ML082490574
| ML082490574 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee  |
| Issue date: | 01/30/2008 |
| From: | Lohse C S, Weitze W F Structural Integrity Associates |
| To: | NRC/SECY/RAS |
| SECY RAS | |
| References | |
| 06-849-03-LR, 10163217, 50-271-LR, Entergy-Applicant-E2-26-VY, RAS M-289 VY-19Q-302, Rev 0 | |
| Download: ML082490574 (12) | |
Text
(2,AS H gq Structural Integrity Associates, Inc. File No.: VY-19Q-302 CALCULATION PACKAGE Project No.: VY-I9Q PROJECT NAME: Provide VY Support for Questions Related to Environmental Fatigue Analyses CONTRACT NO.: 10163217 CLIENT: PLANT: Entergy Nuclear Operations, Inc. Vermont Yankee Nuclear Power Station CALCULATION TITLE: ASME Code Confirmatory Fatigue Evaluation of Reactor Feedwater Nozzle Document Affected Project Manager Preparer(s)
&Documen afe Revision Description Approval Checker(s)
Revision Pages Signature
& Date Signatures
& Date 0 1-12 Original Issue Computer Files ' .T T Herrmann WF Weitze ,'- TJH WFW 01/30/2008 CS ohse CSL 01/ý32008 U.S. NUCLEAR REGL LATORY COMMSSIN In the Matter of V t gw Vei -L So-- _ al-Exhibit No. E 2- 2-OFFERED by4 ýppficant/Lcer -s~e ýInrvenor_______
NRC Staff Other IDENTi-ED
&o.:)t I ! o imess/Panel IJECZ-'Action Taken: AD REJECTED WITHDRAWN Reporter/Clerk lAP'_ _DOCKETED I August 12, 2008 (11:00am)OFFICE OF SECRETARY RULEMAKINGS AND ADJUDICATIONS STAFF Page 1 of 12 F0306-01RO b)ý-o 3 Structural Integrity Associates, Inc.Table of Contents 1.0 O B JE C T IV E .................................................................................................................................
3 2.0 METHODOLOGY
.......................................................................................................................
3 3.0 D E SIG N IN P U T S .........................................................................................................................
3 4.0 CALCULATIONS
........................................................................................................................
9 5.0 RESULTS OF ANALYSIS ...................................................................................................
10
6.0 CONCLUSION
S AND DISCUSSIONS
...............................................................................
11 7.0 R E F E R E N C E S .......................................................................
....................................................
12 List of Tables Table 1: Transients as Input to VESLFAT ......................................................................................
7 Table 2: Temperature-Dependent Material Properties, VESLFAT .........................
8 Table 3: Carbon/Low Alloy Steel Fatigue Curve .............................................................................
8 Table 4: Stress Components Before SCF, psi ............................................................
9 Table 5: Stress Components W ith SCF, psi ....................................................................................
9 Table 6: Fatigue Usage Results for Safe End ..................................................................................
10 Table 7: Fatigue Usage Results for Nozzle Comer ............................................................................
11 List of Figures Figure 1: ANSYS Finite Element Model .........................................................................................
4 Figure 2: Linearization Paths ......................................................................................................
5 File No.: VY-19Q-302 Revision:
0 Page 2 of 12 F0306-01 RO Structural Integrity Associates, Inc.1.0 OBJECTIVE The objective of this calculation package is to perform an ASME Code,Section III fatigue usage calculation for the reactor pressure vessel (RPV) feedwater (FW) nozzle at Vermont Yankee Nuclear Power Station (VYNPS).2.0 METHODOLOGY The methodology to be used for this evaluation was established in a previous calculation package[1], and is summarized herein. A previously-developed finite element model (FEM) is analyzed using the ANSYS program [2]. Thermal transient analysis is performed for each defined transient, and the thermal stresses are added to stresses due to pressure and piping loads, which are scaled based on the magnitudes of the pressure and piping loads. Stress concentration factors (SCFs) are applied as appropriate.
All six components of the stress tensor are used for stress calculations.
The fatigue calculation is performed at previously-examined locations, and uses the methodology of Subarticle NB-3200 of Section III of the ASME Code [3]. Environmental fatigue usage analysis will be performed in a separate calculation package.3.0 DESIGN INPUTS 3.1 Finite Element Analysis'A previous calculation package specifies all design input [1]. The FEM input file is taken from the previous analysis of the FW nozzle [4, file FW.INP], and modified to include temperature-dependent properties
[1, Table 5]. The modified file is named FW-GEOMINP, and is used as input to the files in which the thermal transient and stress analyses are performed.
Figure 1 shows the. FEM [4, Figure 4].For the thermal transient ANSYS analysis, previously defined thermal transients
[1, Table 1] are analyzed, applying heat transfer coefficients
[1, Tables 4 and 6] as appropriate based on flow rate.Bounding reactor temperature is used for Transients 12/13/15 [ 1, Table 1 ], called Transient 13 herein. (In VESLFAT, Transient 13 is run separately since it has a higher reactor pressure.)
For ramps during which the flow rate undergoes a ramp change [5, Attachment 1, p. 3], the set of heat transfer coefficients with the largest values is used. This is done because ANSYS always applies changes to the heat transfer coefficients as step changes, even if the temperature undergoes a ramp change.Note that, for three time periods during Transient 11 [1, Table 1], the nozzle is filled with steam at Region A temperature
[5, Attachment 1, p. 3, Note 1], such that heat transfer coefficients for condensation apply [1, Table 6]. Since it takes a finite amount of time for the water to drain and condensation to begin, the condensation heat transfer coefficients are not applied until the load step after the Region A temperature is reached.Stress analysis is performed using the temperature distributions calculated in the thermal transient ANSYS analysis as input. At the vessel wall, Y displacement is set to zero, and X displacement is File No.: VY-19Q-302 Page 3 of 12 Revision:
0 F0306-O1RO tStructural Integrity Associates, Inc.unconstrained, as was previously done [6, Figure 4]. At the FW pipe, Y displacement is coupled to account for the adjacent piping, as was previously done [6, files FWSVY 25.INP, FWSVY 40.INP, and FWSVY 100.INP].
Figure 1 shows the locations of these boundary conditions.
ELEMENTS Y coupled SEP 6 2002 16:23:51 Y=O Feedwater Nozzle Finite Element Model Figure 1: ANSYS Finite Element Model All ANSYS input files, listed below, are saved in the project computer files: FW-GEOMINP:
Geometry and material properties FW-HTBC.INP:
Set heat transfer boundary conditions TRANO2- T.INP, TRANO2-S.INP:
TRANO3-T.INP, TRANO3-S.INP:
TRANO4- T.INP, TRANO4-S.INP:
TRANO5- T.INP, TRANO5-S.INP:
TRANO6- T.INP, TRANO6-S.INP:
TRAN09-T.INP, TRANO9-S.INP:
TRAN1O-T.INP, TRAN1O-S.INP:
TRAN11-T.INP, TRAN11-S.INP:
TRAN13-T.INP, TRAN13-S.INP:
Transient 2, thermal and stress analysis Transient 3, thermal and stress analysis Transient 4, thermal and stress analysis Transient 5, thermal and stress analysis Transient 6, thermal and stress analysis Transient 9, thermal and stress analysis Transient 10, thermal and stress analysis Transient 11, thermal and stress analysis Transient 12/13/15, thermal and stress analysis File No.: VY-19Q-302 Revision:
0 Page 4 of 12 F0306-O1RO C Structural Integrity Associates, Inc.TRAN14-T.INP, TRA914-S.INP:
Transient 14, thermal and stress analysis TRAN19-T.INP, TRAN19-S.INP:
Transient 19, thermal and stress analysis TRAN20-T.INP, TRAN20-S.INP:
Transient 20, thermal and stress analysis TRAN2OATINP, TRAN2OAS.INP:
Transient 20A, thermal and stress analysis TRAN21-TINP, TRAN21-S.INP:
Transient 21, thermal and stress analysis TRAN25-T.INP, TRAN25-S.INP:
Transient 25, thermal and stress analysis 3.2 Stress Calculation Linearized stress components at Nodes 192 (safe end inside surface) and 657 (nozzle comer inside surface) are used for the fatigue usage analysis [1, Section 3.6], as shown in Figure 2 [6, Figures 7 and 9]. For the nozzle comer location, the stresses used in the evaluation are for the base metal only;that is, the cladding material is unselected prior to stress extraction.
The stress components from the thermal stress analyses are combined with stress components due to pressure and piping loads. A unit pressure stress analysis was performed using ANSYS in a previous calculation package [6], and stress component results are taken from that analysis [6, files PSE. OUT and PBLEND. OUT]. Piping load stress components are taken from previous calculations using closed form solutions
[1, Table 7].Figure 2: Linearization Paths SCFs are applied to the pressure and piping load stress components to yield primary plus secondary membrane plus bending stress components (P+Q) and the total (primary plus secondary plus peak)stress components (P+Q+F) as specified in the methodology calculation package [1].File No.: VY-19Q-302 Revision:
0 Page 5 of 12 F0306-O1 RO Structural Integrity Associates, Inc.3.3 Fatigue Usage Analysis, General The VESLFAT program [7] is used to perform the fatigue usage analysis in accordance with the fatigue usage portion of NB-3200 [3]. VESLFAT performs the analysis required by NB-3222.4(e)
[3] for Service Levels A and B conditions defined by the user. The VESLFAT program computes the primary plus secondary and total stress ranges for all events and performs a correction for elastic-plastic analysis, if appropriate.
The program computes the stress intensity range based on the stress component ranges for all event pairs [3, NB-3216.2].
The program evaluates the stress ranges for primary plus secondary and primary plus secondary plus peak stress based upon six components of stress (3 direct and 3 shear stresses).
If the primary plus secondary stress intensity range is greater than 3 Sm, then the total stress range is increased by the factor Ke, as described in NB-3228.5
[3]. The value of Sm is specified as a function of temperature.
The input maximum temperature for both states of a load set pair is used to determine the temperature upon which Sm is determined from the user-defined values.When more than one load set is defined for either of the event pair loadings, the stress differences are determined for all of the potential loadings, saving the maximum for the event pair, based on the pair producing the largest alternating total stress intensity (Salt), including the effects of K,. The principal stresses for the stress ranges are determined by solving for the roots of the cubic equation: S3 _ ((ix + (iy Y+ Cos)$ + (CYx CTy + (iY (7z + (iz (ix -7xy 2 -X 1x2 _ Tyz2 )s-((ix Cy (iz + 2 Tyz -Yz .- (iy 2,_ z 2 -IxZ 2 ryz 2 )o The stress intensities for the event pairs are reordered in decreasing order of Salt, including a correction for the ratio of modulus of elasticity (E) from the fatigue curve divided by E from the analysis.
This allows a fatigue table to be created to eliminate the number of cycles available for each of the events of an event pair, allowing determination of fatigue usage per NB-3222.4(e)
[3].For each load set pair in the fatigue table, the allowable number of cycles is determined based on Salt.For the VYNPS FW nozzle analysis, transients that consist of both upward and downward temperature and pressure ramps are split so that each successive ramp is treated separately.
Table 1 shows the transients as input to VESLFAT [1, Table 1]. The numbers of cycles in Table 1 are entered in VESLFAT input files VFAT-1LCYC (safe end) and VFAT-21.CYC (nozzle corner).File No.: VY-19Q-302 Page 6 of 12 Revision:
0 F0306-O1 RO Structural Integrity Associates, Inc.Table 1: Transients as Input to VESLFAT VESLFAT Start Time, Temp. Pressure Load Set Transient sec** Change Change Cycles 1 1_Boltup 0 None None *2 2_DesHydrol 0 Upward Upward 120"3 2_DesHydro2 5280 None Downward 120 4 3_Startup 0 Upward Upward 300 5 4 TurbRolll 0 Downward None 300 6 4_TurbRoll2 1801 Upward. None 300 7 5_DailyRedl 0 Downward None 10,000 8 5_DailyRed2 2700 Upward None 10,000 9 6_WklyRedl 0 Downward None 2,000 10 6_WklyRed2 3600 Upward None 2,000 11 9_TurbTripl 0 Downward None 10 12 9_TurbTrip2 2520 Upward None 10 13 10_FWHByp1 0 Downward None 70 14 10_FWHByp2 1890 Upward None 70 15 11 _LoFP1 0 Upward Upward 10 16 11 LoFP2 3.5 Downward Downward 10 17 11_LoFP3 184.5 Upward None 10 18 11 LoFP4 2165.5 Downward Downward 10 19 11_LoFP5 2346.5 Upward Upward 10 20 11_LoFP6 6727.5 Downward Downward 10 21 11 _LoFP7 7148.5 Upward Downward 10 22 11 _LoFP8 11048.5 Upward Upward 10 23 11 LoFP9 18212.5 Downward None 10 24 11 _LoFP 10 20013.5 Upward None 10 25 12_TGTripl 0 None Upward 288 26 12_TGTrip2 15 Downward Downward 288 27 12_TGTrip3 2790 Upward Upward 288 28 13_Overprl 0 None Upward 1 29 13_Overpr2 15 Downward Downward 1 30 13_Overpr3 2790 Upward Upward 1 31 14 SRVBlwdn 0 Downward Downward 1 32 19_RedTo0pct 0 Downward None 300 33 20_HSHeatup 0 Upward None 300 34 20AHSFWInj 1 0 Downward None 300 35 20AHSFWInj2 181 Upward None 300 36 21 Shutdown 0 Downward Downward 300 37 24_HydroTestl 0 None .Upward 1 38 24_HydroTest2 1200 None Downward 1 39 25 Unbolt 0 Downward None 123* Since this transient does not affect the FW nozzle, it is not considered in the cyclic evaluation.
- Note that stress peaks may occur after the start of the subsequent ramp.3.4 Material Properties, VESLFAT Material properties are entered in VESLFAT input files VFA T-1I.FDT (safe end) and VFAT-21.FDT (nozzle comer). Table 2 lists the temperature-dependent material properties used in the analysis [1, Table 5] [8], and Table 3 lists the fatigue curve for the nozzle and safe end materials
[3, Appendix I, Table 1-9.1 and Figure 1-9.1 ]. VESLFAT automatically scales the stresses by the ratio of E on the fatigue curve to E in the analysis, for purposes of determining allowable numbers of cycles, as required by the ASME Code.File No.: VY-19Q-302 Page 7 of 12 Revision:
0 F0306-OIRO Structural Integrity Associates, Inc.Other material properties are input as follows: m = 3.0, n = 0.2, parameters used to calculate factor safe end [9]m = 2.0, n = 0.2, parameters used to calculate factor K,, nozzle comer [9]E from fatigue curve = 30,000 ksi [3, Appendix I, Table 1-9.1 and Figure 1-9.1] [9]Table 2: Temperature-Dependent Material Properties, VESLFAT Material A508 Class I (safe end)T, 'F 70 200 300 400 500 600 70 200 300 400 500 600 E, psi 29.3(10)6 28.6(10)6 28.1(10)6 27.5(10)6 27. 1(10)6 26.5(10)6 27.8(10)6 27. 1(10)6 26.7(10)6 26. 1(10)6 25.7(10)6 25.2(10)6 S., ksi 23.3 21.9 21.3 20.6 19.4 17.8 26.7 26.7 26.7 26.7 26.7 26.7 S,, ksi 36.0 33.0.31.8 30.8 29.3 27.6 50.0 47.0 45.5 44.2.43.2 42.1 A508 Class II (nozzle)Table 3: Carbon/Low Alloy Steel Fatigue Curve Number of Cycles 10 20 50 100 200 500 1,000 2,000 5,000 10,000 20,000 50,000 100,000 200,000 500,000 1,000,000 S., ksi 580 410 275 205 155 105 83 64 48 38 31 23 20 16.5 13.5 12.5 File No.: VY-19Q-302 Revision:
0 Page 8 of 12 F0306-01 RO Structural Integrity Associates, Inc.4.0 CALCULATIONS Table 4 contains the stress components at the locations of interest for the 1,000 psi pressure case [6, files PSE.OUT and PBLEND.OUT]
and for the piping loads [1, Table 7], corresponding to a reactor temperature of 575°F [1, Section 3.1.8].Table 4: Stress Components Before SCF, psi Loading Type Node S" Sy Sz SXV Sxz SZ Unit Membrane 192 -810.7 6116 7853 -450.1 0 0 Pressure, plus Bending 657 -705.2 1198 24020 -3590 0 0 1,000 psi Total 657 -705.2 985.5 27590 -121.1 0 0 Piping Loads Nominal 192 0 7430 0 1210 3176 0 at 575°F 657 0 354 0 98 105 0 SCFs are applied to the pressure and piping load stress components to yield P+Q and P+Q+F stress components as follows [1]: Pressure: Safe end (Node 192): Membrane plus bending from ANSYS equals P+Q Membrane plus bending from ANSYS is multiplied by 1.1 to yield P+Q+F Nozzle comer (Node 657): Membrane plus bending from ANSYS is multiplied by 1.333 to yield P+Q Total stress from ANSYS is multiplied by 1.333 to yield P+Q+F Piping Loads: Safe end (Node 192): Nominal stresses are multiplied by 1.796 to yield P+Q Nominal stresses are multiplied by 1.976 to yield P+Q+F Nozzle comer (Node 657): Nominal stresses are used as is for P+Q and P+Q+F Table 5 shows the stress components with SCFs. The piping load stress components are applied as having negative signs, to yield the largest stress component ranges.Table 5: Stress Components With SCF, psi Membrane plus Bending Total Load Node Sx Sv, S" S-v S, Svz Sv S2 SWv S-z S&7 Pressure 192 -811 6116 7853 -450 0 0 -892 6728 8638 -495 0 0 657 -940 1597 32019 -4785 0 0 -940 1314 36777 -161 0 0 Piping 192 0 13344 0 2173 5704 0 0 14682 0. 2391 6276 0 657 0 354 0 98 105 0 0 354 0 98 105 0 The calculations of VESLFAT stress input are automated in Excel workbooks VFAT-1LXLS (safe end) and VFA T-2I.XLS (nozzle).
These files are organized with sheets labeled as follows:.Overview:
Contains general information.
File No.: VY-19Q-302 Page 9 of 12 Revision:
0 F0306-O1RO Structural Integrity Associates, Inc.* Other Stresses:
Contains calculation of pressure and piping load as shown in Tables 4 and 5.* Rearranger:
There are 16 Rearranger sheets, one for each transient as analyzed by ANSYS.In these sheets, thermal stresses are copied from Excel workbook StressResults.xls, which contains the results of the ANSYS stress linearization for each transient, and rearranged to conform to'VESLFAT input format (including switching the shear stress components Sxz and Syz as required by VESLFAT).
Time-varying scale factors for the piping loads (based on FW nozzle fluid temperature) and pressure are determined, and used to scale the unit load stresses, which are then added to the thermal stresses.
Time-varying pressure is also included in the VESLFAT stress input. The VESLFAT stress input also includes time-varying metal temperature, from the ANSYS output, which is used to determine temperature-dependent properties from the values in Table 2.* VESLFAT: Contains the VESLFAT stress input, obtained from sheets named Rearranger.
Load set numbers are entered on this sheet, as defined in Table 1. These sheets are saved to VESLFAT input files VFAT-1I.STR (safe end) and VFAT-2I.STR (nozzle comer). To avoid double counting of stress states, the initial time steps of each load set before the firststress peak are not included.The files with extension STR are edited if necessary to remove some intermediate stress points, since VESLFAT has a limit of 3,000 total stress states.5.0 RESULTS OF ANALYSIS Tables 6 and 7 give the detailed fatigue usage results for the safe end and the nozzle comer, respectively, from VESLFAT output files VFAT-1I.FAT (safe end) and VFAT-2LFAT (nozzle comer). All VESLFAT input and output files are saved in the project computer files.Table 6: Fatigue Usage Results for Safe End Load Set A Load Set B n Sn, psi Ke S.it, psi N Usage 15 11 LoFP1 18 11 LoFP4 10 61435 1.115 57352 2836.19 0.0035 20 11_LoFP6 27 12_TGTrip3 10 49698 1 40800 8098.01 0.0012 27 12_TGTrip3 34 20AHSFWInj 1 278 42194 1 37182 10769 0.0258 3013_Overpr3 34 20AHSFWInj 1 1 42194 1 37182 10769 0.0001 33 20_HSHeatup 34 20AHSFWInjl 21 42563 1 35966 12060 0.0017 5 4_TurbRolll 33 20_HSHeatup 279 43986 1 35597 12491 0.0223 64 TurbRoll2 23 11 LoFP9 10 39882 1 32197 17579 0.0006 5 4 TurbRolll 64 TurbRoll2 21 39842 1 32178 17615 0.0012 16-11_LoFP2 35 20AHSFWInj2 10 40708 1 31762 1,8413 0.0005 35 20A_HSFWInj2 37 24_HydroTestl 1 20956 1 13081 664055 0.0000 17 11_LoFP3 35 20A HSFWInj2 10 20399 1 12667 887275 0.0000 19 11 LoFP5 35 20A HSFWIni2 10 19602 1 12135 infinite 0.0000 TOTAL= 0.0571 File No.: VY-19Q-302 Page 10 of 12 Revision:
0 F0306-01RO 2 Structural Integrity Associates, Inc.Table 7: Fatigue Usage Results for Nozzle Corner Load Set A 2 2DesHydro 1 2 2DesHydrol 2 2DesHydro 1 2 2DesHydro 1 2 2DesHydrol 54 TurbRolll 3 2_DesHydro2 3 2_DesHydro2 3 2_DesHydro2 34 20AHSFWInj 1 34 20AHSFWInj 1 26 12_TGTrip2 21 11 LoFP7 26 12TGTrip2 2211 LoFP8 4 3 Startup 4 3 Startup 4 3 Startup 4 3 Startup 32 19_RedTo0pct 13 10_FWHBypl 13 10_FWHBypl 35 20AHSFWInj2 9 6 WklyRed 1 Load Set B 1611 LoFP2 2011 LoFP6 18 11 LoFP4 11 9_TurbTripl 54 TurbRolll 39 25 Unbolt 5 4 TurbRolll (23 11 LoFP9 34 20AHSFWInj 1 38 24_HydroTest2 36 21 Shutdown 3621 Shutdown 26 1-2 TGTrip2 31 14 SRVBlwdn 26 12_TGTrip2 26 12_TGTrip2 29 13_Overpr2 28 13_Overprl 32 19_RedTo0pct 33 20_HSHeatup 33 20_HSHeatup 35 20AHSFWInj2 37 24_HydroTestl 35 20A HSFWInj2 n 10 10 10 10 80 123 97 10 13 1 286 14 10 I 10 253 1 1 45 255 45 25 1 274 Sn, psi 65109 50344 50150 65712 64296 63308 61437 63138 49069 49097 49111 60379 49395 42902 32212 30212 30212 28966 24083 18765 19637 20388 19850 19341 Table 7: Fatigue Usage Results for Nozzle Corner Ký1 1 1 S.1t, psi 46047 43990 43205 43011 43008 41430 40391 40101 39657 39622 39616 38556 33091 27518 24687 23513 23513 19423 17665 12883 12679 12624 12359 11952 N 5655.78 6477.19 6832.83 6924.58 6925.97 7738.36 8343.98 8524.36 8810.73 8833.38 8837.88 9578.4 16015 28831 40237 46728 46728 111118 156402 761835 879615 914934 infinite.infinite TOTAL =Usage 0.0018 0.0015 0.0015 0.0014 0.0116 0.0159 0.0116 0.0012 0.0015 0.0001 0.0324 0.0015 0.0006 0.0000 0.0002 0.0054 0.0000 0.0000 0.0003 0.0003 0.0001 0.0000 0.0000 0.0000 0.0889 m .
6.0 CONCLUSION
S AND DISCUSSIONS A previously-developed FEM was analyzed using the ANSYS program. Thermal transient analysis was performed for each defined transient, and the thermal stresses were added to stresses due to,.pressure and piping loads, which were scaled based on the magnitudes of the pressure and piping loads. SCFs were applied as appropriate.
All six components of the stress tensor were used for stress calculations.
The fatigue calculation was performed at previously-examined locations, and used the methodology of Subarticle NB-3200 of Section III of the ASME Code.The 60-year CUF for the safe end location was determined to be 0.0571, and the CUF for the nozzle comer location was determined to be 0.0889. Both values are less than the ASME Code allowable value of 1.0.Environmental fatigueusage analysis will be performed in a separate calculation package.File No.: VY-19Q-302 Revision:
0 Page llofl2 F0306-01 RO Structural Integrity Associates, Inc.
7.0 REFERENCES
- 1. SI Calculation Package, Design Inputs and Methodology for ASME Code Confirmatory Fatigue Usage Analysis of Reactor Feedwater Nozzle, Revision 0, SI File No. VY- 19Q-301.2. ANSYS, Release 8.1 (w/Service Pack 1), ANSYS, Inc., June 2004.3. American Society of Mechanical Engineers, Boiler and Pressure Vessel Code,Section III, Subsection NB, 1998 Edition with Addenda through year 2000.4. SI Calculation Package, Feedwater Nozzle Finite Element Model and Heat Transfer Coefficients, Revision 0, SI File No. VY-10Q-301.
- 5. Entergy Document EC No. 1773, Revision 0 (Design Input Revision 1), Environmental Fatigue Analysis for Vermont Yankee Nuclear Power Station, SI File No. VY- 16Q-209.6. SI Calculation Package, Feedwater Nozzle Stress History Development for Green Functions, Revision 0, SI File No. VY-16Q-301.
- 7. VESLFAT, Version 1.42, 02/06/07, Structural Integrity Associates.
- 8. American Society of Mechanical Engineers, Boiler and Pressure Vessel Code,Section II, Part D, 1998 Edition with Addenda through year 2000.9. SI Calculation Package, Fatigue Analysis of Feedwater Nozzle, Revision 0, SI File No. VY- 16Q-302.File No.: VY-19Q-302 Page 12 of 12 Revision:
0 F0306-O1RO