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Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML20126D7211992-12-16016 December 1992 Potential Part 21 Rept Re Actual Performance of Rosemount Supplied Bailey Bq Differential Pressure Transmitters Differing from Rosemount Original Spec.Bailey Controls Encl.Evaluation Not Yet Performed 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 ML20215G5351986-10-10010 October 1986 Part 21 Rept Re Vendor Tests of air-operated Diaphragm Valves Revealing Natural Frequencies Less than Required Values of 33 Hz.Initially Reported on 841227.No Adverse Effects Noted During Testing ML20215G6801986-10-10010 October 1986 Part 21 Rept Re Vendor Tests of air-operated Diaphragm Valves Revealing Natural Frequencies Less than Required Values of 33 Hz.Initially Reported on 841227.No Adverse Effects Noted During Testing ML20205F6141986-08-13013 August 1986 Part 21 Rept Re Connecting Rod Bolts for Dsrv Engines.Listed Procedures Recommended for Next Connecting Rod Insp, Including Replacement of Bolts Due to Cracked Threads & Large Grooves & Galls in Threads ML20206U0591986-07-0202 July 1986 Part 21 Rept Re Potential Defect in Component of Dsrv Standby Diesel Generators,Involving Problem W/Fastening of Engine Connecting Rod Assembly Which Could Result in Engine Nonavailability.Procedure Will Be Issued by 860718 ML20197H2581986-05-0808 May 1986 Part 21 Rept 135 Re Defect W/Lube Oil Sump Tank Foot Valve of Standby Diesel Generator.Caused by Extrusion of Liner Matl Due to Overpressurization.Corrective Actions Being Developed.List of Affected Sites Modified ML20205N6811986-04-14014 April 1986 Final Part 21 & Deficiency Rept 86-03 Re Consolidated Pipe & Valve Supply,Inc Certified Matl Test Repts.Initially Reported on 860321.Six raised-face Orifice Flanges Statused & Segregated Per QA Procedures ML20205N7381986-04-14014 April 1986 Interim Deficiency & Part 21 Rept 86-02 1 Re Elastomer Liner in Clear Flow Co Foot Valves Used in Lube Oil Sump Tanks of Tdi Diesel Generators.Initially Reported on 860321. Action Will Not Be Pursued Unless Facility Reactivated ML20140H5991986-03-24024 March 1986 Second Interim Deficiency Rept 86-01 Re Error in Bechtel Computer Analysis Program.Initially Reported on 860121.No Corrective Actions Will Be Pursued & No Further Repts Will Be Submitted Unless Project Reactivated 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 ML20153F5391986-02-14014 February 1986 Interim Part 21 & Deficiency Rept Re Error in Bechtel Computer Analysis Program ME101.Initially Reported on 860121.No Corrective Actions or Further Repts Will Be Submitted Until Project Reactivated ML20137N6101986-01-10010 January 1986 Interim Part 21 & Deficiency Rept 85-08 Re Isolated Failures of Betts Spring Co Intake & Exhaust Valve Springs Reported by Tdi.Initially Reported on 851218.Corrective Actions Will Be Pursued If Units Reactivated 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 ML20138B9531985-10-0909 October 1985 Interim Deficiency Rept Re Larger than Anticipated Util Movement Where Freezewall Crossed safety-related Utils at Monitoring Pits 1,2,3 & 4.Initially Reported on 850917.No Action Will Be Taken ML20138C3111985-10-0808 October 1985 Interim Deficiency Rept Re Limitorque motor-operated Butterfly Valves Not Opening Electrically After Closed Manually.Initially Reported on 850912.No Corrective Actions Will Be Taken Unless Facility Reactivated ML20138C3251985-10-0808 October 1985 Interim Deficiency Rept Re Loose Set Screws on Anchor Darling Swing Check Valves & Disc Nut Pin Problems Causing Inoperability.Initially Reported on 850912.No Further Corrective Action Will Be Taken Unless Facility Reactivated 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 ML20132D3191985-07-10010 July 1985 Interim Part 21 & Deficiency Rept Re Rupture During Testing by Wj Woolley Co of Inflatable Seal,Mfg by Presray Corp,Used in Personnel Air Locks in Reactor Containment Sys.Initially Reported on 850614 ML20129G0601985-04-26026 April 1985 Interim Deficiency Rept Re Potential for Cracking of Check Valves in on-engine Mounted Starting Air Piping of Tdi Diesel Generators.Initially Reported on 850401.Cause Not Determined.No Corrective Actions.Related Correspondence ML20112J3951985-03-22022 March 1985 Interim Part 21 & Deficiency Rept Re Failure of Gulf & Western MSIV Actuator Latch Roller Bearing.Matter Will Not Be Pursued Unless Plants Reactivated ML20114D3571984-12-21021 December 1984 Interim Deficiency Rept Re Diesel Fuel Oil Tank Soils Borings.Initially Reported on 841121.No Corrective Actions Necessary Due to Present Project Shutdown ML20100K9791984-11-27027 November 1984 Part 21 & Interim Deficiency Rept Re Ruskin Mfg Co Interlocking Blade Fire Dampers.Initially Reported on 841121.Corrective Action Will Not Be Pursued & No Further Repts Will Be Made Unless Plant Reactivated ML20100D9841984-11-21021 November 1984 Deficiency Rept Re Diesel Fuel Oil Tank Boring Logs.Util Response to Dow Chemical Co 841113 Request for Admissions Encl ML20100E4451984-11-15015 November 1984 Interim Deficiency Rept Re Cardinal Industrial Products Corp Spare Studs Received W/O Ultrasonic Exam.Initially Reported on 841010.Corrective Actions Will Not Be Pursued Unless Midland Reactivated ML20100E2621984-11-15015 November 1984 Interim Part 21 & Deficiency Rept Re Rosemount 1153 Series B Transmitters Potentially Leaking.Initially Reported on 841010.Four Units Shipped to Facilities.Corrective Actions Will Not Be Pursued ML20100E2371984-11-15015 November 1984 Interim Part 21 & Deficiency Rept Re Tdi Fuel Control Level Cap Screws.Initially Reported on 841010.No Corrective Actions Will Be Pursued & No Further Repts on Subj Made Unless Midland Reactivated ML20099E3531984-11-0909 November 1984 Interim Deficiency Rept Re Small Bore Piping Anchor Design. Initially Reported on 840816.Listed Corrective Actions Will Not Be Pursued & No Further Repts Will Be Made Unless Facilities Reactivated ML20093H3961984-08-0202 August 1984 Interim Deficiency Rept Re Seismic Qualification of Power Supplies for Eccas & Ni/Rps Equipment.Initially Reported on 840705.No Activity Being Currently Pursued.No Further Repts Will Be Made Unless Facilities Reactivated ML20093H8521984-08-0202 August 1984 Interim Deficiency Rept Re Field Installation of Itt Grinnell Struts & Extension Pieces.Initially Reported on 840705.No Activity Being Currently Pursued.No Further Repts Will Be Made Unless Facilities Reactivated ML20093H8111984-07-27027 July 1984 Final Part 21 & Deficiency Rept Re Capstan Springs in Mechanical Shock Arrestors Supplied by Pacific Scientific. All Suspect Shock Arrestor Capstan Springs Will Be Inspected for Cracks & Defective Springs Replaced ML20096A7781984-07-27027 July 1984 Final Deficiency Rept Re Defective Capstan Springs in Pacific Scientific Mechanical Shock Arrestors.Initially Reported on 840106.W/o Description of Investigation & Corrective Actions.Related Correspondence ML20093H8871984-07-20020 July 1984 Interim Deficiency Rept Re Reactor Coolant Pump Seals & Seal Covers.Initially Reported on 840622.No Activity Currently Being Pursued.No Further Repts Will Be Made Unless Facilities Reactivated ML20093H4751984-07-17017 July 1984 Interim Deficiency Rept Re Core Flood Line Piping Supports in Reactor Pressure Vessel Connection Supplied by Bechtel. Overstressing Could Occur in Pipe Supports.No Commitment Made for Further Repts ML20093G7891984-07-11011 July 1984 Final Deficiency Rept Re Concrete Embedment Design Using Shear Lugs Located Outside Compression Zone.No Corrective Action Required.Not Reportable Under 10CFR50.55(e) ML20096A2951984-07-11011 July 1984 Final Deficiency Rept Re Concrete Embedment Design Using Shear Lugs Located Outside Compression Zone.Initially Reported on 821203.Use of Shear Lugs Outside Compression Zone Is Proper Design Technique.Related Correspondence ML20093D1511984-07-0909 July 1984 Final Deficiency Rept Re Excessive Wear to Pacific Air Products Linear Converter Shaft Guides.Initially Reported on 840228.Vendor Drawings Reviewed to Ensure All safety-related Dampers Identified ML20093F7131984-07-0606 July 1984 Interim Deficiency Rept Re Differential Settlement Between Diesel Generator Structure & Pedestal.Svc Water Piping Modified,Investigation of Similar Conditions Completed & Personnel Retrained.Next Rept Expected by 840928 ML20093F8311984-06-30030 June 1984 Final Deficiency Rept Re Attachment of non-q/non-seismic Piping to Component Water Sys.Initially Reported on 831216. Investigation Completed.Training Session Held to Reinstruct Design Stress Group on Total Loads ML20093D2041984-06-29029 June 1984 Interim Deficiency Rept Re Sys for Processing Field Changes for Project Design Documents.Program Initiated for Document Review,Audit Performed & Interface Procedure Implemented. Next Rept Will Be Submitted by 841231 ML20093E1431984-06-29029 June 1984 Interim Deficiency Rept Re delivered,safety-related Itt General Controls Electrical Equipment Not Meeting Project Requirements.Evaluation Underway.Interim or Final Rept Expected by 841231 ML20090C8381984-06-29029 June 1984 Interim Deficiency Rept Re Reactor Bldg Spray Piping Supports.All Engineering Corrective Actions Complete.Matl Required for Repairs Procured.Next Rept Will Be Submitted by 850125 ML20092K6121984-06-15015 June 1984 Interim Deficiency Rept Re Control of Retroactive Design Changes.Initially Reported on 840518.Investigation Continuing.Next Rept Will Be Provided by 841130 ML20091R5751984-06-0808 June 1984 Interim Deficiency Rept Re Electrical Raceway Sys Nonconformances.Initially Reported on 830829.Util Evaluating Results from Const Completion Program & Reviewing Bechtel Followup to Mcar 70.Next Rept by 841130 ML20091Q9511984-06-0101 June 1984 Interim Deficiency Rept Re Use of Shear Lugs in Embedment Design.Bechtel Investigations Indicated Use of Shear Lugs Outside Compression Zone Effective Design Technique & That No Safety Concerns Exist.Next Rept Expected by 840928 ML20091L7811984-06-0101 June 1984 Interim Deficiency Rept Re Small Break/Reactor Coolant Pump Operation Interaction During Primary Sys High Void Fraction Conditions.Investigation Incomplete.Next Rept Will Be Submitted by 840831 ML20091L5761984-06-0101 June 1984 Interim Deficiency Rept Re B&W Steam Generator Auxiliary Feedwater Header Design Change.Initially Reported on 820526. No Schedule Established for Design Change & Mod of Hardware. Next Rept Will Be Issued on or Before 841130 1992-12-16
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20058L8721992-12-31031 December 1992 1992 Annual Rept,Cpc ML20126D7211992-12-16016 December 1992 Potential Part 21 Rept Re Actual Performance of Rosemount Supplied Bailey Bq Differential Pressure Transmitters Differing from Rosemount Original Spec.Bailey Controls Encl.Evaluation Not Yet Performed ML20246N1221988-12-31031 December 1988 CMS Energy 1988 Annual Rept 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 ML20196J3801987-12-31031 December 1987 CMS Energy Corp 1987 Annual Rept 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 ML20207R9041986-12-31031 December 1986 CPC 1986 Annual Rept ML20214A0951986-11-14014 November 1986 Insp & Evaluation Re Adequacy of Stabilization Plan,In Response to Util 860701 Request for Withdrawal of Applications to Extend CP & Util Motions Seeking Withdrawal of OL Application ML20215G6801986-10-10010 October 1986 Part 21 Rept Re Vendor Tests of air-operated Diaphragm Valves Revealing Natural Frequencies Less than Required Values of 33 Hz.Initially Reported on 841227.No Adverse Effects Noted During Testing ML20215G5351986-10-10010 October 1986 Part 21 Rept Re Vendor Tests of air-operated Diaphragm Valves Revealing Natural Frequencies Less than Required Values of 33 Hz.Initially Reported on 841227.No Adverse Effects Noted During Testing ML20205F6141986-08-13013 August 1986 Part 21 Rept Re Connecting Rod Bolts for Dsrv Engines.Listed Procedures Recommended for Next Connecting Rod Insp, Including Replacement of Bolts Due to Cracked Threads & Large Grooves & Galls in Threads ML20206U0591986-07-0202 July 1986 Part 21 Rept Re Potential Defect in Component of Dsrv Standby Diesel Generators,Involving Problem W/Fastening of Engine Connecting Rod Assembly Which Could Result in Engine Nonavailability.Procedure Will Be Issued by 860718 ML20197H2581986-05-0808 May 1986 Part 21 Rept 135 Re Defect W/Lube Oil Sump Tank Foot Valve of Standby Diesel Generator.Caused by Extrusion of Liner Matl Due to Overpressurization.Corrective Actions Being Developed.List of Affected Sites Modified ML20203N4171986-04-30030 April 1986 Rev 2 to Tdi Owners Group App Ii:Generic Maint Matrix & Justifications ML20205N6811986-04-14014 April 1986 Final Part 21 & Deficiency Rept 86-03 Re Consolidated Pipe & Valve Supply,Inc Certified Matl Test Repts.Initially Reported on 860321.Six raised-face Orifice Flanges Statused & Segregated Per QA Procedures ML20205N7381986-04-14014 April 1986 Interim Deficiency & Part 21 Rept 86-02 1 Re Elastomer Liner in Clear Flow Co Foot Valves Used in Lube Oil Sump Tanks of Tdi Diesel Generators.Initially Reported on 860321. Action Will Not Be Pursued Unless Facility Reactivated ML20140H5991986-03-24024 March 1986 Second Interim Deficiency Rept 86-01 Re Error in Bechtel Computer Analysis Program.Initially Reported on 860121.No Corrective Actions Will Be Pursued & No Further Repts Will Be Submitted Unless Project Reactivated 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 ML20153F5391986-02-14014 February 1986 Interim Part 21 & Deficiency Rept Re Error in Bechtel Computer Analysis Program ME101.Initially Reported on 860121.No Corrective Actions or Further Repts Will Be Submitted Until Project Reactivated ML20137N6101986-01-10010 January 1986 Interim Part 21 & Deficiency Rept 85-08 Re Isolated Failures of Betts Spring Co Intake & Exhaust Valve Springs Reported by Tdi.Initially Reported on 851218.Corrective Actions Will Be Pursued If Units Reactivated ML20141N8361985-12-31031 December 1985 CPC 1985 Annual Rept ML20138M3891985-12-12012 December 1985 Topical Rept Evaluation of Rev 1 to BAW-1847, Leak Before Break Evaluation of Margins Against Full Break for Rcs.... Rept Presents Acceptable Justification to Eliminate Dynamic Effects of Large Ruptures in Piping 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 ML20138B9531985-10-0909 October 1985 Interim Deficiency Rept Re Larger than Anticipated Util Movement Where Freezewall Crossed safety-related Utils at Monitoring Pits 1,2,3 & 4.Initially Reported on 850917.No Action Will Be Taken ML20138C3111985-10-0808 October 1985 Interim Deficiency Rept Re Limitorque motor-operated Butterfly Valves Not Opening Electrically After Closed Manually.Initially Reported on 850912.No Corrective Actions Will Be Taken Unless Facility Reactivated ML20138C3251985-10-0808 October 1985 Interim Deficiency Rept Re Loose Set Screws on Anchor Darling Swing Check Valves & Disc Nut Pin Problems Causing Inoperability.Initially Reported on 850912.No Further Corrective Action Will Be Taken Unless Facility Reactivated 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 ML20132D3191985-07-10010 July 1985 Interim Part 21 & Deficiency Rept Re Rupture During Testing by Wj Woolley Co of Inflatable Seal,Mfg by Presray Corp,Used in Personnel Air Locks in Reactor Containment Sys.Initially Reported on 850614 ML20129G0601985-04-26026 April 1985 Interim Deficiency Rept Re Potential for Cracking of Check Valves in on-engine Mounted Starting Air Piping of Tdi Diesel Generators.Initially Reported on 850401.Cause Not Determined.No Corrective Actions.Related Correspondence ML20112J3951985-03-22022 March 1985 Interim Part 21 & Deficiency Rept Re Failure of Gulf & Western MSIV Actuator Latch Roller Bearing.Matter Will Not Be Pursued Unless Plants Reactivated ML20100B6361985-01-21021 January 1985 Rept on Welding Allegations ML20114D3571984-12-21021 December 1984 Interim Deficiency Rept Re Diesel Fuel Oil Tank Soils Borings.Initially Reported on 841121.No Corrective Actions Necessary Due to Present Project Shutdown ML20100K9791984-11-27027 November 1984 Part 21 & Interim Deficiency Rept Re Ruskin Mfg Co Interlocking Blade Fire Dampers.Initially Reported on 841121.Corrective Action Will Not Be Pursued & No Further Repts Will Be Made Unless Plant Reactivated ML20100D9841984-11-21021 November 1984 Deficiency Rept Re Diesel Fuel Oil Tank Boring Logs.Util Response to Dow Chemical Co 841113 Request for Admissions Encl ML20100E4451984-11-15015 November 1984 Interim Deficiency Rept Re Cardinal Industrial Products Corp Spare Studs Received W/O Ultrasonic Exam.Initially Reported on 841010.Corrective Actions Will Not Be Pursued Unless Midland Reactivated ML20100E2621984-11-15015 November 1984 Interim Part 21 & Deficiency Rept Re Rosemount 1153 Series B Transmitters Potentially Leaking.Initially Reported on 841010.Four Units Shipped to Facilities.Corrective Actions Will Not Be Pursued ML20100E2371984-11-15015 November 1984 Interim Part 21 & Deficiency Rept Re Tdi Fuel Control Level Cap Screws.Initially Reported on 841010.No Corrective Actions Will Be Pursued & No Further Repts on Subj Made Unless Midland Reactivated ML20099E3531984-11-0909 November 1984 Interim Deficiency Rept Re Small Bore Piping Anchor Design. Initially Reported on 840816.Listed Corrective Actions Will Not Be Pursued & No Further Repts Will Be Made Unless Facilities Reactivated ML20093C3211984-10-0101 October 1984 Rev 0 to QA Program Plan for Shutdown Phase ML20093H3961984-08-0202 August 1984 Interim Deficiency Rept Re Seismic Qualification of Power Supplies for Eccas & Ni/Rps Equipment.Initially Reported on 840705.No Activity Being Currently Pursued.No Further Repts Will Be Made Unless Facilities Reactivated ML20093H8521984-08-0202 August 1984 Interim Deficiency Rept Re Field Installation of Itt Grinnell Struts & Extension Pieces.Initially Reported on 840705.No Activity Being Currently Pursued.No Further Repts Will Be Made Unless Facilities Reactivated ML20096A7781984-07-27027 July 1984 Final Deficiency Rept Re Defective Capstan Springs in Pacific Scientific Mechanical Shock Arrestors.Initially Reported on 840106.W/o Description of Investigation & Corrective Actions.Related Correspondence ML20093H8111984-07-27027 July 1984 Final Part 21 & Deficiency Rept Re Capstan Springs in Mechanical Shock Arrestors Supplied by Pacific Scientific. All Suspect Shock Arrestor Capstan Springs Will Be Inspected for Cracks & Defective Springs Replaced ML20093H8871984-07-20020 July 1984 Interim Deficiency Rept Re Reactor Coolant Pump Seals & Seal Covers.Initially Reported on 840622.No Activity Currently Being Pursued.No Further Repts Will Be Made Unless Facilities Reactivated ML20090G2141984-07-18018 July 1984 Idcvp:Control Room HVAC Sys Performance Requirements, Draft Topical Rept ML20093H4751984-07-17017 July 1984 Interim Deficiency Rept Re Core Flood Line Piping Supports in Reactor Pressure Vessel Connection Supplied by Bechtel. Overstressing Could Occur in Pipe Supports.No Commitment Made for Further Repts ML20096A2951984-07-11011 July 1984 Final Deficiency Rept Re Concrete Embedment Design Using Shear Lugs Located Outside Compression Zone.Initially Reported on 821203.Use of Shear Lugs Outside Compression Zone Is Proper Design Technique.Related Correspondence ML20093G7891984-07-11011 July 1984 Final Deficiency Rept Re Concrete Embedment Design Using Shear Lugs Located Outside Compression Zone.No Corrective Action Required.Not Reportable Under 10CFR50.55(e) 1992-12-31
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, 7 s cm,on. u.ch 2.n Novenber 7,1980 Mr J G Keppler, Regional Director Office of Inspection ?4 Enforcement US Nuclear Regulatory Commission '
Region III 799 Roosevelt Road Glen Ellyn, IL 00137 MIDLA'!D NUCLEAR PLA'iT UNITS 1 AND 2, DOCET NOS 50-329, 50-330 COMPONENT COOLING WATER DESIGN FILE: 0.h.9.h3 UFI: 73*10*01, lolll(S) SERIAL: 10053 This letter confirms the 50.55(e) item concerning the effect of failure of the nonessential portion of the component cooling water (CCW) on the essential (safety-related) pcrtion of the CCW. This conditicn was reported by telephcne call to R Knop and R Sutphin, USNRC Region III, Glen Ellyn, IL, on October 6, 1980.
The attachments to this letter describe the conditions and actions being taken concerning this item.
Another report, either interim or final, will be sent on or before January 30, 1981.
/
WRB/lr Attnehments: 1)' Management Corrective Action Report (MCAR-1), Report No h3, dated October 10, 1980 1
- 2) MCAR h3, Interim Report 1, Component Cooling Water System l Susceptibility to Loss of Coolant Accident Induced Failures, dated October 31, 1980 CC: Director of Office of Inspection & Enforcement Att Mr Victor Stello, USNRC (1,5)
Director, Office of Management Information & Pror.rna Control, USNRC (1)
RCook, USNRC Fecident Inspector Midland Nuclear Plant (1)
$0]114 0 0 38
2 Serial 10053 CC: CBechhoefer, ASLB Panel GALinenbercer, AGLB Panel FPCowan, ASLE Panel AG?nL Appeal Panel MMCherry, Esq MSinclair CH3tephens, USNRC WDPaton, Esq, USNRC FJKelly, Esq, Attorney General SHFreeman, Esq, Asst Attorney General GTTaylor, Esq, Asst Attorney General WHMarshall CJMerritt, Esq, TNK&J Great Lakes QA Managers 9
9 l
1
QUALuiV MSSUMMNCF PROGRAM Serial 10053 l
, MANAGEMENT CORRECTIVE ACTION REPORT MCAR-1 l
, REPORT NO.: 43 JOB NO.: 7220 0 l 3 7 7 ENO.: DATE: October 10, 1980 l l DESCRIPTION * (including References):
Contrary to the safety design bases in FSAR Subsection 9.2.2, the component cooling water (CCW) system may be susceptible to LOCA-induced failures that, in conjunction with a loss of offsite power and a single active failure, could result in complete loss of the system's safety function. Non safety-related CCW lines located inside the containment are not designed for or specifically protected against the effects of a RECOMMENDED ACTION * (Optionai):
- 1. Develop and submit a written report to the AA0 PQAE staff containing all available information on or before October 27, 1980 for coordination with the Consumers Power Company.
REFERRED TO: Z Engineering C Construction O OA Management O O Procurement ISSUED Q [d 10/10/80 d L.A. Dreisbach Protect GA Engineer Date l Telcon J.A. Rutgers to J.W. Cook 11 REPORTABLE DEFICIENCY: l Potentially NOTIFIED CUENT: 10/08/80 9:00 a.m.
Reportable o.s.
O NO XYES m
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Ill CAUSE:
CORRECTIVE ACTION TAKEN:
AUTHORIZED BY:
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GOPD DISTRisvisoN PROJ otsTRtSUYlON OYMER DISTRIBUTION MGR OF CONSTRUCTCN CHtCF CONSTR OC ENGA MGR OF CA . TPO FORM AL REPORT TO CLIENT McR Or ENGiNEe R>NG CufNT GPo.ca uca (if Section ll Applies) cc.
heGR OF PnXUpf MENY PFOCE LAPO - Q A MGR MGR Of PH0J OrtR AT10Ns PROJECT CONSTR MGR SFPD . Q4 MGR uGR Or cUrur, assuaixE Pac 2ECT EetER CONSTRUCTON MGR PfaQa[Cy McA CORRECTIVE ACTION IMPLEMENTED ENGWE E HiNG UCA PRoJ PROCUREMENT MGR SUPPLit R QU4Lif Y boGR SITE MGR Ce soPERvisOR l
VERIFIED BY
- Descret,o en space prowded and affaCh reference dOCumOr,t Pewt C A En;pneer De, cm m Section Numt:cr Page of
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I DESCRIPTION - Cont. 013775 LOCA (e.g. , ia, impingement) .
The isolation valves have closure times of 60 to 75 seconds, exclusive of )
signal' delay times or diesel generator startup time. These closure times !
are inadequate to isolate a gross failure in the nonsafety-related portions of the system before the CCW surge tank c ptics.
If a singic active failure is postulated to concurrently disabic the opposite CCW safety train, the unit will lose CCW heat transfer capability. Following a LOCA, CCW capability is required to transfer heat from the DHR heat exchangers within approximately 22 minutes, and from the DHR, high-pressure injection, and reactor building spray pump coolers within approximately 30 minutes. The engineered safety features pumps have not been evaluated to determine their capability to operate without cooling water.
The CCW system, as presently designed, would accommodate minor leaks in the nonsafety-related portion of the system prior to closure of isolation valves and still allow the safety-related portion of the CCW system to perform its functions but the system is not designed to withstand a full break of the non-seismic CCW piping. Therefore, for completeness, further evaluation of seismic induced stresses and their probable effects is necessary to establish the adequacy of design for the design basis seismic event (SSE) .
II RECOMMENDED ACTION - Cont.
, 2. Perform related high energy line break analysis (HELBA) and seismic analysis to establish the impact on the portion of CCW piping in question.
- 3. Make a final determination on the reportability of this item as soon as sufficient data is available.
- 4. Investigate and identify the root cause and provide corrective action to preclude recurrence.
- 5. Determine if other similar/associsted problems exist.
- 6. Determine the necessary system changes to bring the CCW design in conformance to the applicable design criteria.
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I Serial 10053 Bechtel Associates Professional Corporation OI5296
SUBJECT:
MCAR 43 (issued 10/10/80)
Component Cooling Water System Susceptibility to Loss of-Coolant Accident-Induced Failures INTERIM REPORT 1 DATE: ,0ctober 31, 1980 PROJECT: Consumers Power Company Midland Plant Units 1 and 2 Ecchtel Job 7220 Introduction This report describes the interim status of project activities concern-ing component cooling water (CCW) system susceptibility to loss-of-coolant accident (LOCA)-induced failures.
Description of Deficiency l
The Midland Units 1 and 2 CCW system is a dual purpose system serving both safety and nonsafety-related equipment. For each unit, redundant CCW pump trains supply cooling water to the associated high pressure injection (ilPI) makeup pump lube oil coolers, reactor building spray pump, decay heat removal (DilR) pump seal coolers, and DHR heat exchangers following a LOCA; and to nonsafety-related heat exchangers during normal power operation. The nonsafety-related loads are supplied by either CCW i train during normal power operation while the redundant CCW punp train !
is on stendby. The 16- and 18-inch motor-operated butterfly valves I isolating nonsafety-related loads from the CCW pump trains have a valve closing time of 60 to 75 seconds, exclusive of delay in the control signal to activate them. Each CCW pump train has a CCW surge tank with a total capacity of 1,000 gallons and a nominal minimum operating level of 300 gallons, with a nonseismic makeup from the demineralized water storage and transfer system.
Nonseismic CCW piping to the reactor coolant pump motor coolers, letdown coolers, and control rod drive mechanism in the reactor building may not be adequately protected from LOCA-induced failures such as jet impinge-ment or pipe whip; other CCW piping to the radwaste evaporator condenser in the auxiliary building is not designed as Seismic Category I. There-fore, the piping may not retain its integrity.under LOCA-induced failures or during a seismic event.
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015296 HCAR 43 Page 2 If a pipe break were to occur in CCW piping because of LOCA-induced failures or a seismic event where the line is not specifically designed to withstand cuch an event and its consequences, the CCW surge tank Icvel would drop. For Unit 1, CCW train A, the CCW surge (IT-73A) low-low level signal will trip its associated CCW pump (IP-73A) and initiate closure of its associated motor-operated safety-related loop isolation valves (IM-1610A and IM0-1623A) isolating all nonessential components from the CCW system. This scenario is analogous for each CCW train in both units. If an emergency core cooling actuation signal (ECCAS) occurs, the CCW surge tank low-low level trip signal to the CCW pump will be bypassed, the CCW pump will start, and the safety-related loop
- isolation valves will close.
j With a pipe break in a line not specifically designed to withstand the postulated seismic event, the operating CCW surge tank Icvel could drop to the low-low level setpoint and the closure of the safety-related loop isolation valves will then be initiated. However, because of the slow (60-75 seconds) closure time of the isolation valves, enough water could be lost from the CCW system before the valves completely close that the net positi.2 suction head (npsh) available to the CCW pump would be inadequate. An ECCAS signal would restart the tripped CCW pump, which could result in loss of CCW flow and pump cavitation because of low npsh availability. The standby CCW train is postulated to be unavailable because of a concurrent single active component failure. Thus, the unit would have lost CCW heat transfer capability.
Potential Safety Implications The design deficiency has no effect on the nornal safe operation of the plant. However, following a LOCA, CCW capability is required to trans-fer heat from the DilR heat exchangers within approximately 22 minutes, and from the DllR pump seal coolers, reactor building spray pump seal coolers, and 11PI makeup pump lube oil coolers within approximately 30 minutes. It cannot be ensured that these requirements allow sufficient time following a LOCA to restore the Icvel to the surge tank and restore flow to required compnents. The capability of the engineered safety features pumps to operate without cooling water has not been evaluated.
The capability of the containment air coolers to renove heat is not j affected by this scenario.
Because the current design is a significant deliciency in final design as approved and released for construction such that the delsgn does not con-form to the criteria and bases stated in the safety analysis report and l .
could have an adverse inpact on plant safety throughout the expected life of the plant, the design deficiency is reportable under 10 CFR 50.55(e).
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015296 HCAR Page 3 Corrective Action Corrective action will be taken to ensure that the CCW surge tank level is maintained to ensure adequate npsh for safe operation of CCW pumps and that the design conforms to the design basis stated in the final safety analysis report (FSAR). Therefore further high-energy line break analysis and seismic analysis of the CCW piping under question will not be pursued. It has been determined, af ter reviewing other systems, that similar associated problems would not occur in other systems because the CCW system is the only closed-loop, dual purpose system in the plant.
Design for the corrective actica is proceeding. The cause of the defi-ciency and design details for corrective actions are being reviewed and will be discussed in the next report, which will be provided by January 16, 1981. )
l Prepared by: , _, t. , . /~ l Approved by: k J. A c.r- bC%
Concurrence by: / d '/ l l
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