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| '4-ERDFIN CDRPDRATIDN IJ.ERDFIN Home 5TAN0t4RD t4ND CUSTOM ENGINEERED New York Office Chicago HEATING t4NO COOLING SURFACE Dallas and Plant Lynchburg P.O. BOX 10819 Atlanta Virginia LYNCHBURG, VIRGINIA 24506 1-800-AEROFIN Phone: 804-845-7081 February 15, 1996 Fax: 804-528-6242 1CC: (with attachments) I | | '4-ERDFIN CDRPDRATIDN IJ.ERDFIN Home 5TAN0t4RD t4ND CUSTOM ENGINEERED New York Office Chicago HEATING t4NO COOLING SURFACE Dallas and Plant Lynchburg P.O. BOX 10819 Atlanta Virginia LYNCHBURG, VIRGINIA 24506 1-800-AEROFIN Phone: 804-845-7081 February 15, 1996 Fax: 804-528-6242 1CC: (with attachments) I |
| .~Document Control Desk i | | .~Document Control Desk i |
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| ==Subject:== | | ==Subject:== |
| 1OCFR21 Report: Deviation Evaluation
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| ==Reference:== | | ==Reference:== |
| : 1) Letter from Aerofin (Brian Elliott) to Consumers Power (Barb Dotson) dated October 4, 1995 regarding 1OCFR21 notification (copy of same telefaxed to U.S. NRC on October 5, 1995) | | : 1) Letter from Aerofin (Brian Elliott) to Consumers Power (Barb Dotson) dated October 4, 1995 regarding 10CFR21 notification (copy of same telefaxed to U.S. NRC on October 5, 1995) |
| : 2) Consumers Power Purchase Order G0109437 | | : 2) Consumers Power Purchase Order G0109437 |
| : 3) Aerofin Shop Order No. 947963 | | : 3) Aerofin Shop Order No. 947963 |
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| : 6) Aerofin ASME Design Report dated 11n/94 (copies of original cover page and pages 26 & 27 marked up and attached to show effects of reduced bolt tensile strength and actual maximum system operating pressure) | | : 6) Aerofin ASME Design Report dated 11n/94 (copies of original cover page and pages 26 & 27 marked up and attached to show effects of reduced bolt tensile strength and actual maximum system operating pressure) |
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| 'i Ms. Barb Dotson 10CFR21 Report Consumers Power Company Page 2 | | 'i Ms. Barb Dotson 10CFR21 Report Consumers Power Company Page 2 |
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| l I~ ,f Ms. Barb Dotson Consumers Power Company | | l I~ ,f Ms. Barb Dotson Consumers Power Company |
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| * 1OCFR21 Report Page 3 | | * 10CFR21 Report Page 3 |
| * Actual maximum system operating pressure is on the order of 80 psig which is based upon the zero flow pressure head developed by the system pumps. Compared to a design pressure of 150 psig, there is significant margin available to accommodate substandard bolt strength characteristics. (See Reference 6.) | | * Actual maximum system operating pressure is on the order of 80 psig which is based upon the zero flow pressure head developed by the system pumps. Compared to a design pressure of 150 psig, there is significant margin available to accommodate substandard bolt strength characteristics. (See Reference 6.) |
| * The maximum calculated bolt torque corresponding to the minimum reduced tensile strength is 99 ft-lbs. This is sufficient to seat and seal the EPDM gasketed pressure boundary. | | * The maximum calculated bolt torque corresponding to the minimum reduced tensile strength is 99 ft-lbs. This is sufficient to seat and seal the EPDM gasketed pressure boundary. |
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| Therefore, Aeroiin wiii provide repiacernen( boils ior ir1e 1,453 (5/8"-i i x 3 iiiches) | | Therefore, Aeroiin wiii provide repiacernen( boils ior ir1e 1,453 (5/8"-i i x 3 iiiches) |
| ASME SA 193, Grade B7 bolts if Consumers Power Company will notify Aerofin in writing within 30 days of the date of this letter of its desire to receive replacement bolts. | | ASME SA 193, Grade B7 bolts if Consumers Power Company will notify Aerofin in writing within 30 days of the date of this letter of its desire to receive replacement bolts. |
| By copy of this letter, we are also notifying the NRC of this evaluation and thereby have completed our reporting obligations as required by 1OCFR21. | | By copy of this letter, we are also notifying the NRC of this evaluation and thereby have completed our reporting obligations as required by 10CFR21. |
| If you have any questions or require any additional information at this time, please contact me at 804-528-621 O (telephone) or 80_4-528-6243 (telefax). | | If you have any questions or require any additional information at this time, please contact me at 804-528-621 O (telephone) or 80_4-528-6243 (telefax). |
| Very truly yours, | | Very truly yours, |
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| Manager Nuclear and Code Products cc: D. L. Corell Aerofin President and Chief Operating Officer Michael D. King Consumers Power Company Project Manager Dan Depuydt Consumers Power Company Containment Cooler Responsible Engineer | | Manager Nuclear and Code Products cc: D. L. Corell Aerofin President and Chief Operating Officer Michael D. King Consumers Power Company Project Manager Dan Depuydt Consumers Power Company Containment Cooler Responsible Engineer |
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| Consolidat:ed Power §upply | | Consolidat:ed Power §upply February 13, 1996 Aerofin Corporation 4621 Murray Place Lynchburg, VA 24505 FEB 1 4 1996 AEROFIN CORPORATION Attn: Mr. Barry DeHart QA Manager |
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| * February 13, 1996 Aerofin Corporation 4621 Murray Place Lynchburg, VA 24505 FEB 1 4 1996 AEROFIN CORPORATION Attn: Mr. Barry DeHart QA Manager
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| ==Subject:== | | ==Subject:== |
| Submittal of the Cardinal Industrial Products Final lOCFR Part 21 Report | | Submittal of the Cardinal Industrial Products Final 10CFR Part 21 Report |
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| ==Dear Mr. DeHart:== | | ==Dear Mr. DeHart:== |
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| Steven W. Andrews Quality Assurance Manager Enclosure - Cardinal Final Report (44 Pages) cc: H. Kerr - President, CPS, w/o; M. Mathias - Gen. Mgr., CPS, w/o; NCR# 95-150,w/a 3556 Mary Taylor Road 0 Birmingham, Alabama 35235 * (205) 655-5515 A Division of Consolidated Pipe & Supply Co., Inc. Birmingham, AL | | Steven W. Andrews Quality Assurance Manager Enclosure - Cardinal Final Report (44 Pages) cc: H. Kerr - President, CPS, w/o; M. Mathias - Gen. Mgr., CPS, w/o; NCR# 95-150,w/a 3556 Mary Taylor Road 0 Birmingham, Alabama 35235 * (205) 655-5515 A Division of Consolidated Pipe & Supply Co., Inc. Birmingham, AL |
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| | 'L DATE: February 5, 1996 CUSTOMER: CONSOLIDATED POWER SUPPLY 3556 MARY TAYLOR ROAD BIRMINGHAM, AL 35235 ATTENTION: STEVE ANDREWS, MANAGER OF QUALITY ASSURANCE |
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| * DATE: February 5, 1996 CUSTOMER: CONSOLIDATED POWER SUPPLY 3556 MARY TAYLOR ROAD BIRMINGHAM, AL 35235 ATTENTION: STEVE ANDREWS, MANAGER OF QUALITY ASSURANCE
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| ==SUBJECT:== | | ==SUBJECT:== |
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Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML18066A3301998-11-11011 November 1998 Part 21 Rept Re Potential Safety Hazard Associated with Wrist Pin Assemblies for FM-Alco 251 Engines at Palisades Nuclear Power Plant.Caused by Insufficient Friction Fit Between Pin & Sleeve.Supplier of Pin Will No Longer Be Used ML18066A2771998-08-13013 August 1998 Part 21 Rept Re Deficiency in CE Current Screening Methodology for Determining Limiting Fuel Assembly for Detailed PWR thermal-hydraulic Sa.Evaluations Were Performed for Affected Plants to Determine Effect of Deficiency ML18066A1711998-06-0101 June 1998 Part 21 Rept Re Impact of RELAP4 Excessive Variability on Palisades Large Break LOCA ECCS Results.Change in PCT Between Cycle 13 & Cycle 14 Does Not Constitute Significant Change Per 10CFR50.46 ML18065B1351998-01-0606 January 1998 Part 21 Rept Re Use of Deltstrat Code for RCS Flow Rate Determination.Code Corrects for Temps to Determine Hot Leg Bulk Coolant Temp ML17264A9381997-07-10010 July 1997 Deficiency Rept Re Potential Safety Hazard Associated w/FM-Alco 251 Engin,High Pressure Fuel tube-catalog: 4401031-2 in Which Dual Failure Mode Exists.Caused by Incorrect Forming Process 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 ML18065B0111996-10-18018 October 1996 Part 21 Rept Re Application of Certain Aspects of ABB-CE Safety Analysis Methodology ML18065A5001996-02-15015 February 1996 Part 21 Rept Re Hex Bolts Mfg by Cardinal Industrial Products (Cip).Aerofin Will Provide Replacement Bolts for Bolts in Question If Util Notify Aerofin in Writing within 30 Days of Date of ltr.10CFR21 Rept from CIP Encl ML18065A1441995-10-0404 October 1995 Part 21 Rept Re Fastener Products (Hex Bolts) Mfg by Cardinal Industrial Products.Bolts Used as Header Cover Plate Bolts in Safety Related Containment Air Cooler Replacement Cooling Coils Furnished by Aerofin Corp to CPC ML18064A8841995-08-30030 August 1995 Part 21 Rept Re Presence of Hardwired Connection in Each of Four Containment High Pressure Trip Logic Circuits.Jumpers Removed in Slot 11 of Interconnection Module Assemblies in All Four Channels ML18058B9021993-07-0101 July 1993 Part 21 Rept Re Potential Defect in Vicor Corp mini-mod Dc/ DC Converter Modules.Deficiency Identified During Failure Analysis of Subj Modules While in Svc at Palisades in Apr 1993.Affected Dc/Dc Converter Modules at Plant Replaced 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 ML20125C7161992-12-0707 December 1992 Part 21 Rept Re Possibility for Malfunction of Declutching Mechanisms in SMB/SB-000 & SMB/SB/SBD-00 Actuators. Malfunction Only Occurs During Seismic Event.Balanced Levers May Be Purchased from Vendor.List of Affected Utils Encl ML20127P5861992-11-23023 November 1992 Followup to 921005 Part 21 Rept Re Potential Defect in SB/SBD-1 Housing Cover Screws.Procedure Re Replacement of SBD-1 Spring Cover Bolts Encl.All Fasteners Should Be Loosened & Removed.List of Affected Utils Encl ML20118B4391992-09-11011 September 1992 Part 21 Rept Re Degradation in Abb Type 27N Undervoltage Relays Used in Electrical Switchgear.Recommends That Users Review Applications Requiring Exposures Greater than 1E03 Rads TID W/Time Delay Function Option ML18058B0201992-08-24024 August 1992 Part 21 Rept Re 920513 & 0701,premature Lifting of Farris Safety Relief Valve RV-3128 & SI Tank T-82B Relief Valve. Initially Reported on 920701.Caused by Misalignment of Spring Adjustment Screw Bore.Bonnet & Spring Replaced ML18058B0051992-07-30030 July 1992 Part 21 Rept 23967:on 920513 & 0701,Farris Relief Valve RV-3128 & SI Tank Relief Valve T-82B Lifted Prematurely. Caused by Misalignment of Spring Adjustment Screw Bore in Valve Bonnet.Util Has 23 Subj Valves in Facility ML18058A4551992-05-15015 May 1992 Part 21 Rept Re Allis Chambers Switchgear Breakers Refurbished by Sitek of Milwaukee.Original Procurement of Breakers Before IEEE Stds Were Developed.Breakers Sent to Sitek of Milwaukee for Refurbishment ML18058A4131992-04-23023 April 1992 Part 21 Rept Re Improperly Terminated Wires on Closing Relay for 2,400-volt Switchgear Mfg by Allis Chalmers & Refurbished by Sitek of Milwaukee.Corrective Actions Not Yet Determined.Palisades Only Facility W/Subj Defect ML18054B4681990-02-27027 February 1990 Part 21 Rept Re Defective PORV Block Valve W/Limitorque Actuator Type SMB-00-25.Caused by Missing Pin That Connects Limit Switch Drive Gear to Main Actuator Drive Train.Valve Actuator Disassembled to Find Cause of Malfunction 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 ML18054B0931989-11-0909 November 1989 Part 21 Rept Re Siemens-Allis Breaker mis-wired During Refurbishment Resulting in Blowing of Breaker Fuse.Caused by Vendor Error.Vendor Corrected Drawing File ML18054B1331989-11-0606 November 1989 Part 21 Rept Re Defect in Rockbestos Electrical Cable W/ Incorrect Shield Matl Supplied to Plant.Util Has Identified & Dispositioned Affected Cable Onsite.Rockbestos Has Shipped Replacement Cable & Authorized Return of Defective Cable ML18054A4711988-12-22022 December 1988 Part 21 Rept Re Deficiencies in Sample-Webtrol,Inc Masoneilan Valve Parts.Initially Reported on 881021.All Suspect Matl Remaining in Warehouse Pulled & Being Controlled ML18053A6731988-11-18018 November 1988 Part 21 Rept Re Potential for Counterfeit Masoneilan Valve Parts Being Supplied to Commercial Nuclear Facilities. All Identified Parts from Plant Named in 881021 Rept Segregated & Replaced.Independent Investigation Underway ML18054A3961988-10-21021 October 1988 Part 21 Rept Re Masoneilan Valve Parts Supplied by Sample- Webtrol,Inc Not Meeting Specs.Initially Reported on 881018. Matl in Warehouse Pulled & Location of Issued Matl Being Identified for Disposition or Replacement ML20127L4521988-10-21021 October 1988 Part 21 & Deficiency Rept Re Info on Discovery That Some Masoneilan Valve Parts Supplied by Samole-Webtrol Inc Are Not Genuine.Also Confirms 881018 Telcon Rept Re Notification Criteria of 10CFR21.21(b)(2) ML18054A3071988-05-25025 May 1988 Part 21 Rept Re Failure of Ashcroft Glycerin Filled Bourdon Tube Pressure Gauges That Failed at Pressure within Operating Range.Caused by Separated Weld.Faulty Gauges Replaced ML18053A3891988-05-20020 May 1988 Part 21 Rept Re Missing Cotter Pin in Ite Breaker Trip Mechanism Resulting in Breaker Failing to Close.Initially Reported on 880513.Breaker Repaired,Cotter Pin Inserted & Breaker Reinstalled ML18053A3641988-05-0202 May 1988 Part 21 Rept Re Inaccurate 1,000 Ppm Boron Std Used to Standardize Titrant Used for Boron Concentration Analysis. Initially Reported on 880429.All Suspect Matl Removed & Labeled Not for Use 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 ML20209G1911986-08-13013 August 1986 Part 21 Rept Re Enerfab,Inc Containment Bldg Emergency Escape Airlock Design Deficiency.Initially Reported on 860724.Two Actuating Cams for Inner & Outer Equalizing Valves Modified ML20206S0841986-06-30030 June 1986 Part 21 Rept Re Possible Cut Wires in Wire Harness of Bbc Brown Boveri K600/K800 Circuit Breakers.Initially Reported on 860509.Safety Implications Listed.Gear Guard Designed to Prevent Cut Wires ML20140A5281985-12-19019 December 1985 Part 21 Rept Forwarding Ltr Sent to Customers Re Check Valves Missing Lock Welds on Hinge Supports or Hinge Support Capscrews,Per 851121 Request.List of Customers Receiving Ltr Also Encl ML20087F4281984-02-29029 February 1984 Part 21 Rept Re Apparent Design Deficiency in Siemens Allis Model MA-205B Stored Energy Circuit Breaker.Breaker Insp & Hold Down Device Orientation Will Be Complete by 840401. Determination of Permanent Fix & Implementation by 840601 ML20083E1881983-12-14014 December 1983 Supplemental Part 21 Rept Re Incorrect Boron Stds Purchased from Jt Baker Chemical Co.Initially Reported on 821222. Independent Evaluation Revealed Ph of Boron Std Too Low. Titration Procedure Appropriate & Will Continue to Be Used ML20080N9701983-09-30030 September 1983 Part 21 Deficiency Rept Re Defective ITT-Grinnell Hydraulic Snubbers.Initially Reported in 830928 Telcon.Deficient Snubber Valve Blocks Will Be Remachined & Snubbers Rebuilt ML20072N9891983-07-0808 July 1983 Interim Part 21 Rept Confirming 830705 Telcon Re Anomalies in Artificially Aged Apparatus (Using Ahrrenius Methodology W/Elevated Temp Aging).Deficiency Found During Qualification Testing for IEEE 323-1974.Draft Notices Encl ML20028C2521982-12-22022 December 1982 Part 21 Rept Re Jt Baker Chemical Co Defective 1,000 Ppm Boron Std Used for Standardization of Sodium Hydroxide to Determine Primary Coolant Sys Boron Concentration.Initially Reported 821220.Another Supplier Used ML20041F1911982-03-0303 March 1982 Part 21 Rept Re Defective Diesel Generator Governor Mfg by Woodward Governor Co Initially Reported 820226.Lock Washer & Nut Missing from Shutdown Solenoid & Broken Nut Found Inside Assembly.Governor Replaced & Returned for Repair ML20038C6741981-12-0303 December 1981 Part 21 Rept Re Weld Fractures Possibly Attributable to Modified Installation Procedure for Mounting of Battery Rack.Encl Notices Have Been Sent to Facilities Receiving Similar Frames for L Size Cell Racks ML20038A8711981-11-23023 November 1981 Advises That Sectioned Frame Welds Will Be Examined on Receipt from Bechtel,Compared W/Welds on Rack Qualified at Wyle Labs on 761116 & Examined in Light of Installation Conditions Observed by C&D Personnel at Site 811014-15 ML20011A5791981-10-21021 October 1981 Part 21 Rept Re Welded Subassemblies Found to Have Welds W/Lack of Acceptable Weld Deposit to Base Metal Fusion, Initially Reported 811020.Replacement Racks Have Been Fabricated & Are Being Installed ML18045A8201980-10-17017 October 1980 Part 21 Rept Re Pipe Supports W/Partially or Totally self- Aligning Rod End Bushings.Info Submitted to Other Bechtel Power Divs on 801008 for Review.Rept Will Be Provided If Defect Applies to Other Bechtel Projects ML18045A8021980-10-0808 October 1980 Part 21 Rept Re Pipe Supports W/Partially or Totally Disengaged self-aligning Rod End Bushings Furnished by Itt Grinell,Corner & Lada,Pacific Scientific-Kintech Div & NPS Industries ML19270G4771979-05-11011 May 1979 Natl Pollution Discharge Elimination Sys 790507 Noncompliance Notification Re Excessive Neutralizer Tank Discharge.Caused by Operating Errors.Discharge Procedures Discussed W/Operators ML19290A4731973-08-17017 August 1973 Deficiency Rept Re Grease Leakage Discovered on 730720 from 2090P Casing Filler Mfg by Viscosity Oil Co Into Vertical Tendon Conduits.Liner Plate Checked & No Bulging or Buckling Found.Samples of Leaking Matl Taken 1998-08-13
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML18066A6901999-11-0101 November 1999 Rev 5 to Palisades Nuclear Plant Colr. ML18066A6761999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Palisades Nuclear Plant ML18066A6271999-09-0202 September 1999 LER 98-011-01:on 981217,inadequate Lube Oil Collection Sys for Primary Coolant Pumps Was Noted.Caused by Design Change Not Containing Appropriate Level of Rigor.Exemption from 10CFR50,App R Was Requested.With 990902 Ltr ML18066A6351999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Palisades Nuclear Plant ML18066A6771999-08-31031 August 1999 Operating Data Rept Page of MOR for Aug 1999 for Palisades Nuclear Plant ML18066A6221999-08-20020 August 1999 LER 99-002-00:on 990722,TS Surveillance Was Not Completed within Specified Frequency.Caused by Failure to Incorporate Revised Frequency Into Surveillance Schedule in Timely Manner.Verified Implementation.With 990820 Ltr ML18066A6061999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Palisades Nuclear Plant.With 990803 Ltr ML18066A5201999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Palisades Nuclear Plant.With 990702 Ltr ML18066A4841999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Palisades Nuclear Plant.With 990603 Ltr ML18066A6371999-04-30030 April 1999 Revised Monthly Operating Rept for Apr 1999 for Palisades Nuclear Plant ML18068A5941999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Palisades Nuclear Plant.With 990503 Ltr ML18066A4161999-04-0101 April 1999 Rev 4 to COLR, for Palisades Nuclear Plant ML18066A4501999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Palisades Nuclear Plant.With 990402 Ltr ML18066A4671999-03-31031 March 1999 Rev 0 to SIR-99-032, Flaw Tolerance & Leakage Evaluation Spent Fuel Pool Heat Exchanger E-53B Nozzle Palisades Nuclear Plant. ML18068A5351999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Palisades Nuclear Plant.With 990302 Ltr ML18066A3931999-01-31031 January 1999 Monthly Operating Rept for Jan 1999 for Palisades Nuclear Plant.With 990202 Ltr ML18066A3781999-01-20020 January 1999 LER 98-013-00:on 981222,safeguards Transfer Tap Changer Failure Caused Inadvertant DG Start.Caused by Failed Motor Contactor.Contactor Was Replaced.With 990120 Ltr ML20206F6131998-12-31031 December 1998 1998 Consumers Energy Co Annual Rept. with ML18066A3651998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Palisades Nuclear Plant.With 990105 Ltr ML18066A3421998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Palisades Nuclear Plant.With 981202 Ltr ML18066A3301998-11-11011 November 1998 Part 21 Rept Re Potential Safety Hazard Associated with Wrist Pin Assemblies for FM-Alco 251 Engines at Palisades Nuclear Power Plant.Caused by Insufficient Friction Fit Between Pin & Sleeve.Supplier of Pin Will No Longer Be Used ML18068A4921998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Palisades Nuclear Plant.With 981103 Ltr ML18068A4851998-10-29029 October 1998 LER 97-011-01:on 971012,starting of Primary Coolant Pump with SG Temps Greater than Cold Leg Temps Occurred.Caused by Inadequate Procedures & Operator Decision.Sop Used for Starting Primary Coolant Pump Enhanced ML18066A3181998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Palisades Nuclear Plant ML18066A2901998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Palisades Nuclear Power Plant.With 980903 Ltr ML18066A3191998-08-31031 August 1998 Revised Monthly Operating Rept Data for Aug 1998 for Palisades Nuclear Plant ML18066A2831998-08-18018 August 1998 LER 98-010-00:on 980721,reactor Manually Tripped.Caused by Failure of Coupling Which Drives Feedwater Pump Main Lube Oil Pump.Main Lube Oil Pump Coupling & Associated Components Replaced & Satisfactorily Tested ML18066A2771998-08-13013 August 1998 Part 21 Rept Re Deficiency in CE Current Screening Methodology for Determining Limiting Fuel Assembly for Detailed PWR thermal-hydraulic Sa.Evaluations Were Performed for Affected Plants to Determine Effect of Deficiency ML20237E0301998-07-31031 July 1998 ISI Rept 3-3 ML18066A2701998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Palisades Nuclear Plant.W/980803 Ltr ML18066A2311998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Palisades Nuclear Plant ML18066A2261998-06-30030 June 1998 LER 98-009-00:on 980531,small Pinhole Leak Found on One of Welds,During Leak Test Following Replacement of Pcs Sample Isolation Valves.Caused by Welder Error.Leaking Welds Repaired ML18066A3061998-06-18018 June 1998 SG Tube Inservice Insp. ML20249C4951998-06-17017 June 1998 Rev 1 to EA-GEJ-98-01, Palisades Cycle 14 Disposition of Events Review ML18066A1781998-06-0909 June 1998 LER 98-008-00:on 980511,noted That Procedure Did Not Fully Satisfy Requirement to Test High Startup Rate Trip Function. Caused by Misunderstanding of Testing Requirements.Revised TS Surveillance Test Procedure & Reviewed Other Procedures ML18066A1711998-06-0101 June 1998 Part 21 Rept Re Impact of RELAP4 Excessive Variability on Palisades Large Break LOCA ECCS Results.Change in PCT Between Cycle 13 & Cycle 14 Does Not Constitute Significant Change Per 10CFR50.46 ML18066A1741998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Palisades Nuclear Plant.W/980601 Ltr ML18066A2321998-05-31031 May 1998 Revised MOR for May 1998 for Palisades Nuclear Plant ML18068A4701998-05-31031 May 1998 Annual Rept of Changes in ECCS Models Per 10CFR50.46. ML18065B2451998-05-13013 May 1998 LER 98-007-00:on 980413,HPIS Sys Was Noted Inoperable During TS Surveillance Test.Caused by Performance of Flawed Procedure.Operators & Engineers Will Be Trained to Improve Operational Decision Making Through Resources & Knowledge ML18066A2331998-04-30030 April 1998 Revised MOR for Apr 1998 for Palisades Nuclear Plant ML18068A3461998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Palisades Nuclear Plant.W/980501 Ltr ML18066A3411998-04-22022 April 1998 Rev 0 to EMF-98-013, Palisades Cycle 14:Disposition & Analysis of SRP Chapter 15 Events. ML18065B2071998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Palisades Nuclear Plant.W/980403 Ltr ML20217C2741998-03-31031 March 1998 Independent Review - Is Consumers Energy Method (W Method) of Determining Palisades Nuclear Plant Best Estimate Fluence by Combining Transport Calculation & Dosimetry Measurements Technically Sound & Does It Meet Intent of Pts ML18066A2341998-03-31031 March 1998 Revised MOR for Mar 1998 for Palisades Nuclear Plant ML18068A3041998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Palisades Nuclear Plant.W/980302 Ltr ML18066A2351998-02-28028 February 1998 Revised MOR for Feb 1998 for Palisades Nuclear Plant ML18065B1641998-02-0505 February 1998 Rev 0 to Regression Analysis for Containment Prestressing Sys at 25th Year Surveillance. ML18067A8211998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Palisades Nuclear Plant.W/980203 Ltr 1999-09-30
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'4-ERDFIN CDRPDRATIDN IJ.ERDFIN Home 5TAN0t4RD t4ND CUSTOM ENGINEERED New York Office Chicago HEATING t4NO COOLING SURFACE Dallas and Plant Lynchburg P.O. BOX 10819 Atlanta Virginia LYNCHBURG, VIRGINIA 24506 1-800-AEROFIN Phone: 804-845-7081 February 15, 1996 Fax: 804-528-6242 1CC: (with attachments) I
.~Document Control Desk i
.V~S. Nuclear Regulatory Commission' Washington, D.C.
Palisades Nuclear Plant 22780 Blue Star Memorial Highway Covert, Ml 49043-9530
Subject:
10CFR21 Report: Deviation Evaluation
Reference:
- 1) Letter from Aerofin (Brian Elliott) to Consumers Power (Barb Dotson) dated October 4, 1995 regarding 10CFR21 notification (copy of same telefaxed to U.S. NRC on October 5, 1995)
- 2) Consumers Power Purchase Order G0109437
- 3) Aerofin Shop Order No. 947963
- 4) 10CFR21 Report from Cardinal Industrial Products as transmitted to Aerofin by Consolidated Power Supply by letter dated February 13, 1996 (attached)
- 5) Aerofin ASME Design Report dated 11n/94 (copies of original cover page and pages 26 & 27, attached)
- 6) Aerofin ASME Design Report dated 11n/94 (copies of original cover page and pages 26 & 27 marked up and attached to show effects of reduced bolt tensile strength and actual maximum system operating pressure)
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'i Ms. Barb Dotson 10CFR21 Report Consumers Power Company Page 2
Dear Ms. Dotson:
This letter follows up our initial notification to Consumers Power Company and the U.S. NRC (Reference 1) which addressed 1,475 hex bolts (5/8"-11x3 inches, ASME SA 193, Grade 87), manufactured by Cardinal Industrial Products and supplied to Aerofin by Consolidated Power Supply, which were used as header cover plate bolts in the Safety Related containment air cooler replacement cooling coils furnished by Aerofin to Consumers Power Company (Reference 2). These thirteen coils (twelve coils plus one spare) were shipped to the Palisades Nuclear Plant on or about November 16, 1994.
The bolts in question are listed as Item #16 on "as-built" drawing QA-R-1012 dated 11/1/94 included with the Aerofin Quality Assurance Data Package for this equipment.
These bolts are identified by Cardinal Industrial Products Heat No. CK256 (856 pieces, Trace Code TU2) and Heat No. L63051 (619 pieces, Trace Code CX 1). Of the 1,475 bolts purchased by Aerofin, 1,456 were actually used in the coils.
a Enclosed is complete copy of the 10CFR21 Report from Cardinal Industrial Products as transmitted to Aerofin by Consolidated Power Supply by letter dated February 13, 1996 (Reference 4) and received by Aerofin on February 14, 1996.
Review of the Cardinal Industrial Products repo*rt conclusions reveals that they can make no guarantees as to what percentage of bolts may actually be substandard, but they do state that the actual tensile strength of any substandard bolts is between 60,000 and 70,000 psi as compared to a minimum tensile strength requirement of 125,000 psi for ASME SA-193, Grade 87 material. Given this information, several conclusions can be drawn regarding the header cover plate bolts:
- The allowable stress for ASME SA-193, Grade 87 bolts is 25,000 psi (reference ASME Section Ill, Table 1-7.3) which represents a safety factor of five when compared to the material minimum tensile strength of 125,000 psi. Bolt stresses i.n substandard bolts should be compared to a lower allowable stress. Using an allowable stress equal to one-fifth of the reduced tensile strength is consistent with the safety factor inherent in the Code material mechanical properties. This gives an allowable stress for substandard bolts of 12,000 to 14,000 psi.
- For the design pressure load and nozzle loading, the worst calculated stress is the tensile stress on the short side bolts (13,323 psi - see Reference 5). This is within the range for the reduced allowable stress of 12,000 to 14,000 psi.
l I~ ,f Ms. Barb Dotson Consumers Power Company
- Actual maximum system operating pressure is on the order of 80 psig which is based upon the zero flow pressure head developed by the system pumps. Compared to a design pressure of 150 psig, there is significant margin available to accommodate substandard bolt strength characteristics. (See Reference 6.)
- The maximum calculated bolt torque corresponding to the minimum reduced tensile strength is 99 ft-lbs. This is sufficient to seat and seal the EPDM gasketed pressure boundary.
THEREFORE, IT IS CONCLUDED THAT NO SUBSTANTIAL SAFETY HAZARD EXISTS DUE TO THE POSSIBLE PRESENCE OF ANY SUBSTANDARD BOLTS.
Based upon the conclusions of the Cardinal Industrial Products report, it is unlikely that any of the containment air cooler replacement cooling coils has header cover plate bolts that are entirely (or even that a majority are) substandard. Consequently, it is expected that the equipment will operate satisfactorily with substandard bolts, even if they are present, throughout the equipment's expected operating life. However, it certainly is recognized that Consumers Power Company may have received an indeterminate quantity of bolts that do not meet ASME Code specifications.
Therefore, Aeroiin wiii provide repiacernen( boils ior ir1e 1,453 (5/8"-i i x 3 iiiches)
ASME SA 193, Grade B7 bolts if Consumers Power Company will notify Aerofin in writing within 30 days of the date of this letter of its desire to receive replacement bolts.
By copy of this letter, we are also notifying the NRC of this evaluation and thereby have completed our reporting obligations as required by 10CFR21.
If you have any questions or require any additional information at this time, please contact me at 804-528-621 O (telephone) or 80_4-528-6243 (telefax).
Very truly yours,
/L(1Y24f Brian C. Elliott, P.E.
Manager Nuclear and Code Products cc: D. L. Corell Aerofin President and Chief Operating Officer Michael D. King Consumers Power Company Project Manager Dan Depuydt Consumers Power Company Containment Cooler Responsible Engineer
t.
Consolidat:ed Power §upply February 13, 1996 Aerofin Corporation 4621 Murray Place Lynchburg, VA 24505 FEB 1 4 1996 AEROFIN CORPORATION Attn: Mr. Barry DeHart QA Manager
Subject:
Submittal of the Cardinal Industrial Products Final 10CFR Part 21 Report
Dear Mr. DeHart:
Please find enclosed a complete copy of the subject document. Consolidated Power Supply (CPS) received the document on 2/12/96 from Cardinal Industrial Products, which is now known as Accutech. CPS will retain a copy in our Nonconformance file, which is being closed based on issuance of this correspondence. As all CPS customers affected by the report have been notified, as well as the Nuclear Regulatory Commission, no further actions by CPS are deemed ..
necessary at this time regarding the questionable fasteners.
CPS and Aerofin personnel have had discussions concerning replacement of the fasteners (1475 each, 5/8" - 11 X 3" SA193 B7 hex bolts) that were supplied by CPS against Aerofin Purchase Order 13822. It has been conveyed that these fasteners were used in a component manufactured by Aerofin that was supplied to Consumers Power. If replacement fasteners will be required, it is. suggested that Aerofin obtain written correspondence to this affect from the applicable licensee, including written correspondence from Aerofin indicating the same. Exact quantities should be identified.
If there are questions or_ comments relative to the enclosed in(orn:i~_tion or this corres1xmdence please contact the undersigned.
Sincerely,
~t.J~_,
Steven W. Andrews Quality Assurance Manager Enclosure - Cardinal Final Report (44 Pages) cc: H. Kerr - President, CPS, w/o; M. Mathias - Gen. Mgr., CPS, w/o; NCR# 95-150,w/a 3556 Mary Taylor Road 0 Birmingham, Alabama 35235 * (205) 655-5515 A Division of Consolidated Pipe & Supply Co., Inc. Birmingham, AL
'L DATE: February 5, 1996 CUSTOMER: CONSOLIDATED POWER SUPPLY 3556 MARY TAYLOR ROAD BIRMINGHAM, AL 35235 ATTENTION: STEVE ANDREWS, MANAGER OF QUALITY ASSURANCE
SUBJECT:
10 CFR Part 21 Final Report
Dear Mr. Andrews:
Attached is Cardinal Industrial Products' final report that was submitted to the Nuclear Regulatory Commission (NRC) as required by 10 CFR Part 21. This final report is being provided to you as a courtesy to assist you in resolving this issue.
This report was submitted to the NRC on November 21, 1995. As of this date, the NRC has not provided a reply or correspondence.
Should you have any questions, please contact David Z. Hathcock at (702) 739-1966.
cc: 10 CFR Part 21 file
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