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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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l P03r James W Cook 0k
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Vuce President, AfsJ!and Project
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General of fices: 1945 West Parnall Road, Jackson, Machigan 49201 *(517) 788 0640 May 22, 1980 Mr J G Keppler, Regional Director Office of Inspection and Enforcement US Nuclear Regulatory Commissicn Region III 799 Roosevelt Rcad Glen Ellyn, IL 60137 MIDLA:iD NUCLEAR PLANT UNIT NO 1, DOCKET NC 50-329 UNIT NO 2, DCCKET No 50-330 NSSS COMPCNE'IT IDENTIFICATION FILE: 0.h.9.39 UFI: 73*10*01, 02400(S) SERIAL: 8987 In accordance with the requirements of 10 CFR 50 55(e), this letter constitutes an interim report concerning a potentially unsafe situatien orig'inally reported by a telephone call from G R Eagle, CPCo MPQAD to R Knop, NRC Regicn III, on May 2, 1980.
The attachments to this letter provide a more complete descriptien of the conditicn, the bacis for initial belief that the conditicn was not reportable (pending input from the USSS supplier), and indicate the status of actions beinC taken.
Another report, either interim or final, vill be issued on or before August 22, 1980.
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- GRE/1r Attachments: 1) Quality Assurance Program, Management Corrective Action Report, MCAR-38, dated March 11, 1980
- 2) Letter "MCAI 38 - Component Identification" to L H Curtis, dated March :, 1980
- 3) MCAR-38, Interim Report #1, dated March 11, 1980 h) MCAR-38, Interim Report #2, and Cover Letter dated May 16, 1980 CC: Director of Office of Inspection and Enforcement b Att: Mr Victor Stello, USNRC (15) I l
Information & Prcgram Centrol, USNRC (1) THIS DOCUMENT CONTAINS 8 00628 0 (p a2.1 , POOR QUALITY PAGES
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OUALITY ASSURA'NCE PROGitAM
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. . REPORT NO.
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March 11,1980 _
7220 O NO.
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l ' DESCRIPTION (IncludinD roferences): inconsistent cross referencing betvcen On Ifarch 10, 1980 the Project Engiticer advised that tens (:CII, ICS , ECCAS ,
B&W and Bechtel nutbering systems for B5U-supplied instrtencnt sysThis inconsistent cross r and NI/nPS) has occurred on Unit 2. Because of the inconsistent wiring, the d inconsistent viring of BLU supplied systems.
ICS and I;III will not function properly and some incorrect indications are dispisye ,
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- RECOMMENDED hCTION (Optional) f 1.
Determine if this atic=aly could have an adverse af fect on the ' safety of operation the plant'. Report to PQAE by March 26, 1980. -
- 2. Determine cause and procedural corrective actions. '
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Deterninc most logical fix to probico.
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OOA MANAGEMENT C3 EC: ENGINEERING O CONSTRUCTION REFERRED TO O PROCUREMENT ISSUED BY
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eso,ect oA En; neer cata
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I NOTIFIED CLIEN'T **
11 REPORTABLE DEFICtENOY I
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CORRECTIVE ACTICN TAKEN .
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AUTHORIZED BY Dato au star:OARD 0:SintaVTiOtt ADomot4At. D:STR:DUTIOtt - AG APPROPP. FATE FORMAL REPORT TO CUENT oa.o
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- ritOJ JJPI.7110J CCP.01ft U4.8ACEn nn 04 n. A*e Act.)
Ir N """ * "''" CORRECTIVE ACTION IMPLEMENTED EUv"*'""
no e r.0>tCf ortnatk%$ St AN ACCn [xvWCf 8 l'HOCUn(MSNT MCn .
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A40 rewiset et tar un'*AGU4 rnOJ sv0C04t utter a.6ft (hy Syftttlit CUALily pKn ,
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- AAO WJLOF COMIINCION VEnlFIE.D DY Pfoicct GA Enepneer ,
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Bechtel Power Corporation
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Inter-office Mennorandum
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To L.11. Curtis Date. March 12,.1930 .
Subject Midland Plant Units 1 and 2 From J. A. Clenents
Of 7220 - Licensinr.
IDENTIFICATION *
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Copies to At. Ann Arbor Office .
J. P. Anderson V. J. Manta -
D,. R. Anderson R. L. Rixford File 0534, LG-13.4 L. A. Dreisbach M. O. Rothwell E. M. Ilughes J. N. Vance
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B. P. l'ononcez
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The purpose'o'f this 10:1 is to doce=ent the safety-related basis to be used in conjunc tion with a "significancy" study, to be done by others, to determine if the subject deficiency is reportablic under 10 CFR 50,
. Subsection 50.55(c) .
CONCLUSION: This deficiency, were it to have retai ned uncorrected, could not have af fected adversely the safety of operation:s of tFte Midland Plant at anytime throughout the lifeti=c of the plant.
BASIS: The component identification problem involves inconsistent cross-referencing between BEN and Bechtel numbering systec:s for r,EN supplied coeponents in both the primary and secondary systems of Unit 2. This ^
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inconsistent cross-referencing resulted in inconsis tent viring of the following Unit 2 B6W-supplied instrument systems: *
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+ Nuclear instrucentation/ reactor protection s'astem ('I/RPS)
- Emergency core cooling actuation system (ECClaS)
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- Non-nuclear instru=entation (NNI) .
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- Integrated control system (ICS)
- The analysis completed to date on the B4N-supplied engineered safety :
featurcs actuation systems, i.e., the MI/RPS and ECCAS, have indicated l that their safety-related functions would not have been de.o.raded by the l component numbering problem. These safety systens c".epend upon a 2-out-of-4 coincidence logic to initia te their safet.y functions. Thus, they are unaf fected by the order in which the, input signals a re wired.
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Bechtel Power' orporation.
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Inter-office Memorandun
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There are two problems associated with the non-safety related systems, i.e., the imI and ICS, due to the conponent numbering problem:
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- 1. The IC'I and ICS will not function properly. They arc wired so that'
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secondary side parameters (stcaa generator pressure and Icvel, feedvater -
flow and temperature) and opposite seca= generator primary side paraccters (RCS flow) instead of the same steam generator pricary and secondary side parameters. ,
- 2. Due to the inconsistent wiring of the NNI, control room indication displays labeled as steam generator A (or B) are not all monitoring
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the sa=c secam generator.
The first prob'lem, involving the ICS, has been addressed by 35W in their Specifically, the response responses to NRC questions 031.37 and 232.3."There has been no analysis perfor=ed whic to 031.37 states, in part, identifics f ailure nodes of the ICS that cause an abnormal condition out-sid2 of acceptable linits precisely because such failures are not important to safety." Also, FSAR Subsection 15.0.2, Single-Failure Philosophy, states, in part, "No ICS or operator action is required for reactor
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protection." These state =ents need to be reconfirmed by BMJ in light of the current situation.
The second probica, involving control room indications, could lead to confusion of the control roon operators even though the indications are non-safety related. However, as stated in FSAR Subsection 15.0.2, "No ICS or operator action is required for reactor protection. .All accidents Operator arc analyzed without irrediate ICS or operator action.
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action for maintaining hot shutdown conditions or for initiating cool-down to cold shutdo n conditions is assu=cd only when adequate time and instrument indications are availabic to the operator." Therefore, no operator action has been assumed based upon non-safety related instrumentation.
This position also cust be confirmed by BMJ.
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We are continuing to rescarch this issue and will document any additional information and/or BM1's concurrer a in a subsequent IOM before 3/26/80.
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Prepared by:
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J. A. Clements
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Licensing Group Supervisor
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- Control Systcus Group Supervisor,
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- J. N. Vance Chief Nuclear Engineer .
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Attachment 3 008906 identification), dated March 11, 1980
SUBJECT:
HCAR #38 (component Interim Report #1 Date: April 1, 1980 Project: Consumers Power Company Midland Plant Units 1 & 2 Bechtel Job 7220 Introduction This report is submitted regarding the interim status and actions taken pursuant to MCAR #38. *
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Description of Discrepancy Inconsistent cross-ref erencing between B&W and Bechtel numbering systems for B&W-supplied instrument systc=s (Non-Nuclear Instrumentation (NNI), Integrated Control Systems (ICS), Eccrgency Core Cooling Actuation System (ECCAS), and Nuc1 car Instrumentation and Reactor Protection System (N1/RPS)] and other com-This inconsistent cross-referencing has ponents has occurred on Unit 2. If the inconsistent resulted in ir. consistent wiring of B&W-supplied systems.that the ICS and NNI it can be postulated wiring were to remain uncorrected, indications would be dis-would not function properly and that some incorrect The following is a preli=inary response to the recom-played to the operator.
mended actions of MCAR 38:
- 1. Determine if this situation could have had an adverse affect on the safety of operation of the plant.
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Ecchtel evaluation to date of the numbering inconsistency has indicated that the deficiency, were it to have remained uncorrected, would probably not have affected adversely the safety of operations of the Midland Plant.
On March 20, 1980, the potential for reportability of this Subject matterE&W to further under 10 CFR 50.55(c) was discussed with B&W.
review, B&W tentatively agreed"with BechteJ 's preliminary conclusions that the systcas involved that provide safety functions (ECCAS and HI/RPS) would accomplish their functions under existing conditions.
Based on the information available at that time, B&W could not labels on control room displays would conclude that the incorrect not have adversely affected the safety of operations of the plant.
The B&W response letter as to the safety aspect of reportability of this matter under 10 CFR 50.55(c) is scheduled to be submitted to Bechtel by April 18, 1980.
Our present position on reportability under 10 CFR 50.55(e) is that However, the situation does not presently appear to be reportabic.
this position will be reviewed based on the B&W evaluation and any further results of project investigation.
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00690G 2.
Determine cause and procedural corrective actions.
by The most probabic cause appears Unit 2.to No be some misinte the B&W and Bechtel ccoponent numbering system for fied to specific procedural corrective actions ha.ve been identid
" Corrective Action."
- 3. Determine remedial actions.
and the best i
Several alternative solutions are under consideration, solu
- Action."
Probable Cause i f probable Refer to item 2 under " Description of Discrepancy" for discuss on o cause.
Corrective Action task group (referred to as the " Component i f A multi-discipline Midland projectNumberingThe Task CNTG Group" will actorasCNTC) a has bee schedule, the issue addressed in MCAR 38 and related matters. l As steering grnup to completely define the issue (s), and to p an,and cause monitor, report, part of their activities, the CNTG will determine the cause o
- inconsistency.
Safety Implication f safety Refer to item 1 under " Description as It should be noted that, of Discrepancy" a practical catter, it is believed for discussion d prior to o
fuel implication.
that this iten could not have gone undetected and uncorrecteand system checkouts that load. This is because of the numerous component will be made prior to fuel load.
Forecast Date of Corrective Action 16, 1980.
is scheduled to be issued by liay The next interim report Submitted by: N, m Approved by:
Concurrence by: ./ / Ch^, . t
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Bechtel Power Corporation
- 777 East Eisenhower Parkway .,
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Annareer.u.cnsan 008234 us#Avaress: P.O. Box 1000, Ann Arbor. Michigan 48100 May 16, 1980 BLC-9277 Conseners Power Company 1945 West Parnall Road Jackson, Michigan 49201 Attention: Mr. J.W. Cook Vice President Midland Project
Subject:
Midland Plant Units 1 and 2 .
Consumers Power Company Bechtel Job 7220
- - MCAR 38 Interim Report 2 Attached for your information and use is MCAR 38, Component Identification, Interim Report 2.
In a change from Interim Report 1, we now conclude that the subject issue. is probably reportabic under 10 CFR 50.55(e). Censu=crs Power Cocpany uns notified of this position by telephone on May 2,1980 (confirced in BLC-9260, dated May 13, 1980).
The next interim report is scheduled to be issued by .
August 1, 1980.
/Q & f ?-
John A. Rutge's Project Man er JAR /PJ R/kb
Attachment:
MCAR 38 Interim Repdtt 2
- cc: U.R. Bird w/a G.S. Rec 1cy v/a B.V. Marguglio w/a ,, ,
MAY 20 WBO 5
Response Requested: No
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SUBJCCT: HCAR #38 (Component Identification) dated March 11, 1980 .
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INTCRIM REPORT #2 '
008234 Project: Consumers Power Company Midland Plant Units 1 & 2 Bechtel Job 7220
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Introduction This report is submitted regarding the interim status and actions taken pursuant to MCAR #38. A change from Interim Report #1 (dated April 1,1980) is the current position that the issue addressed in MCAR #38 is probably reportabic under
Dercription of Discrepancv
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Inconsistent cross-referencing has occurred on Unit 2 between B&W and Bechtel '
numbering systems for B&W-supplied instrument systems (Non-Nuclear Instrumentation (NNI). Integrated Control Systems (ICS), Emergency Core Cooling Actuation System (ECCAS), and Nuclear Instrumentation and Reactor Protection System (NI/RPS)] and other components. This inconsistent cross-referencing has resulted in inconsistent wiring of B&U-supplied systems. If the inconsistent wiring were to remain uncorrected, it can be postulated that the ICS and NNI would not function properly and that some incorrect indications would be displayed to the operator.
Status and Actions Taken The Midland Project Component Numbering Task Group (CNTG) is coordinating resolution of the subject issue. The scope of the Midland numbering problem is currently being studied, and information is being solicited from other utilities. .
B&W has indicated that they could not support the preliminary conclusion , expressed in Interim Report #1 (that the deficiency, were it to have remained uncorrected, would probably not have affected adversely the safety of operations of the Midland plant) because the deficiency would invalidate the safety analyses. The as-constructed plant would differ from the plant design assumptions of the safety analyses.
A revised safety analysis postulating that the deficiency remain uncorrected until plane a 'eration might detarmine that the condition would not cause a bona fide safety problem. Houever, this would be an unnecessarily costly and time-consuming process, particularly since remedial action is now in progress.
Saf'ety Implications Based on the crpressed concern that the, inconsistencies could result in inappropriate
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operator action which could adversely affect the safety of plant operations, we conclude t.hst the deficiency probably should be classed within the " adverse to safety" requirement of 10 CPR 50.55(e).
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Corrective Action The CNTG will determine the d and proper No corrective action has been determined at this time.
preferred solution to bc0fMetw"ted 3 aa the evaluation is c *p ete corrective action is definect [n fdture reports.
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Date on Ubich the Corrective Action will be Taken 80, and Preliminary planning indicates a completion of evaluation by July 1,19 completion of implementation by January 1,1981. .
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Reportability_
Based on the safety implications stated above, we conclude This isthat duethe subject to the deficiency is probably reportable under 10 CFR 50.55(e). fact that "significant of 10 CFR 50.55(c) AhT_ it has been determined to be within the deficiency in final design" requirement.
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Additional Information d to
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The CNTG will act as a steering group to completely define the issue s , anan and the preferred plan, schedule, monitor, report, actions.
Several alternative solutions are under consideration, '
rolution will be determined and implemented.
As part of their activities, the CNTG will detcruine the dcause of inconsistency.
design perconnel regarding the system of cross-referencing between the Bt.U an Bechtel component numbering system for Unit 2.
this as a practical matter, it is believed that Thic is Howevet,it chould be noted that, item could not have gone undetected and uncorrected prior to fuel load. ,
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because of the numerous component and system checkouts that will be made prior to . . .
fuel load.
The next interim report is scheduled to be issued by August 1, 1980.
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.M. Anderson Approved by: M# M 9 L.H.'Curtis #
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Concurrence by:
K.D. Ba',iley J
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