining seat material due to theThis extru friction forces created by movement of the seat away from the exhaust port when the solenoid coils were de-energized on August 14, 1909.
A9011081/SNLICFLR
mecnsent to l; ; l, AECM 90/0196 i
TI,e extrusion process leading to ultimate failure may be both temperature and force dep(ndent. It a softening allows the process to begin.ppears that seal materialSeal soften:
ambient temperature, and extreion depends on the softening and the ,
force applied by the solenoid on b the seal material. If seal l softening has not occurred,-then the amount of protrusion of=the
! seal material into the exhaust port is so small that it has no '
l affect on valve operation. ,
The effect that ambient temperature has on the seal material softening is complex in nature. While ambient temperature is known to be a controlling factor in chemical reaction rates and its effects can be predicted utilizing Arrhenius methodology, it appears l
that the softening or extrusion process can occur at temperatures below those specified by the ASCO cualification reports.
The ASCO qualification report specifies a life of eight years at 140 degrees Fahrenheit ambient temperature for ASCO valves tested in an energized condition. A review of the available temperature data indicated that the average ambient temperature in each of the-inboard and outboard MSIV areas at GGNS Unit 1 has been below this temperature. However, evidence of substantial extrusion has been found on all eight MSIV dual solenoid valve seats. GGNS had no history of problems with these NP8323A20E MSIV solenoid-valves until the time of failure. These NP8323A20E dual. solenoid valvea weic installed on all eight MSIVs in March 1985 to replace the ASCO Model HTX8323A20V solenoid valves after three MSIVs failed to close due to the failure of three HTX8323A20V solenoid valves. In October 1985-and during the first refueling outage solenoidvalvewas--removed, disassemble (d,andinspec)ted. No- Fall of 1986 degradation or other problems were found during either inspection.
Successful completion of fast closure of the MSIVs had been documented as recently as startup from the third refueling outage (April 29,1989). Previous to this, successfu% fast closures were achieved on January 5,1989 and August 16, 1988.
System Energy Resources, Inc. (SERI) contacted ASC0iin August, 1989 for additional information relating to potential thermal aging l
effects on the EPDM seal material. utilized in the NP8323A20E valves.
i ASCO provided new, more conservative _ heat rise values than those previously received by SERI.
SERI performed an-evaluation of the themal endurance service life of these solenoid valves using the more conservative ASCO heat rise velues and the thermal endurance test data from tests perfomed for Cleveland Electric's Perry Plant. ' The' tests were performed on three groups of ASCO solenoids with both Viton and EPDM elastomers in each test group. Test-data from one group shows that a solenoid with '
EPDM elastomers functioned after 60 days at 225r~ ambient (oven -
l temperature). Conservatively assuming 135F ambient temperature (equal to-maximum anticipated dr resulted in an expected thermal ywell temperature),
endurance level of at least this evaluation-5.17 A9011081/SNLICFLR i
, , ..-. + . - , - .--.,. - -..-., - . - .--.-. .
- .. -...- ... . - ~ ,- ~ ..~. _ -
Attacnment to 4 .
AECM 90/0196 years. This represents strictly a the'nal life without consideration to other aging effects included in an IEEE 323 test program.
It should be rearesentative cf the installed life at GGNS in that the failed valve lad been eposed to a themal environment with an insignificant cumulative radiation dose. However, all eight of the MS!v solenoid valves had been in service less than this period, one [B21F028A) approximately three years, and were all In similar condstion. Therefore, it is expected that strictly from a thermal endurance standpoint this failed valve should have '
functioned and all the valves should not have been in similar condition.
SERI also performed a design calculation to determine the qualified life based on the new, more conservative ASCO heat rise data and the '
ASCO test data which accounts for the cumulative aging effects and the DBE conditions. This calculation was performed for the Drywell as well as the Auxiliary Building Steam Tunnel applications, assuming 13SF and 12SF, respectively for the ambient conditions.
This calculation results in a qualified life of 2.84 years for the core disk and 4.17 years for the lower disk (GGNS failed part) in the Orywell (B21F022A-D) and 4.37 years for the core disk and 6.56 years for the lower disk in the Auxiliarv Buildino Steam Tunnel (821F028A-D). All of these calculations provide lives less than the e
ASCO reported life of eight years at 140F.
B. Analysis of Safety Implications:
The ASCO NP8323A20E dual solenoid valves are utilized as three-way, normally energized, dual solenoid operated main pilot control valves to reposition the main control valves in the pneumatic control units. The pneumatic control unit for each MSIV is attached to the valve's air operated cylinder and are utilized to control positioning of the MS!vs.
The MSIVs utilize air to open and spring to close with air assist actuators. The air supply to the pneumatic operated cylinder is controlled by a four-way pilot operated valve which applies air pressure to either the top or bottom end of, the air cylinder operator. This four-way pilot operated valve is in turn controlled by a three-way normally energized dual solenoid operated valve. To open the MSIV, either or both solenoids on the three-way dual solenoid valve are energized to feed air pressure to the piston of the four-way pilot operated valve which in turn shifts position to feed a'? pressure to the bottom side of the air operating cylinder and (at the same time) exhaust air from the top side of the air operated cylinder. To close the MSIV both solenoids on the three-way dual solenoid valve must be de-energized to allow the four-way valve to shift position to feed air pressure to the top side of the air operating cylinder and air from the bottom side of the air oper(ated cylinder.at the same time) exha A9011081/SNLICFLR
-AECM 90/0196 At GGNS there are four_ main steam lines and each steam line is equippet: with two MSIVs. One in each line is placed as close as possible to'the inside of the drywell and the other valve is just' outside the containment. The MSIVs are designed to close fast enougn to limit release of radioactivity to the environment to less than the limits of 10CFR100 in the event of a guillotine break of one steam line outside the primary containment.
Based on the deficiency described above, a potential' existed for i
both ASCO NP8323A20E dual. solenoid-valves to fail and not allow the two MSIVs to fast close on a main steam line in the event of a guillotine break on that line.
i Therefore, based on the redundant basic component guidelines, as-i it is conservatively postulated that a defined in NUREG-0302,in failure of both MSIVs a steam line potentially existed.
This- ..
l failure, coincident with a postulated main steam line break outside the primary containment could have resulted in a reduction in the j
degree of protection provided to public health and-safety.
! 5. The date on which the information of.such deficiency ... was j
j obtained:
System Energy Resources, Inc. received information of the deficiency i
' on August 28,1989. = An evaluation under the cuidelines of 10CFR21 was completed on September 13 1989.
i s
- 6. In the case of the basic component. ... the number and location of
- all such component
j There currently are six NP8323A20E dual solenoid valves at GGNS Unit i 1, one located on each of the four Main Steam Isolation Valves in
- the drywell, one on the 'A' steam line- (821F028A) outside -
- containment and one spare located in the warehouse.- 1
(
- We do not have knowledge of the location of other defective l equipment.
!L 7. The. corrective action which has been taken ... the name'of the j individual responsible for the action; and the length of._ time that-i has been ...-taken to complete the action: '.
j A. Corrective Actions Taken 4
j The NP8323A20E dual solenoid valves-on all eight MSIVs were replaced or refurbished prior to_ plant restart. Five of~the i
eight were replaced with new, iaentical valves 4
i .the other three were rWurbished with Viton tomerElas(NP8323A20 rebuild kits,_ making them NP8323A20V.
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i A9011081/SNLICFLR
s
. Attachment to AECM 90/0196
~
- 8. R_e,sponsible Individual W. T. Cottle Vice Pteside,it, Nuclear Operations System Energy Resources, Inc.
C. Length of Time to Complete Actions SERI will continue with an accclerated replecement or refurbishment schedule for the NP8323A20E dual solenoid valves and in parallel is pursuing design change options such as the use of two single solenoid valves in place of the single dual solenoid valve design.
The length of time to complete this action is indeterminate at this time. However, SERI will provide a status update by startup from the fourth refueling cutage,
- d. Any advice related to the deficiency ... that has been, is being, or will be given to purchasers or licensees:
As the deficiency did not origrate with SERI, we have no further advice to offer.
- 9. Status Update A. Corrective Action Taken Duringthefourthrefuelingoutage(RF04),MinorChangePackage (MCO) 89/1126, Rev. I was implemented to replace the dual solencia valves with two single solenoid valves. The removed dual solenoid valves were disassembled and the seats examined.
Engineering Report GGNS-90-0023 was updated with infonnation gained from the solenoid valve seat examination. The report also includes the most recent failure of a MSIV/ASCO solenoid vahe on July 27, 1990 which was determined to be temperature and seating force induced with the presence of a liquid substance (probably a lubricant) on the seat as a contributing factor. The report is considered a final resolution of solenoid valve failures due to elastomeric part degradation and is available for review at GGNS.
The factors contributing to solenoid valve failures were judged to be: higher than expected ambient temperature, high heat rise generated by the dual coil tolenoids, susceptibility of the EFDM to thennal degradation, a possible interaction of unknown liquid substance with the EPDM seat material, and high seating forces, y A9011081/SNLICFLR e
B #
4LCCnment to i
,. , AECM 90/0196 l This new design reduces the expected heat rise by using two single. solenoid valves.- The seating force on the seating material is also reduced. The seating and gasket material has been changed from EPDM to viton which provides better temperature characteristics and is less-susceptible to interaction with lubricants. ,
This is considered Entergy Operations - GGNS's final resolytion and response to Reportable Deficiency (RD)-89/001.
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A9011061/SNLICFLR l
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