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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
ML20064M4521994-02-28028 February 1994
WCAP-13948, Evaluation of Pressurized Thermal Shock for McGuire Unit 1
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
ML20059F1571993-10-31031 October 1993
Nonproprietary Analysis to Determine Relative Tube/Tube Support Plate Displacements Under Steam Line Break Loads for Catawba Unit 1 Sgs
ML20116N0531992-11-11011 November 1992
Rev 1 to Mark-BW Reload LOCA Analysis for McGuire & Catawba
ML20106A8271992-09-30030 September 1992
Nonproprietary WCAP-13495, Technical Support for SG Interim Tube Plugging Criteria for Indications at Tube Support Plates,Catawba Unit 1
ML20106A2931992-09-30030 September 1992
Nonproprietary WCAP-13497, Catawba Unit 1 Steam Generator Tube Interim Plugging Criterion Presentation Matls
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
ML20217A6621990-07-31031 July 1990
DPC Catawba,Unit 1,Reactor Vessel Radiation Surveillance Program
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.
ML20247H0431989-09-13013 September 1989
Revised Pages to Reactor Vessel Surveillance Capsule Z Analysis Rept
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)
ML20154J9831988-04-30030 April 1988
RCS Flow Anomaly Investigation Rept
ML20235T9991987-09-30030 September 1987
Rev 2 to RTD Bypass Elimination Licensing Rept for Catawba Units 1 & 2
ML20235V4271987-08-31031 August 1987
Nonproprietary Tubesheet Region Plugging Criterion for Duke Power Co,Catawba 1,Nuclear Station Steam Generators
ML20235Z5841987-05-31031 May 1987
Nonproprietary Rev 1 to WCAP-11309, Resistance Temp Detector Bypass Elimination Rept for Catawba Units 1 & 2. RCS Nozzle & Thermowell Locations Encl
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
ML20217A6701985-11-30030 November 1985
DPC Catawba,Unit 2,Reactor Vessel Radiation Surveillance Program
ML20137Z5391985-11-30030 November 1985
Nonproprietary COBRA-NC,Analysis for Main Steamline Break in Catawba Unit 1 Ice Condenser Containment
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
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
ML20094D1701984-06-30030 June 1984
Nonproprietary Westinghouse Setpoint Methodology for Protection Sys,Catawba Station. Two Oversize Tables Encl. Aperture Cards Available in PDR
ML20135E2691984-06-30030 June 1984
Technical Bases for Eliminating Large Primary Loop Pipe Rupture as Structural Design Bases for McGuire Units 1 & 2
ML20092H6911984-04-30030 April 1984
Technical Basis for Eliminating Class 1 Accumulator Line Rupture as Structural Design Basis for Catawba Units 1 & 2
ML20084N9291984-04-30030 April 1984
Nonproprietary Technical Bases for Eliminating Large Primary Loop Pipe Rupture as Structural Design Basis for Catawba Units 1 & 2
ML20087G3351984-02-10010 February 1984
Nonproprietary Technical Basis for Eliminating Pressurizer Surge Line Ruptures as Structural Design Basis for Catawba Units 1 & 2
ML20083F2761983-11-30030 November 1983
Nonproprietary Technical Bases for Eliminating Large Primary Loop Pipe Ruptures as Structural Design for Catawba Units 1 & 2
ML20078C2411983-07-31031 July 1983
Nonproprietary Preliminary Version of McGuire Post-Mod Steam Generator Tube Vibration Monitoring Program
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
ML20217H0201999-09-30030 September 1999
Monthly Operating Repts for Sept 1999 for Catawba 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
ML20216E5401999-09-0707 September 1999
Special Rept:On 990826,discovered That Meteorological Sys Upper Wind Speed Cup Set Broken,Causing Upper Wind Channel to Be Inoperable.Cup Set Replaced & Channel Restored to Operable Status on 990826
ML20211B1281999-08-31031 August 1999
Dynamic Rod Worth Measurement Using Casmo/Simulate
ML20212B4711999-08-31031 August 1999
Monthly Operating Repts for Aug 1999 for Catawba Nuclear Station,Units 1 & 2
ML20216E8851999-08-31031 August 1999
Monthly Operating Repts for Aug 1999 for McGuire Nuclear Station,Units 1 & 2
ML20217G8101999-08-31031 August 1999
Revised Monthly Operating Repts for Aug 1999 for McGuire Nuclear Station,Unit 1 & 2
ML20217H0321999-08-31031 August 1999
Revised Monthly Operating Rept for Aug 1999 for Catawba Nuclear Station,Units 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
ML20211A9791999-08-20020 August 1999
Safety Evaluation Granting Licensee Request for Approval of Proposed Relief from Volumetric Exam Requirements of ASME B&PV Code,Section Xi,For Plant,Unit 2
ML20211C1291999-08-17017 August 1999
ISI Rept Unit 1 Catawba 1999 RFO 11
ML20211F3441999-08-17017 August 1999
Updated non-proprietary Page 2-4 of TR DPC-NE-2009
ML20210R1051999-08-0606 August 1999
Special Rept:On 990628,cathodic Protection Sys Was Declared Inoperable After Sys Did Not Pass Acceptance Criteria of Bimonthly Surveillance.Work Request 98085802 Was Initiated & Connections on Well Anode Were Cleaned or Replaced
ML20210S2891999-07-31031 July 1999
Monthly Operating Repts for July 1999 for Catawba Nuclear Station,Units 1 & 2
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
ML20212B4871999-07-31031 July 1999
Revised Monthly Operating Rept for July 1999 for Catawba 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
ML20210S2951999-06-30030 June 1999
Revised Monthly Operating Rept for June 1999 for Catawba Nuclear Station,Units 1 & 2
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
ML20209H4501999-06-30030 June 1999
Monthly Operating Repts for June 1999 for Catawba Nuclear Station,Units 1 & 2
ML20196A0001999-05-31031 May 1999
Monthly Operating Repts for May 1999 for Catawba Nuclear Station,Units 1 & 2
ML20209H1731999-05-31031 May 1999
Revised Monthly Operating Rept for May 1999 for McGuire Nuclear Station,Units 1 & 2
ML20195K3691999-05-31031 May 1999
Monthly Operating Repts for May 1999 for McGuire Nuclear Station,Units 1 & 2
ML20209H4561999-05-31031 May 1999
Revised Monthly Operating Rept for May 1999 for Catawba 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
ML20206P5201999-05-14014 May 1999
Safety Evaluation Accepting GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves
ML20206N3511999-05-11011 May 1999
Safety Evaluation Accepting Licensee Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety- Related Movs
ML20206N8391999-05-0404 May 1999
Rev 16 to CNEI-0400-24, Catawba Unit 1 Cycle 12 Colr
ML20206R1811999-04-30030 April 1999
Monthly Operating Repts for Apr 1999 for Catawba Nuclear Station,Units 1 & 2
ML20196A0041999-04-30030 April 1999
Revised Monthly Operating Repts for Apr 1999 for Catawba Nuclear Station,Units 1 & 2
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
ML20206N8261999-04-22022 April 1999
Rev 15 to CNEI-0400-24, Catawba Unit 1 Cycle 12 Colr. Page 145 of 270 of Incoming Submittal Not Included
ML20205S5551999-04-21021 April 1999
Safety Evaluation Accepting Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions
ML18016A9011999-04-12012 April 1999
Part 21 Rept Re Defect in Component of DSRV-16-4,Enterprise DG Sys.Caused by Potential Problem with Connecting Rod Assemblies Built Since 1986,that Have Been Converted to Use Prestressed Fasteners.Affected Rods Should Be Inspected
ML20205N3651999-04-12012 April 1999
Safety Evaluation Accepting IPE of External Events Submittal
ML20205L2341999-04-0505 April 1999
SFP Criticality Analysis
ML20205P9521999-03-31031 March 1999
Monthly Operating Repts for Mar 1999 for Catawba Nuclear Station,Units 1 & 2
ML20206R1931999-03-31031 March 1999
Revised Monthly Operating Repts for Apr 1999 for Catawba Nuclear Station,Units 1 & 2
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
ML20205P9561999-02-28028 February 1999
Revised Monthly Operating Repts for Feb 1999 for Catawba Nuclear Station,Units 1 & 2
1999-09-07
[Table view] |
Text
f,--
l PROPRIETARY Duke Power Co.
1 .
Table 2-1 Comparison of Robust Fuel Assembly and Mark-BW Fuel Assembly Design Parameters 17x17 Robust Fuel 17x17 Mark-BW Fuel Assembly Design Assembly Desien l Fuel Assembly Length,in.
Assembly Envelope,in.
Fuel Rod Pitch, in.
Fuel Rod Material Fuel Rod Clad OD, in.
Fuel Rod Clad Thickness, in.
Fuel / Clad Gap, mils Fuel Pellet Diameter,in.
Fuel Stack lleight, in.
Guide Thimble Material Outer Diameter of Guide Thimbles, in.
(upper part)
Inner Diameter of Guide Thimbles, in.
(upper part)
Outer Diameter of Guide Thimbles, in.
(lower part)
Inner Diameter of Guide Thimbles, in.
(lower part)
Outer Diameter ofInstrument Guide j Thimbles, in. ;
I Inner Diameter ofInstrument Guide !
Thimbles, in.
i I
End Grid Material
)
Intermediate Grid Material l Intermediate Flow Mixing Grid Material l
2-4 9908300307 990817 PDR ADOCK 05000369 P PDR
-~
V, .
1 Table 5-1 RFA Design Data (TYPICAL) l GENERAL FUEL SPECIFICATIONS Fuel rod diameter, inches (Nominal) 0.374 Guide tube diameter, inches (Nominal) 0.482 Fuel rod pitch, inches (Nominal) 0.496 Fuel Assembly pitch, inches (Nominal) 8.466 Fuel Assembly length, inches (Nominal) 160.0 .,
GENERAL FUEL CHARACTERISTIL S l
Comoonent Material Number Location /Tyne Grids Inconel 1 Lower Protective inconel 2 Upper and Lower Non-Mixing Vane ZlRLO 6 Intermediate Mixing Vane ZlRLO 3 Intermediate Flow Mixing (Non-structural)
Nozzles 304SS 1 Debris Filtering Bottom l
l 304SS 1 Removable Top u
(
l 5-6 l .
L
