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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20236F8131998-06-30030 June 1998 Rev 0 to Defueled SAR Dresden Nuclear Power Station Unit 1 Commonwealth Edison Co ML20135E8551997-02-28028 February 1997 Verification Screening of Key Parameters for Twelve Risk Significant Systems ML20138K2081996-11-18018 November 1996 Rev 0 to Roles & Responsibilities of Dresden Engineering Assurance Group ML20092D2291995-05-23023 May 1995 Rev 0,mod M12-2&3-94-004 to Nep 04-03, 10CFR50.59 Se ML20092C7371995-05-12012 May 1995 Partially Withheld,Rev 1, Shroud & Shroud Repair Hardware Analysis Volume I,Shroud Repair Hardware ML20092C7801995-05-12012 May 1995 Rev 1, Shroud & Shroud Repair Hardware Analysis Volume:1, Shroud Repair Hardware Backup Calculations ML20092C8281995-05-11011 May 1995 Partially Withheld,Rev 1 to Dresden Units 2 & 3 Top Ring Plate & Star Truss Stress Analysis Backup Calculations ML20092C8451994-12-31031 December 1994 Partially Withheld Rev O, Primary Structure Seismic Models, Dec 1994 ML20086A3001994-10-31031 October 1994 Reactor Bldg Crane & Cask Yoke Assembly Mods ML17187A8041994-02-28028 February 1994 Containment Analysis of DBA-LOCA to Update Design Basis for Lpci/Ccs, for GENE-637-042-1193 ML20125D1281992-12-0101 December 1992 Methodology for Estimating ECP in Dresden Unit 2 RWCU Piping ML20082A6931991-03-31031 March 1991 Structural Evaluation of Com Ed BWR Reactor Pressure Vessel Head Stud Cracking ML20067B4921991-02-0404 February 1991 Nonproprietary Fracture Toughness Evaluation of Shell Side Lpcis Heat Exchanger for Dresden Station - Unit 2 ML17202L2881990-06-29029 June 1990 II Upper Vessel Contract Variation Review. ML17347B4621989-12-31031 December 1989 App a to USI A-46 & Generic Ltr 87-02. ML20059B8551989-08-29029 August 1989 LOCA-ECCS Analysis Single Failure Diesel Generator. Related Info Encl ML20246D6871989-08-14014 August 1989 Rev 1 to Criticality Analysis of Byron & Braidwood Station High Density Fuel Racks ML19327B4011989-07-31031 July 1989 Safety Evaluation for Byron/Braidwood Stations Units 1 & 2 Transition to Westinghouse 17 X 17 Vantage 5 Fuel. ML18008A0311989-07-31031 July 1989 NTH-TR-01 Decrease in Heat Removal by Secondary Sys. ML20247H0711989-06-30030 June 1989 Description & Verification Summary of Computer Program, Gappipe ML20246D6711989-06-30030 June 1989 Criticality Analysis of Byron/Braidwood Fresh Fuel Racks ML20247H0791989-06-22022 June 1989 App to Description & Verification Summary of Computer Program,Gappipe ML20247N0621989-05-31031 May 1989 Production Training Dept,Braidwood,Malfunctions & Initial Conditions ML20247K3011989-05-12012 May 1989 Leak-Before-Break Evaluation for Carbon Steel Piping ML20247L1841989-05-12012 May 1989 Leak-Before-Break Evaluation for Stainless Steel Piping, Byron & Braidwood Nuclear Power Stations Units 1 & 2 ML18094A3551989-04-30030 April 1989 Assessment of Impacts of Salem & Hope Creek Generating Stations on Kemps Ridley (Lepidochelys Kempi) & Loggerhead (Carretta Caretta) Sea Turtles. ML20244B5121989-03-31031 March 1989 Determination of Potential Radiological Consequences from Fuel Handling Accident at Dresden Nuclear Power Station Unit 1 ML20247F1321989-03-23023 March 1989 Post-Tensioning Sys Evaluation,Callaway Unit 1 Containment & Wolf Creek Unit 1 Containment ML20005G4211989-02-28028 February 1989 Reactor Vessel Heatup & Cooldown Limit Curves for Normal Operation. ML17251A4811989-02-28028 February 1989 Ultrasonic Indication Sizing Technique Development. Related Info Encl ML20206C7451988-11-30030 November 1988 ATWS Mitigation Sys Specific Design for Byron/Braidwood Stations, Rev 5 ML20205T7501988-11-0404 November 1988 Detection & Skin Dose Evaluation for Characteristic X-Ray in Activation Product Contamination ML20206K3101988-10-31031 October 1988 Rev 1 to Impact of Reg Guide 1.99,Rev 2 on Limerick Generating Station Unit 1 ML20206K3021988-10-31031 October 1988 Rev 1 to Impact of Reg Guide 1.99,Rev 2 on Peach Bottom Atomic Power Station Unit 3 ML20154N6081988-09-30030 September 1988 Rev 1 to Identification of Unisolable Piping & Determination of Insp Locations ML20154K2091988-09-0909 September 1988 Rev 0 to Response to NRC Bulletin 88-005,Nonconforming Matls Supplied by Piping Supplies,Inc at Folsom,Nj & West Jersey Mfg Co.... Proprietary Procedure 1404.1, Leeb Hardness Testing (Equotip).... Encl.Procedure Withheld ML20245B4181988-08-17017 August 1988 Investigation Rept,Design & Operation of Sampling Sys for Analysis of High Purity Water ML20079B6541988-07-12012 July 1988 Nuclear Safety-Related,Containment Cooling Svc Water Pump Room Cooler Heat Load Study, for Plants ML17347A7971988-06-16016 June 1988 Seismic Hazard Data Prepared for Resolution of USI A-46. ML17347A7981988-06-16016 June 1988 Radiological Data Prepared for Resolution of USI A-46. ML20150F2941988-05-31031 May 1988 Rev 4 to, ATWS Mitigation Sys Specific Design for Byron/ Braidwood Stations ML20196L6281988-05-20020 May 1988 Rev 2 to ATWS Mitigation Sys Actuation Circuitry (Amsac) ML20196L6421988-05-0606 May 1988 ATWS Mitigation Sys Actuation Circuitry Response to Unit Transients ML20151H9581988-04-30030 April 1988 CASMO-3G Validation ML20151T4681988-01-31031 January 1988 Experimental & Finite Element Evaluation of Spent Fuel Rack Damping & Stiffness ML20148G5431988-01-15015 January 1988 Nonproprietary Mods to Critical Flow Model in RELAP5YA ML20155K1391987-12-30030 December 1987 Final Rept MSIV 3-Way Dual Solenoid Valve Failures ML20235F0881987-12-17017 December 1987 Marked-up Draft Seismological Analysis of Bodega Head,Ca ML20236Y0941987-10-21021 October 1987 Epri/Westinghouse Owners Group Analysis of DHR Risk at Point Beach, Final Rept ML20235G3041987-09-29029 September 1987 Partially Withheld, Preliminary Investigation of Enrico Fermi II Nuclear Power Plant 1998-06-30
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20249C8491999-09-30030 September 1999 1999 Third Quarter Rept of Completed Changes,Tests & Experiments Evaluated,Per 10CFR50.59(b)(2), for Dresden Nuclear Power Station. with 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 ML20210R6081999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Dresden Nuclear Power,Units 1,2 & 3.With ML20209E1291999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Dresden Nuclear Power Station,Units 1,2 & 3.With ML20209J3481999-06-30030 June 1999 1999 Second Quarter Rept of Completed Changes,Tests & Experiments, Per 10CFR50.59.With ML20210D3071999-06-30030 June 1999 Corrected Page 8 to MOR for June 1999 for DNPS Unit 3 ML20195G6381999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Dresden Nuclear Power Station,Units 1,2 & 3.With ML20195B2591999-05-19019 May 1999 Rev 66a to CE-1-A,consisting of Proposed Changes to QAP for Dnps,Qcs,Znps,Lcs,Byron & Braidwood Stations ML20206N2821999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Dresden Nuclear Power Station,Units 1,2 & 3.With ML20205N7491999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Dresden Nuclear Power Station,Units 1,2 & 3.With ML20206B1901999-03-31031 March 1999 First Quarter Rept of Completed Changes,Tests & Experiments Per 10CFR50.59 for Dresden Nuclear Power Station. with ML20207M6921999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Dresden Nuclear Power Station,Units 1,2 & 3.With 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 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 ML20205M7061998-12-31031 December 1998 Unicom Corp 1998 Summary Annual Rept. with ML20199D3261998-12-31031 December 1998 10CFR50.59 SER for 1998-04 Quarter, of Changes,Tests & Experiments.With ML20199C8951998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Dnps,Units 1,2 & 3 ML20197G8591998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Dresden Nuclear Power Station.With ML20196J0061998-11-19019 November 1998 Rev 66 to Topical Rept CE-1-A, QA Program ML20196A4191998-11-19019 November 1998 Safety Evaluation Accepting QA TR CE-1-A,Rev 66 Re Changes in Independent & Onsite Review Organization by Creating NSRB ML20195D2861998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Dresden Nuclear Power Station.With ML20154L3681998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Dresden Nuclear Power Station,Units 1,2 & 3.With ML20154N4131998-09-30030 September 1998 1998 Third Quarter 10CFR50.59 Rept, for Dresden Nuclear Power Station of Completed Changes,Tests & Experiments ML20153C5061998-09-21021 September 1998 SER Accepting Qualified Unit 1 Supervisor Initial & Continuing Training Program for Dresden Nuclear Power Station,Unit 1 ML20151Y2711998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Dresden Nuclear Power Station,Units 1,2 & 3.With ML20237E2331998-08-21021 August 1998 Revised Pages of Section 20 of Rev 66 to CE-1-A, QA Topical Rept ML20237A7161998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Dresden Nuclear Power Station,Units 1,2 & 3 ML20236Q5851998-06-30030 June 1998 1998 Second Quarter 10CFR50.59 Rept, for Dresden Nuclear Power Station of Completed Changes,Tests & Experiments ML20236T8331998-06-30030 June 1998 COLR for Dresden Station Unit 3,Cycle 15 ML20236T8391998-06-30030 June 1998 Rev 1 to EMF-96-141, Dresden Unit 3 Cycle 15 Reload Analysis Rept ML20236M6041998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Dresden Nuclear Power Station,Units 1,2 & 3 ML20236F8131998-06-30030 June 1998 Rev 0 to Defueled SAR Dresden Nuclear Power Station Unit 1 Commonwealth Edison Co ML20248M3021998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Dresden Nuclear Power Station,Units 1,2 & 3 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 ML20247F3391998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Dresden Nuclear Power Station,Units 1,2 & 3 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 ML20216C9651998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Dresden Nuclear Power Station,Units 1,2 & 3 ML20216D4411998-03-31031 March 1998 First Quarter Rept of Completed Changes,Tests & Experiments for 10CFR5059 ML20216E2531998-02-28028 February 1998 Monthly Operating Repts for Feb 1998 for Dresden Nuclear Power Station ML20202F7831998-01-31031 January 1998 Monthly Operating Repts for Jan 1998 for Dresden Nuclear Power Station ML20199K1651998-01-23023 January 1998 Rev 65h to Topical Rept CE-1-A, Comm Ed QA Tr ML20216D3611997-12-31031 December 1997 Unicom Corp 1997 Summary Annual Rept ML20198P5321997-12-31031 December 1997 Monthly Operating Repts for Dec 1997 for Dresden Nuclear Power Station ML20198P7021997-12-31031 December 1997 Fourth Quarter Rept of Completed Changes,Tests & Experiments Per 10CFR50.59 ML20203F8781997-11-30030 November 1997 Monthly Operating Repts for Nov 1997 for Dresden Nuclear Power Station ML20199B0701997-10-31031 October 1997 Monthly Operating Repts for Oct 1997 for Dresden Nuclear Power Station ML20217H7201997-09-30030 September 1997 Monthly Operating Repts for Sept 1997 for Dresden Nuclear Power Station,Units 1,2 & 3 ML20210V2401997-09-19019 September 1997 Rev 65g to Topical Rept CE-1-A, Comm Ed QA Manual ML20216J3781997-08-31031 August 1997 Monthly Operating Repts for Aug 1997 for DNPS ML20210H5511997-07-31031 July 1997 Monthly Operating Repts for July 1997 for DNPS IAW RG 1.16 & GL 97-02 1999-09-30
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180-DAY REPORT IN RESPONSE TO IE BULLETIN 80-11 FOR DRESDEN NUCLEAR POWER STATION UNITS 2 AND 3 COMMONWEALTH EDISON COMPANY DOCKET NUMBERS 50-237 AND 50-249 i
PREPARED BY: Bechtel Power Corporation Report Date: January 15, 1982 Revision 2 h D 0 R a
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I 4.7 MASONRY WALL TESTING PROGRAM A sampling and testing program is in progress and intends to accomplish the following:
4.7.1 Verify the type and strength of block used for the walls which do not appear on any design drawings.
4.7.2 Justify the assumed stresses used for the block and mortar of the normal and magnetite solid masonry walls.
4.7.3 Determine the allowable stress which can be transmitted across a mortared collar joint.
4.7.4 Justify the use of inspected allowable stresses.
5.0 RESULTS OF MASONRY WALL EVALUATION Table 3 lists the results of the masonry wall reevaluation. The criteria used to justify the wall's acceptance or mode in which it does not meet the criteria are identified.
5.1
SUMMARY
The following summarizes the results of the reevaluation of 92 safety-related masonry walls:
5.1.1 Total number of walls meeting the acceptance criteria:
Ii 5.1.2 Total number of walls which do not meet the acceptance criteria: 34
6.0 REFERENCES
6.1 Building Code Requirements for Concrete Masonry Structures, ACI 531-79, American Concrete Institute, Detroit, Michigan, 1979 6.2 USNRC IE Bulletin 80-11, dated May 8, 1980 l 6.3 Final Safety Analysis Report (FSAR) for the Dresden Nuclear Power Station Units 2 and 3 6.4 Damping Values for Seismic Design of Nuclear Power Plants, U.S.
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