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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 ML20092C7801995-05-12012 May 1995 Rev 1, Shroud & Shroud Repair Hardware Analysis Volume:1, Shroud Repair Hardware Backup Calculations ML20092C7371995-05-12012 May 1995 Partially Withheld,Rev 1, Shroud & Shroud Repair Hardware Analysis Volume I,Shroud Repair Hardware 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. ML20059B8551989-08-29029 August 1989 LOCA-ECCS Analysis Single Failure Diesel Generator. Related Info Encl ML20244B5121989-03-31031 March 1989 Determination of Potential Radiological Consequences from Fuel Handling Accident at Dresden Nuclear Power Station Unit 1 ML20079B6541988-07-12012 July 1988 Nuclear Safety-Related,Containment Cooling Svc Water Pump Room Cooler Heat Load Study, for Plants ML20236G3121987-06-30030 June 1987 Monthly Plant Status Rept, June 1987 ML20214S3081987-05-28028 May 1987 Weekly Status Rept,Assessment of Embedment Plates Status as of 870528 ML20215K2441987-04-30030 April 1987 Assessment of Embedment Plates Status as of 870430, Weekly Status Rept ML20204J7431987-03-12012 March 1987 Assessment of Embedment Plates Status as of 870308, Weekly Status Rept ML20212F8361986-05-31031 May 1986 Evaluation for Effects of Dresden Unit 3 Polyurethane Fire ML20210Q5971986-04-28028 April 1986 Rev 0 to Design Assessment of Dresden Units 2 & 3 Control Room Panel Mounting ML20138S0031985-10-29029 October 1985 Rev 5 to Policy Statement Delineating Requirements & Procedures Re Emergency Plan & Procedures ML20117D3411985-05-31031 May 1985 Detailed Control Room Design Review Final Summary Rept ML20099F3501984-10-31031 October 1984 2 Hydrogen Water Chemistry Program:Assessment of Plant Operation During Initial Fuel Cycle Through Jul 1984 ML18041A1251984-09-14014 September 1984 Rev 4 to, 180-Day Rept in Response to IE Bulletin 80-11 for Dresden Nuclear Power Station Units 2 & 3. ML20211B0741984-05-24024 May 1984 Leak-Before-Break Justification Rwcu,Dresden Station Units 2 & 3,Quad Cities Station Units 1 & 2 ML20080A9211983-12-27027 December 1983 Rev 4 to Control Rod Sequence Package ML20072N8981983-06-27027 June 1983 Plant Unique Analysis Rept, Vol 5,Safety Relief Valve Discharge Piping Analysis ML20077C3921983-06-18018 June 1983 Rev 00 to Dresden 2 Main Steam Monitoring Procedure Test- Analysis Correlation ML20072N8541983-05-31031 May 1983 Plant Unique Analysis Rept,Vol 3,Vent Sys Analysis ML20072N9251983-05-31031 May 1983 Plant Unique Analysis Rept,Vol 6,Unit 1 Torus Attached Piping & Suppression Chamber Penetration Analysis ML20072N9531983-05-31031 May 1983 Plant Unique Analysis Rept,Vol 7,Unit 2 Torus Attached Piping & Suppression Chamber Penetration Analysis ML20072N8271983-05-31031 May 1983 Plant-Unique Analysis Rept,Vol 1,General Criteria & Methodology ML20072N8771983-05-31031 May 1983 Plant Unique Analysis Rept,Vol 4,Internal Structures Analysis ML20072N8431983-05-31031 May 1983 Plant Unique Analysis Rept,Vol 2,Suppression Chamber Analysis ML20072K8171983-05-31031 May 1983 Rev 0 to Dresden Nuclear Power Station,Units 2 & 3,Plant- Unique Analysis Rept,Vol 3,Vent Sys Analysis ML20072A4761983-05-0909 May 1983 Rev 3 to 180-Day Rept in Response to IE Bulletin 80-11 for Dresden 2 & 3 & Quad Cities 1 & 2 ML20076L1861982-09-30030 September 1982 Rev 1 to Improved Dynamic Vacuum Breaker Valve Response for Quad Cities 1 & 2 ML20063H0481982-07-27027 July 1982 SEP Topic III-5.A,High Energy Pipe Breaks Inside Containment, Revised Draft Interim Progress Rept ML20054H2801982-05-19019 May 1982 Impact Effects on Spent Fuel Pool Slab ML20040D7761982-01-15015 January 1982 180-Day Rept in Response to IE Bulletin 80-11 for Dresden Nuclear Power Station,Units 2 & 3. ML20040D7801982-01-15015 January 1982 180-Day Rept in Response to IE Bulletin 80-11 for Quad Cities Nuclear Power Station,Units 1 & 2. ML20039C4041981-12-31031 December 1981 Control Room Habitability Study for Dresden 2 & 3, Final Rept ML17194A3721981-12-31031 December 1981 Control Room Habitability Study for Quad Cities 1 & 2, Final Rept ML20038B9391981-11-23023 November 1981 180-day Rept in Response to IE Bulletin 80-11. ML20038B9411981-11-23023 November 1981 180-day Rept in Response to IE Bulletin 80-11. ML17193A7081980-11-30030 November 1980 SEP Review of NRC Safety Topic VI-7.A.3 Associated W/ Electrical,Instrumentation & Control Portions of ECCS Actuation Sys. ML19339D0241980-11-30030 November 1980 SEP Review of NRC Safety Topic VI-10.A Associated W/ Electrical,Instrumentation & Control Portions of Testing of Reactor Trip Sys & Engineered Safety Features,Including Response Time. 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 ML20206B1901999-03-31031 March 1999 First Quarter Rept of Completed Changes,Tests & Experiments Per 10CFR50.59 for Dresden Nuclear Power Station. with ML20205N7491999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Dresden Nuclear Power Station,Units 1,2 & 3.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 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 ML20205M7061998-12-31031 December 1998 Unicom Corp 1998 Summary Annual Rept. with ML20197G8591998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Dresden Nuclear Power Station.With 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 ML20196J0061998-11-19019 November 1998 Rev 66 to Topical Rept CE-1-A, QA Program 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 ML20236F8131998-06-30030 June 1998 Rev 0 to Defueled SAR Dresden Nuclear Power Station Unit 1 Commonwealth Edison Co 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 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 ML20216D4411998-03-31031 March 1998 First Quarter Rept of Completed Changes,Tests & Experiments for 10CFR5059 ML20216C9651998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Dresden Nuclear Power Station,Units 1,2 & 3 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 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 ML20216D3611997-12-31031 December 1997 Unicom Corp 1997 Summary Annual Rept 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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ATTACHMENT B Methodology for Estimatirg ECP in Dresden-2 RWCU Piping December 1,1992 (Methodology generated by General Electric) 9212150016 921204 fDR ADOCK 05000237PDR ztrain2/268/1
1 1
1 i
METHODOLOGY FOR ESTIMATING ECP IN DRESDEN - 2 RWCU PIPING The following is the methodology to be used to estimate the ECP at points ofinterest in the RWCU piping at Dresden 2. It should be noted that the RWCU flow comes only from the recirculation water; the bottom head drain is not used.
- 1. Obtain the ECP values measured in the recirculation flange at various feedwater hydrogen injection rates.
- 2. Determine the location of the ECP flange relative to the recirculation piping inlet.
- 3. Determine the location of the RWCU piping inlet relative to the recirculation piping inlet.
- 4. Determine the location of the point of interest for ECP estimation in the RWCU piping relative to the RWCU piping inlet.
- 5. Utilize the information on the locations (Steps 2-4), line lengths, recirculation and RWCU pipe sizes, flow rates and temperatures to calculate the hydrogen peroxide concentrations at the point ofinterest on the RWCU piping relative to the concentrations at the electrode locations at several feedwater hydrogen concentrations which will be determined.
5a. The iW<R water radiolysis model indicates that the predominant oxidizing species is hydrogen peroxide at feedwater hydrogen concentrations where the IGSCC protection point is approached in the recirculation system.
5b. I.aboratory data obtained previously [1] and being obtained currently [2] on the variation of the ECP with increasing hydrogen peroxide concentrations indicates a substantially more positive ECP than obtained at corresponding oxygen concentrations, especially at lower concentrations.
- 6. Calculate the extent of hydrogen peroxide decomposition at the point ofinterest on the RWCU piping relative to that at the recirculation pipe location utilizing a formula which takes into account the effects of flow rate, surface-to-volume ratio, temperature and mass transfer. The formula includes Sherwood, Reynolds and Schmidt numbers.
1
6a. This information is described in a journal article [3) Relevant calculations are summarized as follows:
l C=Co exp(-k.t) I k = kmk,,/km+ k,,
I kmis calculated from laboratory data shown in Figure A 1 of [3], attached.
k ,is calculated from the following equations:
k,, = KS/V Sh = Kd/D Re = dU/v Sc = v/D u
K = 0.023Re semD/d where:
C = H 220 concentration at time t C, = Initial H 20 2concentration at time t = 0 t = reaction time k = observed hydrogen peroxide decomposition rate constant km= rate constant from chemical activation k , = rate constant from diffusion Sh = Sherwood number Re = Reynolds number Sc = Schmidt number d = pipinginner diameter D = diffusivity of H2 02 U = water flow velocity v = kinematic viscosity (S/V) = surface to volume ratio 2
l 6b. The basic values for the decomposition rate constants were obtained in laboratory studies [1], [2]. Data from [2] is shown graphically in Figure 1, attached.
- 7. For the previously determined feedwater hydrogen concentrations, compare the hydrogen peroxide concentrations at the point ofinterest on the RWCU piping relative to the electrode location. Using the information in 6b estimate the ECP at the point ofinterest on the RWCU piping compared with the electrode location.
References
- 1. C. C. Lin, et al, " Electrochemical Potential Measurements Under Simulated BWR Water Chemistry Conditions," Corrosion, Vol. 48, No.1, January 1992
- 2. Y. Kim, et al, Effect of Water Flow Velocity on Electrochemical Corrosion Potential of Stainless Steel in 288+C Water," National Association of Corrosion Engineers, to be published in 1993.
- 3. C. C. Lin, et. al., " Decomposition of Hydrogen Peroxide in Aqueous Solutions at Elevated Temperatures", Int. Journal of Chem. Kinetics, Vol. 23,971-978 (1991).
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WORKING ELECTRODE:
S 304 SS IN TUBING O 304 SS IN AUTOCLAVE
-700 0.1 1 10 .100 1000 TOTAL OxtDANT (ppb)
R6vRE 1 Effects of H 20 2on the ECP of 304 SS in High Purity Water at 270 C.
Average of Several Measuresnents Using Ag/AgC1, Cu/Cu2O and Pt Reference Electrodes.
MG1234