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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 ML20236V3121998-07-29029 July 1998 Final Part 21 Rept Re Enterprise DSR-4 & DSRV-4 Edgs.Short Term Instability Was Found During post-installation Testing & Setup as Part of Design mod/post-work Testing Process. Different Methods Were Developed to Correct Problem ML20248A1671998-05-22022 May 1998 Interim Part 21 Re Enterprise DSR-4 & DSRV-4 Emergency diesel.Post-installation Testing Revealed,High Em/Rfi Levels Affected New Controllers,Whereas Original Controllers Were unaffected.Follow-up Will Be Provided No Later than 980731 ML17309A6211997-09-29029 September 1997 Part 21 Rept Re Final Disposition of Masterflow 713 & Embeco 636 Grout Nonconformance Reported by Master Builders,Inc. Licensee Continuing to Monitor shelf-life of Masterflow 713 & Embeco 636 Grouts Produced at Rancho Cucamonga 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 ML20134H3361996-11-0505 November 1996 Part 21 Rept Re Defective Inner Thrust Bearing 1801461-01 Used in PSA 35 Mechanical Shock Arrestor Used as Restraint on Piping Sys for Nuclear Generating Plant.Lot of Defective Parts Located & Isolated to Three Customers 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 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 ML20059H7721994-01-17017 January 1994 Part 21 Rept Re Virginia Power Notifying Fairbands Morse Via Failure Analysis Rept NESML-Q-058 of Defective Air Start Distributor cam,16104412 ML20059F2631994-01-0707 January 1994 Part 21 Rept Re Air Start Distributor Cam Mfg by Fairbanks Morse.Mfg Suggests That Site Referenced in Encl App I Inspect Air Start Distributor Cam as Soon as Practical ML20058K3841993-12-0909 December 1993 Part 21 Rept Re Potential Defect in Component of Dsrv & Dsr Enterprise Standby DG Sys,Regarding Potential Problem W/ Subcover Assembled Atop Power Head ML20127H2301993-01-15015 January 1993 Part 21 Rept Re Potential Defeat in Component of Dsrv & Dsr Enterprise Standby DG Sys.Starting Air Distributor Housing Assemblies Installed as Replacement Parts at Listed Sites ML20126J5961992-12-31031 December 1992 Part 21 Rept Re Potential Loss of RHR Cooling During Nozzle Dam Removal.Nozzle Dams May Create Trapped Air Column Behind Cold Leg Nozzle Dam.Mod to Nozzle Dams Currently Underway. Ltrs to Affected Utils Encl ML20126B0421992-12-17017 December 1992 Final Part 21 Rept Re Potential Problem W/Steel Cylinder Heads.Initially Reported on 921125.Caused by Inadequate Cast Wall Thickness at 3/4-inch-10 Bolt Hole.Stud at Location Indicated on Encl Sketch Should Be Removed ML20127D1491992-09-0404 September 1992 Part 21 Rept Re Defect in Component of DSRV-16-4 Enterprise Standby DG Sys Jacket Water Pump Shaft.Caused by Incorrect Tapers Machined on Shaft Due to Vendor Mismatching.All Affected Shafts Recalled & Quality Insp Plans Changed 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 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 ML20087D3191992-01-14014 January 1992 Potential Part 21 Rept Re Problems W/Elmwood/Fasco Contactor Carriers Breaking in Contactor Model 30-FO-30. Caused by Distortion/Shrinkage of Molded Phenolic Contactor Carrier.Replacement Contactors Installed ML17223A5941990-03-0909 March 1990 Errata to 900126 Part 21 Rept Re Anchor/Darling Actuators Incorporating Use of Teldyne-Republic four-way Valves.Lists Plants Inadvertently Left Out in Original Rept 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 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 ML20246K7401989-04-26026 April 1989 Part 21 Rept Re Incorrectly Stamped Name Plates on Certain Asco Nuclear Qualified Valves.Vendor Will Contact Each Affected Facility & Furnish Correctly Stamped Plates & in Near Future Discontinue Sale of Rebuild Kits for Valves ML20247P7991989-04-0404 April 1989 Part 21 Rept Re Atmospheric Dump Valves.Cause of Failure Speculative But Result of Piston Ring That Failed to Seal. Resolution to Problem Requires Increasing Pilot Valve Capacity & Reworking of Plug to Enlarge Pilot Flow Area ML20206M4401988-11-21021 November 1988 Deficiency Rept Re Misapplication of Raychem Criteria in Selection of Some Matl Used in Electrical Cable Field Splice Kits.Initially Reported on 880920.Investigation Is in Process.Final Rept Will Be Submitted by 881222 ML20205C9291988-10-18018 October 1988 Part 21 & Deficiency Rept Re Valves Installed Opposite to Direction of Flow,Per 10CFR21 & 50.55 Requirements.Item Being Tracked by MTS EAI B-5115 & Scheduled for Completion 881030 ML20205D6651988-10-18018 October 1988 Part 21 & Deficiency Rept Re Penetration Seals Found Not to Be Watertight.Initially Reported on 880609.Water Leakage Tests Performed on Unit Upper Cable Spreading Room Seals. All Floor Penetration Seal Assemblies Repaired 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 ML20155D6471988-09-28028 September 1988 Deficiency Rept Re Valves Installed Opposite to Direction of Flow.Initially Reported on 880629.Final Rept Delayed Until 881020 ML20207J7361988-09-20020 September 1988 Interim Deficiency Rept Re Misapplication of Vendor Criteria in Selection of Some Matl Used in Electrical Cable Field Splice Kits.Initially Reported on 880601.Final Rept Expected Prior to 881123 ML20153E2271988-09-0101 September 1988 Part 21 & Deficiency Rept Re ESF Filtration Unit Bolts. Initially Reported on 880628.Contractor Conducted Training Session for Personnel to Stress Importance of Clarifying Incomplete Drawing Info & Requirements of Bolting Procedure ML20151V1901988-08-16016 August 1988 Deficiency Rept Re non-water Tight Penetration Seals.Test Rig Constructed to Simulate Typical Upper Cable Spreading Room Configuration & Sealants Verified to Provide Waterproof Seal.Next Rept Will Be Submitted by 881020 ML20196L4811988-07-0707 July 1988 Part 21 & Deficiency Rept Re Valves Installed Opposite to Direction of Flow.Initially Reported on 880601.Investigation in Progress to Determine Full Scope of Condition.Final Rept Will Be Submitted by 881001 ML20151A7781988-07-0606 July 1988 Deficiency Rept Re nonwater-tight Penetration Seals. Initially Reported on 880609.Investigation Incomplete.Next Rept Expected by 880818 ML20196C2971988-06-28028 June 1988 Deficiency Rept Re ESF Filtration Bolts.Initially Reported on 880601.Investigation of Root Cause of Condition Ongoing. Final Rept Will Be Submitted by 880901 ML20195D8541988-06-16016 June 1988 Part 21 Rept Re Potentially Reportable Condition Associated W/Dresser Model 7440W Check Valves Supplied W/Flow Direction Arrow Stamped Opposite to Valve Flow.Investigation Being Conducted.Evaluation of Bechtel Western Power Co Ltr Encl 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 ML20154A6841988-05-10010 May 1988 Deficiency Rept Re Electrical Cable Tray Separation. Initially Reported on 880414.Walkdown of All safety-related Cable Trays Conducted to Ensure Any Unacceptable Separation Distance Identified 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 ML20151K2621988-04-14014 April 1988 Interim Deficiency & Part 21 Rept Re Control Room Essential HVAC Sys.Initially Reported on 870914.Addl Concern Noted Re Incorrect Assumption in Design Calculation.Corrective Action Beyond Calculation Review Involves Logic Mod ML20151K2371988-04-14014 April 1988 Part 21 & Deficiency Rept Re Damage to Emergency Diesel Generator Jacket Water HX During Flushing.Initially Reported on 860917.HX Repaired & Installed in Unit 2.Thermostatic Valves Being Modified ML20148R6441988-01-27027 January 1988 Part 21 & Deficiency Rept Re Protection of Containment Electrical Penetration Assemblies Fabricated by Conax Buffalo Corp.Initially Reported on 871203.LOCA Could Cause One or More of nonsafety-related Circuits to Short Circuit ML20237E9941987-12-22022 December 1987 Deficiency Rept Re Protection of Containment Electrical Penetration Assemblies (Epa).Initially Reported on 871203. Investigations in Progress.Final Rept Will Be Submitted by 880130 ML20236V2981987-11-19019 November 1987 Deficiency Rept Re Electrical Separation Criteria Specified in Const Spec X3AR01.Initially Reported on 870909.Second Test of Electrical Separation Requirements Very Positive. Final Rept Expected to Be Submitted Prior to 880301 ML20236K1431987-11-0202 November 1987 Interim Part 21 & Deficiency Rept Re Inductive Current Interruptive Capacity of Solid State Protection Sys Motor Driven Relay Contacts.Shunt Suppression Device Will Be Added to Solenoid ML20236J5371987-10-29029 October 1987 Part 21 & Deficiency Rept Re Solid State Protection Sys motor-driven Relay Contacts Inductive Current Interruptive Capacity.Initially Reported on 870110.Hardware Mods to Affected Circuits Planned Prior to Fuel Load ML20239A2111987-09-14014 September 1987 Part 21 & Deficiency Rept Re Design of Control Room Essential (CRE) HVAC Sys.Initially Reported on 870713. Backdraft Dampers Added to Unit 1 CRE HVAC Units & Will Be Added to Unit 2 Commensurate W/Const Schedule ML20237H7741987-08-12012 August 1987 Interim Deficiency Rept Re Emergency HVAC Sys in Control Room.Initially Reported on 870713.Engineering Evaluation in Progress to Determine Potential Impacts of Condition on Plant Safety.Final Rept Will Be Submitted by 870915 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 1999-04-12
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217K4591999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Vogtle Electric Generating Plant,Units 1 & 2.With ML20217K8041999-09-30030 September 1999 Rev 1 to Vegp,Unit 2 Cycle 7 Colr ML20217K7741999-09-30030 September 1999 Rev 1 to Vegp,Unit 1 Cycle 9 Colr ML20216E5061999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Vegp,Units 1 & 2. with ML20210P9841999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Vogtle Electric Generating Plant,Units 1 & 2.With ML20209H1211999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Vogtle Electric Generating Plant,Units 1 & 2.With ML20196F9711999-05-31031 May 1999 Owner Rept for ISI for Vogtle Electric Generating Plant, Unit 1 Eighth Maint/Refueling Outage ML20195G1731999-05-31031 May 1999 Monthly Operating Repts for May 1999 for VEGP Units 1 & 2. with ML20206N2141999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Vogtle Electric Generating Plant,Units 1 & 2.With ML20206A6561999-04-21021 April 1999 Safety Evaluation Authorizing Licensee Re Rev 9 to First 10-year ISI Interval Program Plan & Associated Requests for Relief (RR) 65 from ASME Boiler & Pressure Vessel Code 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 ML20206C2291999-03-31031 March 1999 Revised Monthly Operating Repts for Mar 1999 for Vogtle Electric Generating Plant,Units 1 & 2 ML20205Q8081999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Vegp,Units 1 & 2. with ML20205A9581999-03-31031 March 1999 Rev 0 to VEGP Unit 1 Cycle 9 Colr ML20207K6051999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Vogtle Electric Generating Plant,Units 1 & 2.With ML20209H3951999-02-15015 February 1999 Rev 2 to ISI Program Second 10-Year Interval Vogtle Electric Generating Plant Units 1 & 2 ML20209H4091999-02-15015 February 1999 Rev 1 to ISI Program Second 10-Year Interval Vogtle Electric Generating Plant Units 1 & 2 ML20202H9851999-01-29029 January 1999 Safety Evaluation Accepting Rev 8 to First 10-year Interval Inservice Insp Program & Associated Requests for Relief for Vogtle Electric Generating Plant,Unit 1 ML20199F8041999-01-13013 January 1999 Corrected Pages to VEGP-2 ISI Summary Rept for Spring 1998 Maint/Refueling Outage ML20199E7561998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Vogtle Electric Generating Plant,Units 1 & 2.With ML20198S1781998-12-31031 December 1998 SER Re Second 10-year Interval Inservice Insp Program Plan & Associated Requests for Relief for Southern Nuclear Operating Co,Inc Units 1 & 2 ML20196E5221998-12-0101 December 1998 Rev 8 to ISI-P-014, ISI Program for VEGP-2 ML20198B8571998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Vogtle Electric Generating Plant,Units 1 & 2.With ML20195H2131998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Vogtle Electric Generating Station,Units 1 & 2.With ML20154L5681998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Vegp,Units 1 & 2 ML20151W3681998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Vogtle Electric Generating Plant Units 1 & 2.With ML20154L5721998-08-31031 August 1998 Corrected Page from MOR for Aug 1998 for Vegp,Unit 2 ML20237D2051998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Vogtle Electric Generating Plant Units 1 & 2 ML20236V3121998-07-29029 July 1998 Final Part 21 Rept Re Enterprise DSR-4 & DSRV-4 Edgs.Short Term Instability Was Found During post-installation Testing & Setup as Part of Design mod/post-work Testing Process. Different Methods Were Developed to Correct Problem ML20236P6991998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Vogtle Electric Generating Plant,Units 1 & 2 ML20236Q3051998-06-30030 June 1998 Owner'S Rept for ISI for Sixth Maint/Refueling Outage of Vogtle Electric Generating Plant,Unit 2 ML20249A3911998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Vogtle Electric Generating Plant ML20248A1671998-05-22022 May 1998 Interim Part 21 Re Enterprise DSR-4 & DSRV-4 Emergency diesel.Post-installation Testing Revealed,High Em/Rfi Levels Affected New Controllers,Whereas Original Controllers Were unaffected.Follow-up Will Be Provided No Later than 980731 ML20249A3931998-04-30030 April 1998 Revised MOR for Apr 1998 for Vogtle Electric Generating Plant Unit 1 ML20247F3841998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Vogtle Electric Generating Plant,Units 1 & 2 ML20154Q9721998-04-20020 April 1998 10CFR50.59(B) Rept of Facility Changes,Tests & Experiments for Vogtle Electric Generating Plant,Units 1 & 2 ML20217H7181998-04-0101 April 1998 Corrected Page 5 to 980324 SER Re Relief Requests Associated W/Second 10-year Interval Insp program.RR-21 in Error in That Component,Suction Damper Inadvertently Omitted. Corrected Page 7 of Technical Ltr Rept Also Encl ML20216D6141998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Vogtle Electric Generating Plant,Units 1 & 2 ML20217Q1301998-03-31031 March 1998 Rev 0 to Vepc Unit 2 Cycle 7,COLR ML20217B8831998-03-24024 March 1998 SER Accepting Relief Request RR-5,RR-19,RR-20,RR-21,RR-23 & RR-24 for Second 10-yr Interval ISI Program Plan ML20216E2421998-02-28028 February 1998 Monthly Operating Repts for Feb 1998 for Vogtle Electric Generating Plant,Units 1 & 2 ML20203H9551998-02-23023 February 1998 SER Denying Quality Assurance Program Description Change for Vogtle Electric Generating Plant,Units 1 & 2 ML20203E4831998-02-11011 February 1998 Rev 1 to Vogtle Electric Generating Plant,Units 1 & 2 Second Ten-Yr Interval Pump Inservice Test Program ML20198T1211998-01-31031 January 1998 Owners Rept for Inservice Inspection for Seventh Maintenance/Refueling Outage ML20202G5441998-01-31031 January 1998 Monthly Operating Repts for Jan 1998 for Vogtle Electric Generating Plant,Units 1 & 2 ML20199E5431998-01-31031 January 1998 Rev 3 to WCAP-14720, Vogtle Units 1 & 2 Spent Fuel Rack Criticality Analysis W/Credit for Soluble Boron ML20198L6471997-12-31031 December 1997 Monthly Operating Repts for Dec 1997 for Vogtle Electric Generating Plant,Units 1 & 2 ML20203C2811997-12-0909 December 1997 Safety Evaluation Authorizing Request for Relief of Second 10 Yr Interval Inservice Insp Program ML20202B7881997-12-0101 December 1997 Rev 8 to ISI-P-006, ISI Program for Gpc Vogtle Electric Generating Plant Unit 1 ML20203H0601997-11-30030 November 1997 Monthly Operating Repts for Nov 1997 for Vegp,Units 1 & 2 1999-09-30
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, . _ . _ _ _ _ _ _ - -
' 'f f i Geo.gia Fher Co6.pny Fdst Office Box 282
,. Wayfiesboro, Georg a 30830
?3!ephone 404 554 9961, Extension 3413 404 724-8114, Est<tnsion 3413 L
P. D. Ric. Georgia Power NeYYN April 14,1988 U. S. Nuclear Regulatory Commission File: X78G03-M109 ATTN: Document Control Desk Log: GN-1439
. Washington, D.C. 20555
Reference:
Vogtle Electric Generating Plant - Units 1 & 2; 50-424, 50-425 Diesel Generator Jacket Water Heat Exchanger Letter GN-1079, dated September 17, 1986 In the referenced letter, NRC of a reportable condition Georgia underPower Company 10CFR50.55(e )(GPC)damage involving notified the to the emergency diesel generator's jacket water heat exchanger during flushing on Unit 1. This heat exchanger was repaired and installed in Unit 2, but was damaged again during testing for Unit 2. The subsequent investigation resulted in a 10CFR21 notification by the vendor to the NRC of a potential defect in the jacket water heat exchanger.
The attached report for Unit 2 modifies our previous report on this subject and provides additional information relating to the root cause of the heat exchanger damage. GPC has concluded that this condition is also reportable under 10CFR21. This reponse contains no proprietary information and may be placed in the NRC Public Document Room.
P. D. Rice PDR/wk1 Attachment xc: USNRC - Region II Suite 2900 101 Marietta Street, N.W.
Atlanta, GA 30323 H. G. Baker D. R. Altman L. T. Gucwa G. F. Head J. A. Bailey C. W. Hayes R. H. Pinson G. Bockhold, Jr. R. W. McManus E. D. Groover G. R. Frederick Sr. Resident (NRC)
C. T. Moore J. E. Swartzwelder D. H. Smith (0PC) f)qdl R. A. Thomas G. A. McCarley J. E. Joiner (TSLA)
NORMS k
8804210277 880414 PDR ADOCK 05000424 S -
DCD-
, 9; EVALUATION OF A P0TENTIALLY REPORTABLE CONDITION - UNIT 2 DIESEL GENERATOR JACKET WATER HEAT EXCHANGER Initial Report: On April 10, 1986, Mr. R. E. Folker, Vogtle Quality Assurance Engineer, informed Mr. E. F. Christnot of the USNRC Region II of a potentially reportable condition concerning the diesel generator jacket water heat exchanger. In letter GN-1079, dated September 17, 1986, GPC provided an evaluation of this condition which concluded that a reportable condition per 10CFR50.55(e) did exist.
Background Information: The class 1E diesel generators provide an onsite supply of emergency electrical power to safety-related equipment to ensure their continued operation in the event of a loss of offsite power. The diesel generator jacket water heat exchanger (shell and tube type) removes heat from the diesel generator coolant loop during engine operation. The jacket water flows through the shell side of the heat exchanger, and cooling water from the nuclear service cooling water (NSCW) system flows through the tube side. The engine driven jacket water pump circulates coolant through the engine cooling system. The amount of coolant flow varies according to its temperature and is controlled by a three-way thermostatic valve installed at the inlet of the shell side of the heat exchanger.
The diesel generator cooling water system provides a sufficient heat sink to permit the diesel engine to start and operate for three minutes without flow from the NSCW system. This margin is provided because the NSCW pumps require approximately 85 seconds to regain full flow following a loss of preferred power.
During the time that NSCW is not supplied to the diesel generator jacket water coolers, the temperature of the jacket water will rise.
The thermostatic valve will continue to open, allowing more flow through the heat exchangers (up to a maximum of 1800 gpm). This l will continue until the NSCW flow is restored and provides sufficient t
l cooling to lower the jacket water temperature at the thermostatic valve.
During flushing operations of the Unit 1 train A diesel generator engine jacket water system in 1985, it was ooserved that the jacket water design flow of 1800 gpm could not be achieved through the shell side of the heat exchanger. Inspection of the heat exhanger revealed that the restricted flow was the result of heat exchanger tubes bent
! at the shell side inlet and outlet nozzles. This damaged heat l exchanger was returned for repair and a replacement was obtained I from Unit 2. The replacement heat exchanger successfully passed l the flushing operation which put the design flow through the heat l exchanger, and the repaired heat exhanger was installed on the Unit 2 1
diesel generator.
i During recent flushing operations of the Unit 2 diesel generator, i the previously repaired heat exchanger was damaged again. The tube l bundle was bent and forced against the discharge port on the jacket l water side, resulting in water leakage due to tube damage.
I L
. , ,' i 4 l Bent tubes in the heat exchanger could restrict the flow through the tubes and through the shell inlet and outlet nozzles. This flow restriction through the heat exchanger could result in an increase in engine coolant temperature, which in turn could cause an engine trip on high Jacket water temperature. The diesel generator jacket water heat exchangers used at Vogtle were manufactured by Thermxchanger Inc., a company no longer in business and are No. 2422, Type AEW.
Engineering Evaluation: Investigation as a resul t of the initial condition in 1985 concluded that the jacket water heat exchanger design flow of 1800 gpm had probably been exceeded during flushing operations. A flush cloth was used in addition to the wire mesh strainer normally used in the evaluation of system cleanliness.
The flushing log indicated that the flush cloth failed to hold and broke. It was suspected the flush cloth may have collected enough particles to severely restrict system flow, which caused the cloth to eventually fail. It was concluded that this restriction and subsequent release probably resulted in a flow surge transient in the system that could have caused the damage to the heat exchanger i tubes.
When the heat exchanger was damaged during Unit 2 flushing, a flow surge transient was not suspected to have caused the tube damage.
Investigation of heat exchanger design indicates that the damage was a result of the 1800 gpm flow used during the flushing operation.
Flushing- was performed at the design flow rate specified by the manufacturer. However, calculations reveal that actual inlet and outlet nozzle velocities exceed the standards established by the Tubular Exchanger Manufacturers Association (TEMA).
Review for Quality Assurance Program Breakdown: A review for a Quality Assurance Program Breakdown has been conducted. The review concluded that this deficiency does not represent a significant breakdown in the quality assurance program of the diesel generator manufacturer.
Conclusion:
Georgia Power Company has evaluated this condition and l
concluded that a reportable condition as defined by 10CFR21 does
' exist, in addition to the praviously reported 10CFR50.55(e). Based on the guidance in NUREG-0302, Revision 1, concerning duplicate l reporting of an event, Georgia Power Company is reporting this event l per the criteria of 10CFR50.55(e). This report provides additional information relating to the cause of the heat exchanger damage and the new corrective action proposed. The previous determination that a reportable event exists per 10CFR50.55(e) has not changed.
l Corrective Action: The Unit 2 diesel generator therrrostatic valves are being modified by adding mechanical stops to limit jacket water flow through the heat exchanger to a maximum of 750 gpm. IM0 Delaval Inc., (the diesel generator vendor) concludes that this flow is within TEMA standards and will be sufficient for flushing. IM0 Delaval also states that normal operating flow required for proper heat transfer in this installation is 500 gpm.
This modification will be made on Unit 2 commensurate with the Unit 2 construction schedule prior to fuel load.
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