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Non-proprietary Rev 1 to DPC-NE-3004, Mass & Energy Release & Containment Response MethodologyML20196L188 |
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Mcguire, Catawba, McGuire ![Duke Energy icon.png](/w/images/7/75/Duke_Energy_icon.png) |
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Issue date: |
05/31/1999 |
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From: |
DUKE POWER CO. |
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To: |
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Shared Package |
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ML20137R188 |
List: |
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References |
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DPC-NE-3004, DPC-NE-3004-R01, DPC-NE-3004-R1, NUDOCS 9905270161 |
Download: ML20196L188 (7) |
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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 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 ML20106A2931992-09-30030 September 1992 Nonproprietary WCAP-13497, Catawba Unit 1 Steam Generator Tube Interim Plugging Criterion Presentation Matls 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 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 ML20094D1701984-06-30030 June 1984 Nonproprietary Westinghouse Setpoint Methodology for Protection Sys,Catawba Station. Two Oversize Tables Encl. Aperture Cards Available in PDR 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 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 ML20212B4711999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Catawba 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 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 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 ML20212B4871999-07-31031 July 1999 Revised Monthly Operating Rept for July 1999 for Catawba Nuclear Station,Units 1 & 2 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 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 ML20209H4501999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Catawba Nuclear Station,Units 1 & 2 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 ML20196A0001999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Catawba 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 ML20195K3691999-05-31031 May 1999 Monthly Operating Repts for May 1999 for McGuire Nuclear Station,Units 1 & 2 ML20196L1881999-05-31031 May 1999 Non-proprietary Rev 1 to DPC-NE-3004, Mass & Energy Release & Containment Response Methodology ML20209H1731999-05-31031 May 1999 Revised Monthly Operating Rept for May 1999 for McGuire Nuclear Station,Units 1 & 2 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 ML20206R0891999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for McGuire Nuclear Station,Units 1 & 2 ML20195K3761999-04-30030 April 1999 Revised MORs 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 ML20205N3651999-04-12012 April 1999 Safety Evaluation Accepting IPE of External Events Submittal 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 ML20205L2341999-04-0505 April 1999 SFP Criticality Analysis 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 ML20205P9521999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Catawba 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
1
, j Attachment 1 Duke Power Company McGuire Nuclear Station Catawba Nuclear Station MASS AND ENERGY RELEASE AND CONTAINMENT RESPONSE METHODOLOGY DPC-NE-30(M Revision i May 1999 i
Nuclear Engineering Division Nuclear Generation Department Duke Power Company 9905270161 990520 PDR ADOCK 05000369 '
P pon
)
( -
l .
Table of Contents (cont.)
1 Appendix A - GOTHIC Ice Condenser Model With Finer Nodalization l
I I
viii
6.5-l '
CNS-12.4 ft 2MSLB Average Lower Containment Temperature 6.5-2 CNS-12.4 ft 2MSLB Break Compartment Temperature 6.5-3 CNS-12.4 ft: MSLB Average Lower Containment Pressure 6.5-4 CNS-12.4 ft 2MSLB Ice Mass Melted A-1 Revised GOTHIC Containment Model Nodalization l
l l
l l
l xxi l L:
Cpre Cooling Systems, the Auxiliary Feedwater System, the Containment Spray Systems, the Containment Air Return Fan System, the Component Cooling Water System, the Nuclear Service Water System, and the ice condenser and containment. The modeling of the actuation, alignment, and automatic or manual control of these systems is described in the report. Potential revisions to the Technical Specification limiting conditions for operation, and the control and operation of these systems in the station emergency operating procedures will be based on analyses using the methods described in this report.
Chapter 2 describes the three computer codes comprising the methodology, the simulation models, and validation of the code and models. Chapter 3 describes the mass and energy release methods, assumptions, and results for LOCA using RELAP5 MOD 3. Chapter 4 describes the mass and energy release assumptions and results for steam line breaks using RETRAN-02.
Chapter 5 describes the LOCA containment response assumptions and results using GOTHIC.
Chapter 6 describes the SLB containment response assumptions and results using GOTHIC.
Chapter 7 provides a brief summary.
The guidance provided in the Standard Review Plan Section 6.2 (Reference 1-8), Regulatory Guide 1.89 (Reference 1-9), and ANSI /ANS-56.4-1983 (Reference 1-10) was considered in the development of the methodology in this report. It is noted that the ice condenser containment design is not thoroughly addressed by these references.
Reference 1 11 described the Duke Power methodology for analyzing the mass and energy releases and containment responses for a B&W design PWR with a dry containment design.
That methodology is similar in that a version of the RELAP5 code, a sister code (FATHOMS / DUKE) to the GOTHIC code, and the RETRAN-02 code are the main components of the methodology. This report builds on that work and extends the methodology to the Westinghouse NSSS with an ice condenser containment design.
l Appendix A describes a revision to the GOTHIC simulation model for finer nodalization detail l
within the ice condenser region. This increased detail allows the modeling of various regions l- within the ice condenser with different initial ice weights. There are no changes to the basic l thermal-hydraulic behavior of the model which are introduced by the increased detail within the ice condenser region.
l-3
Appendix A GOTHIC Ice Condenser Model With Finer Nodalization For the purpose of analyzing a non-uniform initial ice mass distribution within a subset of the ice baskets, a revised GOTHIC ice condenser containment model is developed with a finer nodalization in the ice condenser region.
The nodalization of the ice condenser for the existing model, as described in Section 2.3.2 of the main body of this report,is l
l It is desired to nodalize the ice condenser with different ice weights in various regions. This may be accomplished by finer nodalization in the I
1 l
A-1
g . . ,
i l
f 1
I
~
)There are no modeling changes introduced as a result of the finer nodalization
~
which would alter the basic thermal-hydraulic behavior of the model.
A-2
r Figure A-1 l
l l
)
l l
1 l
l I
i l
l l
I i
Revised GOTHIC Containment Model Nodalization A-3