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Category:REPORTS-TOPICAL (BY MANUFACTURERS-VENDORS ETC)
MONTHYEARML20211B1281999-08-31031 August 1999 Dynamic Rod Worth Measurement Using Casmo/Simulate ML20211F3441999-08-17017 August 1999 Updated non-proprietary Page 2-4 of TR DPC-NE-2009 ML20196L1881999-05-31031 May 1999 Non-proprietary Rev 1 to DPC-NE-3004, Mass & Energy Release & Containment Response Methodology ML20236U1601998-07-31031 July 1998 Non-proprietary DPC-NE-2009, DPC W Fuel Transition Rept ML20202D1921997-12-31031 December 1997 Rev 2 to UFSAR Chapter 15 Transient Analysis Methodology ML20197J3011997-11-30030 November 1997 Non-proprietary TR DPC-NE-3004-A, Mass & Energy Release & Containment Response Methodology ML20248L2631997-02-20020 February 1997 Non-proprietary Version of DPC-NE-2004-A, Duke Power Co McGuire & Catawba Nuclear Stations Core Thermal-Hydraulic Methodology Using VIPRE-01 ML20108D2091996-04-30030 April 1996 Nonproprietary App C, Mcguire/Catawba Plant Specific Data Mark-BW Fuel BWU-Z CHF Correlation to DPC Thermal- Hydraulic Statistical Core Design Methodology ML20107M8931995-10-31031 October 1995 Nonproprietary DPC Fuel Reconstitution Analysis Methodology ML20073J9151994-09-19019 September 1994 Replacement Steam Generator Topical Rept ML20070K0711994-06-30030 June 1994 Rev 1 to FSAR Chapter 15 Sys Transient Analysis Methodology ML20065D8061994-02-28028 February 1994 Analysis of Capsule V Specimens & Dosimeters & Analysis of Capsule Z Dosimeters from Duke Power Co McGuire Unit 1 Reactor Vessel Radiation Surveillance Program ML20064M4521994-02-28028 February 1994 WCAP-13948, Evaluation of Pressurized Thermal Shock for McGuire Unit 1 ML20116N0531992-11-11011 November 1992 Rev 1 to Mark-BW Reload LOCA Analysis for McGuire & Catawba ML20114A9771991-12-31031 December 1991 Nonproprietary McGuire & Catawba Nuclear Stations Core Thermal-Hydraulic Methodology Using VIPRE-01 ML20114A9911991-11-30030 November 1991 Nonproprietary Multidimensional Reactor Transients & Safety Analysis Physics Parameters Methodology ML20114A9711991-11-30030 November 1991 FSAR Chapter 15 Sys Transient Analysis Methodology ML20065M7381990-11-30030 November 1990 Mark-BW Reload LOCA Analysis for Catawba & McGuire Units ML20073H6281990-01-31031 January 1990 Nonproprietary Topical Rept DPC-NE-2001-A, Fuel Mechanical Reload Analysis Methodology for Mark-BW Fuel, Rev 1 ML20011E2541989-12-31031 December 1989 ARROTTA-HERMITE Code Comparison, Final Rept ML19351A4191989-09-30030 September 1989 Mark-BW Reload LOCA Analysis for Catawba & McGuire Units. ML20042F2321989-08-31031 August 1989 Nonproprietary DCHF-1 Correlation for Predicting Critical Heat Flux in Mixing Vane Grid Fuel Assemblies. ML19332C1531989-08-31031 August 1989 Analysis of Capsule X from Duke Power Co McGuire Unit 1 Reactor Vessel Radiation Surveillance Program. ML20235M9111989-02-20020 February 1989 Nonproprietary Catawba Unit 1 Evaluation for Tube Vibration Induced Fatigue ML20207L7781988-10-0606 October 1988 Nonproprietary WCAP 11936, McGuire Unit 2 Evaluation for Tube Vibration Induced Fatigue ML20207L9261988-09-30030 September 1988 Nonproprietary Addendum 2 to COBRA-NC,Analysis for Main Steamline Break in Catawba Unit 1 Ice Condenser Containment (Response to NRC Questions) ML20212B8841986-07-31031 July 1986 Nonproprietary Tubesheet Region Plugging Criterion for Duke Power Co McGuire Nuclear Station Units 1 & 2 Steam Generators ML20137L0591985-12-31031 December 1985 Nonproprietary Supplementary Info to WCAP-10585, Technical Bases for Eliminating Large Primary Loop Pipe Rupture on Structural Region Bases for McGuire Units 1 & 2 ML20127K1381985-06-30030 June 1985 Nuclear Physics Methodology for Reload Design ML20100H4581985-02-28028 February 1985 Analysis of Capsule U from Duke Power Co McGuire Unit 1 Reactor Vessel Radiation Surveillance Program ML20093N0811984-10-19019 October 1984 App a to Topical Rept DPC-NF-2010, Code Summary ML20135E2691984-06-30030 June 1984 Technical Bases for Eliminating Large Primary Loop Pipe Rupture as Structural Design Bases for McGuire Units 1 & 2 ML20092N5761984-06-30030 June 1984 Nonproprietary Technical Basis for Eliminating RHR Line Rupture as Structural Design Basis for Catawba Units 1 & 2 & McGuire Units 1 & 2 ML20078C2411983-07-31031 July 1983 Nonproprietary Preliminary Version of McGuire Post-Mod Steam Generator Tube Vibration Monitoring Program ML19331C6921980-07-31031 July 1980 Reliability Analysis of Auxiliary Feedwater Sys for McGuire Nuclear Station Unit 1. 1999-08-31
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217G7951999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for McGuire Nuclear Station,Units 1 & 2 ML20217F3661999-09-22022 September 1999 Rev 18 to McGuire Unit 1 Cycle 14 Colr ML20212D1911999-09-20020 September 1999 SER Accepting Exemption from Certain Requirements of 10CFR50,App A,General Design Criterion 57 Closed System Isolation Valves for McGuire Nuclear Station,Units 1 & 2 ML20216E8851999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for McGuire Nuclear Station,Units 1 & 2 ML20211B1281999-08-31031 August 1999 Dynamic Rod Worth Measurement Using Casmo/Simulate ML20217G8101999-08-31031 August 1999 Revised Monthly Operating Repts for Aug 1999 for McGuire Nuclear Station,Unit 1 & 2 ML20211G5261999-08-24024 August 1999 SER Accepting Approval of Second 10-year Interval Inservice Insp Program Plan Request for Relief 98-004 for Plant,Unit 1 ML20211F3441999-08-17017 August 1999 Updated non-proprietary Page 2-4 of TR DPC-NE-2009 ML20210S2371999-07-31031 July 1999 Monthly Operating Repts for July 1999 for McGuire Nuclear Station,Units 1 & 2 ML20216E8951999-07-31031 July 1999 Revised Monthly Operating Repts for July 1999 for McGuire Nuclear Station,Units 1 & 2 ML20209E4361999-07-0909 July 1999 SER Agreeing with Licensee General Interpretation of TS LCO 3.0.6,but Finds No Technical Basis or Guidance That Snubbers Could Be Treated as Exception to General Interpretation ML20196K6631999-07-0707 July 1999 Safety Evaluation Supporting Licensee 990520 Position Re Inoperable Snubbers ML20209H1631999-06-30030 June 1999 Monthly Operating Repts for June 1999 for McGuire Nuclear Station,Units 1 & 2 ML20210S2491999-06-30030 June 1999 Revised Monthly Operating Rept for June 1999 for McGuire Nuclear Station,Units 1 & 2 ML20209H1731999-05-31031 May 1999 Revised Monthly Operating Rept for May 1999 for McGuire Nuclear Station,Units 1 & 2 ML20206T4771999-05-31031 May 1999 Rev 3 to UFSAR Chapter 15 Sys Transient Analysis Methodology ML20196L1881999-05-31031 May 1999 Non-proprietary Rev 1 to DPC-NE-3004, Mass & Energy Release & Containment Response Methodology ML20195K3691999-05-31031 May 1999 Monthly Operating Repts for May 1999 for McGuire Nuclear Station,Units 1 & 2 ML20206N3511999-05-11011 May 1999 Safety Evaluation Accepting Licensee Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety- Related Movs ML20195K3761999-04-30030 April 1999 Revised MORs for Apr 1999 for McGuire Nuclear Station,Units 1 & 2 ML20206R0891999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for McGuire Nuclear Station,Units 1 & 2 ML20205L2341999-04-0505 April 1999 SFP Criticality Analysis ML20206R0931999-03-31031 March 1999 Revised Monthly Repts for Mar 1999 for McGuire Nuclear Station,Units 1 & 2 ML20205P8991999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for McGuire Nuclear Station,Units 1 & 2 ML20205C4171999-03-25025 March 1999 Special Rept 99-02:on 801027,Commission Approved for publication,10CFR50.48 & 10CFR50 App R Delineating Certain Fire Protection Provisions for Nuclear Power Plants Licensed to Operate Prior to 790101.Team Draft Findings Reviewed ML20207K2051999-03-0505 March 1999 Special Rept 99-01:on 990128,DG Tripped After 2 H of Operation During Loaded Operation for Monthly Test.Caused by Several Components That Were Degraded or Had Intermittent Problems.Parts Were Replaced & Initial Run Was Performed ML20204C8911999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for McGuire Nuclear Station,Units 1 & 2 ML20205P9021999-02-28028 February 1999 Revised Monthly Operating Repts for Feb 1999 for McGuire Nuclear Station,Units 1 & 2 ML20204C8961999-01-31031 January 1999 Revised Monthly Operating Repts for Jan 1999 for McGuire Nuclear Station,Units 1 & 2 ML20199E0301998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for McGuire Nuclear Station,Units 1 & 2 ML20216F9931998-12-31031 December 1998 Piedmont Municipal Power Agency 1998 Annual Rept ML20198A4481998-12-11011 December 1998 Safety Evaluation Concluding That for Relief Request 97-004, Parts 1 & 2,ASME Code Exam Requirements Are Impractical. Request for Relief & Alternative Imposed,Granted ML20198D7561998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for McGuire Nuclear Station,Units 1 & 2 ML20199E0491998-11-30030 November 1998 Revised Monthly Operating Rept for Nov 1998 for McGuire Nuclear Station,Units 1 & 2 Re Personnel Exposure ML20199E9651998-11-24024 November 1998 Rev 1 to ATI-98-012-T005, DPC Evaluation of McGuire Unit 1 Surveillance Weld Data Credibility ML20196D4171998-11-24024 November 1998 Special Rept 98-02:on 981112,failure to Implement Fire Watches in Rooms Containing Inoperable Fire Barrier Penetrations,Was Determined.Repair of Affected Fire Barriers in Progress ML20196G0581998-11-0606 November 1998 Rev 17 to COLR Cycle 13 for McGuire Unit 1 ML20196G0761998-11-0606 November 1998 Rev 15 to COLR Cycle 12 for McGuire Unit 2 ML20198D7771998-10-31031 October 1998 Revised Monthly Operating Rept for Oct 1998 for McGuire Nuclear Station,Units 1 & 2 ML20195E5961998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for McGuire Nuclear Station,Units 1 & 2 ML20154L6251998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for McGuire Nuclear Station,Units 1 & 2 ML20195E6021998-09-30030 September 1998 Revised Monthly Operating Rept for Sept 1998 for McGuire Nuclear Station,Units 1 & 2 ML20154B4131998-09-22022 September 1998 Rev 0 to ISI Rept for McGuire Nuclear Unit 1 Twelfth Refueling Outage ML20151W3521998-09-0808 September 1998 Special Rept 98-01:on 980819,maint Could Not Be Performed on FPS Due to Isolation Boundary Leakage.Caused by Inadequate Info Provided in Fire Impairment Plan.Isolated Portion of FPS Was Returned to Svc ML20154L6321998-08-31031 August 1998 Rev 1 to MOR for Aug 1998 for McGuire Nuclear Station,Unit 1 ML20153B3741998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for McGuire Nuclear Station,Units 1 & 2 ML20236U1601998-07-31031 July 1998 Non-proprietary DPC-NE-2009, DPC W Fuel Transition Rept ML20237B2381998-07-31031 July 1998 Monthly Operating Repts for July 1998 for McGuire Nuclear Station,Units 1 & 2 ML20153B3931998-07-31031 July 1998 Revised Monthly Operating Repts for Jul 1998 for McGuire Nuclear Station,Units 1 & 2 ML20236P0451998-07-0808 July 1998 Part 21 Rept Re non-conformance & Potential Defect in Component of Nordberg Model FS1316HSC Standby Dg.Caused by Outer Spring Valves Mfg from Matl That Did Not Meet Specifications.Will Furnish Written Rept within 60 Days 1999-09-30
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f MCGUIRE POST MODIFICATION STEAM GENERATOR TUBE VIBRATION MONITORING PROGRAM PRELIMINARY REPORT JULY 1983 f
G WESTINGHOUSE ELECTRIC CORPORATION Nuclear Energy Systems P. O. Box 355 Pittsburgh, Pennsylvania 15230 8309270495 830914 PDR ADOCK 05000369 P PDR 0824s:10-2
i l
i l
1.0 INTRODUCTION
Westinghouse has designed and tested a modification to reduce flow l induced vibration of the tubes in the preheater section of the Model D2 steam generators. This andt fication was installed in the McGuire Unit 1
~
kclear Pwer Plant. Selec,ted tubes in one of the steam generators at
~
McGuire Unit 1 were instrumented with accelerometers. During May and l June of 1983. field vibration data were recorded on tbse selected tubes l for power levels from 0 percent to 100 percent power. This report provides the results of the preliminary vibration analysis for the 100 l
percent power level. The purpose of this analysis is to provide initial
- infcrmation regarding preheater tube vibration with the preheater inlet modi fica tion. The evaluation of the preheater modification performance l will be based on eddy current examination. -
. It should be noted that the data for Tubes R49C40 and R49C71 in this l report are correct. The data for these tubes are interchanged in the
" Westinghouse Preheat Steam Generator 02/03 Design Modification Evaluation Package" dated Decernber 1982. This error is due to a mislabeling of signal l wires.
i l
0824s:10-3
2.0
SUMMARY
AND CONCLUSIONS The data at 100 percent power were analyzed to obtain the three para-meters that are used to characterize tube motion: the peak-to-peak acceleration, G, the RMS tube displacement, a, and['
pra from the instrumented tubes indicate that the manifold is performing as expected, reducing the potential for tube wear. The observed post-modification RMS displacement and peak-to-peak acceleration values are consistent with the results obtained from the 50 percent power pre-modification and the full scale test model data analyses. The frequency contents of the tube vibration data obtained at 100 percent power are similar to those observed from 50 percent power pre-modification data and full scale test model data.
0824s:10-4
3.0 TEST RESULTS Prior to the installation of the manifold modification, four biaxial ,
I accelerometers were installed in Tube R49C40 and in Tube R49C71. The four accelerometer locations in Tube R49C40 are designated, for example, as 40TX, 40TY, 40BX, and 40BY (T - top, B - bottom, X, Y - coordinate ,
directions). The other accelerometers are similarly designated.
i Pre-modification flow vibration data measurements were made in March 1982. The March data set included various power levels from 0 percent to 75 percent in 5 percent power increments. Following the installation of the modification, accelerometers were installed in two additional tubes (R49C31 and R49C60). Figures 1 and 2 show the accelerometer locations and their orientation. Figures 3 and 4 show tube vibration responses at 100 percent power for Tubes R49C40 and R49C71 along with i
the pre-modification responses at 50 percent power. Figures 5 through 19 show post-modification RMS acceleration and displacement spectra at 75, 90, and 100 percent power. The narrow band peaks seen on some of the figures at the hamonics of 60 Hz are the result of. line noise, and do not represent tube motion.
0824s:10-5
4.0 DISCUSSION OF RESULTS Vibration measurements were taken from 0 percent to 100 percent power.
The results of the data reduction at 100 percent power are compared in this report to the results of the 50 percent power level prior to,the modi fication. Values of the peak-to-peak acceleration, RMS displace-
, s., c .e ment,and[ are provided in Table 1 for each of the accelerometer locations. - .
o.,c.,e_.
~
0824s:10-6
Figure 1 i
McGUIRE 1 ACCELEROMETER TUBE LOCATIONS VIEWED FROM PRIMARY SIDE OF TUBESHEET. '
STEAM GENERATOR A g CHANNEL HEAD MANWAY
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e 888 (
Column 71 :d M PP'r *ll 3r 8 .
P' W
g
?O m Column 60
__ggi L a ( )
8 _, -
L-Reverse Flow Feedwater Inlet Limiter Venturi j ]
I Column 40 -
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41 j p
Double h11ed mnifold Distributor
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j l ll \
l Column 31 "$l Mli'?'i R.C. NOIILE I
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.- - - - _ - - . . - _ _ _ _ _ _ _ _ . __ _a
a,b,c,e Figures 2 thru 19 and Table 1 contain tube vibration data which is considered Westinghouse proprietary 0018G/JRS/8-15-83