Part 21 Rept Re Heat Numbers to Be Added & Deleted from Sublist Sheet A,Based on Review of NRCML20128G510 |
Person / Time |
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Site: |
Dresden, Hope Creek, Byron, Braidwood, Waterford, Zion, LaSalle, 05000000, 05000355 |
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Issue date: |
05/24/1985 |
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From: |
Kale D BONNEY FORGE |
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To: |
Anderson W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
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References |
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REF-PT21-85, REF-PT21-85-259-000 PT21-85-259, PT21-85-259-000, NUDOCS 8505300192 |
Download: ML20128G510 (8) |
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Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML20217A1691999-09-22022 September 1999 Part 21 Rept Re Engine Sys,Inc Controllers,Manufactured Between Dec 1997 & May 1999,that May Have Questionable Soldering Workmanship.Caused by Inadequate Personnel Training.Sent Rept to All Nuclear Customers ML20217M0211999-09-20020 September 1999 Part 21 Rept Re Possible Deviation of NLI Dc Power Supply Over Voltage Protection Circuit Actuation.Caused by Electrical Circuit Conditions Unique to Remote Engine Panel. Travelled to Hope Creek to Witness Startup Sequence of DG ML18107A3441999-06-0101 June 1999 Interim Part 21 Rept Re Premature Over Voltage Protection Actuation in Circuit Specific Application in Dc Power Supply.Testing & Evaluation Activities Will Be Completed on 990716 ML20207M9231999-03-12012 March 1999 Amended Part 21 Rept Re Cooper-Bessemer Ksv EDG Power Piston Failure.Total of 198 or More Pistons Have Been Measured at Seven Different Sites.All Potentially Defective Pistons Have Been Removed from Svc Based on Encl Results ML20207E9311999-02-26026 February 1999 Part 21 Rept Re Sprague Model TE1302 Aluminum Electrolytic Capacitors with Date Code of 9322H.Caused by Aluminum Electrolytic Capacitors.Affected Capacitors Replaced ML18106B0931999-02-25025 February 1999 Part 21 Rept Re Possible Defect in Swagelok Pipe Fitting Tee,Part Number SS-6-T.Caused by Crack Due to Improper Location of Heated Bar.Only One Part Out of 7396 Pieces in Forging Lot Was Found to Be Cracked.Affected Util,Notified ML18106B0551999-02-0101 February 1999 Part 21 Rept Re Possible Matl Defect in Swagelok Pipe Fitting Tee,Part Number SS-6-T.Defect Is Crack in Center of Forging.Analysis of Part Is Continuing & Further Details Will Be Provided IAW Ncr Timetables.Drawing of Part,Encl ML18106B0441999-01-29029 January 1999 Part 21 Rept Re Possible Defect in Swagelok Pipe Fitting Tee Part Number SS-6-T.Caused by Crack in Center of Forging. Continuing Analysis of Part & Will Provide Details in Acoordance with NRC Timetables ML20202F6861999-01-26026 January 1999 Engine Sys,Inc Part 21 (10CFR21-0078) Rept Re Degradation of Synchrostat Model ESSB-4AT Speed Switches Resulting in Heat Related Damage to Power Supply Card Components.Caused by Incorrect Sized Resistor.Notification Sent to Customers ML20199M0891999-01-22022 January 1999 Part 21 Rept Re Failure of Square Root Converters.Caused by Failed Aluminum Electrolytic Capacitory Spargue Electric Co (Model Number TE1302 with Mfg Date Code 9322H).Sent Square Root Converters Back to Mfg,Barker Microfarads,Inc ML20153D0191998-09-18018 September 1998 Part 21 Rept Re Defect in Gap Conductance Analyses for co- Resident BWR Fuel.Initially Reported on 980917.Corrective Analyses Performed Demonstrating That Current Operating Limits Bounding from BOC to Cycle Exposure of 8 Gwd/Mtu ML20153C6771998-09-17017 September 1998 Part 21 Rept Re Defect Relative to MCPR Operating Limits as Impacted by Gap Conductance of co-resident BWR Fuel at Facilities.Operating Limit for LaSalle Unit 2 & Quad Cities Unit 2 Will Be Revised as Listed ML17354B0971998-09-0909 September 1998 Part 21 Rept Re Possible Machining Defect in Certain One Inch Stainless Steel Swagelok Front Ferrules,Part Number SS-1613-1.Caused by Tubing Slipping Out of Fitting at Three Times Working Pressure of Tubing.Notified Affected Utils 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 ML20236N6751998-07-0909 July 1998 Part 21 & Deficiency Rept Re Notification of Potential Safety Hazard from Breakage of Cast Iron Suction Heads in Apkd Type Pumps.Caused by Migration of Suction Head Journal Sleeve Along Lower End of Pump Shaft.Will Inspect Pumps ML20248F3531998-05-21021 May 1998 Part 21 Rept Re Electronic Equipment Repaired or Reworked by Integrated Resources,Inc from Approx 930101-980501.Caused by 1 Capacitor in Each Unit Being Installed W/Reverse Polarity. Policy of Second Checking All Capacitors Is Being Adopted ML20217D0281998-04-22022 April 1998 Part 21 Rept Re Additive Constants Used in MCPR Determination for Siemens ATRIUM-9B Fuel by Core Monitoring Sys Were Found to Be non-conservative.SPC Personnel Notified All Customers w/ATRIUM-9B Lead Test Assemblies ML20217D5701998-03-20020 March 1998 Part 21 Rept 40 Re Governor Valve Stems Made of Inconel 718 Matl Which Caused Loss of Governor Control.Control Problems Have Been Traced to Valve Stems Mfg by Bw/Ip.Id of Carbon Spacer Should Be Increased to at Least .5005/.5010 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 ML20198K5081998-01-0606 January 1998 Part 21 Rept Re Transient Analyses at Exposures Prior to End of Cycle.Caused by Component Defect.Notified Commonwealth Edison of Defect & Provided Revised Limits by Siemens Power Corp ML20203B3691997-12-10010 December 1997 Part 21 Rept Re Potential to Exceed Operating Limits.Cycle 8 Delayed Until Fall 1998 ML20203J2521997-12-0101 December 1997 Deficiency Rept Re Failed Mdr Relays at Entergy Operations Inc,Waterford 3 Nuclear Generation Station.Caused by Contaminated Grease.Housekeeping Procedures Formalized & Added Enclosed Booth Isolating Mdr Final Assembly LD-97-033, Part 21 Rept Re Defect in Potter & Brumfield Mdr Relays, Models 170-1 & 7032.Extended Problem to Include All Mdr Relay Models W/Date Codes 93XX-95XX.Root Cause Analysis, Written Rept & Recommended Corrective Actions Due by 9712011997-11-20020 November 1997 Part 21 Rept Re Defect in Potter & Brumfield Mdr Relays, Models 170-1 & 7032.Extended Problem to Include All Mdr Relay Models W/Date Codes 93XX-95XX.Root Cause Analysis, Written Rept & Recommended Corrective Actions Due by 971201 LD-97-028, Part 21 Rept Re Contamination of Lubricant Which Has Led to Hardening of Lubricant in Certain Potter & Brumfield Mdr Relay Models 170-1 & 7032.Will Distribute Copy of Rept to Utils Having ABB-CE Designed Nuclear Steam Supply Sys1997-10-13013 October 1997 Part 21 Rept Re Contamination of Lubricant Which Has Led to Hardening of Lubricant in Certain Potter & Brumfield Mdr Relay Models 170-1 & 7032.Will Distribute Copy of Rept to Utils Having ABB-CE Designed Nuclear Steam Supply Sys LD-97-024, Part 21 Rept Re Error in Energy Redistribution Factor Used in LOCA Analysis for Listed Plants for Which ABB-CE Performed Analysis.Issued Recommendations Info Bulletin 97-0041997-08-14014 August 1997 Part 21 Rept Re Error in Energy Redistribution Factor Used in LOCA Analysis for Listed Plants for Which ABB-CE Performed Analysis.Issued Recommendations Info Bulletin 97-004 ML20140A9661997-05-29029 May 1997 Part 21 Rept Re Ksv Emergency Diesel Generator Power Piston Failure.Caused by Jacket Water in Combustion Chamber. Recommends That Users Verify That Crown Thickness at Valve Cutout Be 100 Minimum NSD-NRC-97-5093, Part 21 Rept Re W Identified Defects That Could Create Substantial Safety Hazard Should Defect Remain Uncorrected. Plans to Complete Proper Refurbishment of All of Returned Breakers Being Established1997-05-14014 May 1997 Part 21 Rept Re W Identified Defects That Could Create Substantial Safety Hazard Should Defect Remain Uncorrected. Plans to Complete Proper Refurbishment of All of Returned Breakers Being Established ML20210E3591997-03-27027 March 1997 Part 21 Rept Re Sorrento Electronics Inc Has Determined Operation & Maint Manual May Not Adequately Define Requirements for Performing Periodic Surveillance of SR Applications.Caused by Hardware Failures.Revised RM-23A ML20137G6261997-03-25025 March 1997 Svcs Part 21 Rept Re Emergency Generators Installed at Zion Station Which Developed Significant Drop in Crankcase Lube Oil Level.Caused by Crack in Liner Wall,Allowing Jacket Water to Enter Chamber ML20135E3811997-03-0303 March 1997 Part 21 Rept Re Output Drift W/Increasing Temperature on Several RTD Amplifiers Noted During Installation of RTD by-pass Mod at Station.Action to Identify All Circuit Cards W/Affected Date Codes,Identified ML20134Q0801996-11-27027 November 1996 Part 21 Rept Re Deficiency of Wkm Model 70-13 Pneumatic Actuators Manufactured by Anchor Darling Valve Company Due to Incorrect Calculation of Bench Set & Supply Air Set Points.All Affected Valves Have Been Reviewed & Evaluated ML18065B0111996-10-18018 October 1996 Part 21 Rept Re Application of Certain Aspects of ABB-CE Safety Analysis Methodology ML20128F5011996-10-0404 October 1996 Part 21 Rept & Deficiency Rept Re Wkm Model 70-13 Pneumatic Actuators Mfg by Anchor Darling Valve Co.All Affected Valves Being Reviewed/Evaluated & Design Changes Are Being Initiated as Required ML20117P3141996-09-11011 September 1996 Part 21 Rept Re Deficiency of GE Type RMS-9 Overcurrent Trip Device Programmers ML20117K9731996-09-10010 September 1996 Follow-up Part 21 Rept of Re Failures of Waterford 3 Dedication Testing Process of Seven Commercial Grade Barksdale Pressure Switches ML20116C7031996-07-29029 July 1996 Part 21 Rept Re Failures Identified by Waterford 3 Dedication Testing Process of 7 Commercial Grade Barksdale Pressure Switches ML20117G4641996-05-14014 May 1996 Part 21 Rept Re Cooper Bessemer Reciprocating Products,Div of Cooper Cameron Corp,Issued Ltr to Define Utils/Plants Containing Similar Equipment as Supplied on Cooper Bessemer Ksv & Enterprise Dsr EDGs LD-96-009, Part 21 Rept Re Potential Instrumentation Decalibr at Low Power.Affected Utils Should Ensure That Log Power Channels Properly Calibr & cross-correlated to Linear Power Channels at 100% Reactor Power1996-04-15015 April 1996 Part 21 Rept Re Potential Instrumentation Decalibr at Low Power.Affected Utils Should Ensure That Log Power Channels Properly Calibr & cross-correlated to Linear Power Channels at 100% Reactor Power ML20097J6351996-01-30030 January 1996 Part 21 Rept Re Intermittent Failure of DG Relay Mfg by Amerace Electronic Components.Suspect Relays at Plants Identified & Replaced.Amerace Indicated That Operators & QC Personnel Made Aware of Need for Proper Soldering ML20096E6511996-01-18018 January 1996 Part 21 Rept Re Failure of MOV Motor Pinion Gear Mfg by Limitorque at Byron Station.Replacement & Insp Activities Initiated for Potentially Impacted Populations of MOVs at Byron & Braidwood Stations ML20096A4021995-12-28028 December 1995 Interim Part 21 Rept Failure of Scram Discharge Vol Drain Valve 1BFHV-F011.Possible Causes of Failure,Includes Spring mis-adjustment,change in Spring Adjuster Setting & Spring Relaxation.Further Investigation Ongoing ML20094R7391995-11-28028 November 1995 Potential Part 21 Rept Re Ksv EDG Sys Mfg by Cooper-Bessemer Reciprocating Products Div,Div of Cooper Cameron Corp. Recommends That All Utils Verify Open Oil Passage in Assembly ML20082S7401995-04-26026 April 1995 Part 21 Rept Re Hinge Arms Associated W/Sixteen Swing Check Valves Mfg by Anchor-Darling Valve Co ML20082Q9491995-04-21021 April 1995 Part 21 Rept Re Notifying Commission of Potential Design Defect of Ksv EDG Sys ML20081L7701995-03-29029 March 1995 Initial Part 21 Rept Re Anchor-Darling Check Valve Hinge Arms.Cs Pump B Discharge Check Valve Failed to Close in Nov 1994 Because Butt Stop on Hinge Arm Not of Sufficient Length.New Butt Stop Hinge Arm,Hinge Pin & Disc Installed ML20082B5271995-03-28028 March 1995 Part 21 Rept Re Notification 9505 Automatic Switch Co Pilot Solenoid Valve Model NP8323A20V.Caused by Failures of MSIVs to Close to Asco Pilot Solenoid Valves.Subj Valves Replaced W/Valcor 3-way Solenoid Valves ML20082E1901995-03-27027 March 1995 Part 21 Rept Re Sticking of B Core Assembly to Plugnut on Automatic Switch Co Dual Solenoid Valve Model NP8323A20V. Unit 2 Valves Replaced.Unit 1 Valves Will Be Replaced ML20077D3431994-11-29029 November 1994 Part 21 Rept Re Suspect Master Connecting Rods & Contains Info Location in Engine for Rods ML20078G3051994-11-0909 November 1994 Rev to Part 21 Rept Re Potential Problem W/Master Power Connecting Rods.Vendor Recommends Listed Utils Perform Visual Insp of Master Rods to Determine Applicability of Rept ML20071J1891994-07-22022 July 1994 Final Part 21 Rept Re Cracks Found in Body to Bonnet Nuts on Copes-Vulcan Airoperated Valves.Operability Evaluation for Byron Units 1 & 2,of Affected Valves W/Nuts of Heat Numbers H & I Completed on 940622 1999-09-22
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217J4791999-10-18018 October 1999 SER Approving Exemption from Certain Requirements of 10CFR73 for Zion Nuclear Power Station,Units 1 & 2.NRC Concluded That Proposed Alternative Measures for Protection Against Radiological Sabotage Meets Requirements of 10CFR73.55 ML20217G9961999-10-14014 October 1999 SER Accepting First 10-year Interval Inservice Insp Requests for Relief for Plant,Units 1 & ML20217F2891999-10-13013 October 1999 Drill 99-08 Emergency Preparedness Exercise on 991013 ML20217C9121999-10-12012 October 1999 SER Input Authorizing Licensee Proposed Request to Modify Definition of Core Alteration in Section 1.0 of TS & Update Sections 3/4.1,3.4.3 & 3/4.9 to Reflect Proposed Definition Change ML20217F1501999-10-12012 October 1999 Special Rept:On 990929,south Plant Vent (SPV) Range Ng Monitor Was Inoperable.Monitor Was Inoperable for More than 72 H.Caused by Electronic Noise Generated from Noise Suppression Circuit.Replaced Circuit ML20217H5221999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Byron Station, Units 1 & 2.With ML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data ML20249C8491999-09-30030 September 1999 1999 Third Quarter Rept of Completed Changes,Tests & Experiments Evaluated,Per 10CFR50.59(b)(2), for Dresden Nuclear Power Station. with ML20217N6531999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Hope Creek Generating Station,Unit 1.With BW990066, Monthly Operating Repts for Sept 1999 for Braidwood Station, Units 1 & 2.With1999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Braidwood Station, Units 1 & 2.With ML20217F9091999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for LaSalle County Stations,Units 1 & 2.With A99026, Monthly Operating Repts for Sept 1999 for Zion Nuclear Power Station,Units 1 & 2.With1999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Zion Nuclear Power Station,Units 1 & 2.With ML20217G7211999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Waterford 3 Ses. with ML20217P6351999-09-29029 September 1999 Non-proprietary Rev 6 to HI-982083, Licensing Rept for Spent Fuel Rack Installation at Byron & Braidwood Nuclear Stations ML20217A1691999-09-22022 September 1999 Part 21 Rept Re Engine Sys,Inc Controllers,Manufactured Between Dec 1997 & May 1999,that May Have Questionable Soldering Workmanship.Caused by Inadequate Personnel Training.Sent Rept to All Nuclear Customers ML20217M0211999-09-20020 September 1999 Part 21 Rept Re Possible Deviation of NLI Dc Power Supply Over Voltage Protection Circuit Actuation.Caused by Electrical Circuit Conditions Unique to Remote Engine Panel. Travelled to Hope Creek to Witness Startup Sequence of DG ML20212A7441999-09-10010 September 1999 Safety Evaluation Concluding That Alternatives Contained in Relief Request 12R-07 Provide Acceptable Level of Quality & Safety ML20211N5531999-09-0808 September 1999 Safety Evaluation Supporting Amend 121 to License NPF-57 BW990056, Monthly Operating Repts for Aug 1999 for Braidwood Station, Units 1 & 2.With1999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Braidwood Station, Units 1 & 2.With ML20212B9261999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Byron Station,Units 1 & 2.With ML20212C4501999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for LaSalle County Station,Units 1 & 2.With ML20211K0401999-08-31031 August 1999 SER Accepting Approval of Defueled Station Emergency Plan & Exemption from Certain Requirements of 10CFR50.47, Emergency Plans for Plants,Units 1 & 2 ML20211Q2141999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Waterord 3 Ses.With A99023, Monthly Operating Repts for Aug 1999 for Zion Nuclear Power Station,Units 1 & 2.With1999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Zion Nuclear Power Station,Units 1 & 2.With ML20210R6421999-08-13013 August 1999 ISI Outage Rept for A2R07 ML20211B3781999-08-13013 August 1999 Special Rept 99-002:on 990730,NPV Radiation Monitoring Sys Was Declared Inoperable.Caused by Voltage Induced in Detector Output by Power Cable to Low Range Sample Pump. Separated Cables & Secured in Place to Prevent Recurrence ML20210U8111999-08-0404 August 1999 SER Granting Licensee Relief Requests VR-1,VR-3 & Portion of VR-2 Pursuant to 10CFR50.55a(a)(3)(ii).Relief Request VR-4 Does Not Require Explicit NRC Approval Because Relief Applies to Valves Not Required by 10CFR50.55a BW990048, Monthly Operating Repts for Jul 1999 for Braidwood Station, Units 1 & 2.With1999-07-31031 July 1999 Monthly Operating Repts for Jul 1999 for Braidwood Station, Units 1 & 2.With ML20210R6081999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Dresden Nuclear Power,Units 1,2 & 3.With ML20210U4721999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Hope Creek Generating Station,Unit 1.With ML20210R3431999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Byron Station, Units 1 & 2.With ML20210Q6361999-07-31031 July 1999 Corrected Monthly Operating Rept for July 1999 for Waterford 3 ML20210S0581999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Waterford 3.With ML20210R0671999-07-31031 July 1999 Monthly Operating Repts for July 1999 for LaSalle County Station,Units 1 & 2.With A99022, Monthly Operating Repts for July 1999 for Zion Nuclear Power Station,Units 1 & 2.With1999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Zion Nuclear Power Station,Units 1 & 2.With ML20210K9861999-07-30030 July 1999 Safety Evaluation Accepting Licensee 60-day Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs ML20216D8721999-07-26026 July 1999 Review of Submittal in Response to USNRC GL 88-20,Suppl 4: 'Ipeees,' Fire Submittal Screening Review Technical Evaluation Rept:Hope Creek Rev 1:980518 ML20216D8331999-07-26026 July 1999 Safety Evaluation Concluding That Licensee IPEEE Complete Re Info Requested by Suppl 4 to GL 88-20 & That IPEEE Results Reasonable Given HCGS Design,Operation & History ML20210D8951999-07-23023 July 1999 Safety Evaluation Accepting First 10-yr Interval Inservice Insp Plan Requests for Relief ISI-018 - ISI-020 ML20210F3331999-07-22022 July 1999 Safety Evaluation Granting Relief Requests RR-B1,RR-C1,RR-D1 & RR-B3.Finds That Proposed Alternative for RR-B3 Provides Acceptable Level of Quality & Safety & Authorizes Alternative Pursuant to 10CFR50.55a(a)(3)(i) ML20210E2251999-07-21021 July 1999 B1R09 ISI Summary Rept Spring 1999 Outage, 980309-990424 M990002, Revised NFM9900022, Braidwood Unit 2 Cycle 8 COLR in ITS Format & W(Z) Function1999-07-12012 July 1999 Revised NFM9900022, Braidwood Unit 2 Cycle 8 COLR in ITS Format & W(Z) Function ML20216D3841999-07-12012 July 1999 Revised NFM9900022, Braidwood Unit 2 Cycle 8 COLR in ITS Format & W(Z) Function ML20210C1681999-07-0909 July 1999 Seventh Refueling Outage ASME Section XI Summary Rept ML20209G1751999-07-0808 July 1999 SG Eddy Current Insp Rept,Cycle 9 Refueling Outage (B1R09) ML20207H8071999-06-30030 June 1999 Rev 0 to WCAP-15178, Byron Unit 2 Heatup & Cooldowm Limit Curves for Normal Operations ML20216D8901999-06-30030 June 1999 IPEEEs Technical Evaluation Rept High Winds,Floods & Other External Events ML20210D3071999-06-30030 June 1999 Corrected Page 8 to MOR for June 1999 for DNPS Unit 3 ML20209J3481999-06-30030 June 1999 1999 Second Quarter Rept of Completed Changes,Tests & Experiments, Per 10CFR50.59.With ML20210C4731999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Hope Creek Generating Station,Unit 1.With 1999-09-08
[Table view] |
Text
(~
f BONNEY FORGE.
CEDAR & MEADOW STnEETS P.O DOX 359 ALLENTOWN. PA 18105 (800) 345 7546 (215) 4 % 9611 Hny 24, 1985 TELEX 847453 Director, Office Of Inspection and Enforcement U.S. Nuclear Regulatory Commission se Washington, DC 20555 Attn: Dr. W. F. Anderson M.S. 359 E/W
Dear Dr. Anderson,
in response to your letter of 4/24/85, we have reviewed the data enclosed. The following must be added to sublist sheet 'A'-
1). Jollet Valves, Job 5758, It. 2, 2 pcs., Heat 40400, F304, p.0. 10125, 14-12 x 3 WOL 2). Taylor Forge Canada Ltd, Job 8724, It. 142, 16 pcs.,
llent 274AA, A105, P.O. T0292, Rev. 3, 26 (1.0) x 10(1.125) WOL The following may be deleted from sublist sheet 'A' ns each of these pieces has been successfully ann 11 red for chemistry -
Line items 43, 44, 45, 46, 47, 48, 49 in addition, I have enclosed copies of the Donney Forge letter dated 8/2/84 and the Bonney Forge response to Guyon Alloys' letter dated 5/7/84.
Based on the information contained on Donney Forge letter dated 8/2/84, all items with those particular heat numbers may be deleted from total listing sheet 'A'.
No additional Information is avallnble on any other items at this time. I would appreclate a copy of the revised data sheets when they are avnllable.
If you have any further questions or comments, plense do not hesitate to call Very truly yours, hk 0 ho 7
. D. L. Knie DLK/cmd Product Engr'g Supvr.
Encl.
cci P. R. Dennvides (( b '
i i e
. s 20i Wost Mount Street, CCalineille, Illinois 63636 G bnney Forge Gu't
- Western Manufacturog Company August 2, 1984 (2iri as4.ocii.1wx: si0.cc3 2esi g
Commonwealth Edison P. O. Box 767 Chicar;o, IL 60690 Attn Mr. Paul Donavin Project Engineering Div.
RE: A) Bonney Notification Letter Dated 2/15/04 ,
Gentlenois, ,
It has come to our attention through additional research at our main office in Allentown, Pa.
numberswereincludedinreference(k)thatthefollowingheat in error. Complete documentation exists on these heat numbers to indicate they
.woro purchased in accordance with NA3700 and/or NCA3800.
We regret any inconvenience this may have caused. Please doloto all reference to the following heat numbers: DL53, DM58 BM65 DP13,DR07,UR21,DR22,BR57,BR85,BU94, BV14, DM79, DN66, DN75,DX34,DX35,andbX45.
Ve'y t yours,
. , , e
. D. L. Kale Quality Control Manager cc: P.R.Donnviden I
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e
ru .
...-.a.... i s . . s. . . - . . a...... .
201 West Mount Street. Carlinville, tilinois 62626 yg (217)854 9611.TWX:910 GG3 2651 Gulf a hiern Manufactunng Company June 15, 1984 Guyon Alloys, Inc.
950 S. Fourth St.
Harrison, NJ 07029 Attn: George H. Grunthaler
-RE: Your Letter of May 7, 1984
Dear Mr. Grunthaler,
Enclosed please find a copy of the completed list which you included in your letter referenced above. Please note that two of our job numbers have been removed from the list because of the following reasons:
Job No. 8268 item #349 300 pcs. Chemical check performed
- Job No. 0753 item #4 10 pcs. Pieces being returned
, Job No. 0753 item #5 20 pcs. Pieces being returned Copies of the letter and telex referencing these~ items are ,
enclosed.
If you have any further questions or comments, please do not hesitate to call.
Si c re y, a
D. L. Kale
. Quality Control Manager !
. Enclosure cc: P.R.Benavides .
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107. So tr-r = 3/c n Ntpotet. 5 oteto stis Y N Y N toe. 49 36 -te a 3/4 mi Ntpotets) oteto 52ts Y N Y N N N N N N w26 49.
1 ottto otteo sesz Y T Y N N N rY 'N7 26 49.
9026 62.
121. to tr-s" x 2 a Ntpotets oteto 49tz Y N Y N N N N N N otete mz Y N N N N _N N_ N. _N 9026 62;,
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'. 124. 20 tr-r a 3/r m utpotece J gg) _ etteo 521s Y N Y N_ _H. _N N. R. NN 9026 91 to"-r : 3/4" m wipotets) ottro 521s V N Y N N N N N 126. 20
- Y N N N NN N " 5-A-sutt-w 5. to 2V' = 3/r et soaotet. ge2 Y N
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A 51543-w M9. 30o 2" x 1" ei su pesetna ths>ttrue s/160 SA-to5 m*4Chtm. Ok.Igr,$pp[g{l 8768 -
I' " '#' ** * *#'~ * " "'"'** U" Y Y Y N N N N N N A-5553t-N' 4. 3 r x 3/c ei srect.c. sA-te2 F3t6
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. A-525-M - 17. 8 tV* 3i su cmgures SA 82 208 Y N Y N N _
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- 22. 7 3/r m su n tr emettre. Mtto me T- N Y N N N NN N 973s s.
sA-ts2 ms Y N Y N N N NN N 9m 11.
A n9n-w . 11. t r a 3/r s/4o a toewtet rwa A-520e4-w 75. w t/4" ei n o.d.: ca. (s) sA-tos 59n Y Y Y. N N N NN N 8825 75.
con t.
A-52u5-w 1. 3 6" s/so x 3/4" s/40 wtdotets sA-182 F316L
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cUToM alt.ofs _rAct 2 or 2 SONNET roRet tit.e No. sp.c/ He.t QUEsTtoM ANsVERS Order No. Order / ttem
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58/s Y N Y N N N N 'N N t
Y N Y N H Il Y N N tos3
- 16. 2 tr = 3/r et sanot.e meto sen t.
A-suss-se s. 25 tr namd su et, sA-ter oss r306L Y Y Y N N NN N N 107' 5-A-snu-N 1. to r a r s/4o a t tmtn g
sA- s2 se7s Y N Y N N N N N N oxt t.
A-6n20-w 12. 3 2" x 3/r at socket.u g et sA- se2s Y Y Y N N N N N N " ***
A sees-se 9. 7 s = 3/4 m s=*ota.
gs swa Y Y Y N N N N N N osse 9.
A-476es-Ne 1. 3 3/r n m. used thr d.d rius. ss-462 tore Y N Y N N N N N N u39 1.
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- 2. 4 t No.. m.a thr a.d rtum. otete isas Y N Y N N N N N N un 2.
A-6ao64-txi u. to e a 3/r et s=* t.e. sA-ter sass Y Y Y N N N N N N out u.
r3o4 u?69s-se: to. 4 tv-tv i 1/r at saket.t. sA-ts2 357: to-nts Y Y Y N N N N N N 1266 it. 4 2r-r n in m s=*. tee. ) otero 557s Y Y Y N N N N N N tru it. _
- u. 4 s"-r a 1/r m sanot.c. J (h) ~ oteto ss7s Y Y Y __N N __ N N N N 12m u.
- u. 4 tr = r sisasot.c. meto voc Y Y Y N N N N N N 1266 17.
te. 4 r a e si s=*et.c. mero ucc Y Y Y _H _N_N N u66 N N is.
- 19. 7 2V' x 1" 31 aochot.t. ottto voc Y Y l_N _N _h JL_H b- ira n.
2o. 4 noe Y Y n.
3r-r = r si sanot.c. mete l H _N _h _H _N b' 12 " 20-4 tv-tr = ur s/40 (see mat.c. meco 557s Y .Y Y N _N _N N N __N use 21.
- u. 4 2r-2" = t/2" s/40 (see mat.c. ottro ss7s Y Y Y N N _h_H_J _N 1266 22.
- 23. 4 e"-r a 1/2" s/40 (sed) mat.c. (h) ottro ss7s Y Y Y N _N N N N N 12 % 23.
- 26. 4 tv m ta s/40 (see mtdoter. otete noc Y Y Y N _.E _N N N N 12m 26 27I 4 2" x r s/so (see mtdotees otete voc Y X- 1._L _N J _N__N F 2266 27-2s. 4 2r a la s/40 (see mtdotets oteto ucc Y Y Y 3 N 3 N N h 1266 2s.
- 29. 4 3r-rxt- s/40 (see mat.c. meto 17ac Y Y T 7 N 1 N -H N uu 29.
A-4not-Nc . 2. en r a t/2 es socket.c. gs: 163c Y N Y N N N N N N et 2.
A-sMt9-N u. 25 tr-r a e 2f sa*ot t. sA-182 58ss Y Y Y N N N N N N om u.
rm
- u. 25 s -c = t otte. meto sess Y Y Y N N N N N N em u.
1s. 2r=r ")
25 otte. meta sass Y Y Y N N N N _N N om u.
- 16. 5 2" a r otete meco sess Y Y Y N N _.N N__N _ H_ 0" 16-
- 17. 5 1%" a 1" ottto ottto 585s y y y 0* U-M _N _NE._N N
- 21. 15 36"-14" m 3/4" Jf sakotet. oteto 582: Y Y Y N N N N N N 0700 21.
A-56736-Net 4. to 3 a 1" et socketet. sA-182 500s 4.
rm
- Pc s. being re turne<1 0753
- s. 20 3* a 1/2" et Sm*otet. oltto 582 1 ' 18 ' Pt o753 5.
A-3769e-N 21. t tr-6 = t 3n sanot.e s4-ts sess Y Y Y N N N N N N one 21.
rm u26s9-w 6. 20 tr = 3/r et sw niet.t.
pags2 :46c Y Y Y N N N N N N oen 6.
- 7. 3 6" x 3/4" et su Etbot.c. Ditto s5ts Y Y Y N N N N_J H "U '-
s oteto ottro 246c Y Y Y J N N N N N con 7.
I 4 preto otete 556 s Y Y Y N _N _N N_N N oen 7.
8 pitto Ditto l7ec Y Y Y N N N N N N oen 7.
A-47796-Mc 1. 8 tr-6" a 1" 3t socket.c. SA-403 585 Y Y Y N N N N N N o't8 t-wu
- 3. s rt.c = r w s=+nt.t. otteo sess Y Y Y N N N N N N cotn 3.
A-62803-W, 1. 3 r a r s/80 m a t.t. sA-182 553s Y Y Y N N N N N N zon t.
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/REF: 5.YOUR 4-56756-BRN 4
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~U h , YOUR TL'< DarED 5-30-84 r3 PLEASE USE TlilS AS YOi1R AUTHORI?A TION . 00 RErdR9 OME
,jPIECE E4CH 04. THE 400VE I TEMS TO DE DESTROYED FOR
'4 PRODUCT 444 LYSES. . AFTEfl TESTING WE WILL PROVIDE
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'YOUiWITH i 4 REDOHr OM EAC51 L0 r 9'NGEll. PLE4SE RETUR9
- THEjTWO ; PIECES TO US HERE AT THE C4ttLI 9VILLE PL49r
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[IlETURN GOODS 8591 dHICH M.JST APPFAR 09 rHE OUTSIDE ,
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PLEASE SHIP THESE RAC+< TO US RY UPS. t
.:iG 6I0YOU'HAVE 49Y'00ESTIO.95, PLEASE'LEr US KNOW. -
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'v.LI GH r - WI SHES TO REr0R 9 TO YOil FOR PEllFOR149CE OF PROD'JC r 4 94 LYSES rBY;YOU,- 09E PIECE E4CH OF THE REFERE9CED I TEMS C095IS TING OF 3"XI" 6M - AN D 3 " X 1/2" 6M F304 SOCKOLErS OF IIEar CODES- 5900 490 15999 Cp.RESPECTIVELY.-
W .IT'IS ASSUMED Thor THE PIECES WOULD HAVE TO RE'DESTR0(ED TO
-% PERFORM .THE REqdIllED PRODUCT 494 LYSES AND ACCORDINGLY YOU wouLD 9' ;
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CREDIT FOR T5fE RETURMED PIECES.
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&" TESTING,. PROVIDE TRACE 4GLE DOCUME9forION THEREOF, 49D ALLOW CREDIT 3 9 TOGETHER WITH YOUR RETUR9 AU'rHORI?.4 TION $90 APPLIC4GLE SHIPPING Mi' W INSTRUCTIO.9S- FOR THE PIECES TO GE REFUR9ED TO YOU.
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201 West Mount Street. Carlinville. I!! nois 62626 Bonney Forge <2in ason.mmua 2osi cuis + western uanufacturing company June 6, 1984 Bechtel Construction Hope Creek Power Plant P. O. Box B Hancock's Bridge, N.J. 08038 Attn. !b1 vin Crowl RE: Our letter of February 12, 1984 and your conversation with P. R. Benavides on May 31, 1984
Dear Mr. Crowl,
Heat number CH50 for 300 pieces was shown on our certifi-cation in error. The correct heat number which is marked on the pieces ond shown on our chemical check report (attached) is CG50. This item should not have been included on our list that was sent to Guyon Alloys. A corrected certification is enclosed.
If you have any further questions or comments, please do not hesitate to call.
Si cere y D. L. Kale Quality Control Manager Enclosures
'cc: P. R. Benavides
.