Letter Sequence Other |
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Results
Other: L-09-268, Calculation, 0800777.309, Rev. 0, Sensitivity Study of Temperbead Surface Area Limitations for Large Bore Weld Overlay Repairs Over Ferritic Materials (from 500 to 1,000 Square Inches)., L-10-132, 0800368.408, Revision 0, Summary of Weld Overlay Ultrasonic Examinations for Reactor Coolant Pump Suction and Discharge Nozzle Welds, Core Flood Nozzle Welds, and Cold Leg Drain Nozzle Welds, L-10-133, Summary of Design and Analysis of Weld Overlays (Mode 4 Report), ML093360324, ML093360325, ML093360326, ML093360327, ML093360328, ML093360329, ML093360330, ML093360331, ML100271531, ML101230640
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MONTHYEARL-09-020, 10 CFR 50.55a Requests for Alternative Dissimilar Metal Weld Repair Methods for Reactor Vessel Nozzles, Reactor Coolant Pump Nozzles, and Reactor Coolant Piping2009-01-30030 January 2009
10 CFR 50.55a Requests for Alternative Dissimilar Metal Weld Repair Methods for Reactor Vessel Nozzles, Reactor Coolant Pump Nozzles, and Reactor Coolant Piping
Project stage: Request
ML0933603252009-04-0808 April 2009
Calculation, 0800368.311, Rev. 0, Design Loads for the 28 I.D. Reactor Coolant Pump (RCP) Suction and Discharge Nozzles.
Project stage: Other
ML0933603242009-04-21021 April 2009
Calculation, 0800368.301, Rev 0, Material Properties for Davis-Besse Unit 1, RCP Suction, RCP Discharge, Cold Leg Drain and Core Flood Nozzles Preemptive Weld Overlay Repairs.
Project stage: Other
ML0933603272009-05-22022 May 2009
Calculation, 0800368.322, Rev. 1, Finite Element Models of the Reactor Coolant Pump Discharge Nozzle with Weld Overlay Repair.
Project stage: Other
ML0933603282009-05-23023 May 2009
Calculation, 0800368.323, Rev. 1, Thermal and Unit Mechanical Stress Analyses for Reactor Coolant Pump Discharge Nozzle with Weld Overlay Repair.
Project stage: Other
ML0933603262009-05-27027 May 2009
Calculation, 0800368.320, Rev. 1, Optimized Weld Overlay Sizing for the 28 I.D. Outlet/Discharge Reactor Coolant Pump Nozzle.
Project stage: Other
ML0915301512009-06-11011 June 2009
Request for Additional Information Related to Relief Requests for Alternative Dissimilar Metal Weld Repair Methods for Reactor Vessel Nozzles, Reactor Coolant Pump Nozzles, and Reactor Coolant Piping
Project stage: RAI
ML0915504232009-06-15015 June 2009
Request for Additional Information Related to Relief Requests for Alternative Dissimilar Metal Weld Repair Methods for Reactor Vessel Nozzles, Reactor Coolant Pump Nozzles, and Reactor Coolant Piping
Project stage: RAI
ML0933603292009-07-10010 July 2009
Calculation, 0800368.324, Rev. 0, Residual Stress Analysis of Reactor Coolant Pump Discharge Nozzle with Weld Overlay Repair.
Project stage: Other
L-09-179, Response to Requests for Additional Information Related to Alternative Dissimilar Metal Weld Repair Methods2009-07-13013 July 2009
Response to Requests for Additional Information Related to Alternative Dissimilar Metal Weld Repair Methods
Project stage: Response to RAI
ML0933603312009-07-20020 July 2009
Calculation, 0800368.326, Rev. 0, Crack Growth Evaluation of Reactor Coolant Pump Discharge Nozzle with Weld Overlay Repair.
Project stage: Other
L-09-227, License Amendment Request to Update the Leak-Before-Break Evaluation for the Reactor Coolant Pump Suction and Discharge Nozzle Dissimilar Metal Welds2009-09-28028 September 2009
License Amendment Request to Update the Leak-Before-Break Evaluation for the Reactor Coolant Pump Suction and Discharge Nozzle Dissimilar Metal Welds
Project stage: Request
ML0927205912009-10-0808 October 2009
RAI Related to Relief Requests for Alternative Dissimilar Metal Weld Repair Methods
Project stage: RAI
L-09-268, Calculation, 0800777.309, Rev. 0, Sensitivity Study of Temperbead Surface Area Limitations for Large Bore Weld Overlay Repairs Over Ferritic Materials (from 500 to 1,000 Square Inches).2009-11-0202 November 2009
Calculation, 0800777.309, Rev. 0, Sensitivity Study of Temperbead Surface Area Limitations for Large Bore Weld Overlay Repairs Over Ferritic Materials (from 500 to 1,000 Square Inches).
Project stage: Other
ML0933603302009-11-23023 November 2009
Calculation, 0800368.325, Rev. 0, ASME Code, Section Iii Evaluation of Reactor Coolant Pump Discharge Nozzle with Weld Overlay Repair.
Project stage: Other
ML0933603232009-11-23023 November 2009
Davis-Besse, Response to Requests for Additional Information Related to Alternative Dissimilar Metal Weld Repair Methods
Project stage: Response to RAI
ML1000400162009-12-15015 December 2009
Relief Request A-32 and A-33 - Request for Additional Information - Supplemental Information
Project stage: Supplement
ML1000805732010-01-21021 January 2010
Unit, Relief Request RR-A33 for the Application of Full Structural Weld Overlays on Dissimilar Metal Welds of Reactor Coolant Piping
Project stage: Acceptance Review
ML1002715312010-01-29029 January 2010
Relief Request RR-A32 for the Application of Full Structural Weld Overlays on Dissimilar Metal Welds of Reactor Coolant Piping
Project stage: Other
L-10-132, 0800368.408, Revision 0, Summary of Weld Overlay Ultrasonic Examinations for Reactor Coolant Pump Suction and Discharge Nozzle Welds, Core Flood Nozzle Welds, and Cold Leg Drain Nozzle Welds2010-04-25025 April 2010
0800368.408, Revision 0, Summary of Weld Overlay Ultrasonic Examinations for Reactor Coolant Pump Suction and Discharge Nozzle Welds, Core Flood Nozzle Welds, and Cold Leg Drain Nozzle Welds
Project stage: Other
ML1012306402010-04-29029 April 2010
Davis-Besse, Summary of Weld Overlay Ultrasonic Examinations
Project stage: Other
L-10-133, Summary of Design and Analysis of Weld Overlays (Mode 4 Report)2010-06-18018 June 2010
Summary of Design and Analysis of Weld Overlays (Mode 4 Report)
Project stage: Other
2009-06-11
[Table View] |
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Category:Calculation
MONTHYEARL-20-093, Offsite Dose Calculation Manual, Revision 372019-11-0404 November 2019
Offsite Dose Calculation Manual, Revision 37
ML20142A4012019-02-13013 February 2019
Offsite Dose Calculation Manual, Revision 36
L-16-134, Offsite Dose Calculation Manual, Revision 312015-06-30030 June 2015
Offsite Dose Calculation Manual, Revision 31
L-15-310, C-CSS-099.20-069, Rev 0, Shield Building Laminar Cracking Limits.2015-05-0606 May 2015
C-CSS-099.20-069, Rev 0, Shield Building Laminar Cracking Limits.
ML16147A0092015-01-14014 January 2015
Offsite Dose Calculation Manual, Revision 30
ML15280A3092014-09-0303 September 2014
C-CSS-099.20-063, Rev 1, Shield Building Design Calculation. Part 1 of 7
ML15280A3032014-09-0303 September 2014
C-CSS-099.20-063, Rev 1, Shield Building Design Calculation. Part 4 of 7
ML15280A3042014-09-0303 September 2014
C-CSS-099.20-063, Rev 1, Shield Building Design Calculation. Part 5 of 7
ML15280A3052014-09-0303 September 2014
C-CSS-099.20-063, Rev 1, Shield Building Design Calculation. Part 6 of 7
ML15280A3062014-09-0303 September 2014
C-CSS-099.20-063, Rev 1, Shield Building Design Calculation. Part 7 of 7
ML15280A3102014-09-0303 September 2014
C-CSS-099.20-063, Rev 1, Shield Building Design Calculation. Part 2 of 7
ML15280A3112014-09-0303 September 2014
C-CSS-099.20-063, Rev 1, Shield Building Design Calculation. Part 3 of 7
L-15-010, Offsite Dose Calculation Manual, Revision 292014-05-14014 May 2014
Offsite Dose Calculation Manual, Revision 29
ML15155B3672014-02-0101 February 2014
Offsite Dose Calculation Manual, Revision 28
L-14-135, Offsite Dose Calculation Model, Revision 272013-02-27027 February 2013
Offsite Dose Calculation Model, Revision 27
ML13009A3752012-12-12012 December 2012
Enclosure B to L-12-444, Calculation No. 32-9195651-000, Equivalent Margins Assessment of Davis-Besse Transition Welds for 52 EFPY - Non-Proprietary.
ML13009A3742012-12-11011 December 2012
Enclosure a to L-12-444, Calculation 32-9195423-000, DB-1 EMA of RPV Inlet & Outlet Nozzle-to-Shell Welds for 60 Years - Non-Proprietary.
ML12213A3332012-07-27027 July 2012
SB-0033 - Calculation C-CSS-099.20-054, Revision 0
ML12213A3342012-07-27027 July 2012
SB-0034 - Bechtel Response to Calculation C-CSS-099.20-054, Revision 0
L-12-152, Offsite Dose Calculation Manual, Revision 262011-11-0202 November 2011
Offsite Dose Calculation Manual, Revision 26
ML15280A3082011-10-31031 October 2011
C-CSS-099.20-055, Rev. 01, Ii/I Evaluation for Architectural Flute Shoulder.
ML11109A0842011-04-15015 April 2011
Attachments B-D, to L-11-107, Reply to Request for Additional Information for the Review of the Davis-Besse Nuclear Power Station, Unit No. 1, License Renewal Application
L-11-150, Offsite Dose Calculation Manual, Rev. 242011-03-11011 March 2011
Offsite Dose Calculation Manual, Rev. 24
ML12174A0962011-02-22022 February 2011
Offsite Dose Calculation Manual, Revision 25
ML1014004062010-05-11011 May 2010
Areva Calculation 32-9136508-002, DB-1 CRDM Nozzle J-Groove Weld Flaw Evaluation for Idtb Repair, Enclosure B
ML1014004072010-05-0707 May 2010
Areva Calculation 32-9135800-001, DB-1 CRDM Nozzle Weld Anomaly Flaw Evaluation of Idtb Repair, Enclosure C
ML1014004052010-05-0606 May 2010
Areva Calculation 32-9136884-001, DB-1 CRDM Nozzle Weld Anomaly Flaw Evaluation of Idtb Alternate Repair with Alloy 52M/82, Enclosure a
L-10-131, Additional Information Regarding 10 CFR 50.55a Request RR-A34 for Alternative Repair Methods for Reactor Pressure Vessel Head Penetration Nozzles2010-04-21021 April 2010
Additional Information Regarding 10 CFR 50.55a Request RR-A34 for Alternative Repair Methods for Reactor Pressure Vessel Head Penetration Nozzles
ML1011101482010-04-0808 April 2010
Calculation 32-91358000-000, DB-1 CRDM Nozzle Weld Anomaly Flaw Evaluation of Idtb Repair.
ML0933603302009-11-23023 November 2009
Calculation, 0800368.325, Rev. 0, ASME Code, Section Iii Evaluation of Reactor Coolant Pump Discharge Nozzle with Weld Overlay Repair.
L-09-268, Calculation, 0800777.309, Rev. 0, Sensitivity Study of Temperbead Surface Area Limitations for Large Bore Weld Overlay Repairs Over Ferritic Materials (from 500 to 1,000 Square Inches).2009-11-0202 November 2009
Calculation, 0800777.309, Rev. 0, Sensitivity Study of Temperbead Surface Area Limitations for Large Bore Weld Overlay Repairs Over Ferritic Materials (from 500 to 1,000 Square Inches).
ML0933603312009-07-20020 July 2009
Calculation, 0800368.326, Rev. 0, Crack Growth Evaluation of Reactor Coolant Pump Discharge Nozzle with Weld Overlay Repair.
ML0933603292009-07-10010 July 2009
Calculation, 0800368.324, Rev. 0, Residual Stress Analysis of Reactor Coolant Pump Discharge Nozzle with Weld Overlay Repair.
ML1014105112009-06-11011 June 2009
Offsite Dose Calculation Manual, Revision 23
ML0933603262009-05-27027 May 2009
Calculation, 0800368.320, Rev. 1, Optimized Weld Overlay Sizing for the 28 I.D. Outlet/Discharge Reactor Coolant Pump Nozzle.
ML0933603282009-05-23023 May 2009
Calculation, 0800368.323, Rev. 1, Thermal and Unit Mechanical Stress Analyses for Reactor Coolant Pump Discharge Nozzle with Weld Overlay Repair.
ML0933603272009-05-22022 May 2009
Calculation, 0800368.322, Rev. 1, Finite Element Models of the Reactor Coolant Pump Discharge Nozzle with Weld Overlay Repair.
ML0933603242009-04-21021 April 2009
Calculation, 0800368.301, Rev 0, Material Properties for Davis-Besse Unit 1, RCP Suction, RCP Discharge, Cold Leg Drain and Core Flood Nozzles Preemptive Weld Overlay Repairs.
ML0933603252009-04-0808 April 2009
Calculation, 0800368.311, Rev. 0, Design Loads for the 28 I.D. Reactor Coolant Pump (RCP) Suction and Discharge Nozzles.
L-09-111, Offsite Dose Calculation Manual, Revision 222008-09-0303 September 2008
Offsite Dose Calculation Manual, Revision 22
L-08-056, Reactor Protection System High Flux Trip Setpoint Calculation2008-02-14014 February 2008
Reactor Protection System High Flux Trip Setpoint Calculation
IR 05000124/20280082007-04-12012 April 2007
Enclosure 3, Areva Np Calculation 32-5012428-08, Davis-Besse Heat Balance Uncertainty.
ML0710705782007-04-12012 April 2007
Enclosure 3, Areva Np Calculation 32-5012428-08, Davis-Besse Heat Balance Uncertainty.
ML0612304032005-12-22022 December 2005
Offsite Dose Calculation Manual Revision 20.0
ML0512502282004-12-22022 December 2004
Offsite Dose Calculation Manual, Revision 19.0
ML0512502232004-01-23023 January 2004
Offsite Dose Calculation Manual, Revision 18.0
ML0310401082003-03-31031 March 2003
Computations on Failure Pressure of as-found Cavity FENOC Cavity Analysis with Handwritten Notes
ML0308501852003-02-0505 February 2003
Preliminary Responses to NRC Staff Comments & Questions on Davis Besse Safety Significance Assessment
2019-02-13
[Table view] |
Text
Structural Integrity Associates, Inc. File No.: 0800368.311 CALCULATION PACKAGE Project No.: 0800368 Z Q -' Non-Q PROJECT NAME: Davis Besse Phase 2 Alloy 600 CONTRACT NO.: 49151, Rev. 1 CLIENT: PLANT: Welding Services Inc- (WSI) Davis-Besse Nuclear Power Station, Unit I CALCULATION TITLE: Design Loads for the 28" I.D. Reactor Coolant Pump (RCP) Suction and Discharge Nozzles Document Affected Project Manager Preparer(s)
&Revision Pages Revision Description Approval Checker(s)
Signature
& Date Signatures
& Date 0 1-9 Original Issue Z 5 Computer Files 5 Richard L. Ba Nader Sadeghi RLB 4/!/2009 N 4/8/2009 Raju Ananth RA 4/8/2009 Page 1 of 9 F0306-01 RO A Structural Integrity Associates, Inc.Table of Contents 1.0 2.0 3.0 4.0 5.0 6.0 OBJECTIVE
.................................................................................................................................
3 M ETHODOLOGY
.......................................................................................................................
3 DESIGN INPUTS .........................................................................................................................
4 CALCULATION S ........................................................................................................................
7 RESULTS OF ANALYSIS ......................................................................................................
8 REFEREN CES .............................................................................................................................
8 List of Tables Table 1: Transients
...............................................................................................................................
5 Table 2: Bounding Piping Interface Loads for RCP Suction Nozzle ...............................................
6 Table 3: Bounding Piping Interface Loads for RCP Discharge Nozzle ..........................................
6 Table 4: Properties of Liquid W ater ...............................................................................................
7 Table 5: Bounding Transients for Analysis ......................................................................................
8 File No.: 0800368.311 Revision:
0 Page 2 of 9 F0306-O1RO Structural Integrity Associates, Inc.1.0 OBJECTIVE A weld overlay repair is being designed for the 28" I.D. Suction Reactor Coolant Pump (RCP)nozzle-to-elbow weld and the 28" I.D. Discharge RCP safe end-to-elbow weld at the Davis-Besse Nuclear Power Station, Unit 1. The purpose of this calculation package is to determine the loading conditions that are applied to these locations, including piping interface loads, pressure, and thermal transients.
2.0 METHODOLOGY
The loading developed herein will be used to perform stress and fatigue usage analysis in accordance with Figure NB-3222-1 of Section III of the ASME Code [1], as well as crack growth analysis.Piping interface loads are tabulated for deadweight, thermal expansion, and seismic events. Thermal transients are also tabulated, and heat transfer coefficients are calculated as described below.2.1 Internal Heat Transfer Coefficients, Forced Convection Holman [2, pp. 226-227] gives the following equation for turbulent flow heating in tubes: Nu =0.023 Re" Pro", where Nu = Nusselt number = hD/k Re = Reynolds number = pVD/t Pr = Prandtl number, non-dimensional h = heat transfer coefficient, Btu/hr-ft 2-°F D = inside diameter, ft k = thermal conductivity, Btu/hr-ft-°F p = density, lbm/ft 3 V = velocity, ft/hr = Q/(rcD 2/4) = m'/(pmcD 2/4)Q = volumetric flow rate, ft 3/hr mv = mass flow rate, lbm/hr[L = viscosity, lbm/ft-hr Solving for heat transfer coefficient and substituting V = m'/(pntD 2/4) yields: h = 0.023 (k/D) (pVD/t)0°8 Pr 0.4 h = 0.023 (k/D) {(pD/Q)[m'/(pirD 2/4)]}0'8 Pro 4 h = 0.023 (k/D) {(1/p)[4m'/(7rD)]}° 8 Pr°4 h = 0.023 (k/D) [4m'/(grnD)]° 8 Pr°4 h = {0.023 k 8 Pr 0" 4} (m')°8/D 1 8 The portion inside the curly brackets is defined as ýA, and is temperature dependent.
The above equation is valid for Reynolds number, Re, greater than 2300 [2, p. 172]; Re is given by: Re = pVD/[t Re = (pD/g)[m'/(p7rD 2/4)]File No.: 0800368.311 Page 3 of 9 Revision:
0 F0306-O1RO Structural Integrity Associates, Inc.Re = (1/ t)[4m'/(QtD)]
Re = 4m'/(gutD)
Re = 4/(utr) (m'/D)2.2 Internal Heat Transfer Coefficients, Natural Convection For transients where no flow rate or heat transfer coefficient is given, the flow rate is assumed to be essentially zero, and heat transfer coefficients are determined based on natural circulation.
For natural circulation in enclosed vertical or horizontal cylinders, Holman [2, p. 289] gives the following formula: Nuf= 0.55 (GrfPrf)1 4 , where Gr/ = Grashof number, dimensionless
= g 13 AT D 3/v 2 P = temperature coefficient of volume expansion (fluid), 1/0 F g = acceleration due to gravity = 32.174 ft/sec 2 AT = temperature difference between the fluid and wall, 'F v = kinematic viscosity, ft 2/sec Other symbols are the same as previously defined. The subscriptf indicates that the properties are evaluated at the film temperature, which is the average of the free-stream fluid temperature and the wall temperature
[2, p. 273]. Separating constants and physical properties as before, the equation becomes: h = 0.55 (k/D) (g 13 AT D 3 Prj/v 2)1/4 h = 0.55 k [g 03 AT D 3 Pr/(D 4 v 2)]1/4 h = 0.55 k [g 3 AT Prj/(D v2)]1/4 h = {0.55 k (g P3 Prj/v 2)1/4} (AT/D)" 4 The portion inside the curly brackets is defined as 4B, and is temperature dependent.
2.3 Other
Heat Transfer Coefficients All outside surfaces are assumed to be perfectly insulated.
There is no heat transfer to the surroundings.
Therefore, no heat transfer coefficients or temperatures are applied to the insulated outside surfaces.3.0 DESIGN INPUTS File No.: 0800368.311 Page 4 of 9 Revision:
0 F0306-01RO V Structural Integrity Associates, Inc.10-69--m IVIUL'm a-U -File No.: 0800368.311 Revision:
0 Page 5 of 9 F0306-O IRO V Structural Integrity Associates, Inc.Table 4 lists the properties of liquid water, which are used to calculate heat transfer coefficients, from Cheremisinoff
[6, Table 1-8] up to 600'F and Rohsenow et al [7, p. 3-53] above 600'F. For temperatures above 600'F, the parameter P3 is calculated as (dv/dT)/v, where v is the specific volume[7, p. 3-52] and T is the temperature.
File No.: 0800368.311 Revision:
0 Page 6 of 9 F0306-O1RO V Structural Integrity Associates, Inc.Table 4: Properties of Liquid Water ji, Ibm/ft- k, Btu/hr- gO3/v 2 , T, °F hr v, ft'/sec ft-OF Pr 3,/F 1/OF-ft 3 60 2.736 1.22E-05 0.340 8.07 8.OOE-05 80 2.081 9.29E-06 0.353 5.89 1.30E-04 ---100 1.649 7.36E-06 0.364 4.51 1.80E-04 1.07E+08 200 0.742 3.42E-06 0.392 1.91 3.70E-04 1.01E+09 300 0.468 2.27E-06 0.395 1.22 5.60E-04 3.51E+09 400 0.335 1.74E-06 0.382 0.95 7.80E-04 8.35E+09 500 0.252 1.43E-06 0.349 0.86 1.10E-03 1.74E+10 600 0.208 1.37E-06 0.293 1.07 1.75E-03 3.03E+10 638.3 0.186 1.34E-06 0.270 1.30 2.83E-03 ---656.3 0.174 1.32E-06 0.257 -1.52 3.98E-03 4.0 CALCULATIONS 4.1 Heat Transfer Coefficients Heat transfer coefficients are calculated as described in Section 2.0. The inside diameter used is: o Nozzle and pipe: D = 28" = 2.33' [4, p. 8]Parameters cIA and ýB are evaluated at each temperature in Table 4, and then interpolated to the temperatures in Table 1; this is done in the sheet labeled "Properties" in Excel workbook DB-311.xlsx.
Heat transfer coefficients are calculated as h = ýA (m')8 i/D 1 8 (for transients with flow) or qIB (AT/D)1/4 (for transients without flow) as appropriate for each time point in Table 1 in the sheet labeled "Transients" in Excel workbook DB-311.xlsx.
For transients without flow, AT is taken as 5 0 F, which is expected to be conservative based on the slowness of the ramp transients.
For transients with flow, Reynolds number is calculated as Re = 4/([tT[) (m'/D) in the sheet labeled"Properties" in Excel workbook DB-311.xlsx, and is found to be much greater than 2300.The maximum values of ýA and for the applicable temperatures in Table 1 are 0.0293 and 68.0567, respectively, so that the maximum heat transfer coefficients are: Nozzle etc., forced convection:
Nozzle etc., natural convection:
h = 0.0293 (46323539)08/(2.3333)18
= 8666.6 Btu/hr-ft 2-°F h = 68.0567 (5/2.3333)'/4
= 82.3 Btu/hr-ft 2-°F 4.2 Interface Loads T is equal to the fluid temperature during the given transient in 'F.File No.: 0800368.311 Revision:
0 Page 7 of 9 F0306-O1RO V Structural Integrity Associates, Inc.5.0 RESULTS OF ANALYSIS Table 5 provides the transient definitions, applicable heat transfer coefficients, and interface load factors for the bounding transients.
The thermal transients are to be considered as concurrent with the thermal expansion interface loads from Tables 2 and 3 multiplied by the factors shown in Table 5. Total OBE interface loads from Tables 2 and 3 can occur simultaneously with any thermal transient, up to the total number of OBE events, which is 650. The number of OBE events and the numbers of cycles in Table 5 occur over 40 years. To account for 20 years of additional life, the number of cycles in Table 5 should be multiplied by a factor of 1.5.Deadweight loads in Tables 2 and 3 are provided for use in the crack growth analysis.M M ' 11 I-Ua-Iil-u-U I-U-rýýý-'U--.a File No.: 0800368.311 Revision:
0 Page 8 of 9 F0306-O1RO Structural Integrity Associates, Inc.
6.0 REFERENCES
- 1. ASME Boiler and Pressure Vessel Code,Section III, Rules for Construction of Nuclear Facility Components, 2001 Edition with Addenda through 2003.2. Holman, J.P., Heat Transfer, Fifth Edition, McGraw-Hill, 1981.a 6. Cheremisinoff, N., Heat Transfer Pocket Handbook, Gulf Publishing Co., Houston, 1984.7. Rohsenow, W. M., Hartnett, J. P., Ganic, E. N., Handbook of Heat Transfer Fundamentals, Second Edition, McGraw-Hill, 1985.8. Davis Besse USAR, revision 26, Table 5.1-8, Transient Cycles-40-Year Design Life, Rev. 22, SI File No. 0800368.248.
COMPUTER FILES: DB-311.xlsx File No.: 0800368.311 Revision:
0 Page 9 of 9 F0306-O1RO
