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| number = ML081570606
| number = ML081570606
| issue date = 04/28/2008
| issue date = 04/28/2008
| title = 2008/04/28-New England Coalition, Inc., Contentions 2A and 2B Prefiled Exhibits, NEC-JH_03 - NEC-JH_24, Volume 1
| title = New England Coalition, Inc., Contentions 2A and 2B Prefiled Exhibits, NEC-JH_03 - NEC-JH_24, Volume 1
| author name = Hopenfeld J
| author name = Hopenfeld J
| author affiliation = New England Coalition, Inc
| author affiliation = New England Coalition, Inc
| addressee name = Karlin A S, Reed W H, Wardwell R E
| addressee name = Karlin A, Reed W, Wardwell R
| addressee affiliation = NRC/ASLBP
| addressee affiliation = NRC/ASLBP
| docket = 05000271
| docket = 05000271
Line 16: Line 16:


=Text=
=Text=
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION ATOMIC SAFETY AND LICENSING BOARD Before Administrative Judges: In the Matter of Alex S. Karlin, Chairman Dr. Richard E. Wardwell Dr. William H. Reed))ENTERGY NUCLEAR VERMONT YANKEE, LLC )and ENTERGY NUCLEAR OPERATIONS, INC. ))(vermont Yankee Nuclear Power Station) )Docket No. 50-271-LR ASLBP No. 06-849-03-LR NEW ENGLAND COALITION, INC.CONTENTIONS 2A and 2B PREFILED EXHIBITS NEC-JH 03- NEC-JH 24 April 28, 2008 Volume 1 NEC-JH_03'V Review of Entergy Nuclear Vermont Yankee, LLC and Entergy Nuclear Operations, Inc. ("Entergy")
{{#Wiki_filter:}}
Analyses of the Effects of Reactor Water Environment on Fatigue Life of Risk-significant Components During the Period of Extended Operation Dr. Joram Hopenfeld 1724 Yale Place Rockville, MD 20850 (301) 801-7480 April 21, 2008 TABLE OF CONTENTS I. B A C K G R O U N D ................................................................................
1 A .B asic T echnical Principles
............................................................
1 B. Regulatory Requirements
...........................................................
2 II. ENTERGY'S CUFen ANALYSES .........................................................
4 A .B rief H istory .................................................................
.........
4 III. ASSESSMENT OF ENTERGY'S CUFen REANALYSES
........................
8 A .Incom plete Inform ation ............................................................
8 B .E ntergy's A ssum ptions ...............................................................
9 C. Assessment of Assumptions
........................................................
10 1. Environmental Correction Factor, Fen ...................................
10 2. H eat T ransfer ..............................................................
12 3. B ase M etal C racks .........................................................
15 4. N um ber of Transients
......................................................
16 5. O xygen ...................................................................
16 6. G reen's F unction ...........................................................
17 D .L ack of E rror A nalysis ..............................................................
18 E. "Confirmatory" Analysis of Feedwater Nozzle ..................................
18 IV. HOPENFELD CUFen RECALCULATION
............................................
19 V .SU M M A R Y ....................................................................................
20 V I. R E F E R E N C E S .............................................................................
21 VII. GLOSSARY OF TERMS .................................................................
22 I. BACKGROUND A. Basic Technical Principles Fatigue is an age-related degradation mechanism caused by cyclic stressing of a component by either mechanical or thermal stresses that eventually cause the component to crack. Under such cyclic loading, a crack will be initiated and the component will fail under stresses that are, substantially lower than those that cause failure under static loadings.During each loading cycle, some fraction of the component's fatigue life is exhausted, its size depending on the magnitude of the applied stress.Eventually, after N cycles, the component's allowable fatigue life is fully expended.
The number of cycles n at any given stress amplitude divided by the corresponding N is called the usage fatigue factor. The cumulative usage fatigue factor, CUF, is simply a summation of the individual usage factors.ASME Code Section III requires that CUF must not exceed unity. The CUF is expressed as CUF Y nk INk The basic equation that describes the crack growth rate for a given stress intensity includes two empirical constants, C and x. A large data base exists on the empirical constants C and x, which was derived from laboratorytests mostly in air under controlled conditions.
This equation can predict crack growth reliably as long as it is used under the conditions that were used to calibrate C and x. This principle is very important in assessing how Entergy used laboratory data to calculate fatigue life of selected components at the VY plant.To account for the fact that crack propagation in water is different than in air, the individual usage factor in air is multiplied by a corresponding correction factor Fen. Fen is simply the ratio of the fatigue life in air at room temperature to the fatigue life in water at the local temperature.
The environmentally corrected CUF is defined as, CUFen = Fen (CUF)
Fen is derived from laboratory data on the effect of strain on fatigue life, i.e.the number of cycles to failure. NUREG/CR-6909 describes such laboratory tests in detail.The procedures to analyze components for fatigue are specified in Section III of the ASME Code. The Code provides fatigue curves for I various materials, which specify the allowable number of cycles for a given stress intensity.
The code requires that the CUF at any given location be maintained below one. Since the Code used data from laboratory tests with smooth specimens, the code made allowances (2 on stress and 20 on cycles)in recognition that a test specimen in air may have a longer fatigue life than actual components in a reactor. The most current ASME code also provides a simplified set of rules in Subparagraph NB-3600, and a more rigorous rule in Subparagraph NB- 3200, which is based on using a finite element analysis to calculate CUF values. Replacing the simplified analysis with a more detailed analysis has the advantage of removing unwanted conservatism from the results of the simplified analysis.
Since the detailed analysis may require a larger data base than the simplified analysis, the user must ascertain that the necessary data base exists. When such information is not available, and the user instead makes arbitrary assumptions, the benefit of the detailed analysis is completely negated.B. Regulatory Requirements 3 NRC regulation 10 CFR § 54.2 1(c) requires that each license renewal application must include "an evaluation of time-limited aging analyses" I ("TLAA") for components covered by the license renewal regulations.
1 If TLAAs are defined as: Those licensee calculations and analyses that: (1) Involve systems, structures, and components within the scope of license renewal, as delineated in § 54.4(a);(2) Consider the effects of aging;(3) Involve time-limited assumptions defined by the current operating term, for example, 40 years; i (4) Were determined to be relevant by the licensee in making a safety determination; (5) Involve conclusions or provide the basis for conclusions related to the capability of the system, structure and component to perform its intended functions, as delineated in § 54.4(b); and n 2 the applicant is unable to demonstrate that TLAAs "remain valid for the period of extended operation" or that they "have been projected to the end of the period of extended operation," it must demonstrate that "the effects of aging on the intended function(s) will be adequately managed for the period of extended operation." 10 C.F.R. 54.21 (c)(I)(i)-(iii).
NUREG- 1801, Rev. 1, Generic Aging Lessons Learned (GALL)Report (2005) ("NUREG- 1801") also provides guidance for the preparation of TLAAs.2 NUREG- 1801 advises that a license renewal applicant may address "the effects of the coolant environment on component fatigue life by assessing the impacts of the reactor coolant environment on a sample of critical components for the plant." Id., Vol. 2 at X M- 1. Examples of critical components are identified in NUREG/CR-6260, Application of NUREG/CR-5999 Interim Fatigue Curves to Selected Nuclear Power Plant Components (1995). The sample of critical components "can be evaluated by applying environmental life correction factors to the existing ASME Code fatigue analyses." NUREG-1801, Vol. 2 at X M-1. If these components are found not to comply with the acceptance criteria (i.e., CUF less than one), "corrective actions" must be taken that "include a review of additional affected reactor coolant pressure boundary locations." Id. at X M-2. As explained further in industry guidance document MRP-47: The locations evaluated in NUREG/CR-6260
[2] for the appropriate vendor/vintage plant should be evaluated on a plant-unique basis. For cases where acceptable fatigue results are demonstrated for these locations for 60 years of plant operation including environmental effects, additional evaluation or locations need not be considered.
However, plant-unique evaluations may show that some of the NUREG/CR-6260
[2] locations do not remain within allowable limits for 60 years of plant operation when environmental effects are considered.
In this situation, plant specific evaluations should expand (6) Are contained or incorporated by reference in the CLB [current licensing basis].2 NUREG- 1801 is referenced with approval in Regulatory Guide 1.188, Rev. 1, Standard Format and Content for Applications to Renew Nuclear Power Plant Operating Licenses (2005) ("Reg. Guide 1.188").3 I the sampling of locations accordingly to include other locations where m high usage factors might be a concern.3 II. ENTERGY'S CUFen ANALYSES A. Brief Historyi The VYNPS License Renewal Application (LRA) Table 4.3-3 summarizes Entergy's evaluation of effects of reactor water environment on the fatigue life of nine components for the period of extended operations.
The components selected correspond to the limiting locations identified in NUREG/CR-6260.
4 LRA Table 4.3-3 states that the environmentally corrected Cumulative Usage Factor (CUFen) of the following risk-significant reactor components will exceed unity: feedwater nozzle, RR inlet nozzle, RR outlet nozzle, RR piping tee, core spray nozzles, core spray safe end, and feedwater piping.To address this problem, Entergy chose to "refin[e]
the fatigue analyses to lower the predicted CUFs to less than 1.0." 5 Entergy's refinement of its CUFen analysis proceeded in two steps: (1) an initial reanalysis involving, in part, the use of a simplified Green's function method to calculate stress loads during plant transient operations; and (2) a"confirmatory" reanalysis of only the feedwater nozzle that did not involve 3 use of the simplified Green's function method. I have reviewed the reports of both Entergy's initial CUFen reanalysis, and its "confirmatory" reanalysis of the feedwater nozzle that Entergy produced to NEC.The five elements of Entergy's initial reanalysis included: I 3 MRP-47, Revision 1, Electric Power Research Institute, Materials Reliability Program: Guidelines for Addressing Fatigue Environmental Effects in a License Renewal Application at 3-4 (2005).4 Safety Evaluation Report Related to the License Renewal of Vermont Yankee Nuclear Power Station (February 2008)("FSER"), NRC Staff Exh_01 at 4-32.5 LRA at 4.3-7.6 These reports are submitted in this proceeding as Exhibits NEC-JH_04
-NEC-JH_21.
I 4 1
: 1. Development of a finite element model 2. Development of heat transfer coefficients
: 3. Development of Green Functions 4. Development of thermal transient definitions
: 5. Performance of Stress and Fatigue Analysis.Entergy reported the results of its initial reanalysis in the Table 1, reproduced below: TABLE 1 VYNPS Cumulative Usage Factors for NUREG/CR-6260 Limiting Locations 7 Material Overall*Environmental Environmentally NUREG-6260 Location Multiplier (Fen) Adiusted CUF I RPV vessel shell/ bottom head Low alloy steel 9.51 0.08 2 RPV shell at shroud support Low alloy steel 9.51 0.74 3 Feedwater nozzle forging blend radius Low alloy steel 10.05 0.64 4 RR Class 1 piping (return tee) Stainless steel 12.62 0.74 5 RR inlet nozzle forging Low alloy steel 7.74 0.50 6 RR inlet nozzle safe end Stainless steel 11.64 0.02 7 RR outlet nozzle forging Low alloy steel 7.74 0.08 8 Core spray nozzle forging blend radius' Low alloy steel 10.05 Q-044 0.1668 9 Feedwater piping riser to RPV nozzle Carbon steel 1.74 0.29 Effective multiplier for past and projected operating history, power level, and water chemistry.
The NRC Staff rejected Entergy's initial CUFen reanalysis.
As reported in the FSER, Entergy and the NRC Staff "were unable to resolve the issues raised [with respect to Entergy's use of Green's functions to calculate stress loads].'8 The NRC Staff therefore requested that Entergy perform, and Entergy did perform, the additional "confirmatory" CUFen analysis of the feedwater nozzle, using the ASME Code Section III, Subsection NB-3200 methodology to calculate the stress intensities "without referencing Green's function." 9' Exhibit NEC-JH_35 at Attachment 2.8 FSER, NRC Staff Exhibit 01 at 4-40.9 FSER, NRC Staff Exhibit 01 at 4-41; See also, Exhibit NEC-JH_22 (Summary of Meeting Held on January 8, 2008, Between the U.S. Nuclear Regulatory Commission Staff and Entergy Nuclear Operations, Inc. Representatives to Discuss the Response to a Request for Additional Information Pertaining to the Vermont Yankee Nuclear Power Station License Renewal Application).
5 At the February 7, 2008 meeting of the ACRS, which I attended, the NRC Staff informed the ACRS that it was satisfied with the CUFen calculations based on Entergy's then-reported "confirmatory" results for the feedwater nozzle. As reported in the FSER, however, during a subsequent February 14, 2008 audit of Entergy's confirmatory analysis, the NRC Staff requested that Entergy recalculate the feedwater nozzle CUFen yet again, substituting a different Fen value. Specifically, NRC Staff requested use of"the maximum Fen value used in [Entergy' s] previous analyses," rather than"different, but appropriate" Fen values Entergy had used in its"confirmatory" analysis.'
0 The following Table 2 summarizes how Entergy's reported CUFen values for the feedwater nozzle have changed with each iteration of its analysis.Table 2- CUFen Calculations For the Feedwater Nozzle REFERENCE CUF Fen CUFen License Renewal Application 0.750 3.81 2.86 Table 4.3-3 Entergy Initial CUFen Reanalysis 0.0636 10.05 0.6392 Using Simplified Green's Function.NEC Exhibit JH_18 at 3-18, Table 3-10.Entergy "Confirmatory" CUFen 0.0889 3.97 0.3531 Reanalysis.
NEC Exhibit JH 21 at 7, Table 1.Adjusted "Confirmatory" Reanalysis 0.8930 result verbally provided during February 14, 2008 NRC Staff audit of Entergy's "Confirmatory" Reanalysis.
FSER, NRC Staff Exhibit 1 at 4-42.A comparison of Entergy's result using the simplified Green's function method, 0.639, with its "confirmatory" result, ultimately 0.8930 as recalculated February 14, 2008, demonstrates that the simplified Green's I I I I I I I I I I I I I I I I I I"O FSER, NRC Staff Exhibit 01 at 4-42.6 function method underestimates CUF by about 40%. As reported in the FSER, the NRC Staff therefore concluded that "the results of the Green's function application using the specific software could underestimate CUF, and therefore cannot be the analysis of record." 1 1 The NRC Staff has designated Entergy's "confirmatory" analysis the"analysis of record" for the feedwater nozzle.'2 The NRC Staff has also recommended a license condition that would require Entergy to perform the"confirmatory" analysis for the spray (CS) and recirculation (RR) nozzles no later than two years before the start of the life extension period.13 The NRC Staff is now revisiting the sufficiency of environmentally-assisted fatigue analyses based on the simplified Green's function method, which the NRC had previously accepted in support of license renewal for plants other than Vermont Yankee. On April 18, 2008, the NRC Staff issued a Regulatory Issue Summary ("RIS"), requesting that "license renewal applicants that have used this simplified Green's function methodology perform confirmatory analyses to demonstrate that the simplified Green's function analyses provide acceptable results."'1 4 This RIS also states: "For plants with renewed licenses, the staff is considering additional regulatory actions if the simplified Green's function methodology was used."'1 5 On April 3, 2008, the NRC Staff issued a Notification of Information in Docket No. 50-219-LR (License Renewal for Oyster Creek Nuclear Generating Station), stating that it will require "confirmatory" fatigue analyses due to Oyster Creek's reliance on the simplified Green's function method.16"Id. at 4-43.I1d. at 4-43.13 Id.14 Exhibit NEC-JH-23 at 2.15 Id.16 Exhibit NEC-JH_24.
7 I III. ASSESSMENT OF ENTERGY's CUFen REANALYSES The following discussion explains my assessment of both Entergy's initial and "confirmatory" CUFen reanalyses.
Part A explains that Entergy I failed to produce information necessary to validate both analyses.
Part B lists key assumptions underlying both analyses.
Part C explains why, as a 3 results of Entergy's key assumptions, both analyses underestimated CUFen, and overestimated expected fatigue life. Part D discusses the significance of Entergy's failure to perform an error analysis.
Part E explains why the"confirmatory" analysis of the feedwater nozzle does not bound the analysis for other components.
A. Incomplete Information The materials Entergy has produced to NEC in the ASLB proceeding do not include all the information necessary to establish the validity of Entergy's CUFen reanalyses, initial or "confirmatory." Specifically, Entergy has not provided: 1. Adequate layout drawings of the plant piping. Based on the information provided, I cannot determine how the connecting pipes are n oriented with respect to the nozzles; how many diameters the pipe is straight upstream of each nozzle; or whether there are any discontinuities, such as welds, upstream of the nozzle.1 7 This information is necessary to validate I the assumption of uniform heat transfer distribution.
: 2. A complete description of the methods or models used to determine velocities and temperatures during transients.
For example, the following discussion appears in the Structural Integrity Associates, Inc.("SIA") report of Entergy's initial CUFen reanalysis, VY-16Q-307:
The internal heat transfer coefficient h for the transients with I flow occurring in the pipe is calculated based on the following relation for forced convection:
Il7 Exhibit NEC-JH_25 is illustrative of the layout drawings Entergy produced to NEC.I 8!
h = 0.023 Re 0.8 Pr 0.4 k/D Where Re Reynolds'number Pr Prandtl number k Thermal conductivity D Pipe diameter The heat transfer coefficients were calculated by PIPESTRESS using the above relation.
The flow rates described for each transient in Section 3 were used. For the transients where flow is stopped, the natural convection heat transfer coefficient was used. The formula for h is: h=0.55 (Gr Pr) 025 k/L Where Gr = Grashof Number L = Pipe diameter PIPESTRESS only has the forced convection heat transfer formula built in, so an equivalent flow rate was determined that would give the same heat transfer coefficient as the free convection coefficient.'
8 I cannot determine, based on this discussion, how this was done when the flow goes to zero. I discuss this issue in more detail in Part III(C)(2) of this report.B. Entergy's Assumptions Both Entergy's Initial and "Confirmatory" CUFen Reanalyses incorporated the following assumptions:
: 1. The environmental correction factor, Fen, depends only on the temperature, the dissolved oxygen, the sulphur content and the strain rate.18 Exhibit NEC-JH_10 at 12-13 (emphasis added).9
: 2. With respect to determination of the heat transfer coefficients in all I three nozzles: I a. Nozzle entrance and exit effects can be neglected b. Water properties do not change with temperature
: c. Uniform circumferentially.
: 3. The base metal under the cladding at the feedwater blend radius has no cracks.4. The number of transients will increase linearly with time during the I life extension period.'9 It was assumed that the 40-year CUFs can be multiplied by 1.5 to project those values to the end of the 60 year extended period.5. The oxygen at the surface of any component can be evaluated based I on plant records, using the EPRI -BWRVIA computer code.Entergy's Initial CUFen Reanalysis also included the following additional assumption:
: 6. Green's functions can be used as a substitute for the ASME Code Section III, Subsection NB-3200 method.C. Assessment of Assumptions Entergy's above-stated assumptions resulted in the underestimation of CUFen, and the overestimation of expected fatigue life, for the following reasons.1. Environmental Correction Factor, Fen i Entergy calculated the Fen parameters based on outdated Argonne 3 National Laboratory (ANL) statistical equations stated in N-UREG/CR 6583 and NUREG/CR 5704 ("the NUREG equations"), which were derived more'9 Exhibit NEC-JH 18 at 3-18, note 2 (CUF results based on "actual cycles accumulated I to-date and projected to 60 years.").I 10 than nine years ago. In February 2007, ANL updated the previous data and published its results in NUREG/CR-6909.
2' The revised ANL equations are based on a much larger database and the limits of their applicability is more clearly stated.The developer of the revised ANL equations, 0. Chopra, stated to the ACRS: To apply the laboratory data to actual reactor components, we need to adjust these results to account for parameters or variables which we know affect fatigue life but are not included in this data. And these variables are mean stress, surface finish, size, and loading history.2 2 This same caveat is repeated in NUREG/CR-6909.
To account for uncertainties, the NUREG report states: "Under certain environmental and loading conditions, fatigue lives in water relative to those in air can be a factor ofz12 lower for austenitic stainless steels, z3 lower for Ni-Cr-Fe alloys, and z17 lower for carbon and low-alloy steels." NUREG/CR-6909 at 62.23 Entergy did not provide any data on the surface roughness of the components it evaluated.
The ANL equations were developed using a crack free, smooth specimen.
In comparison to a smooth surface, a rough surface 24 would reduce the fatigue life by a factor of 3. Since most of the components Entergy evaluated were fabricated from carbon or low alloy steel, they are susceptible to flow accelerated corrosion, FAC, which characteristically increases surface roughness.
In the case of the VY 20 Exhibit NEC-JH_18 at 3-1.21 Exhibit NEC-JH_26.
22 Exhibit NEC-JH_27 at 22.23 Exhibit NEC-JH_26 at 62.24 Exhibit NEC-JH_26 at 14.11 I feedwater nozzle, the existence of surface cracks at the blend radius both in I the clad and the base metal is another factor that must be considered (see Comment 3 below).Because of the above uncertainties, I believe that it is appropriate to use a factor of 17, at a minimum, to correct the CUFs for environmental n effects.I At the February 7, 2008 ACRS meeting, which I attended, in response to an ACRS member question as to why Entergy is allowed to use old fatigue data, the NRC staff stated only that it has traditionally used the old data in approving LRAs and did not want to change the procedures at this time.2 5 The Staff stated that the new data will apply to new reactor applications.
2 6 It would appear that it would be equally important, if not more important, to apply the new data to a 40 year reactor.2. Heat Transfer Entergy used the following heat transfer equations to calculate the thermal stress for each transient:
: 1. h 0.023 (Re )-8 (Pr).4 k/D 2 7 2. h 0.55 (GrPr)2 5 k/L 28 U 3. h= 0.555 ( R ( R-Rs)gk 3 hfg/ ( ud del T ) ).25 (R=-rho, u =mu)2 9  i Equation I is applicable only to a fully developed turbulent flow, constant fluid properties in pipes. The flow in all three nozzles is not the same as in a straight pipe because the nozzle is relatively short and it 25 Exhibit NEC-JH_28 at 96-97.26 Id.27 Exhibit NEC-JH_04 at 11, Table 4. 1 28 Exhibit NEC-JH_14 at 14.29 Exhibit NEC-JH_19 at 7.I 12 [
contains discontinuities.
It is difficult to see how the flow could be fully developed, especially at the exit from the nozzle at the blend radius area (Region 6).3o Nevertheless, depending on the Reynolds number and the distance from the inlet to the nozzle, the heat transfer can be either above or below the value specified by Equation 1. Plots for calculating the heat transfer at the entrance section of pipes can be found on page 212 of Reference 2.31 Equation 1 also must be corrected by the ratio of the viscosities evaluated at the bulk and wall temperatures during each transient.
Page 212 of Reference 2 also provides such a correction.
3 2 To justify the use of the axixsymetrical model, Entergy must first show that the flow upstream of each nozzle is fully developed at the entrance to the nozzle and its main axis coincides with the axis of.. .. ....the nozzle. As shown in Reference 3 and the above sketch, the velocity distribution in the nozzle will vary circumferentially.
3 3 Such flow distribution would lead to circumferentially varying wall temperature and different stress distribution than would be predicted by an axixsymetrical model.To my knowledge, Entergy has not provided to NEC the complete piping layout as it exists now in the plant. Unless special precautions were 30 See, Exhibit NEC-JH_04 at 16.31 Exhibit NEC-JH_29.
32 Id." Exhibit NEC-JH_30.
13 I taken during installation, one must assume that the connecting pipe is at u some angle with respect to the nozzle and therefore the axixsymetrical assumption is not valid.Equation 2 is used to calculate average heat transfer coefficients when the flow is driven by gravitational forces. This equation is not appropriate I for applications where one is required to determine local stress distributions along the pipe and not average stress distributions.
Equation 2 does not apply because, for some transients, the forced convection internal flow in pipes stops, and the flow becomes driven by I gravity forces.3 4 Based on physical considerations, the flow does not just suddenly go from forced convection to natural convection, but it rather goes through a mixed forced/free convection region. In the free convection region, the flow is driven by gravity forces and its fundamental characteristic is commonly described by a flow down a vertical plate where both the velocity and the heat transfer coefficient vary with the height of the plate.The natural convection flow inside a pipe is more complex and'is based on empirical correlations of the average heat transfer coefficient such as given in Equation 2 for laminar flow. This equation does not describe the variation in the heat transfer coefficient, and the stresses, along the pipe.The following statement quoted from one report of Entergy's initial CUFen reanalysis demonstrates that Entergy ignored the inherently local feature of natural convection:
PIPESTRESS only has the forced convection heat transfer formula built in, so an equivalent flow rate was determined that would give the same forced convection heat transfer coefficient as the free convection heat transfer coefficient.
3 5 Such a procedure is appropriate for the determination of overall heat balances but not for the determination of stress distributions., In my opinion, the stress analysis should not be dictated by what is available in a given computer program; it should be driven by the nature of the problem.14 Exhibit NEC-JH_14 at 14.35 Id.14 Equation 3 is an empirical equation for the average heat transfer coefficient during condensation of refrigerants at low laminar velocities.
For higher flow rates, a different equation must be used. Entergy did not specify that the flow in the nozzle was laminar. More importantly, to calculate the temperature distribution in the nozzle, one must use local heat transfer coefficients, not average values. Average heat transfer coefficients can only be used to calculate overall heat balances, not local temperatures.
Entergy's CUFen results are based on the assumption that the stresses are axixsymetric in all nozzles. As shown on page 26 of SIA report VY-16Q-3 10, the stress in a given nozzle is very sensitive to the heat transfer coefficient.
3 6 Throughout its analyses, Entergy used location-independent heat transfer coefficients, which is inappropriate, as I have explained in the above discussion.
: 3. Base Metal Cracks In the late 1970s, the feedwater nozzles of most BWR plants developed cracks due to high cycle fatigue because of differences in the thermal properties of the cladding and the base metal. The cladding was removed from most BWR plants, with the exception of Vermont Yankee and a few others. NUREG-0609.
In the Millstone I plant, some cracks penetrated to 1/3' at the blend radius area. Because the cladding is 5/16" thick and high cycle fatigue cracks propagate to depths of about 1/4" or more, the base metal may contain cracks, especially after 40 years of service. Id.In RAI 4.3-H-02, VY admitted that the cladding may contain cracks, 3 7 but has not provided any data to indicate that these cracks did not penetrate the base metal. They did, however, admit to the possibility that such cracks will penetrate the base metal. The 2001 inspection of the feedwater nozzles only indicates that the results were "acceptable".
3 8 Since Ultrasonic Inspection, UT, measures only the total length of a crack and, based on the VY drawings Entergy has produced, the exact thickness of the clad is not known, 3 9 36 Exhibit NEC-JH_13 at 26.37 Exhibit NEC-JH_32.
38 Exhibit NEC-JH_33 at 4.39 Exhibit NEC-JH_25.
15 n Entergy has not provided any proof that the base metal is not cracked. One i therefore must assume that the base metal is cracked and account for these cracks in the ASME Code analysis.
The ASME Section III, NB 3122.3 does i not require Entergy to include the cladding in the structural analysis because the cladding is less than 10% of wall thickness.
When, however, subsurface cracks are known to exist, they can not be ignored in the ASME Code analysis, and must be included together with the cladding.4. Number of Transients Entergy's apparent assumption that the number of transients the plant i would experience varies linearly with time must be challenged.
The failure frequency of pressure vessels (and mechanical and electrical components) is n statistically very high later in life due to aging of the plant. The recent VYNPS 20% power uprate introduced new stresses on already aging components, and will likely increase the number of unanticipated transients, as demonstrated by the August, 2007 collapse of the VYNPS cooling tower and plant shutdown due to a steam valve failure. VYNPS experienced two unanticipated transients within 10 days in late August 2007. Based on this experience and the assumption of linearity, one could predict 912 transients during the next 25 years. The above extreme case illustrates that Entergy must consider a more conservative number of transients than predicted by the linear formula to project the number of transients during the extended3 period of operation.
Entergy provided no justification for selecting a non-conservative i factor for projecting the number of transients.
In my opinion, the number of transients proposed by Entergy should be at a minimum multiplied by 1.2 to account for the probability of an increase in unanticipated failures due to the 20% power uprate. 3 5. Oxygen I Even though the Fen varies exponentially with oxygen concentration, Entergy did not discuss the reasons for not including unanticipated changes in water chemistry (oxygen excursions) during the extended period. Nor did I they explain how the chemistry data from the feedwater line or the 1 16 i electrochemical potential measurements relate to the oxygen concentration at the component surface during transients.
Only in February 2008, in response to an NRC Staff request for information concerning how Entergy's CUFen analysis accounted for water chemistry effects, Energy stated for the first time that the EPRI -BWRVIA computer code was used at VY to assess the oxygen concentration at the surface of a given component.
4 0 NRC requires that analytical codes be assessed and benchmarked against measured plant data. Safety Evaluation by the Office of Nuclear Reactor Regulation Related to Amendment No. 229 to Facility Operating License No. DPR-28, Entergy Nuclear Vermont Yankee, LLC and Entergy Nuclear Operations, Inc., Vermont Yankee Nuclear Power Station, Docket No. 50-271 § 2.8.7.1.41 A code is only considered valid within the range in which the data was provided.4 2 Entergy did not describe how the BWRVIA code was benchmarked.
The oxygen concentration at the surface of any given component can only be estimated by considering the kinetics of oxide buildup and dissolution throughout the plant. Since Entergy has not described the algorithm in the BWRVIA code, one must assume that the oxygen concentrations that were used by Entergy to calculate the Fens contain unknown errors.6. Green's Function In its initial analysis, Entergy applied a simplified Green's function method to calculate stresses for each transient, instead of using the ASME Code, Section III, Subsection NB-3200 approach.4 3 The Green's function is a powerful tool that, when properly applied, can considerably reduce the cost of the ASME code analysis, especially when the number of transients is 40 Exhibit NEC-JH_34 at Attachment 2.41 Exhibit NEC-JH_ 35.42 Id.43 See, e.g., Exhibit NEC-JH_04.
17 very large. The Green's function is also, however, an approximate technique in comparison to the NB-3200 methodology, which may introduce errors in the final calculations of the CUF.As discussed in Part II(A) of this report, a comparison of Entergy's results using the simplified Green's function method with the results of its"confirmatory" analysis for the feedwater nozzle demonstrate that the Green's function method underestimated CUF by about forty percent. For this reason, also as discussed in Part II(A) of this report, the NRC Staff rejected Entergy's initial CUFen analysis.
3 D. Lack of Error Analysis To validate its analytical techniques, Entergy should have performed an error analysis to show the admissible range for each variable.
Based on the reports of Entergy's CUFen reanalyses produced to NEC, 4 4 it has not done so. The lack of error analysis is troubling.
For example, Entergy reported a CUFen of 0.74 for the RHR Class 1 piping (Table 1, above). In i light of the fact that data scatter in fatigue studies often exceeds an order of magnitude, the value of 0.74 without an error band has little significance and imparts little confidence that fatigue failure will not occur.E. "Confirmatory" Analysis of Feedwater Nozzle I I have reviewed the reports produced to NEC of the additional"confirmatory" CUFen analysis of the feedwater nozzle that Entergy conducted at the request of the NRC Staff.4 5 This analysis contains all of the errors in calculation of both CUF and Fen values that I have discussed in Part IlI(C) above, except that the simplified Green's function method was not used.Even if it were valid, I do not agree that the "confirmatory" analysis would bound the analysis for components other than the feedwater nozzle. 3 There are considerable differences in geometry, heat transfer characteristics, and loadings between the feedwater and the other two nozzles. These differences could result in different stress distributions which would affect 14 Exhibits NEC-JH_04
-NEC-JH-_21.
5 Exhibits NEC-JH 19 -NEC-JH 21.I 18i the CUFs. Entergy did not discuss these differences; instead it only provided the following vague and unscientific statement:
The analysis of the feedwater nozzle is bounding for the core spray and recirculation outlet nozzles since the calculated usage factors are at least 70% less than those for the feedwater nozzle and the number and severity of thermal transients are less.4 6 The statement that the feedwater nozzle results are bounding could only be justified if Entergy had demonstrated an understanding of the reasons for the differences in the CUFs obtained by the simplified Green's function analysis and those that were obtained by the more exact classical ASME analysis.
Entergy was not able to do so.IV. HOPENFELD CUFen RECALCULATION The CUFens calculated by Entergy, with and without the simplified Green's function method, contain error and they are unreliable.
An alternative to these calculations is to use the conservative CUFs as were originally provided in LRA and multiply them by the bounding values given in NUREG/CR-6909.
The results of this procedure are given below in Table 3.46 Exhibit NEC-JH 35 at Attachment 1.19 I I I TABLE 3 -Recalculated Cumulative Usage Factors for Sample Locations at VYNPS U.No. NUREG/CR-6260 Sample Location (License Renewal Application, Table 4.3-3)1 Vessel shell & bottom head CUF (VYNPS Lice Renewal Applicati(Table 4.3-3)0.400:nse Fen)n, (Ref. 1)17 12 Recalculated CUFen 6.80 -2'3 4 65 16 U i Core spray safe end Feed water nozzle RHR return Piping 0.182 2.18 12.75 is 0.750 17 i -M 0.032 r ------- ---12 17 0.38 10.37 I i RR inlet nozzle 0.610: RR piping tee 0.397 F ]17 1 RR outlet nozzle 8 Core spray nozzle* 9 iFeed water piping 0.810 12 17 17 4.76 I 13.77 10.62 0.625 I 0.427 17 7.26 V.
 
==SUMMARY==
By introducing five key assumptions, excluding those connected with use of the Green's function methodology, Entergy purports to show that the CUFens for all NUREG/CR-6260 limiting locations are less than one. My assessment demonstrates that Entergy ignored critical factors in making its assumptions.
When these assumptions are lifted and more appropriate and conservative assumptions are introduced, the CUFen for all but one of the components exceeds unity.Entergy has not demonstrated that the predicted fatigue life of risk-significant components at VY will meet the ASME criteria for safe operation for the extended period of operation.
Neither Entergy's initial analysis nor its "confirmatory" analysis demonstrate that CUFens for the components listed in License Renewal Application 4.3-3 or NUREG/CR-6260 limiting locations are less than one. It is my opinion that acceptance of Entergy's results will lead to an unjustified reduction in the scope of fatigue monitoring at the Vermont Yankee plant.20 U I I I I I I I I I Entergy should be required to develop a valid methodology for calculating CUFen; expand its fatigue analysis to components in addition to the NUREG/CR-6260 locations if a valid CUFen analysis indicates that CUFen for any NUREG/CR-6260 location will exceed unity; and formulate a meaningful plan to properly inspect and maintain all components which are susceptible to fatigue.VI. REFERENCES
: 1. J. P. Holman, Heat Transfer, 1981 Ed.nd 2. E. R. G. Eckert and R. Drake, Heat and Mass Transfer 2' , Ed 1959.3. H. Schlichting, Boundary Layer Theory, 4th Ed. 1960.4. NUREG/CR-6909, "Effect of LWR coolant Environment on Fatigue Life of Reactor Materials" (Final Report), ANL -06/08 U.S. NRC, Wash., D.C. Feb. 2007.5. NUREG/CR-6583, "Effect of LWR Coolant Environment on Fatigue-Design Curves of Carbon and Low Alloy Steels," March 1998.6. NUREG/CR 5704, "Effect of LWR Coolant Environments on Fatigue Design Curves of Austenitic Stainless Steel," April 1999.7. NUREG/CR-6936, "Probability of Failure and Uncertainty Estimate for Passive Components
-A Literature Survey," May 2007.21 VII. GLOSSARY OF TERMS Cumulative Usage Factor (CUF) -A summation of usage fatigue factors.Fatigue -- An age-related degradation mechanism caused by cyclic stressing of a component by either mechanical or thermal stresses that eventually cause the component to crack Feedwater Nozzle- A short pipe welded to the reactor vessel through which feedwater enters the vessel. I Fen -An environmental correction factor used to account for differences between fatigue in water and fatigue in air, defined as the ratio of the fatigue life in air at room temperature to that in water at the service temperature.
Green's Function -A simplified numerical technique for thermal stress calculations.
n Laminar Flow -Sometimes known as streamline flow, it occurs when a fluid flows in parallel layers, with no disruption between layers.Recirculation Nozzle -A short pipe welded to the reactor vessel through n which water flow either in or out of the jet pump.Spray Nozzle -A nozzle on top of the vessel used to cool the core in case of I an accident.Transient
-Plant response to a change in power level.Turbulent Flow -Fluid (gas or liquid) flow in which the fluid undergoes I irregular fluctuations or mixing, in contrast to laminar flow, in which the fluid moves in smooth paths or layers. In turbulent flow, the speed of the 3 fluid at a point is continuously undergoing changes in both magnitude and direction.
Usage Fatigue Factor -- The number of cycles n at any given stress amplitude divided by the corresponding number of cycles to end of life, N.2 22 Structural Integrity Associates, Inc. File No.: VY-16Q-301 NEC-JH_04 CALCULATION PACKAGE 'Project No.: VY-i6Q PROJECT NAME: Environmental Fatigue Analysis of VYNPS CONTRACT NO.: 10150394 CLIENT: PLANT: Entergy Nuclear Operations, Inc Vermont Yankee Nuclear Power Station CALCULATION TITLE: Feedwater Nozzle Stress History Development for Green Functions Document Affected Project Manager Preparer(s)
&Revision Pages Revision Description
.Approval.
Checker(s)
Signature
& Date Signatures&
Date 0 1-27, Initial Issue Terry J. Herrmann Appendix:
07/12/2007
-, Al-A2 Minghao Qin 07/11/07 John F. Staples 07/11/07 Page 1 of 27 F0306-O I RO Structural Integrity Associates, Inc.Table of Contents 1.0 O BJECTIV E ........................
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4 2.0 FEEDWATER NOZZLE MODEL ......................................................................................
4 3.0 A PPL IE D L O A D S .......................................................................
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4 4.0 THERMAL AND PRESSURE LOAD RESULTS ...............................
7 5.0 R E FE RE N C E S ...........................................................................
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9 APPENDIX A FINITE ELEMENT ANALYSIS FILES .............................
Al List of Tables Table 1: M aterial Properties
@ 300'F ..........................................................................................
10 Table 2: Nodal Force Calculation for End Cap Load ................
0........................................................
10 T able 3: Pressure R esults ....................................................................................................................
11 Table 4: Heat Transfer Coefficients for Region 1 (40% Flow) ...................................
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11 I I I I I I I I I I I I I I I I I I I File No.: VY-16Q-301 Revision:
0 Page 2 of 27 F0306-01 RO Structural Integrity Associates, Inc.I! i Aist of Figures Figure 1: ANSYS Finite Element M odel .........................
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12 Figure 2: Feedwater Nozzle Internal Pressure Distribution
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13 Figure 3: Feedwater Nozzle Pressure Cap Load..........................................................................
14 Figure 4: Feedwater Nozzle Vessel Boundary Conditions
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15 Figure 5: Nozzle and Vessel Wall Thermal and Heat Transfer Boundaries
[1] .........
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16 Figure 6: Safe End Critical Thermal Stress Location ...........
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17 Figure 7: Safe End Limiting Linearized Stress Paths ..................................................................
18 Figure 8: Blend Radius Limiting Pressure Stress Location...............................
19 Figure 9: Blend Radius Linearized Stress Path ..............................................................................
20 Figure 10: Safe End 100% Flow Total Stress Intensity
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21 Figure 11: Blend Radius 100% Flow Total Stress Intensity..............................
21 Figure 12: Safe End Total Stress History for 100% Flow .......................................
22 Figure 13: Safe End Membrane Plus Bending Stress History for 100% Flow ......................
I ...........
22 Figure 14:. Safe End Total Stress History for 40% Flow;...........................................................
23 Figure 15: Safe End Membrane Plus Bending Stress History for 40% Flow .............................
..... 23 Figure 16: Safe End Total Stress History for 25% Flow.............................................................
24 Figure 17: Safe End Membrane Plus Bending Stress History for 25% Flow ............................
24 Figure 18: Blend Radius Total Stress History for 100% Flow ..........................
25 Figure 19: Blend Radius Membrane Plus Bending Stress History for 100% Flow ......................
25 Figure 20: Blend Radius Total Stress History for 40% Flow ...........................
26.Figure 21: Blend Radius Membrane Plus Bending Stress History for 40% Flow ........................
26 Figure 22: Blend Radius Total Stress History for 25% Flow ........................................................
27 Figure 23: Blend Radius Membrane Plus Bending Stress History for 25% Flow ........................
27 File No.: VY-16Q-301 Revision:
0 Page 3 of 27 F0306-01 RO Structural Integrity Associates, Inc..1.0 OBJECTIVE The objective of this calculation is to compute the pressure stresses, thermal stresses, and the Green's Functions for high (100%), mid (40%), and low (25%) flow thermal loading of the Vermont Yankee Nuclear. Power Station feedwater nozzle.2.0 FEEDWATER NOZZLE MODEL An axisymmetric.
finite element model of the feedwater nozzle was developed in Reference
[1] using ANSYS [2]. The geometry used in Reference
[1] was utilized in this calculation.
The material properties are taken at an average temperature of 3007F. This average temperature is based on a thermal shock of 500F to 100°F which will be applied to the FE model for Green's Function development.
Table 1 listed the material properties at 300TF. The meshed model is shown in Figure 3.0 APPLIED LOADS Both pressure and thermal loads will be applied to the finite element model.3.1 Pressure Load A uniform pressure of 1000 psi was applied along the inside surface of the feedwater nozzle and the vessel wall. A pressure load of 1000 psi was used because it is easily scaled up or down to account for different pressures that occur during transients.
In addition, a cap load was applied to. the piping at the end of the nozzle. Since only nodes were modeled, the nodal forces shown in Table 2 are defined by the following equation: Feimenien
= r(IR)2 P -)where: P = Pressure 1,000 psi IR = Inner Radius 4.8345 in OR = Outer Radius 5.42 in Ri = Inside Radius of element that node is attached to R 0 = Outside Radius of element that node is attached to Fnode = The average of the element forces on either side of the node..Note.: The force on the innermost and outermost nodes is calculated as one half of the force on the element that they are attached to. I The calculated nodal forces were applied as positive values so they would exert tension on the end of the model. The ANSYS input file FWPVY.INP, in the computer files, contains the feedwater File No.: VY-16Q-301 Page 4 of 27 I Revision:
0 F0306-OIRO m
I V Structural Integrity Associates, Inc.nozzle geometry as well as the pressure Ic distribution, cap load, and symmetry conc)ading. Figures 2, 3, and 4 show the internal pressure lition applied to the vessel end of the model, respectively.
 
===3.2 Thermal===
Load Thermal loads are applied to the feedwater nozzle model. The heat transfer coefficients after power uprate were determined from Reference
[1]. These values were determined for various regions of the finite element model for 100% (4,590 GPM), and 25% (1,148 GPM) [1]. The annulus leakage flow rate is assumed to be 25 GPM for non-EPU conditions and 31 GPM for EPU conditions.
The 25 GPM value is calculated by scaling the 23 GPM [Page 6, 4] value up by approximately 9%. The 23 GPM value is scaled up to provide some conservatism and allow for inaccuracies in the determination of leakage flow. The .31 GPM value is calculated by multiplying the 25 GPM value by 1.25 [Page 6, 4]. Based on this, the annulus leakage flow rate is assumed to be 8 GPM for EPU conditions with 25% flow rate. The temperatures used are based upon a thermal shock from 500F to 100°F. An additional 40% flow rate (1836 GPM and 13.GPM) was added in this calculation.
3.2.1 Heat Transfer Coefficients Referring to Figure 5, heat transfer coefficients were applied as following:
Region 1 The heat transfer coefficient, h. for 100% flow is 3705 BTU/hr-ft 2-OF at 300 0 F. [1, Table 5]The heat transfer coefficient, h, for 40% flow is 1780 BTU/hr-ft 2-OF at 300TF. [Table 4]The heat transfer coefficient, h, for 25% flow is 1222.2 BTU/hr-ft 2-OF at 300 0 F. [1, Table 4]Region 2 Per Reference
[1], the heat transfer coefficient for Region 2 (safe end-to-thermal sleeve contact region) should be linearly transitioned from the value of the heat transfer coefficient used in Region 1 to the value used in Region 3.Region 3 The heat transfer coefficient, h, for 100% flow is 1489 BTU/hr-ftZ-°F at 300 0 F. [1, Table 9]The heat transfer coefficient, h, for 40% flow is 743 BTU/hr-ft 2 -F at 300TF. [1, Table 9]The heat transfer coefficient, h, for 25% flow is 504 BTU/hr-fi 2 -F at 300 0 F. [1, Table 9]Region 4 File No.: VY-16Q-301 Revision:
0 Page 5 of 27 F0306-01 RO Structural Integrity Associates, Inc. 1 Per Reference
[I], the he heat transfer coefficient for Region 4 (thermal sleeve transition in I diameter) should be linearly transitioned from the value of the heat transfer coefficient used in Region 3 to the value used in Region 5.Region 5 The heat transfer coefficient, h, for 100% flow is 177.4 BTU/hr-ft 2-F at 300 0 17. [1, Table 16]The heat transfer coefficient, h, for 40% flow is 88.5 BTU/hr-ft 2-°F at 300 0 F. [1, Table 16]The heat transfer coefficient, h, for 25% flow is 60 BTU/hr-ft 2_-F at 300TF. [1, Table 16]Region 6 Per Reference
[1], the heat transfer coefficient for Region 6 (nozzle inner blend radius)should be linearly transitioned from the value of the heat transfer coefficient used in Region 5 to the value used in Region 7.Region 7 Per Reference
[1], the heat transfer coefficient for Region 7 (reactor vessel inside wall) is a .constant of 864 BTU/hr-ft 2 o-F. This value is consistent with the feedwater nozzle work performed in the past for VY and should be used for all reactor conditions.
3 Region 8 The heat transfer coefficient, h, is 0.2 BTU/hr-ft 2-OF [1].3.2.2 Boundary Fluid Temperatures For the Green's Functions, a 500°F -100I F thermal shock is run to determine the stress response to a one-degree change in temperature.
The following temperatures are valid when there is water flow. Values between defined points are linearly interpolated.
For the 100%, 40%, and 25% flow cases, the thermal shock is run as follows: Regions I to5 5 T = 500°F -100WF Region 6 u Linearly transitioned from the value of the temperature used in Region 5 to the value used in Region 7 Region 7 T =500°F Region 8 T= 120°F File No.: VY-16Q-301 Page 6 of 27 I Revision:
0 F0306-OI RO I UStructural Integrity Associates, Inc.I 4.0, THERMAL AND PRESSURE LOAD RESULTS I The three flow dependent thermal load cases outlined in Section 3.0 were run on the finite element model. Appendix A contains the thermal transient input files FWT-VY_100.INP, FWTVY_40.INP, and FWTVY_25.INP for 100%, 40%, and 25% full flow rate, respectively.
The three flow dependent input files for the stress runs are also included in Appendix A. The stress filenames are FWSVY_100.INP, FWSVY_40.INP, and FWSVY 25.INP for 100%, 40%, and 25% full flow rate, respectively.
* The critical safe end location was chosen as node 192, which has the highest stress intensity due to* thermal loading under high flow conditions.
As shown in Figures 6 and 7, Node 192 is located on the inside diameter of the nozzle safe end of the model and the maximum stress occurs at 1.4 3 seconds.The critical blend radius location was chosen, based upon the highest pressure stress.Conservatively assuming the cladding has cracked, the critical location is selected as node 657 at base metal of the nozzle, as shown in Figures 8 and 9.The stress intensity for use in the Green's functions are calculated from the component stresses (X, Y, and Z) and compared to the stress intensity reported by ANSYS. As seen in Figure 10, the Z-X calculated total stress intensity best matches the ANSYS reported stress intensity for 100% flow at the safe end. Therefore, the Z-X stress will be used for the total and membrane plus bending Green's functions for all flow rates for the safe end. As seen in Figure 11, the Z-X calculated total stress intensity best matches the ANSYS reported stress intensity for 100% flow at the blend radius* in very beginning.
Therefore, the Z-X stress will be used for the total and membrane plus bending Green's functions for all flow rates for the blend radius.The stress time history for the critical paths was extracted during the stress run for 100% flow rate.* This produced two files, HFSE.OUT and HFBLEND.OUT, which contain the thermalstress history.The membrane plus bending stresses and total stresses for the Green's Functions were extracted.
from these files to produce the files HFSEInside.RED and HFBLENDInside.RED, where SE and.BLEND corresponded to the safe end and blend radius locations, respectively.
The stress time history for the critical paths was extracted during, the stress run for 40% flow rate.This produced two files, MFSE.OUT and MFBLEND.OUT, which contain the thermal stress history. The membrane plus bending stresses and total stresses for the Green's Functions were I extracted from these files to produce the files MFSEInside.RED and MFBLENDJnside.RED where SE and BLEND corresponded to the safe end and blend radius locations, respectively.
I The stress time history for the critical paths was extracted during the stress run for 25% flow rate.This produced two files, LFSE.OUT and LFBLEND.OUT, which contain the thermal stress history.The membrane plus bending stresses and total stresses for the Green's Functions were extracted from these files to produce the files LFSEInside.RED and LFBLENDInside.RED, where SE and BLEND corresponded to the safe endand blend radius locations, respectively.
I File No.: VY-16Q-301 Page 7 of 27 Revision:
0 F0306-OIRO Structural Integrity Associates, Inc. n As the models were run with a 400'F step change in temperature, and the Green's Functions are for a 1VF step change in temperature, all data values were divided by 400. The governing Green's Functions for the feedwater nozzle during 100% flow, 40% flow, and 25% flow are shown in Figures 12 to 23. The data for the Green's Functions is included in the files HFBRM+B-Green.xls, HFBRT-Green.xls, HFSEM+B-Green.xls, HFSET-Green.xls, MFBR M+B-Green.xls, MFBRT-Green.xls, MFSEM+B-Green.xls, MFSE_T-Green.xls, LFBRM+B-Green.xls, LFBRT-Green.xls,LFSE_M+B-Green.xls, and LFSET-Green.xls in the project Files. Where HF, MF, and LF corresponded to 100% flow, 40% flow, and 25% flow rate, respectively.
M+B and T corresponded to membrane plus bending stress and total stress, respectively.
.The pressure stress intensities for the path were extracted during the pressure run. The pressure stresses were extracted along the nodal paths as shown in Figures 7 and 9. This produced two files, PSE.OUT and PBLEND.OUT for the safe end and blend radius locations, respectively.
For the pressure loading specified (1,000 psig), the total stress intensity at Node 192 and Node 657 were determined to be 8,891 psi and 28,300 psi, respectively.
The membrane plus bending stress.intensity at Node 192 and Node 657 were determined to be 8,693 and 27,490 psi, respectively.
Table 3 shows the pressure results. i Results were also extracted from the vesselportion of the model to verify the accuracy of the pressure results obtained from the ANSYS model, and to check the results due to the use of the I .5 I multiplier on the vessel radius. These results are contained in the file, PVESS.OUT.
Based on earlier work [1], the radius of the finite element model (FEM) was multiplied by a factor of 1.5 to account for the fact that the vessel portion of the two-dimensional (2D) axisymmetric model is a i sphere, but the true geometry is the intersection of two cylinders.
The equation for the membrane hoop stress for a sphere is: (pressure) x (radius)2 x thickness l Considering a vessel base metal radius, R, of 105.90625 inches increased by a factor of 1.5, a vessel base metal thickness, t, of 5.4375 inches, and an applied pressure, P, of 1,000 psi, the calculated stress for a sphere is PR/(2t) = 14,608 psi. This compares very well with the remote vessel wall membrane hoop stress from the ANSYS result file, PVESS.OUT, of 13,410 psi. 'Thus, considering the peak total pressure stress of 28,300 psi reported above, the stress concentrating effect of the nozzle comer is 28,300/14,608
= 1.94. In other words, the peak nozzle comer stress is 1.94 times higher than nominal vessel wall stress for the 2D axisymmetric model.The equation for the membrane hoop stress in a cylinder is: (pressure) x (radius)thickness i File No.: VY-16Q-301 Page 8 of 27 Revision:
0 F0306- OIRO I Structural Integrity Associates, Inc.Based on the previous dimensions, the calculated stress for a cylinder without the-1.5 factor is 19,477 psi. Increasing this by a factor of 1.94 yields an expected peak nozzle corner stress of 37,785 psi, which would be expected from a cylindrical geometry that is. representative of the nozzle configuration.
Therefore, the result from the ANSYS file for the peak nozzle comer stress (28,300 psi) is lower than the peak nozzle comer stress for a cylindrical geometry because of the use of the 1.5 multiplier.
This is consistent with SI's experience where a factor of two increase in radius is typical for representing the three-dimensional (3D) effect in a 2D axisymmetric model.Based on the foregoing, the ANSYS pressure stresses for the vessel blend radius are increased for use in the subsequent fatigue analysis by 1.33 (2.0/1.5).
Thus, the blend radius results presented in Table 3 were obtained by multiplying the ANSYS stresses for the pressure loading by a 1.33X multiplication factor.
 
==5.0 REFERENCES==
: 1. SI Calculation No. VY- IOQ-301, Revision 0, "Feedwater Nozzle Finite Element Model and Heat Transfer Coefficients." 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 II, Part D, 1998 Edition, 2000 Addenda.4. VY Calculation Change Notice (CCN), CCN Number 1 for Calculation VYC1005 Revision 2,"This CCN Provides, a Basis for the Power Uprate Safety Analysis Report being submitted as part of the power uprate project. The 50.59 assessment will be handled by the EPU design change and NRC SER for this submittal." SI File Number VY-05Q-208.
: 5. J. P. Holman, "Heat Transfer," 4th Edition, McGraw-Hill, 1976.6. J. P. Holman, "Heat Transfer," 5th Edition, 1981.7. GE Nuclear Energy Certified Design Specification, "Reactor Vessel -Extended Power Uprate," Revision 1, SI File No. VY-05Q-236.
: 8. N. P. Cheremisinoff, "Heat Transfer Pocket Handbook," Gulf Publishing Co, 1984.File No.: VY-16Q-301 Revision:
0 Page 9 of 27 F0306-OI RO V Structural Integrity Associates, Inc.I I I Table 1: Material Properties
@ 300'F (1)Instantaneous Young's Coefficient of Density, Conductivity, Diff-usivity, Specific Heat, Poisson's Material Modulus, Thermal P *k d j C Ratio Ident. E x 106 Expansion, (lb/in 3) (BTU/hrft.F) (f,'hr) (BTU/Ibm-°F)(psi) a x 10-6 (assumed)
(' (see Note 5) (assumed)_______________
__________ (in/in-0 F) I_______SA533 Grade B, A508 Class 11 26.7 7.3 0.283 23.4 0.401 0.119 0.3 (see Note 2)SS Clad 27.0 9.8 0.283 9.8 0.160 0.125 0.3 (see Note 3)A508 Class I 28.1 7.3 0.283 32.3 0.561 0.118 0.3 (see Note 4)AI06 Grade B" 28.3 7.3 0.283 32.3 0.561 0.118 0.3 (see Note 4)Notes 1. The material properties applied in the analyses are taken from ASME Section II Part D 1998 Edition with 2000 Addenda. This is consistent with information provided in the Design Input Record (page 13 of VY EC No. 1773, SI File No. VY-16Q-209).
The use of a later code edition than that used for the original design code is acceptable since later editions typically reflect more accurate material properties than was published in prior Code editions.
Material Properties are evaluated at 300'F from the 1998 ASME Code, 2000 Addenda, Section II, Part D, except for density and Poisson's ratio, which are assumed typical values [3].2. Properties of A508 Class II are used (3/4Ni-I/2Mo-lI/3Cr-V).
: 3. Properties of 18Cr- 8Ni austenitic stainless steel are used.4. Composition
= C-Si.5. Calculated as [k/(pd)]/12 3.I I H I I I I I I I I I I Table 2: Nodal Force Calculation for End'Cap Load Node Element Radius A Radius R o2-Ri 2  Felement Fnode Number Number (in) (in) (in2 (lIb) (Ilb)1 5.42 : 7678.0 1022 0.1171 1.25565 15356.1 2 5.3029 15188.4 1021 0.1171 1.22823 15020.7 3 5.1858 _ 14853.0 1020 0.1171 1.20080 14685.3 4 5.0687 14517.6 1019 0.1171 1.17338 14349.9 5 4.9516 14182.2 1018 0.1171 1.14595 14014.5 6 4.8345 1 1 1 7007.3 File No.: VY-16Q-301 Revision:
0 Page 10 of 27 I I I F0306-01 RO Structural Integrity Associates, Inc.I Table 3: Pressure Results Membrane Plus Total Stress Location Bending Stress Intensity (psi)Intensity (psi)Safe End 8693 8891 Blend Radius 36653 37733 Note: The results for the Blend Radius have been increased by a factor of 1.33 (2.0/1.5) as discussed in Section 4.0.Table 4: Heat Transfer Coefficients for Region 1 (40% Flow)Calculation of Heat Transfer Coefficients for Feedwater Nozzle Flow Path Pipe Inside Diameter, D Flow, % of rated = -li Fluid Velocity, V = 8.022 Characteristic Length, L = D 0.806 T -T., AT = assumed to be 12% of fluid temperature
= 8.40 12.00 inches flsec =ft=24.00 0.806 ft 0.246 m 1,826.0 gpm=0 246 m 100% rated flow = 4,5110 gpm@ T 311,91 "F Density. a = 1lbm,3 0.793742524 MIb/hr.36.00 48.00 60.00 72.00 " F_,_____e_________________Value at Fluid Temperature, T [8) Units Conversion 70 100 200 300 400 500 .600 °F Water Property Factor [51 21.11 37.78 93.33 148.89 204.44 2680.00 315.56 C k 1.7307 0.5997 0.6300 0.6784 *0.6836 0.6611 0.6040 0.5071 W/m-ZC.(I..C ýytyý -.3L46 0.60 ..90 35 032 03 0.2930 Btu.1,r-ft-TF
.... ..... ..... The _a .C ...............
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................
.: ...........
_ 0 q -q. ;920 ... ................... .. .39 0. ..... ..... q, 0:.3 _ _... _-_ .-_-_c 4.1869 4.185 4.179 4.229 4.313 4.522 4.982 6.322 .kJ/kg-*C p 16.018 997.1 994.7 962.7 917.8 858.6 784.9 679.2 kg/m'(Density) 62.3 62.1 60.1 57.3 53.6 49.0 42.4 Ibm/ft 5 I 1.8 1.89E-04 3.24E-04 6.66E-04 1.01E-03 1.40E-03 1.986-03 3.15E-03 m3/m3-_C (Volumetric Rate of Expansion) 1.05E-04 1.80E-04 3.70E-04 5.60E-04 7.80E-04 1.10E-03 1.75E-03 ft'/ft'-F 0 -0.3048 9.806 .9.806 9.806 9.806 9.806 9.806 9.806 " m/s'(Gravitationat Constant) 32.17 32.17 32.17 32.17 32.17 32.17 32.17 ft/S'p 1.4881 9.96E-04 6.82E-04 3,07E-04 1.93E-04 1.38E-04 1.04E-04 8.62E-05 kg/m-s------- ) ..6..........
.- .4 04 2 -04 ..........
130 4. 30E 5 .Ibm f-s Pr 6.980 4.510 1.910 1.220 0.950 0.859 1.070 -(Prandtl Number)Calculated Parameter Formula 70 100 200 300 400 580 600"oF Reynold's Number, Re pVD/p 6.0147E+05 8.7645E-05 1.6859E+06 2.8491E+06 3.7255E+06 4.5248E+06 4.7336E+06
-Grashof Number, Gr 1.2852E+08 6.6834E+08 1.2721E+10 6.5918E+10 2.0931E+11 5.4429E+11 1.1372E+12
-Raleigh Number Ra GrPr 8.9710E+08 3.0142E+09 2.4297E+10 8.0420E+10 1.9885Et11 4.6755E+11 1.2166E+12
-trom [5]:.Inside Surface Forced Convection Heat Transfer Coefficient:
Hy,. = 0.023Re 5 8 Pr&deg;-k/D 5,132.76 6,119.10 8,626.61 10,107.53 10,960.57 11,236.63 10,678.39 W/m-.C 1.4EO _-&#xfd;4- 91EA ~3 434E-03~<
3.724E-03., 3.1E0 3 SE0 tu/sec-in'-*F From [51." Inside Surface Natural Convection Heat Transfer Coefficient:
Case: Enclosed cylinder C= r, n : eMo 16))H- C(GrPr)nk.L 232.43 330.57 599.85. 15.28 988.69 1,118.84 1,192.73'40.3 2 143.58 174.12 K'1968994,:,:1 210.06/ Gtu/&#xfd;r-ft'.F 7&#xfd;836E8(85 I &#xfd;.L 3 -O4.'>.2,0136E-04 2.7,NE-4.7 3.355JE04AK
:3,800E, 0 1 4 ~4062E.104' use-n File No.: VY-16Q-301 Revision:
0 Page I I of 27 F0306-0 1 RO Structural Integrity Associates, Inc.ELEMENTS SEP 6 2002 16:23:51 Y Feedwater Nozz1e'FT-ite Element Model Figure 1: ANSYS Finite Element Model File No.: VY-16Q-301 Revision:
0 Page 12 of 27 F0306-01 RO V Structural Integrity Associates, Inc.i ELEMENTS PRES-NORM 1000 AUN SEP 13 2002 12:16:11/'1 I Feedwater Nozzle Finite Element Model I Figure 2: Feedwater Nozzle Internal Pressure Distribution File No.: VY-16Q-301 Revision:
0 Page 13 of 27 F0306-O1RO Structural Integrity Associates, Inc.Figure 3: Feedwater Nozzle Pressure Cap Load File No.: VY-16Q-301 Revision:
0 Page 14 of 27 F0306-O1RO V
Integrity Associates, Inc.ELEMENTS p 7AN\Y SEP 13 2002 12:20:02 Feedwater Nozzle Finite Element Model Figure 4: Feedwater Nozzle Vessel Boundary Conditions File No.: VY-16Q-301 Revision:
0 Page 15 of 27 F0306-O1RO Structural Integrity Associates, Inc.RegIan 7 Region 8-F Region I~ ' Region 4 Region 5 Ail eke Region 6 I I I I I I I I U I I I Notes: Point A: Point B: Point C: Point D: Point E: Point F: End of thermal sleeve = Node 204 = 0.25" from feedwater inlet side of thermal sleeve flat.Beginning of annulus = Node 252.Beginning of thermal sleeve transition
= approximately 4.0" from Point A = Node 294.End of thermal sleeve transition
= approximately 9.5." from Point A = Node 387.End of inner blend radius (nozzle side) = Node 553.End of inner blend radius (vessel wall side) = Node 779.Figure 5: Nozzle and Vessel Wall Thermal and Heat Transfer Boundaries
[11 File No.: VY-16Q-301 Revision:
0 Page 16 of 27 I F0306-OIRO I
Structural Integrity Associates, Inc.I 1VS~V~. ]A206 7.~.. 28~JO?71'57 21254 F6dwateir>NozzIe .Finite E'lenierit Mo. del,*'A9 A7-535:1 G3,5 .4*Figure 6: Safe End Critical Thermal Stress Location File No.: VY-16Q-301 Revision:
0 Page 17 of 27 F0306-01 RO Structural Integrity Associates, Inc. I l MAT, -NUM*ANSYS&#xfd; &#xfd;1AL MAR9 2o007,: 13:,25: 09 Figure 7: Safe End Limiting Linearized Stress Paths File No.: VY-16Q-301 Revision:
0 Page 18 of 27 F0306-01 RO Structural Integrity Associates, Inc.Figure 8: Blend Radius Limiting Pressure Stress Location File No.: VY-16Q-301 Revision:
0 Page 19 of 27 F0306-0 1 RO Structural Integrity Associates, Inc.19 200O7 1D:36: 47.Feedwater, Nozzle -Jnite Eement Model Figure 9: Blend Radius Linearized Stress Path File No.: VY-16Q-301 Revision:
0 Page 20 of 27 F0306-01 RO Structural Integrity Associates, Inc.Total Stress Intensity 70000 a-0 100 200 300 400 Time (sec)Figure 10: Safe End 100% Flow Total Stress Intensity Total Stress Intensity 500 a-U, 0 100 200 300 400 Time (sec)Figure 11: Blend Radius 100% Flow Total Stress Intensity 500 File No.: VY-16Q-301 Revision:
0 Page 21 of 27 F0306-O1RO Structural integrity Associates, Inc.Total Stress Intensity a.cn 0 100 200 300 400 Time (sec)Figure 12: Safe End Total Stress History for 100% Flow 500 Total Stress Intensity a.I I I I I I ge 22 of 27 I F0306-O1RO 0 100 200 300 400 Time (see)500 Figure 13: Safe End Membrane Plus Bending Stress History for 100% Flom File No.: VY-16Q-301 Revision:
0 CStructural Integrity Associates, Inc.Total Stress Intensity 500G0 20000 0 100 200 300 400 Time (sec)Figure 14: Safe End Total Stress History for 40% Flow Total Stress Intensity 500 40000 0~(6 0 100 200 .300 400 Time (sec)500 Figure 15: Safe End Membrane Plus Bending Stress History for 40% Flow File No.: VY-16Q-301 Revision:
0 Page 23 of 27 F0306-OI RO Structural Integrity Associates, Inc.Total Stress Intensity-sz-sx 400 300(20 K)O O0 0 ....1000 ,-10300 0V 0 100 200 300 400 50 Time (sec)Figure 16: Safe End Total Stress History for 25% Flow Total Stress Intensity I I I I I I I I O0I I I I I I I I I ge 24 of2 I F0306-O1R0RO C-100 200 300 400 500 Time (sec)Figure 17: Safe End Membrane Plus Bending Stress History for 25% Flow File No.: VY-16Q-301 Revision:
0 Pai Structural Integrity Associates, Inc.I Total Stress Intensity 30000 25000 20000 15000 10000 5000-1000 2000 3000 4000 5000 Time (sec)Figure 18: Blend Radius Total Stress History for 100% Flow Total Stress Intensity 15000 0)0 1000 2000 3000 4000 5000 Time (sec)Figure 19: Blend Radius Membrane Plus Bending Stress History for 100% Flow File No.: VY-16Q-301 Revision:
0 Page 25 of 27 F0306-OI RO C Structural Integrity Associates, Inc.Total Stress Intensity 30000 25000-20000 15000 10000/ szs.0 0 1000 2000 3000 4000 500 Time (sec)Figure 20: Blend Radius Total Stress History for 40% Flow Total Stress Intensity I I I I I I I I 0O I I I I I I I o I ge 26of 27 I F03 06-01] RO 15000 0 1000 2000 3000 4000 5000 Time (sec)Figure 21: Blend Radius Membrane Plus Bending Stress History for 40% Fi File No.: VY-16Q-301 Revision:
0 Structural Integrity Associates, Inc.Total Stress Intensity 30000 25000 20000 15000 Un 10000 5000 ( -4 1 ______________
______________ -sz.sx 0 1000 2000 3000 4000 5000 Time (sec)Figure 22: Blend Radius Total Stress History for 25% Flow Total Stress Intensity 30000 25000 200 a I 150 U)00 ___00 __________
100(50(0 1000 2000 3000 4000 5000 Time (sec)Figure 23: Blend Radius Membrane Plus Bending Stress History for 25% Flow File No.: VY-16Q-301 Revision:
0 Page 27 of 27 F0306-01 RO V .Structural Integrity Associates, Inc.I I APPENDIX A FINITE ELEMENT ANALYSIS FILES File No.: VY-16Q-301 Revision:
0 Page Al of A2 F0306-OI RO
.' Structural Integrity Associates, Inc.FWP VY.INP Input File for Pressure Load In Computer files FWT VY lOO.INP Input File for 100% Flow Thermal Analysis In Computer files FWS VY 100.INP Input File for 100% Flow Stress Analysis In Computer files FWT VY 40.INP Input File for 40% Flow Thermal Analysis In Computer files FWS VY 40.INP Input File for 40% Flow Stress Analysis In Computer files FWT VY 25.INP Input File for 25% Flow Thermal Analysis In Computer files FWS VY 25.INP Input File for 25% Flow Stress Analysis In Computer files PSE.OUT Stress Output at Safe End with Pressure Load In Computer files PBLEND.OUT Stress Output at Blend Radius with Pressure Load In Computer files PVESS.OUT Stress Output at Vessel with Pressure Load In Computer files#FSE.OUT Stress Output at Safe End In Computer files#FBLEND.OUT Stress Output at Blend Radius In Computer files#FSE INSIDE.RED Stress Extracted at Safe End In Computer files#FBLEND INSIDE.RED Stress Extracted at Blend Radius In Computer files#FSE T-Green.XLS Green Function with Total Stress at Safe End In Computer files#FSE_M+B-Green.XLS Green Function with Membrane plus Bending Stress In Computer files at Safe End#FBR T-Green.XLS Green Function with Total Stress at Blend Radius In Computer files#FBRM+B-Green.XLS Green Function with Membrane plus Bending Stress In Computer files at Blend Radius Where # is H, M,L meaning 100%, 40%, and 25% flow rate, respectively.
File No.: VY-16Q-301 Revision:
0 Page A2 of A2 F0306-O I RO
[ Structural Integrity Associates, Inc. File No.: VY-16Q-302 NEC-JH 05 CALCULATION PACKAGE Project No.: VY-16Q PROJECT NAME: Environmental Fatigue Analysis of VYNPS CONTRACT NO.: 10150394 CLIENT: PLANT: Entergy Nuclear Operations, Inc. Vermont Yankee Nuclear Power Station CALCULATION TITLE: Fatigue Analysis of Feedwater Nozzle Project Manager Preparer(s)
&Document Affected Revision Description Approval Checker(s)
Revision Pages Signature
& Date *Signatures&
Date 0 1-34, Initial Issue Terry J. Herrmann Minghao Qin Appendix:
7/18/2007 7/12/2007 Al1-A2 John F. Staples 7/12/2007 Page 1 of 34 F0306-OI RO Structural Integrity Associates, Inc.Table of Contents 1.0 OBJECTIVE
.....................
4 I ..........................................................................................................
4 2.0 M ETHODOLOGY
.......................................
..............
..............................
.. .... .......................
4 3.0 ANALYSIS .......................................................................
.....................................................
7 4.0 FATIGUE USAGE RESULTS................................................................................................
11 5.0 ENV IRONM ENTAL FATIGUE ANALYSIS ...........................................................................
I 1
 
==6.0 REFERENCES==
..................................................................
..........................................................
12 APPENDIX A SUM M ARY OF OUTPUT FILES ....................................................................
Al List of Tables I I I I I I I I I ,I U I I I I I I Table 1: Table 2: Table 3: Table 4: Table 5: Table 6: Table 7: B lend Radius Transients
..................................................................................................
14 Safe End Transient
..........................................................................
........ ....... ...........
14 Maximum Piping Stress Intensity Calculations
............................................................
15 Blend Radius Stress Summary ..........................................
16 Safe End Stress Summary ....................
I .........................
o.. 18 Fatigue Results for Blend Radius (60 Years) .......................
I ........................................
20 Fatigue Results for Safe End (60 Years) ........................
...............
22 File No.: VY-16Q-302 Page 2 of 34 Revision:
0 I I F0306-OIRO UStructural Integrity Associates, Inc.List of Figures Figure 1: Typical Green's Functions for Thermal Transient Stress ....................
..................
24 Figure 2: Typical Stress Response Using Green's Functions
...........................
25 Figure 3: External Forces and Moments on the Feedwater Nozzle ...............................................
26 Figure 4: Transient 1, Bolt-up .......................................................................................................
26 Figure 5: Transient 2, Design H YD Test............................................................................................
27 Figure 6: Transient 3, Startup .....................................................................................................
27 Figure 7: Transient 4, Turbine Roll and Increased to Rated Power ..........................................
28 Figure 8: Transient 5, Daily Reduction 75% Power...................
..................................................
28 Figure 9: Transient 6, Weekly Reduction 50% Power ...............................
29 Figure 10: Transient 9, Turbine Trip at 25% Power ...... : ...........................................
29 Figure 11: Transient 10, Feedwater Bypass ............................................................................
3..... I ...30 Figure 12: Transient 11, Loss of Feedwater Pumps .................................
30 Figure 13: Transient 12, Turbine Generator Trip ...........
........................
31 Figure 14: Transient 14, SRV Blowdown ........................................
31 Figure 15: Transient 19, Reduction to 0% Power ...................................
32 Figure 16: Transient 20, Hot Standby (Heatup Portion) .................................................................
....32 Figure 17: Transient 20A, Hot Standby (Feedwater Injection Portion) .........................................
33 Figure 18: Transient 21-23, Shutdow n ..................................................
........................................
!..33 Figure 19: Transient 24, Hydrostatic Test ........................................
.34 Figure 20: Transient 25, U nbolt .......................................
.............................................................
34 File No.: VY-16Q-302 Revision:
0 Page 3 of 34 F0306-O1 RO V Structural Integrity Associates, Inc.i 1.0 OBJECTIVE The purpose of this calculation is to perform a revised fatigue analysis for the feedwater nozzle. Two locations will be analyzed for fatigue acceptance:
the safe end (SA508 Class 1) and the blend radius.(SA508 Class 2). Both. locations are chosen based on the highest overall stress of the analysis performed in Reference
[1]. A revised cumulative fatigue factor (CUF) will be determined for both locations, the nozzle forging and safe end, respectively.
In the end, the environmental fatigue usage factors will be determined for both locations.
 
==2.0 METHODOLOGY==
In order to provide an overall approach and strategy for evaluating the feedwater nozzle, the Green's I Function methodology and associated ASME Code stress and fatigue analyses are described in this section.Revised stress and fatigue analyses are being performed for the feedwater nozzle using ASME Code, Section III methodology.
These analyses are being performed to address license renewal requirements to evaluate environmental fatigue for this component in response to Generic Aging Lessons Learned (GALL) Report [I1] requirements.
The revised analysis is being performed to refine the fatigue usage so that an environmental fatigue factor can be determined for subsequent license renewal efforts. U Two sets of rules are available under ASME Code, Section fII, Class 1 [10]. Subparagraph NB-3600 of Section III provides simplified rules for analysis of piping components, and NB-3200 allows for more detailed analysis of vessel components.
The NB-3600 piping equations combine by absolute sum the stresses due to pressure, moments and through wall thermal gradient effects, regardless of where within the pipe cross-section the maximum value of the components of stress are located. By considering stress signs, affected surface (inside or outside) and azimuthal position, the stress ranges.may be significantly reduced. In addition, NB-3600 assigns stress indices by which the stresses are i multiplied to conservatively incorporate the effects of geometric discontinuities.
In NB-3200, stress indices are not required, as the stresses are calculated by finite element analysis and consider applicable stress concentration factors. In addition, NB-3200 methodology accounts for the different locations within a component where stresses due to thermal, pressure or other mechanical loading are a maximum. This generally results in a net reduction of the stress ranges and consequently, in the calculated fatigue usage. Article 4 [12] methodology was originally used to evaluate the feedwater nozzle. NB-3200 methodology, which is the modem day equivalent to Article 4, is used in this analysis to be consistent with the Section III design bases for this component, as well as to allow a more detailed analysis of this component.
In addition, several of the conservatisms originallyused in the original feedwater nozzle evaluation (such as grouping of transients) are removed in the U current evaluation so as to achieve a more accurate CUF.For the feedwater nozzle evaluated as a part of this work, stress histories will be computed by a time integration of the product of a pre-determined Green's Function and the transient data. This Green's File No.: VY-16Q-302 Page 4 of 34 i Revision:
0 F0306-OI RO Structural Integrity Associates, Inc.Function integration scheme is similar in concept to the well-known Duhamel theory used in structural dynamics.
A detailed derivation*
of this approach and examples Of its application to s locations is contained in Reference
[2]. A general outline is provided in this section.The steps involved in the evaluation are as follows:* Develop finite element model* Develop heat transfer coefficients and boundary conditions for the finite element model I Develop Green's Functions o Develop thermal transient definitions
* Perform stress analysis to determine stresses for thermal transients
* Perform fatigue analysis A Green's Function is derived by using finite-element.
methods to determine the transient stress response of the component to a step change in loading (usually a thermal shock). The critical location in the component is identified based on the maximum stress, and the thermal stress response over time is extracted for this location.
This response to the input thermal step is the "Green's Function." Figure 1 shows a typical set of two Green's Functions, each for a different set of heat transfer coefficients (representing different flow rate conditions).
I To compute the thermal stress response for an arbitrary transient, the loading parameter (usually local fluid temperature) is deconstructed into a series of step-loadings.
By using the Green's Function, the response to each step can be quickly determined.
By the principle of superposition, these can be added (algebraically) to determine the response to the original load history. The result is demonstrated in Figure 2. The input transienttemperature history contains five step-changes of 3 varying size, as shown in the upper plot in Figure 2. These five step changes produce the five successive stress responses in the second plot shown in Figure 2. By adding all five response curves, the real-time stress response for the input thermal transient is computed.The Green's Function methodology produces identical results compared to running the input transient through the finite element model. The advantage of using Green's Functions is that many individual transients can be run with a significant reduction of effort compared to running all transients through the finite element model. The trade-off in this process is that the Green's Functions are based on constant material properties and heat transfer coefficients.
Therefore, these parameters are chosen to bound all I transients that constitute the majority of fatigue usage, i.e., the heat transfer coefficients at 300'F bound the cold water injection transient.
In addition, the instantaneous value for the coefficient of thermal expansion is used instead of the mean value for the coefficient of thermal expansion.
This conservatism I is more than offset by the benefit of not having to analyze every transient, which was done in the VY reactor feedwater nozzle evaluation.
I Once the stress history is obtained for all transients using the Green's Function approach, the remainder of the fatigue analysis is carried out using traditional methodologies in accordance with ASME Code, Section III requirements.
I File No.: VY-16Q-302 Page 5 of 34 Revision:
0 F0306-O1 RO Structural Integrity Associates, Inc. H Fatigue calculations are performed in accordance with ASME Code, Section III, Subsection NB-3200 methodology.
Fatigue analysis is performed for the two limiting locations (one in the safe end and one in the nozzle forging, representing the two materials of thenozzle assembly) using the Green's Functions developed for thee three feedwater flow conditions and 60-year projected cycle -counts.Three Structural Integrity utility programs will be used to performthe fatigue analysis.
The first two calculate stresses in response to transients.
The transients analyzed are those described in the thermal cycle diagrams [3] for the feedwater nozzle. These transients are shown in Figures 4 -20.The temperatures and pressures for these transients have been modified to account for power uprate[4]. The power uprate pressures and temperatures were used for this analysis.
The last program calculates fatigue based on the stress output. The three programs are STRESS.EXE, P-V.EXE, and FATIGUE.EXE.
The first program, STRESS.EXE, calculates a stress history in response to a thermal transient using a Green's Function.
The second program, P-V.EXE, reduces the stress history to peaks and valleys, as required by ASME Code fatigue evaluation methods. The third n program, FATIGUE.EXE, calculates fatigue from the reduced peak and valley history using ASME Code, Section III range-pair methodology.
All three programs are explained in detail and have been independently verified for generic use in the Reference
[5] calculation.
In order to perform the fatigue analysis, Green's Functions are developed using the finite element model. Then, input files with the necessary data are prepared and the three utility computer I programs are run. The first program (STRESS.EXE) requires the following three input files:* Input file "GREEN.DAT":
This file contains the Green's Function for the location being evaluated.
For each flow condition, two Green's Functions are determined:
a membrane plus bending stress intensity Green's Function and a total stress intensity Green's Function.
This allows computation of total stress, as well as membrane plus bending stress, which is necessary I to compute K, per ASME Code, Section III requirements.
* Input file "GREEN.CFG":
This file is a configuration file containing parameters that define the Green's Function (i.e., number of points, temperature drop analyzed, etc.).* Input file "TRANSNT.INP":
This file contains the input transient history for all thermal transients to be analyzed forthe location being evaluated.
Pressure and piping stress intensities are also included for each transient case, based on pressure stress results from finite element analysis and attached piping load calculations.
The second program (P-V.EXE) simply extracts only the maxima and minima stress (i.e., the peaks and valleys) from the stress histories generated by program STRESS.EXE.
The third program (FATIGUE.EXE) performs the ASME Code peak event-pairing required to calculate a fatigue usage value. The input data consists of the output peak and valley history from program P-V.EXE and a configuration input file that provides ASME Code configuration data relevant to the fatigue analysis (i.e., K, parameters, Sm, Young's modulus, etc.). The output is the final fatigue calculation for the location being evaluated.
n File No.: VY-16Q-302 Page 6 of.34 Revision:
0 F0306-01 RO I Structural Integrity Associates, Inc.The Green's Function methodology described above uses standard industry stress and fatigue analysis practices, and is the same as. the methodology used in typical stress reports. Special approval for the use of this methodology is therefore not required.3.0 ANALYSIS The fatigue analysis involves the preparing of input files for, and running of three programs verified and described in Reference
[5]. The programs STRESS.EXE and P-V.EXE are run together through the use of a batch file. The program FATIGUE.EXE is run after processing the output from P-V.EXE. The steps associated with this process are described in the following sub-sections.
 
===3.1 Transient'Definitions===
(for program STRESS.EXE)
The program. STRESS.EXE requires the following three input files for analyzing an individual transient:
* Green.dat.
There are 12 stress history functions obtained from Reference
[1]. They represent the membrane plus bending and total stress intensities at the blend radius and safe end locations.
Both of the blend radius and the safe end have two stress history functions for each of the, following flow conditions; 100%, 40%, and 25% flow..* Green.cfg is configured as described in Reference
[5].* Transnt.inp.
These files are created to represent the transients shown on the thermal cycle diagrams and redefined by power uprate. Note that transients 12, 13, and 15 are nearly* identical on the thermal cycle diagram [3] and the results from running transient 12 will be used for all three transients.
Transient 16, 17 and 18 will not be considered since there is no temperature change. Tables 1 and 2 show the thermal history used to represent each transient.
Based upon the thermal cycle diagram for the feedwater nozzle [3], the transients are split into the following groups based upon flow rate: o Transients 3, 20, 20A, and 21-23 are run at 25% flow. Although Reference
[3]shows 15% flow rate, it is conservative to use 25% flow rate for these transients.
Transient 20, Hot Standby, is split up into two parts. The first portion is "Heatup portion" and the second portion is "Feedwater Injection portion" that are defined from Reference
[3].o Transient 11 is run at 40% flow.. Transient 1 starts off and ends at 100% flow.o Transients 5, 6, 9, 10, and 19 are run at 100% flow.o Transient 4' is run at 100% flow only to obtain the last stress point. The remainder of the stress points for transient 4 is obtained from the 25% flow stress results.The results are pulled from the two flow case results based upon the flow rates defined in the thermal cycle diagram [3].o Transients 12, 13, 14 and 15 were run at 100% flow. Heat transfer coefficients were not re-calculated for the 1 minute intervals each of these transients is at 110% flow. Theeffect of this small flow rate increase for such a relativelyshort duration should be minor.o Transients 1, 2, 24, and 25 are set as no thermal stress due to very small temperature changes (70 0 F to 100TF) at these transients.
File No.: VY-16Q-302 Revision:
0 Page 7 of 34 F0306-O1RO Structural Integrity Associates, Inc.3.2 Peak and Valley Points of the Stress History (for program P-V.EXE)The program P-V.exe is then run to extract the peaks and valleys from the STRESS.OUT file produced by the STRESS.EXE program. The only input required for this program is STRESS.OUT and it outputs all the peaks and valleys to P-V.OUT. Columns 2 through 5 of Tables 4 (for the blend radius) and 5 (for the safe end) show the final peak and valley output. The pressure for column 6 is then filled in using the thermal cycle diagrams.
Pressure and piping loads have to be added to the peak and valley points to calculate the final stress values used for fatigue analysis.3.3 Pressure Load The pressure stress associated with a 1000 psi internal pressure was determined in Reference
[.1].These values are as follows: Pressure stress for the safe end: I* 8693 psi membrane plus bending stress intensity.
* 8891 psi total linearized stress intensity.
.Pressure stress for the blend radius:* 36653 psi membrane plus bending stress intensity.
* 37733 psi total linearized stress intensity., These pressure stress values for each location were linearly scaled with pressure.
The actual pressure for column 6 of Tables 4 and 5 is obtained from Tables 1 and 2. The scaled pressure stress values are shown in columns 7 and 8 of Tables 4 and 5.The pressure stress is combined with the thermal and piping loads to calculate the final stress values used for fatigue analysis.3.4 Attached Piping Loads Additionally, the piping stress intensity (stress caused by the attached piping) was determined.
U These piping forces and moments are determined as shown in Figure 3.The following formulas are used to determine the maximum stress intensity in the nozzle at the two locations of interest.
From engineering statics, the piping loads, at the end of the model can be translated to the first and second cut locations using the following equations:
I (M&#xfd; , =M. -FYL, For Cut I: (MY), = My + FL (M,)2 = MX -FL 2 For Cut Ii: (My)2 = My + FxL2 File No.: VY-16Q-302 Page 8 of 34 Revision:
0 F0306-O1 RO II Structural Integrity Associates, Inc.I The total bending moment and shear loads are obtained using the equations below: For Cut 1: MX = F(MII)12 +(MY'),, F (Fx).2 ++/-(Fy)1 2=2 2 I MXY = V(Mx),2 +(My),2 l ~For Cut 11: .2 2 Fx= &#xfd;(F)2 2 ++/-(F).2 2 The distributed loads for a thin-walled cylinder are obtained using the equations below: NZF + Mxy X RN L2 RN irRN[~ 2RNI To determine the primary stresses, PM, due to internal pressure and piping loads, the following i equations are used.For Cut I, using thin-walled equations:
I(PM PaN Nz.(E)~=2 tN t N I (pM)o, =Pa N tN I (PM)R -P qN TM -SIA_ -2 ((PM)O -(PM)R + (fr.)Z 0 2 I or Because pressure was considered separately in this analysis, the equations used for Cut I are valid for Cut II.U File No.: VY-16Q-302 Page 9 of 34 Revision:
0 F0306-OI RO Structural Integrity Associates, Inc. .where: L, = The length from the end of the nozzle where the piping loads are applied to .the location of interest in the safe end.L2= The length from the end of the nozzle where the piping loads are applied to the location of interest in the blend radius.My= The maximum bending moment in the xy plane.Fyx = The maximum shear force in the xy plane.Nz = The normal force per inch of circumference applied to the end of the nozzle in the z direction.
qN = The shear force per inch of circumference applied to the nozzle.RN = The mid-wall nozzle radius.Since the pressure was considered separately in this analysis, the equations can be simplified as follows: Nz*(PM.), t (PM)9 =0 (PM)R =0 tN SImx :2(= M )or SIm =2t 71 +(r2 zt 0 Per Reference
[6], the feedwater nozzle piping loads are as follows: Fx = 3,000 lbs M, = 28,000 fl-lb = 336,000 in-lb I Fy = 15,000 lbs my = 13,000 ft-lb =156,000 in-lb F, = 3,200 lbs Mz= 40,000 ft-lb = 480,000 in-lb i The loads are applied at the connection of the piping and safe end. Therefore, the L, is. equal to 12.0871 inches and the L 2 is equal to 27.572 inches. The calculations for the safe end and blend radius are shown in Table 3. The first cut location is the same as the Green's Function cross section per [1] at the safe end, and the second cut is from Node 645. (outside) to Node 501 (inside).
The maximum stress intensities due to piping loads are 5707.97 psi at the safe end and 265.47 psi at the blend radius, respectively.
The piping load sign is set as the same as the thermal stress sign.These piping stress values are scaled assuming no stress occurs at an ambient temperature of 70&deg;F and the full values are reached at reactor design temperature, 575TF. The scaled piping stress values File No.: VY-16Q-302 Page 10 of 34 Revision:
0 F0306-O I RO 1 .Structural Integrity Associates, Inc.are shown in columns 9 and 10 of Tables 4 and 5. Columns II and 12 of Tables 4 and 5 show the summation of all stresses for each thermal peak and valley stress point.3.5 Fatigue Analysis (for program FATIGUE.EXE)
The number of cycles projected for the 60-year operating life is used for each transient
[3]: Column 13 in Tables 4 and 5 shows the number of cycles associated with each transient.
The number of cycles for 60 years was obtained from Reference
[3].The program FATIGUE.EXE performs the "ASME Code style" peak event pairing required to calculate a fatigue usage value. The input data for FATIGUE.CFG is as follows: Blend Radius Safe End Parameters m and. n for 2.0 & 0.2 (low alloy 3.0 & 0.2 (carbon steel)Computing K, steel) [10] [10]Design Stress Intensity 26700 psi [8] @ 600&deg;F 17800 psi [8] @ 600TF Values, Sm.Elastic Modulus from 30.0x106 psi [10] 30.0x106 psi [10]Applicable Fatigue Curve Elastic Modulus Used in Finite Element Model 26.7x 106 psi 28.1xl0 6 psi The Geometric Stress ChGonentrationFacStore1.0 1.34 [7, page 35 of S4]Concentration Factor K, The results of the fatigue analyses are presented in Tables 6 and 7 for the blend radius and safe end for 60 years, respectively.
The results described are contained in EXCEL files BRresults.xls and SEresults.xls, which are contained in the computer files.4.0 FATIGUE USAGE RESULTS The blend radius cumulative usage factor (CUF) from system cycling is 0.0636 for 60 years. The safe end CUF is 0. 1471 for 60 years.5.0 ENVIRONMENTAL FATIGUE ANALYSIS In the response to NRC request for additional information (RAI) 4.3-H-02, VYNPS states that they have conservatively assumed that fatigue cracks may be present in the clad. VYNPS manages this cracking by performing periodic inspections that were implemented in response to Generic Letters 80-095 and File No.: VY-16Q-302 Revision:
0 Page 1I of 34 F0306-OI RO Structural Integrity Associates, Inc.8 81-11, and NUREG-0619.
The inspection frequency is based on the .calculated fatigue crack growth of a I postulated flaw in the nozzle inner blend radius. The VYNPS fatigue crack growth calculation uses methods in compliance with GE BWR Owners Group Topical Report "Alternate BWR Feedwater Nozzle Inspection Requirements", GE-NE-523-A71-0594, Revision 1, August 1999 and the associated NRC Final Safety Evaluation (TAC No. MA6787) dated March 10, 2000. The NRC has reviewed and approved this approach to handling FW nozzle inner blend radius cracking (Letter D.H. Dorman (USNRC) to D.A. Reid (VYNPC),
 
==Subject:==
Evaluation of Request for Relief from NUREG-0619 for VYNPS dated 2/6/95, (TAC No. M88803)).The analysis performed for the feedwater nozzle calculated fatigue in the blend radius base metal, not the clad. This is consistent with the VYNPS.position stated in the response to RAI 4.3-H-02, and is also consistent with ASME Code methodology since cladding is structurally neglected in fatigue analyses, per ASME Code, Section III, NB-3122.3.
Per Reference
[9], the dissolved Oxygen (DO) calculation shows the overall HWC availability is 47%. This means the time ratio under NWC (pre-HWC) is 53%.For the safe end location, the environmental fatigue factors for post-HWC and pre-HWC are all 1.74 I from Table 3 of Reference
[9]. It results in an EAF adjusted CUF of 1.74 x 0.1471 = 0.2560 for 60 years, which is acceptable (i.e., less than the allowable value of 1.0). The overall environmental multiplier is 1.74. I For the blend radius location, the environmental fatigue factors for post-HWC and pre-HWC are 11.14 and 8.82 from Table 4 of Reference
[9]. These results in an EAF adjusted CUF of(1 1.14 x m 53%.+ 8.82 x 47%) x 0.0636 = 0.6392 for 60 years, which is acceptable (i.e., less than the allowable value of 1.0). The overall environmental multiplier is 10.0496.
 
==6.0 REFERENCES==
: 1. SI Calculation No. VY- 16Q-301, Revision 0, "Feedwater Nozzle Stress History Development for Green Functions." 2. Kuo, A. Y., Tang, S. S., and Riccardella, P. C., "An On-Line Fatigue Monitoring System for I Power Plants, Part I -Direct Calculation of Transient Peak Stress Through Transfer Matrices and Green's Functions," ASME PVP Conference, Chicago, 1986. .3. Entergy Design Input Record (DIR) EC No. 1773, Revision 0, "Environmental Fatigue U Analysis for Vermont Yankee Nuclear Power Station," 7/3/07, S1 File No. VY- 16Q-209.4. GE Certified Design Specification No. 26A6019, Revision 1, "Reactor Vessel -Extended Power Uprate," SI File No. VY-05Q-236.
: 5. Structural Integrity Associates Calculation (Generic)
No. SW-SPVF-OIQ-301, Revision 0,"STRESS.EXE, P-V.EXE, and FATIGUE.EXE Software Verification." I 6. GE Drawing No. 919D294, Revision 11, Sht. No. 7, "Reactor Vessel," SI File No. VY-05Q-241.7, Chicago Bridge & Iron Company Contractor 9-6201, Revision 2, "Section S4, Stress Analysis Feedwater Nozzle Vermont Yankee Reactor Vessel," SI File No. VY-05Q-238.
File No.: VY-16Q-302 Page 12 of 34 Revision:
0 F0306-O I RO V Structural Integrity Associates, Inc.8. American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section II, Part D, 1998 Edition, 2000Addenda.
: 9. SI Calculation No. VY-16Q-303, Revision 0, "Environmental Fatigue Evaluation of Reactor Recirculation Inlet Nozzle and Vessel Shell Bottom Head." 10. American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section III Subsection NB, 1998 Edition, 2000 Addenda.11. NUREG-1801, Revision 1, "Generic Aging Lessons Learned (GALL) Report," U. S. Nuclear Regulatory Commission, September 2005.12. American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section 1.1, Subsection A, Article 4, 1965. Edition with Winter 1966 Addenda.File No.: VY-16Q-302 Revision:
0 Page 13 of 34 F0306-OI RO C Structural Integrity Associates, Inc.I I Table 1: Blend Radius Transients Trwtuiete Timern ,. T 3 $ Plressure Transient Time Temp Time Step Prssure Treestnst.
Time Tem Time Step Pressure 123Cycles 10 70 10 0 t0. M Heat.r 7O Cycles WF 80 265 _ 90&#xfd; 1010 2650 t 80411 20701 302 100O 1010* 14.060V 0 392 I 11 Hlmdmr____
60 275 6 I Cycles 6 tOO 90 HF 100 000 100W.DTestgn l.... C.. .....0 70 100 100 5200 100 1 00"Lo 1080 0 5000 50 C 540 16164 _1010..... 1 21164-5491 i 4. TurtetRntluo 0 -549 i ! 1010
% ~ ~ ~ ~ ~ ... .....i --........
T -T ......and~ ~ 100asdt 1 11..... ...... .............
.... ...... ...i 3u' 1002 20 1 11 LF21. HF 100 0002 302 5000 W010"t. Day 0 392 1010 Redus-se 000 310 9000 10 1- 70 oe 270.0 _310 5o it1 e 11 HF_10.00 t600Lj = .302 Soo00 1500-32 .. 160..... Plenty " "Seauu"- " t ..7070 302 i 000 & 1010 11. Intentf 0 302 .1010....... .... .......... .... .l................
... ' L .- -- ---.- .... ... ... ........ .35 55" 25 t 1135............. .] '" -' -1565.5 66S 2135 50 6 0 1135 21M5 50 lIi 50465l 440 1 300
* 1135*." ........ .... -- ' i.. .....................
... ... _i... ... .. .r ---" " -....................
1 ...........
....1 + + " -" + --, : H +...5655 .05 31 M 115 S10415. 505~ 1130.. ....... .... .......-.-.... " +" '- -..... ... ":-_ -..l_ ......181 .5 1 50 1 113 23.5 t50 100 546 40. 18600 .00 27814.5 392 13O .1010 z~1405 J 50 420o j 675 1. neducuouteoO%
J 0 392 j 1010 P-we 500 Ble M10 265 18 a11....... 10 ........ W00 -205--- 50 0-............
i-iaa ........ -" " '6 T ..20265 1rdb 1010 300 Cycles 3020 549 3924 < 1010 8920 0025 549 5000 1010 20A. Hot Stndby .549 4 5010=50~~~~ ~ ~ ~ ~~ ~ ~ ~~~~~ c.. .....i+.........
............
+ -.... .........I ....(190 toencttnPets 100 1 J1010 i~~~~~i ~ ~ .........
.........
.... ..T. -+' -j .-"...".-T ..........5451 549 50" 1010 21423.Shum 1010..... ..... ...... .3 ...... .... ... ... .......300 Cyc 828. 4 350 6a04-1 s I I I I I1 64% Pume 2,000 Cycles HFJeelyReO c*1800 200 1800 1010-00 200 fool00 0!O 00 392 1"0 1010 10400 T 02 500 01 11 24. Hyidrestuto 0 100 -50......... -... -" -i ' -.I Cycles 1200 T90 00 i 16 180l9 0 1 00 60 5_i2400 10 ,0 .00 -r 1 5 5.+ Tuntee HF 100 0 i:7j47 360 1010 2340 205 50 30 1010 3960 26-5 ' 1010 10400 J 392 N0 1010 3420 -0 1010_ 25. UCetut -_ 0- .15 .---LOBOj100 0 00 I M *0 70 500 12. Turbire Gelerter Trdp 4 CyWcl..22. cycl,.-0 j 302 1010.. 32 .'.........
.. V T /2375'90 25 60 M4...._i '
--i& 1 "&#xfd;1 ...3120 138 4 3210 2 4 31 101 9591 302 1530010 J 1010 I I Note: I. The indicated time or pressure was assumed 2. 1375 psi is for Transient 13 only.Table 2: Safe End Transient Trerslellt Time Temp Time Step Pressure Transiet Time Temp imeStep Pressure Transient Time lTemp TimeStp PresurM..umber. ...........3 CyI 10 70 t 0 I HFI100* 50 26 0 loio 1890 260 000o 1010 2570 302 S00 1010.60 775 i 6 i== y == 960 10too 900 .50 HF 100 14. 0 1' 0 5- ---...Test.r...............1"'M 100 1000 0 7 16i0 150 1 54 .10 5280 150 300 10 6380 100 500 5 1I. tOS. ot 108 3. Slarbtp 0 'O0 , 56 tFO2 16664 .549 500 1010.4.TrlnRoll.andlc..n.....
t0nted 1801... 1.... 00. _..+ ....... ............
-. ... 1 .....182 .......1210  0_Iy 392 4 11 Redcons 9006 *310 900 1010R, 75% P~mm -.2700 310 -i I H8.800 C 41u0300 392 900 1010 5 + W kly Rduce 8  IWOn.& -29 200 low80 1010 HF10 5400 392 18oo 1010 0 i 392 1010... .55 25 1.... 1 13.5 i 50 9 1135 145 50 1.71 1135.55.5 ..... .565 2165.5 565 600 1135 21605050 547&#xfd;5 .565 1 15 6775 505 132 1135 7148.5 50 42 675 11048530 67 164125 549 1 1010-18,21.25' 591.0 11 18213 100 100 20213:5 1 100 18000 10 200)145 2 7 1 '101 21814.5 392 180 01 22. 145 .39 50 1010 .20. Hot Standby FW j6ecton Portion]O8 Cycles 1F129 0 540 181 100 21 : 290 41 549.... 1. 54""+ " -9+I ~ 440 1 w01 20. ~ ~ ~ 4, 0 6 i 1010 300Cycles 3925 549 S 3924 .1010...2.. 4420'-- .' 0 ' 1010 ...18. RednuO to 0% 1 0 392 1010.H.. F 10 ........ ib2 " 26" 5 1 800- 1010 1W 1010_160 " 0 .....210 1010 500. .010 2-309 Cylshdo.. .. F.. 2. 5.... .*2 0 3754 6264 5010.. --33~ ' 60 50 15144 100 82800 5 I I I I I TClest 100 100 600 1563 1800 i 100 8 000 50 24 00 1 600 50 1560 70 o00 0 0. Turbnee 10 Cyc.es 0100... i :T _ :'!4i ; -"-6 ..- .....I0 1 1010 2340 8 0 300 1010 342D 265 900 U. 1010.260...,.
..-. ... 1010..54900 302 100 1010 5900G .SOO50 1.10 12. Torbine 228 cyclre HF_100 10 32 5 1101010 90 275 0 0 5 40 2750 10 82 2791 26094 3210 251 41" 1010 4991 392 1381 1010 S0o1 5"2- 500 1010 " Note: 1. These transients are the same as in Table I with the exception of the 500 second steady state time increment that is used The transients in Table I are plotted using a 5000 second steady state increment.
The difference is due to the length of the Green's Function for the safe end which is shorter compared to the blend Radius.2. The indicated time or pressure was assumed 3. 1375 psi isfor Transient 13 only.I I 1 File No.: VY-16Q-302 Revision:
0 File No.: VY-16Q-302 Revision:
0 Page 14 of 34 I F0306-OI RO V Structural Integrity Associates, Inc.Table 3: Maximum Piping Stress Intensity Calculations Safe End External Pioina Loads Blend Radius External Piping Loads Parameters Parameters Fx 3.00 kips Fy 15.00 kips.Fz 3.20 kips MX_ = .336.00 in-kips my= 156.00 -in-kips Mz= 480.00 in-kips OD= 11.86 in ID= 10.409 in RN = 5.57 in L= 12.09 in tN = 0.72 in (M) = 154.69 in-kips M = 192.26 in-kips MXY 246.77 in-kips Fxv= 15.30 kips Nz= 2.63 kips/in qN -1.59 kips/in Primary Membrane Stress Intensity* PMz 3.63 ksi= -2.20 ksi Slmax 5.71 ksi Slmax 5707.97 psi Fx = 3.00 kips Fv= 15.00 kips Fz 3.20 kips MX= 336.00 in-kips my = 156.00 in-kips Mz 480.00 in-kips OD= 22.67 in 1D= 10.750 in RN= 8.35 in L= 27.57 in tN= 5.96 in (Mx)2 = -77.58 in-kips S(M1)2 = 238.72. in-kips= 251.01 in-kips Fxy = 15.30 kips Nz= 1.21 kips/in qN = -0.51 kips/in Primary Membrane Stress Intensity PMz 0.20 ksi T = -0.09 ksi Slmax= 0.27 ksi Slmax = 265.47 psi Note: The locations for Cut I and.Cut II were defined paths, respectively.
in Reference
[1] for safe end and blend radius File No.: VY-16Q-302 Revision:
0 Page 15 of 34 F0306-0 I RO Structural Integrity Associates, Inc. U I Table 4: Blend Radius Stress Summary 1 2 3 4 5 6 7 8 9 10 11 12 13 Total M+B Total M+B Total Total Number Total M+B Pressure Pressure Piping Piping Total M+B of Transient Time Stress Stress Temperature Pressure Stress Stress Stress Stress Stress Stress Cycles Number (s) (psAi (psi) F (pski) (psi) (psi) fpsi[ (psi pIWO fpsil (60 years)1 0 0 0 70 0 0 0 0 0 0.00 0.00 123 0 0 0 70 0 0 0 0 .0 0.00" 0.00 120 2 1680 0 0 100 1100 41506.3 40318.3 15.77042 15.77042 41522.07 40334.07 120 10880 0 0 100 50 1886.65 1832.65 15.77042 15.77042 1902.42 1848.42 120 0 29166 23676 100 50 1886.65 1832.65 15.77042 15.77042 31068.42 25524.42 300 3 16782.8 "-3577 -3138 549 1010 38110.33 37019.53 -251.801 -251.801 34281.53 33629.73 300 21164 -3532 -3138 549 1010 38110.33 37019.53 -251.801 -251.801 34326.53 33629.73 _ 300 0 -3530 -3158 549 1010 38110.33 37019.53 -251.801 -251.801 34328.53 33609.73 O 300 4 1801.9 29465 22266 244.004 1010 38110.33 37019.53 91.47053 91.47053 67666.80 59377.00 300 8602 7720 6749 392 1010 38110.33 37019.53 169.2692 169.2692 45999.60 43937.80 300 60 7720 672 392 1010 38110.33 37019.53 169.2692 169.2692 45999.60 43940.80 10000____0 7720 6752 392 1010 38110.33 37019.53 169.2692 169.2692 45999.60 43940.80 10000 5 2229.8 13598 11941 311.002 1010 38110.33 37019.53 126.6901 126.6901 51835.02 49087.22 10000 8600 7720 6752 392 1010 38110.33 37019.53 169.2692 169.2692 45999.60 43940.80 10000 0 7720 6752 392 1010 38110.33 37019.53 169.2692 169.2692 45999.60 43940.80 2000 6 2820.3 15742 13892 280.691 1010 38110.33 37019.53 110.7562 110.7562 53963.09 51022.29 2000 10400 7720 6752 392 1010 38110.33 37019.53 169.2692 169.2692 45999.60 43940.80 2000 0 7720 6752 392 1010 38110.33 37019.53 169.2692 169.2692 4599960 43940.80 10 9 2524 29006 23417 118.311 1010 38110.33 37019.53 25.39616 25.39616 .67141.73
-60461.93 10 10400 7720 6752 392 1010 38110.33 37019.53 169.2692 169.2692 45999.60 43940.80 10 0 7720 6752 392 1010 38110.33 37019.53 169.2692 169.2692 45999.60 43940.80 70 10 1632.4 16828 14701 267.399 1010 38110.33 37019.53 103.7688 103.7688 55042.10 51824.30 70 7070 7720 6752 392 1010 38110.33 37019.53 169.2692 169.2692 45999.60 43940.80 .70 707 7720 6752 392 1010 38110.33 37019.53 169.2692 169.2692 45999.60 43940.80 10 3.5 6620 6632 565 1190 44902.27 43617.07 260.2119 260.2119 51782.48 50509.28 10 4,5 6190 6608 50 1185 44713.61 43433.81 .10.51361 10.51361 50914.12 50052.32 10 194.5 31720 .21067 109.348 1135 42826.96 41601.16 20.68448 20.68448 74567.64 62688.84 10 2166.3 -4761 -1859 513.483 972 36676.48 35626.72 -233.1304
-233.1304 31682.35 .33534.59 10 11 2362.5 31268 22070 102.255 1010 38110.33 37019.53 16.95583 16.95583 69395.29 59106.49 10 6728.3 -4913 -3149 513.448 1010 38110.33 37019.53 -233.112 -233.112 32964.22 33637.42 10 7149.9 32114 21472 83.333 1010 38110.33 37019.53 .7.0089 7.0089 70231.34 58498.54 10 18213.3 -3565 -3162 503.978 -1010 38110.33 37019.53 -228.1338
-228.1338 34317.20 33629.40 10 19122.6 29156 23083 100.048 1010 38110.33 37019.53 15.79565 15.79565 .67282.13 60118.33 10 26814.5 7720 6410 392 .1010 38110.33 37019.53 169.2692 169.2692 45999.60 43598.80 10 0 7720 6752 392 1010 38110.33 37019.53 169.2692 169.2692 45999.60 43940.80
* 60 10 7720 6752 392 1135 42826.96 41601.16 169.2692 169.2692 50716.22 48522.42 60 12 30 7720 -6752 392 940 35469.02 34453.82 169.2692 169.2692 43358.29 41375.09 60 2033.7 28648 25301 132.007 940 35469.02 34453.82 32.59588 32.59588 64149.62 59787.42 60 9591 7720 6752 392 1010 38110.33 37019.53 169.2692 169.2692 45999.60' 43940.80 60 0 7720 6752 392 1010 38110.33 37019.53 169.2692 169.2692 45999.60 43940.80 1 10 7720 6752 392 1375 51882.88 50397.88 169.2692 169.2692 59772.14 57319.14 1 13 30 7720 6752 392 940 35469.02 34453;82 169.2692 169.2692 43358.29 41375.09 1 2033.7 28648 25301 132.007 .1010 38110.33 37019.53 32.59588 32.59588 66790.93 62353.13 1 9591 7720 6752 392 1010 38110.33 37019.53 169.2692 169.2692 45999.60 43940.80 1 14 0 7720 6752 392 1010 38110.33 37019.53 169.2692 169.2692 45999.60 43940.80 1 14 5960 28487 25650 100 50 1886.65 1832.65 15.77042 15.77042 30389.42 27498.42 t1 0 7720 6752 392 1010 38110.33 37019.53 169.2692 169.2692 45999.60 .43940.80 228 10 7720 6752 ---392 1135 42826.96 41601.16 169.2692 169.2692 50716.22 48522.42 228 15 30 7720 6752 392 940 35469.02 34453.82 169.2692 169.2692 43358.29 41375.09 228 2033.7 28648 25301 132.007 1010 38110.33 37019.53 32.59588 32.59588 66790.93 62353.13 228 9591 7720 6752 .392 -1010 38110.33 37019.53 169.2692 169.2692 45999.60 43940.80 228 19 0 7720 6752 392 1010 38110.33 37019.53 169.2692 169.2692 45999.60 43940.80 300 6800 16752 14971 265 1010 38110.33 37019.53 102.5077 102.5077 54964.84 52093.04 300 30 0 17151 13815 265 1010 .38110.33 37019.53 102.5077 102.5077 55363.84 50937.04 300 8925 -3531 -3146 549 1010 38110.33 37019.53 -251.801 -251.801 34327.53 33621.73 300 2 8 -3530 -3158 549 1010 38110.33 37019.53 -251.801 -251.801 34328.53 33609.73 300 20A 183 28102 12153 233 1010 38110.33 37019.53 85.68595 85.68595 66298.02 49258.22 300 5451 -3530 -3158 549 1010 38110.33 37019.53 -251.801 -251.801 34328.53 33609.73 300 0 -3530 -3158 549 1010 38110.33 37019.53 -251.801 -251.801 34328.53 33609.73 300 21-23 20144 29168 23656 100 50 1886.65 1832.65 15.77042 15.77042 31070.42 25504.42 300 0 0 0 100 50 1886.65 1832.65 15.77042 15.77042 1902.42 1848.42 1 24 600 .0 0 100 1563 58976.68 57288.64 15.77042 15.77042 58992.45 57304.41 1 2400 .0 0 100 50 1886.65 1832.65 15.77042 15.77042 1902.42 1848.42 .1 0 0 60 100 0 0 0 15.77042 15.77042 15.77 15.77 123 25 1580 0 0 70 00 ! 0 15.7 0 461 0 0.00 0.00 123 File No.: VY-16Q-302 Page 16 of 34 Revision:
0 I F0306-01 RO UStructural Integrity Associates, Inc.Table 4: Blend Radius Stress Summary (Continue)
NOTES: Column 1: Transient number identification.
Column 2: Time during transient where a maxima or minima stress intensity occurs from P-V.OUT output file.Column 3: Maxima or minima total stress intensity from P-V.OUT output file.Column 4: Maxima or minima membrane plus bending stress intensity from P-V.OUT output file.Column 5: Temperature per total stress intensity.
Column 6: Pressure per Table 1.Column 7: Total pressure stress intensity from the quantity (Column 6 x 37733)/1000
[Table3, 1].Column 8: Membrane plus bending pressure stress intensity from the quantity (Column 6 x 36653)/1000
[Table 3, 1].Column 9: Total external stress from calculation in Table 3, 265.47 psi*(Column 5-70&deg;F)/(575&deg;F
-70&deg;F).Column 10: Same as Column 9, but for M+B stress.Column 11: Sum of total stresses(Columns 3, 7, and 9).Column 12: Sum of membrane plus bending stresses (Columns 4, 8, and 10).Column 13: Number of cycles for the transient (60 years).File No.: -VY-16Q-302 Revision:
0 Page 17 of 34 F0306-01 RO Structural Integrity Associates, Inc. a I Table 5: Safe End Stress Summary 1 2 3 4 5 6 7 8 .9 .10 11 12 13 Total M+B Total M+B Total Total Number Total M+B Pressure Pressure Piping Piping Total M+B of Transient Time Stress Stress Temperature ,Pressure Stress Stress Stress Stress Stress Stress Cycles Number (s) (psi) (psi) F (psig) (psi) (psi) (psi) (psi) psi) (60 years 1 0 0 0 70 0 0 00 0 0.00 0.00 123 0 0 0 70 0, 0. 0 0 0 0.00 0.00 120 2 1680 0 0 100 1100 9780.1 9562.3 339.0875 339.0875 10119.19 9901.39 1201 6960 0 0 100 50 444.55 434.65 339.0875 339.0875 783.64 773.74 120 0 -170 -165 100 50 444.55 434.65 -339.0875
-339.0875
-64.54 -69.44 300 153.2 -235 -212 104.256 50 444.55 434.65 -387.1927
-387.1927
-177.64 -164.54 300 16328.2 2 3 549 1010 -8979.91 8779.93 5414.097 5414.097 14396.01 14197.03 300 16664 -1 0 549 1010 8979.91 8779.93 -5414.097 5414.097 3564.81 14194:03 300 0 2 '549 1010 8979.91 8779.93 -5414.097
-5414.097 3562.81 3363.83 300 3.6 44060 30988 .100 1010 8979.91 8779.93 339.0875 339.0875 53379.00 40107.02 300 1804.6 -15889 -11224 260.286 1010 8979.91 :8779.93 -2150.787
-2150.787
-9059.88 -4594.86 300 4102 21 23 392 1010 8979.91 8779.93 3639.539 3639.539 12640.45 12442.47 "300 0 22 23 ..392 1010 8979.91 8779.93 3639.539 3639.539 12641.45 12442.47 10000 900.1 244 189 310. 1010 8979.91 8779.93 2712.7 2712.7 11936.61 11681.63 10000 5 3600 -169 -110 392 .1010 8979.91 8779.93 -3639.539
-3639.539 5171.37 5030.39 10000 3684.4 33 35 392 1010 8979.91 8779.93 3639.539 3639.539 12652.45 12454.47 10000 F -4100 22 23 392 .1010 8979.91 8779.93 3639.539 3639.539 12641.45 12442.47 10000 0 22 23 .392 1010 8979.91 8779.93 3639.539 3639.539 12641.45 12442.47 2000 1800.1 196 159 280 1010 8979.91 8779.93 2373.612 2373.612 11549.52 11312.54 2000 6 5400.2 -108 -68 392 1010 8979.91 8779.93 -3639.539
-3639.539 5232.37 5072.39 2000 5496.6 29 31 392 1010 8979.91 8779.93 3639.539 3639.539 12648.45 12450.47 2000 5900 22 23 392 1010 8979.91 8779.93 3639.539 3639.539 12641.45 12442.47 2000 0 22 23 392 1010 8979.91 8779.93 3639.539 3639.539 12641.45 12442.47 10 97.3 180 137 385.135 1010 8979.91 8779.93 3561.945 3561.945 12721.85 12478.87 10 1884.1 63 65 265 1010 8979.91 8779.93 2204.069 2204.069 11246.98 11049.00 10 2059.2 1161 859 226.597 1010 8979.91 8779.93 1770.003 1770.003 11910.91 11408.93 10 9 3420.1 -334 -211 265 1010 8979.91 8779.93 -2204.069
-2204.069 6441.84 6364.86 10 3490.2 97 98 265 1010 8979.91 8779.93 2204.069 2204.069 11280.98 11082.00 10 5400.1 -126 -80 " 392 1010 8979.91 8779.93 -3639.539
-3639.539 5214.37 5060.39 10 5470.6 31 32 392 1010 8979.91 8779.93 3639.539 3639.539 12650.45 12451.47 10 5900 22 23 392 1010 8979.91 8779.93 3639.539 3639.539 12641.45 12442.47 10 0 23 22 392 1010 8979.91 8779.93 3639.539 3639.539 12642.45 12441.47 70 77.1 2308 3188 285.461 1010 8979.91 8779.93 2435.338 2435.338 13723.25 14403.27 70 169.4 13 265 1010 8979.91 8779.93 -2204.069
-2204.069 6763.84 6562.86 70 10 1890 74 72 265 1010 8979.91 8779.93 2204.069 2204.069 11257.98 11056.00 70 1968.2 -1069 -1511 322.362 1010 8979.91 8779.93 -2852.427
-2852.427.
5058.48 4416.50 70 2147.2 91 90 392 1010 8979.91 8779.93 3639.539 3639.539 12710.45 12509.47 70 2570 23 22 392 1010 8979.91 8779.93 3639.539 3639.539 12642.45 12441.47 70 0 27 392 1010 8979.91 8779.93 -3639.539
-3639.539 5311.37 5113.39 10 2.9 -20317 -13859 565 1.147 10197.98 9970.871 -5594.944
-5594.944
-15713.97
-9483.07 '10 6.8 42852 29563 565 1172 10420.25 10188.2 5594.944 5594.944 58867.20 45346.14 .10 1567.4 -15216 -10526 565, 1135 10091.29 9866.555 -5594.944
-5594.944
-10719.66
-6254.39 10 2168.4 60377 41773 50 '1134 10082.39 9857.862 -226.0583
-226.0583 70233.34 51404.80 10 11 5409.4 -14924 -10329 565 1054 9371.114 9162.422 -5594.944
-5594.944
-11147.83
-6761.52 10 6730.4 60377 41773 50 1133 10073.5 9849.169 -226.0583
-226.0583 70224.44 51396.11 10 7243.2 -1965 .-1434 128.917 675 6001.425 5867.775 -665.9339
-665.9339 3370.49 3767.84 10 18215.4 52636 36417 .100 1010 8979.91 8779.93 339.0875 339.0875 61955.00 45536.02 10 20015.5 -24511 -16189 260.183 1010 8979.91 8779.93 -2149.623
-2149.623
-17680.71
-9558.69 10 22314.5 22 23 392 937 8330.867 8145.341 3639.539 3639.539 11992.41 11807.88 10 0 23 22 392 1010 8979.91 8779.93 3639.539 3639.539 12642.45 12441.47 60 10 23 22 392 1135 10091:29 9866.555 3639.539 3639.539 13753.82 .13528.09 60 30 23 22 392 940 8357.54 8171.42 3639.539 3639.539 12020.08 11832.96 60 90 3174 4383 275 940 8357.54 8171.42 2317.098 2317.098 13848.64 14871.52 60 2793.5 -16189 -24511 260.183 -941 8366.431 8180.113 -2149.623
-2149.623
-9972.19 -18480.51 60 5091 23 22 392 1010 8979.91 8779.93 3639.539 3639.539 12642.45 12441.47 60 0 23 22 392 1010 8979.91 8779.93 3639.539 3639.539 12642.45 12441.47 1 10 23 22 .392 1375 12225.13 11952.88 3639.539 3639.539 15887.66 15614.41 1 30 23 22 392 940 8357.54 8171.42 3639.539 3639.539 12020.08 11832.96 _1, 90 3174 4383 275 940 8357.54 8171.42 2317.098 2317.098 13848.64 1487,1.52 1 2793.5 -16189 -24511 260.183 941 8366.431 8180.113 -2149.623
-2149.623
-9972.19 -18480.51 1.5091 23 22i 392 1010 8979.91 8779.93 3639.539 3639.539 12642.45 12441.47 1 I I I I I I I U I I I I I I File No.: VY-16Q-302 Page 18 of 34 Revision:
0 I I I F0306-OI RO V Structural Integrity Associates, Inc.Table 5: Safe End Stress Summary (continue) 1 2 3 4 5 6. 7 8 9 10 11 12 13 Total M+B Total M+B Total Total Number Total M+B Pressure Pressure Piping Piping Total M+B of Transient Time Stress Stress Temperature Pressure Stress Stress Stress Stress Stress Stress Cycles Number W (psi R psi) F (osil) (pspsi) ps fps Jt i)} (s (psi) (60 years)0 22 23 392 1010 8979.91 8779.93 3639.539 3639.539 12641.45 12442.47 1 60 4383 3174 275 885 7868.535 7693.305 23.17.098 2317.098 14568.63 13184.40 1 14 148 420 300 258.492 803 7139.473 6980.479 2130.509 2130.509 9689.98 9410.99 1 960 544 424 100 50 .444.55 434.65 339.0875 339.0875 1327.64 1197.74 1 1460 137 139 100 50 444.55 434.65 339.0875 339.0875 920.64 912.74 1 0 23 22 392 1010 8979.91 8779.93 3639.539 3639.539 12642.45 12441,47 228 10 23 22 392 1135 10091.29 9866.555 3639.539 3639.539 13753.82 13528.09 i228 30 23 22 392 940 8357.54 8171.42 3639.539 3639.539 12020.08 11832.96 228 90 3174 4383 275 940 8357.54 8171.42 2317.098 2317.098 13848.64 14871.52 228 2793.5 -16189 -24511 260.183 941 8366.431 8180.113 -2149.623
-2149.623
-9972.19 -18480.51 228 5091 23 22 .392 1010 8979.91 8779.93 3639.539 3639.539 12642.45 12441.47 228 0 22 23 392 1010 8979.91 8779.93 3639.539 3639.539 12641.45 12442.47 300 19 1800 219 177 265 1010 8979.91 8779.93 2204.069 2204.069 11402.98 11161.00 ' 300 2300 72 .74 265 1010 8979.91 8779.93 2204.069 2204.069 11255.98 11058.00 300 0 -109 .-105 265 1010 8979.91 8779.93 -2204.069
-2204.069 6666:84 6470.86 300 20 4 -17288 -12189 440.106 1010 8979.91 8779.93 -4183.277
-4183.277
-12491.37
-7592.35 300 4425 1 549 1010 8979.91 8779.93 -5414.097
-5414.097 3563.81 3364.83 300 0 2 549 1010 8979.91 8779.93 -5414.097
-5414.097 3562.81 3363.83 300 4 44060 30988 100 1010 897,9.91 8779.93 339.0875 .339.0875 53379.00 40107.02 300 20A 241 -7461 -5525 290.247 .1010 8979.91 8779.93 -2489.433
-2489.433
-970.52 765.50 300 572 128 132 .549 1010 8979.91 8779.93 5414.097 5414.097 14522.01 14326.03 300 951 2 549 1010 8979.91 8779.93 -5414.097.
-5414.097 3562.81 3363.83 300 0 2 549 1010 8979.91 8779.93 -5414.097
-5414.097 3562.81 3363.83 300 138 62 45 545.167 989 8793!199 8597,377 5370.773 5370.773 14225.97 14013.15 300 21-23 6264 20 374.97 50 444.55 434.65 -3447.05 *-3447.05
-3007.50 -3032.40 300 6390 104 59 366.172 50 .444.55. 434.65 3347.607 3347.607 3896.16 3841.26 300 15644 -173 -167 100 50 444.55 434.65 -339.0875
-339.0875
-67.54 -71.44 300 0 0 0 100 50 444.55 434.65 339.0875 339.0875 783.64 773.74 1 24 600 0 0 100 1563 13896.63 13587.16 339.0875 339.0875 14235.72 13926.25 1 2400 0 0 100 50 444.55 434.65 339.0875 339.0875 783.64 773.74 1 0 0 0 100 1 0 O 0 339.0875 339.0875 339.09 339.09 123 25 1580 0 0 70 00 .0 0 " -0 .0 0.00 0.00 123 NOTES: Column 1: Transient number identification.
Column 2: Column 3: Column 4: Column 5: Column 6: Column 7: Column 8: Column 9: Column 10 Column I1: Column 12 Column 13 Time during transient where a maxima or minima stress intensity occurs from P-V.OUT output file.Maxima or minima total stress intensity from P-V*OUT output file.Maxima or minima membrane plus bending stress intensity from P-V.OUT output file.Temperature per total stress intensity.
Pressure per Table 2.Total pressure stress intensity from the quantity (Column 6 x 8891)/1000
[Table 3, 11.Membrane plus bending pressurestress intensity from the quantity (Column 6 x 8693)/1000
[Table3, f].Total external stress from calculation in Table 3, 5707.97 psi*(dolumn 5-70&deg;F)/(575&deg;F
-70&deg;F).Same as Column 9, but for M+B stress.Sum of total stresses (Columns 3, 7, and 9).Sum of membrane plus bending stresses (Columns 4, 8, and 10).Number of cycles for the transient (60 years).File No.: VY-16Q-302 Revision:
0 Page 19 of 34 F0306-01 RO Structural Integrity Associates, Inc.Table 6: Fatigue Results for Blend Radius (60 Years)LOCATION = LOCATION NO. 2 -- BLEND RADIUS FATIGUE CURVE = 1 (1 = CARBON/LOW ALLOY, 2 = STAINLESS STEEL)m =2.0 n= .2 Sm = 26700. psi Ecurve 3.OOOE+07 psi Eanalysis
= 2.670E+07 psi Kt = 1.00 I I I I UI MAX 74568.70231.69395.67667.67667.67667.67282.67142.66791.66791.66791.66791.66298.66298.66298.66298.66298.64150.64150.59772.58992.55364.55364.55364.55364.55042.54965.*54965.54965.53963.53963.53963.53963.53963.53963.53963.53963.53963.53963.51835.51835.51835.51782.MIN RANGE MEM+BEND Ke Salt Napplied Nallowed 0.0.0.0.0.0.0.0.0.0.16.1902.1902.1902.1902.30389.31068.31068.31070.31070.31070.31070.31682.32964.34282.34282.34282.34317.34327.34327.34328.34329.34329.34329.34329.41522.43358.43358.43358.43358.46000.46000.46000.74568.70231.69395.67667.67667.67667.67282.67142.66791.66791.66775.64889.64396.64396.64396.35909.35230.33081.33079.28702.27922.24293.23681.22400.21082.20761.20683.20648.20638.19637.19636.19635.19635.19635.19635.12441.10605.10605.10605.8477.5835.5835.5783.62689.58499.59106.59377.59377.59377.60118.60462.62353.62353.62337.60505.47410.47410.47410.21760.23734.34263.34283.31815.31800.25433.17402.17300.17307.18195.18463.18464.18463.17393.17401.17413.17413.17413.17413.10688.9647.9.647.9647.7712 5149.5146.6568.1.000 1 000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000.1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 41892..39456.38986.38015.38015.38015.37799.37720.37523.37523.37514.36454.36177.36177.36177.20173.19792.18585.18584.16125.15687.13648.13304.12584.11844.11663.11620.11600.11595.11032.11031.11031.11031.11031.11031.6989.5958..5958.5958.4762.3278.3278.3249.1000E+01 1. OOOE+01 1.OOOE+01 9. 300E+01 1.200E+02.8. 700E+01 1.OOOE+01 1.OOOE+01 1. OOOE+00 1. 500E+01 1.230E+02 9.OOOE+01 3.000E+01 1. OOOE+00 1. OOOE+00 1.OOOE+00 2. 670E+02 3.300E+01 2.700E+01 1.OOOE+00 1. OOOE+00 2 .710E+02 1. OOOE+01 1.OOOE+01 9. OOE+00 7 .OOOE+01 2.210E+02 1. OOOE+01 6.900E+01 2. 310E+02 3. OOOE+02 3. OOOE+02 3. OOOE+02 3.OOOE+02 3. 0OOE+02 1.200E+02 6. OOOE+01 1. OOOE+00 8.800E+01 1. 400E+02 3. OOOE+02 9. 560E+03 1. OOOE+01 7.488E+03 8. 944E+03 9.2 68E+03 9. 988E+03 9. 988E+03 9. 988E+03 1. 018E+04 1.025E+04 1.044E+04 1.044E+04 1. 045E+04 1. 152E+04 1. 182E+04 1.182E+04 1. 182E+04 9. 581E+04 1.038E+05 1. 303E+05 1.303E+05 22. 222E+05 2 519E+05 4. 757E+05 5. 703E+05 9.414E+05 1. 912E+06 2. 231E+06 2. 310E+06 2.348E+06 2. 358E+06 3.757E+06 3.-758E+06 3.760E+06 3.760E+06 3. 760E+06 3. 760E+06 1. OOOE+20 1.OOOE+20 1. OOOE+20 1.OOOE+20 1.000E+20 1.000E+20 1. OOOE+20 1. OOOE+20.0013.0011.0011.00.93.0120.0087.0010.0010.0001.0014.0118.0078.0025.0001.0001.0000.0026.0003.0002.0000 0000.0006.0000.0000.0000.0000.0001.0000.0000.0001.0001.0001.0001..0001.0001.oo0o.0000.0000.0000.0000.0000.0000.0000 I I I I I U I I I I I I I I File No.: VY-16Q-302 Revision:
0 Page 20 of 34 F0306-0IRO V Structural Integritv Associates, Inc.I -, Aq1 A AQ1 C ; r 1 1 9 50716.50716.46000.46000.46000.46000.46000.46000.46000.46000.46000.46000.46000.46000.46000.46000.46000.46000.46000.46000.46000.46000.46000.46000.46000.46000.46000.46000.46000.46000.46000.46000.46000.46000.46000.46000.46000.46000.4717.4717.0.0.0.0.0.0.0.0.0..0.0.0.0.0.0.0.0.4582.4582.0.0.0.0.0.0.0.0.0.0.0.0.0.0.0.0.0.1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000.1.000 2761.2650.2650.0.0.0.0.0.0.0.0.0.0.0.0.0.0.0.0.0.1. 00.OE+01 6. OOOE+01 2.280E+02 1. 320E+02 1. OOOE+04 2. OOOE+03 2. OOOE+03 1.OOOE+01 1. OOOE+01 7. OOOE+01 7.OOOE+01 1.OOOE+01 1. OOOE+01 6. OOOE+01 6. OOOE+01 1. OOOE+00 1. OOOE+00 1. OOOE+00 2. 280E+02 2.. 280E+02 1. OOOE+20 1. OOOE+20 1.00 OE+20 1.OOOE+20 1.OOOE+20 1.OOOE+20 1. OOOE+20 1.OOOE+20 1.OOOE+20 1.OOOE+20 1.OOOE+20 1.OOOE+20 1.OOOE+/-20 1. OOOE+20 1.000E+20 1.OOOE+20 1. OOOE+20 1.OOOE+20 1.OOOE+20 1.OOOE+20.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0636 TOTAL USAGE FACTOR =File No.: VY-16Q-302 Revision:
0 Page 21 of 34 F0306-01 RO Structural Integrity Associates, Inc.Table 7: Fatigue Results for Safe End (60 Years)LOCATION = LOCATION NO. 1 SAFE END FATIGUE CURVE = 1 (1 = CARBON/LOW ALLOY, 2 = STAINLESS STEEL)m = 3.0 n= .2 Sm = 17800. psi Ecurve = 3.000E+07 psi Eanalysis
= 2.810E+07 psi Kt = 1.34 MAX:70233.70224.61955.58867.53379.53379.53379.53379.53379.53379.53379..15888.14569.14522.14522.14396.14396.14236.14226.14226.13849.1384 9.13849.13849.13754.13754.13723.13723.12722.12710.12652.12652.12652.12652.12652.12652.12652.12652.12652.12652.12652.12652.12652.MIN RANGE MEM+BEND Ke Salt Napplied Nallowed-17681.-15714.-12491.-12491.-12491.-11148.-10720.-9972.-9972.-9972.-9060.-9060.-9060.-9060.-3008.-3008.-971.-971.-971.-178.-178.-178.-178.-68.-68.-68.-68.-65.-65.-65.-65.0.0.0.339.784.784.784.921.1328.3370.3563.3563.87914.85938.74446.71359.65870.64527.64099.63351.63351.63351.62439.24948.23629.23582.17530.17404.15367.15206.15196.14404.14026.14026.14026.13916.13821.13821.13791..13788.12786.12775.12717.12652.12652.12652.12313.11869.11869.11869.11732.11325.9282.9090.9090.60963. 1.283 60879. 1.280 53128. 1.000 52938. 1.000 47699. 1.000 46869. 1.000 46361. 1.000 58588. 1.194 58588. 1.194 58588. 1.194 44702. 1.000 20209. 1.000 17779. 1.000 18921. 1.000 17358. 1.000 17229. 1.000 13432. 1.000 13161. 1.000 13248. 1.000 14178. 1.000 15036. 1.000 15036. 1.000 15036.. 1.000 14943. 1.000 13600. 1.000 13600. 1.000 14475. 1.000 14473. 1.000 12548. 1.000 12579. 1.000 12524. 1.000 12454. 1.000 12454. 1.000 12454. 1.000 12115. 1.000 11681. 1.000 11681. 1.000 11681. 1.000 11542. 1.000 11257. 1.000 8687. 1.000 9091. 1.000 9091. 1.000 74422.72869.49383.47700.43819.42951.42631.53087.53087.53087.41444.16985.15840.16022.12508.12417.10641.10506.10516.10262.10216.10216.10216.10141.9846.9846.9.989.9987.9103.9102.9061.9014.9014.9014.8772.8456.8456.8456.8357.8088.6531.6502.6502.1.OOOE+01 1.OOOE+01 1.000E+01 1. OOOE+01 2. 800E+02 1.000E+01 1. OOOE+01 6.OOOE+01 1. IOOE+00 2.280E+02 1. 100E+01 1. OOOE+00 1. 000E+00 2.870E+02 1. 300E+01 2.870E+02 1. 300E+01 1. OOOE+00 2. 860E+02 1.400E+01 6. OOOE+01 1. OOOE+00 2. 250E+02 3. OOOE+00 6. OOOE+01 2.280E+02 9. OOOE+00 6.100E+01 1.OOOE+01 7. OOOE+01 1 590E+02 1.230E+02 1. 200E+02 1. 230E+02 1. 230E+02 1. 200E+02 1. OOOE+00 1. OOOE+00 1. OOOE+00 1.OOOE+00 1000E+01 3.OOOE+02 3. OOOE+02 1.338E+03 1.415E+03 4. 568E+03 5. 094E+03 6. 552E+03 6.953E+03 7. 109E+03 3. 628E+03 3. 628E+03 3. 628E+03 7.731E+03 1.802E+05 2. 410E+05 2.287E+05 9. 944E+05 1. 083E+06 5. 165E+06 5.563E+06 5. 531E+06 6. 379E+06 6. 547E+06 6. 547E+06 6. 547E+06 6. 837E+06 8. 117E+06 8. 117E+06 7 .465E+06 7.474E+06 1.729E+07 1.730E+07 1. 833E+07 1. 959E+07 1. 959E+07 1. 959E+07 2. 905E+07 4. 952Et07 4 .952E+07 4. 952E+07 5.4 62E+07 7. 100E+07 1.OOOE+20 1.OOOE+20 1. OOOE+20 U.0075.0071.0022.0020.0427.0014.0014.0165.0003.0628.0014.0000.0000 0013.0000 0003.0000.0000.0001.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000 0000.0000.0000.0000.0000.0000.0000 I I I I I I I I I U U I I I I I I I I File No.: VY-16Q-302 Revision:
0 Page 22 of 34 F0306-01RO H Structural Integrity Associates, Inc.12652.12652.12652.12652.12652.12652.12652.12650.12648.12642.12642.12642.12642.12642.12642..12642.12642.12641.12641.12641.12641.12641.12641.12641.12641.12641.12641.12641.12641.12641.12641.12641.12641.12641.12641.12641.1264 1.12641.12641.12641.12641.1264 1.12641.12641.12641.12641.3563.3563.3564.3565.3896.5058.5171.5171.5171.5171.5171.5171.5171.5171.5171.5171.5171.5171.5214.5232.5311.6442.6667.6764.9690.10119.11247.11256.11258.11281.11403.11550.11911.11937.11937.11992.12020.12020.12020.12640.12641.12641.12641.12641.12641.12641.9090.9090.9089.9088.8756.7594.7481.7479.7477.7471.7471.7471.7471.7471.7471.7471..7471.7470.7427.7409.7330.6200.5975.5878.2951.2522.1394.1385.1383.1360.1238.1092.731.705.705.649.621.621.621.1.0.0.0.0.0.0.9091.9091.9090.-1740.8613.8038.7424.7421.7420.7411.7411.7411.7411.7411.7411.7411.7411.7412.7382.7370.7329.6078.5972.5880.3031.2541.1393.1384.1386.1360.1281.1130.1034.761.761.635.610.610.610.0.0.0.0.0.0.0.1.000 1.000 1.000 1.000 1.000 1.000 1.0oo 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1 .00.0 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000O 1.000 6502.6502.6501.4535 6237.5513.5341.5339.5338.5333.5333.5333.5333.5333.5333.5333.5333.5333.53.04.5293.5243.4412.4273.4.205.2126.1808.997.991.990.973.894.788.578.514.514.462.442.442.442.1.0.0.0.0.0.0." 3. OOOE+02 3. OOE+02 3.OOOE+02 3. OOOE+02.3. OOOE+02 7. 000E+01 7.048E+03 1.OOOE+01*2.0OOE+03 7.OOOE+01 7. 000E+01 6. OOOE+01 6. OOOE+01 1.OOOE+00 1. OOOE+00 2.280E+02 2.280E+02 2.240E+02 1.OOOE+01 2. OOOE+03 1. 000E+0.1 1.OOOE+01 3.OOOE+02 7.000 E+01 1. OOOE+00 1.200E+02 1.OOOE+01 3. OOOE+02 7. OOOE+01 1.OOOE+01 3. OOOE+02 2. OOOE+03 1.OOOE+01 4. 555E+03 5. 445E+03 1. OOOE+01 6. OOOE+01 1. OOOE+00 2.280E+02 3. OOOE+02 3. 956E+03 2. OOOE+03 2. 000E+03 1.OOOE+01 1. OOOE+01 1. OOOE+00 1.000E+20 1.OOOE+20 1.OOOE+20 1. OOOE+20 1.000E+20 1.OOOE+20 1. OOOE+20 1. OOOE+20 1.000E+20 1. OOOE+20 1.000E+20 1. OOOE+20 1.OOOE+20 1. 00OE+20 1.000E+20 1.OOOE+20 1.OOOE+20 1.006E+20 1.OOOE+20 1. OOOE+20 1. OOOE+20 1. OOOE+20 1. OOOE+20 1. OOOE+20 1.OOOE+20 1.OOOE+20 1.OOOE+20 1.060E+20 1.OOOE+20 1.OOOE+20 1. 000OE+20 1. OOOE+20 1.OOOE+20 1. OOOE+20 1.OOOE+20 1. OOOE+/-20 1.OOOE+20 1. OOOE+20 1.OOOE+20 1. OOOE+20 1.000E+20 1.OOOE+20 1.OOOE+20 1. OOOE+20 1.OOOE+20 1. OOOE+20.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000..0000.0000.0000.oooo.0000.0000.0000 0000.0000-.0000.00ooo.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000,.0000.0000.0000.1471 TOTAL USAGE FACTOR File No.: VY-16Q-302 Revision:
0 Page 23 of 34 F030601 RO
! Structural Integrity Associates, Inc.Time (sec) 92825r0 Note: A typical set of two Green's Functions is shown, each for a different set of heat transfer coefficients (representing different flow rate conditions).
Figure 1: Typical Green's Functions for Thermal Transient Stress I I I File No.: VY-16Q-302 Revision:
0 Page 24 of 34 F0306-O1RO V Structural Integrity Associates, Inc.&#xfd; W&#xfd;n I .-I .200 .+SOS,-2&#xfd;5 Skp 1-15 SkP.IIlllll Is1%n.02400 4W6080r10400
-W IAK180 IBMZOW Tbminss SJI 6.=15 ,i*,.-41.. ..S i i:' ii : i 0- ."-6O 0!20 .400 600 8$0 10001200 140 1600 ?N Tbm.,.w Figure 2: Typical Stress Response Using Green's Functions File No.: VY-16Q-302 Revision:
0 Page 25 of 34 F0306-O I RO Structural Integrity Associates, Inc.I Fj Figure 3: External Forces and Moments on the Feedwater Nozzle[- Temp (&deg;) --Pressure (psig)60 1 70 60 50 , 40.4, 30 20 0-0.0.Stress.exe program calculates steady state values at beginning of transients.
The time length for this transient can therefore be any value greater than zero.The chosen length of 10 seconds has no significance as there is no temperature change during this transient.
-1 0 1 2 3 4 5 Time (seconds)6 7 8 9 10 Figure 4: Transient 1, Bolt-up File No.: VY-16Q-302 Revision:
0 Page 26 of 34 F0306-O1 RO I Structural Integrity Associates, Inc.17Temp CT) --pressure (psig)l 120*100 8O E 40 20 1200 I I a 1000 2000 3000 4000 5000 6000 Time (seconds)Figure 5: Transient 2, Design HYD Test-Temp ('F) -Pressure (psig)600-1080 1040 300 E I8 a 5000 10000 15000 20000 Time (seconds)Figure 6: Transient 3, Startup File No.: VY-16Q-302 Revision:
0 Page 27 of 34 F0306-OI RO V Structural Integrity Associates, Inc.-&#xfd;Temp VF)--Prsrepsg 600.500 400 300 E 2-200 I--Temp ('F) m -Pressure (psig) ]S.t'ess.exe program automatically calculates steady stale conditions at beginning of transients.
This transient 1 begins at 549*F and steps Idown to 100F in one second.Temperature of 100"F is held long enough so that steady state is reached. It is conservatively assumed that steady state is reached before the next temperature spike occurs.emperature of 392'F is held for 5000 seconds so that steady state is reached. That way, this transient will match up with the following one which will start off at a steady state of 392&deg;F. No length of time for the 392"F value is specfied on the thermal cycle diagrams, so steady state conditions were assumed. -I 1080 1040 1000 960 920 880 840 800 760 720-680-640-600 560-520 480 440 400 360 320 280 240 200 160 120 80 40 a I-100 .f-0 0 1000 2000 3000 4000 Time (second!5000 6000 7000 8000 Figure 7: Transient 4, Turbine Roll and Increased to Rated Power 1--Temp (&deg;F) --Pressure (psig) I I I I I I I I I I I I I I I I I I I I 800 700 600 500 400 300 200 100 0-1200 1160 1120 1080 1040 1000 860 920 880 840-600 760*-680.640 600 560.520 480 440 400 360 320 280 240 200 160 120 80 40 0 P 5-i Stress.exe program calculates steady state values at beginning of transients.
The time length for this transient can therefore be any value greater than zero. The chosen length of 10 seconds has no" significance as there is no temperature change during this transient.
u 1000 2000 '3000 4000 5000 6000 7000 8000 Time (seconds)Figure 8: Transient 5, Daily Reduction 75% Power File No.: VY-16Q-302 Revision:
0 Page 28 of 34 F0306-OI RO V Structural Integrity Associates, Inc.!-Temp(F)-n
-Pressure (psig)I 6MP 5M0 400.300 E 200 100 0-1080 1040 1000 960 920 880 840 800-760-720 F 680-640-600-560 520-480-440-400-360-320-280-240 200 160.120 80-40 0C 5oo 1000 1500 2000 2500 3000 3500 4000 4500 Time (seconds)5000 5500 6000 6500 Figure 9: Transient 6, Weekly Reduction 50% Power I -- Temp (F) ---Pressure (psig)450 0.o S 8 4,.4000 5000 Time (seconds)Figure 10: Transient 9, Turbine Trip at 25% Power File No.: VY-16Q-302 Revision:
0 Page 29 of 34 F0306-01 RO Structural Integrity Associates, Inc..-Temp (T) -=Pressure (psig)5oo 450 400 350-300 250 E 1- 200 150 100 so 0-0 600 550 500 450 400&#xfd;'- 350 300 E' 250 200 150 100 50 0 13-40 0 h0 7000 1000 2000 3000 4000 5000 600 Time (seconds)Figure 11: Transient 10, Feedwater Bypass{- Temp (F) ---Pressure (psig).1200 1000 a 600 a.5000 10000 15000 .20000 25000 Time (seconds)Figure 12: Transient 11, Loss of Feedwater Pumps File No.: VY-16Q-302 Revision:
0 Page 30 of 34 F0306-OI RO VStructural Integrity Associates, Inc.-Temp (F) --Pressureps), 250 200 1080 1020-980-940 900 860 820 780 740 o 700 660 620 580 540 500-30 970 1970 2970 3970 Time (seconds)..Figure 13: Transient*12, Turbine Generator Trip-I Temp (&deg;F) ---Pressure (psig)fl 4970 1100 1050 1000 950 350 300 250 E 200 150 100 50 0a 350 300 250 200 150 100 50 0 1000 2000 3000 4000 5000 Time (seconds)Figure 14: Transient 14, SRV Blowdown File No.: VY-16Q-302 Revision:
0 Page 31 of 34 F0306-O1 RO Structural Integrity Associates, Inc.I- Temp (F) --Pressure (psig)4 L 400-350 4 300 E 250 200 150 1080 F 1040 1000 960 920 880 840-800-760-720-680-640-600 7-560.-520 =.480-440 a.400.360* 320.280 240 200 160 120 s0 40 0 0 500 1000 1500 2000 2500 3000 3500 4000 4500 5000 5500 6000 6500 Time (seconds)Figure 15: Transient 19, Reduction to 0% Power I- Temp (-F) --Pressure (psig)]600 1100 1000 6 E 1!0.100 200 300 400 500 600 700 800 900 1000 Time (seconds)Figure 16: Transient 20, Hot Standby (Heatup Portion)File No.: VY-16Q-302 Revision:
0 Page 32 of 34 F0306-OIRO V Structural Integrity Associates, Inc.I-Temp (*F) --rsue(s 600 500 E 200-100 0-(_'F) --Pressure (psig) [This transient continues at steady state to 5451 seconds.1100 1000 900 800 5 0-700 600 1500 600 700 800 900 1000 0 100 200 300 400 500 Time (seconds)Figure 17: Transient 20A, Hot Standby (Feedwater Injection Portion)"The pressure between tis Temp (&deg;F) --Pressure (psig)point and the next is shown 600 as a straight line for -1150 simplicity.
The pressure 1100 actually follows saturation.
1050 1000 500" 950 9 000-850 500 400 750 700 650 'a.600 a 300 550 500 S .450 400 200 \ 350 300 250 200 100 150 100 I-1 50 14000 16000 18000 20000 2000 4000 6000 8000 10000 12000 Time (seconds)Figure 18: Transient 21-23, Shutdown File No.: VY-16Q-302 Revision:
0 Page 33 of 34 F0306-01 RO V Structural Integrity Associates, Inc. " 150 130 110
-(psig)/\/\//\/////I///70 E 12 1600 1500 1400 1300 1200 1100 1000 900 800 700 600 500-400* 300 200-100 S 50-30 10 f/////-104 -,-~ 0 0 100 200 300 400 500 600 700 800 Time (seconds)900 1000 1100 1200 1300 Figure .19:. Transient 24, Hydrostatic Test-- Pressure (psig)I I I, I I I I I I I I I I I I 150 -130--500.400 110 90 so a70 s.50.300 200 a.30 10 100-101 0 1000 2000 3000 Time (seconds)4000 5000 64 0)00 Figure 20: Transient 25, Unbolt File No.: VY-16Q-302 Revision:
0 Page 34 of 34 I I F0306-01 RO V I Structural Integrity Associates, Inc.APPENDIX A
 
==SUMMARY==
OF OUTPUT FILES File No.: VY-16Q-302 Revision:
0 Page Al of Al F0306-O1RO V Structural Integrity Associates, Inc. -Transient Table.xls Definition of Transients In Computer files BRresults.xls Blend Radius Stress Summary In Computer files SEresults.xls Safe End Stress Summary In Computer files TRANSNT XX.INP Input File for Each Transient In Computer files Green.dat Input File for Green Functions In Computer files P-V XX.OUT Output File for Stress Analysis In Computer files GREEN.CFG Input File for Defining Green Function In Computer files FATIGUE.CFG Input File for Defining Fatigue Analysis In Computer files FATIGUE.DAT Input File for Fatigue Curves In Computer files FATIGUE.inp Input file for Fatigue Analysis from BRresults.xls or In Computer files SEresults.xls FATIGUE.OUT Fatigue Output File In Computer files I I I I I Where XX is defined for each transient.
I I I I I I I File No.: VY-16Q-302 Revision:
0 Page A2 of A2 F0306-01 RO 7&#xfd;&#xfd;REDACTED COPY Structural Integrity Associates, Inc. File No.: VY-16Q-303 NEC-JH_06 ,CALCULATION PACKAGE Project No.: VY-16Q PROJECT NAME: Environmental Fatigue Analysis of VYNPS CONTRACT NO.: 10150394 CLIENT: PLANT: Entergy Nuclear Operations, Inc. Vermont Yankee CALCULATION TITLE: Environmental Fatigue Evaluation of Reactor Recirculation Inlet Nozzle and Vessel Shell/Bottom Head Document Affected Project Manager Preparer(s)
&Revision Pafes Revision Description Approval Checker(s)
Signature
& Date Signatures
& Date 0 -24, Initial issue. Terry J. Herrmann Gary L. Stevens Appendices:
07/05/07 07/05/07 Al -A2, I' I-BI -B2 W. 1V,", In computer files TelTy J. Herrmann 07/05/07 Page 1 of 24 F0306-0 IRO C .011PIR-i's. "Vetrelm" NEC065998 Structural Integrity Associates, Inc.Table of Contents
 
==1.0 INTRODUCTION==
/STATEMENT OF PROBLEM/ OBJECTIVE
...........................................
3 2.0 TECHNICAL APPROACH OR METHODOLOGY
.................................................................
3 3.0 A SSU M PTIO N S / D ESIG N INPU TS ...........................
I ..................................................................
4 4 .0 C A L C U L A T IO N S ........................................................
................
.................................................
6 4.1 RPV Lower Head ................................................................................
..............
..........
7 4.2 R R Inlet N ozzle ..........................................................................................................
9 5.0 R E SU LT S O F A N A L Y SIS ...........................................................................................................
11u
 
==6.0 CONCLUSION==
S AND DISCUSSION
...................................................................................
11 7 .0 RE F E R E N C E S ..............................................................................................................................
12 APPENDIX A VY WATER CHEMISTRY INFORMATION
[8] .............................................
Al APPENDIX B VY LICENSE DATE [10] .........
................................
B I List of Tables Table 1: W ater Chem istry C alculations
.........................................................................................
14 Table 2: Bounding Fen Multipliers for Recirculation Line ..............................
.15 Table 3: Bounding Fen Multipliers for Feedwater Line .........
...........................
16 Table 4: Bounding F,,, Multipliers for RPV Upper Region ..........................................................
17 Table 5: Bounding Fn Multipliers for RPV Beltline Region ............................
18 Table 6: Bounding F,, Multipliers for RPV Bottom Head Region ........................
19 Table 7: EAF Evaluation for RPV Shell/Bottom Head Location ........................
....................
20 Table 8: EAF Evaluation for Limiting RPV ShelllShroud Support Location ..............................
21 3 Table 9: EAF Evaluation for RR Inlet Nozzle Forging Location .................................................
22 Table 10: EAF Evaluation for RR Inlet Nozzle Safe End Location .............................................
23 Table 11: Summary of EAF Evaluation Results for VY ........................................
24 I I File No.: VY-16Q-303 Page 2 of 24 Revision:
0 F0306-OIRO NEC065999 Structural Integrity Associates, Inc.
 
==1.0 INTRODUCTION==
/STATEMENT OF PROBLEM/ OBJECTIVE The purpose of this calculation is to perform a plant-specific evaluation of reactor water environmental effects for the reactor recirculation (RR) inlet nozzle and the reactor pressure vessel (RPV) shell/bottom head locations identified within NUREG/CR-6260
[1] for the older vintage General Electric (GE) plant for the Vermont Yankee Nuclear Power Plant (VY).The water chemistry input used in this calculation covers several portions of the RPV, as well as the feedwater and recirculation lines. Although these regions encompass more areas than needed to address the two components of interest in this calculation, environmental fatigue multipliers are developed for all of these regions in this calculation for potential use in other evaluations associated with this project.2.0 TECHNICAL APPROACH OR METHODOLOGY Per Chapter X, "Time-Limited Aging Analyses Evaluation of Aging Management Programs Under 10 CFR 54.2 l(c)(l)(iii)," Section X.M1, "Metal Fatigue of Reactor Coolant Pressure Boundary," of the Generic Aging Lessons Learned (GALL) Report [2], detailed, vintage-specific, fatigue calculations are required for plants applying for license renewal for the locations identified for the appropriate vintage plant in NUREG/CR-6260.
In this calculation, detailed environmentally assisted fatigue (EAF) calculations are performed for VY for two of the locations associated with the older vintage GE plant in NUREG/CR-6260.
The older-vintage GE plant is the appropriate comparison to VY since the original piping design at VY was in accordance with USAS B31.1 [3], as well as the fact that the older-vintage boiling water reactor (BWR) in NUREG/CR-6260 was a BWR-4 plant, which is the same as VY.Entergy performed an initial assessment of EAF effects for VY in their License Renewal Application (LRA) that was submitted to the NRC in January 2006. Table 4.3-3 of the VY LRA provides the results of those evaluations.
All but two of the VY locations evaluated for EAF in the LRA did not yield acceptable results for 60 years of operation.
Further refined analyses are currently underway in other calculations associated with this project to address those components.
This calculation documents the EAF evaluation for the RR inlet nozzle and RPV shell/bottom head locations, where it is expected that acceptable EAF results can be achieved based on the existing analyses without the need for additional refined evaluations.
File No.: VY-16Q-303 Page 3 of 24 Revision:
0 F0306-01 RO NEC066000 V Structural Integrity Associates, Inc.I I 3.0 ASSUMPTIONS
/ DESIGN INPUTS Per Section X.MI of the GALL Report [2], the EAF evaluation must use the appropriate Fen relationships from NUREG/CR-6583
[4] (for carbonflow alloy steels) and NUREG/CR-5704
[5] (for stainless steels), as appropriate for the material for each location.
These expressions are: Fe, = exp (0.585 -0.00124T'
-0.10IS*T*O*
C*) I For Carbon Steel [4, p. 691: Substituting T' = 256C in the above expression, as required by NUREGi/CR-6583 to relate room temperature air data to service temperature data in water [6], the following is obtained: Fen = exp (0.585 -0.00124(25&deg;C)
-0.101 S* T* 0* E*)= exp (0.554 -0.101 S* T* 0* F*)For Low Alloy Steel [4, p. 69]: Fn = exp (0.929 -0.00124T'
-0.10lS*T*O*
E*)Substituting T = 25'C in the above expression, as required by NUREG/CR-6583 to relate room temperature air data to service temperature data in water [6], the following is obtained: where [4, pp. 60 and 65]: Fen S :1: T 0*Fn = exp (0.929 -0.00124(25&deg;C)
-0.101 S* T* 0* *)=exp (0.898 -0.101 S* T* 0*t')= fatigue life correction factor S for 0 < sulfurcontent, S < 0.015 wt. %0.015 for S > 0.015 wt. %0 for T < 150'C (T -150) for 150< T< 350'C fluid service temperature (0 C)0 for dissolved oxygen, DO < 0.05 parts per million (ppm)ln(DO/0.04) for 0.05 ppm < DO < 0.5 ppm= ln(1.2.5) for DO >0.5 ppm U I I I I I I I I I I I 0 for strain rate, e > 1%/see 1n(s*) for 0.001 < e 1 I%/sec= ln(0.001) for 6 < 0.001%/sec File No.: VY-16Q-303 Revision:
0 Page 4 of 24 F0306-01RO C~OP fAhr \'zridd~ P~&p~ iUa~y Jnf~rmqtirp I I NEC066001 Structural Inte/rity Associates, Inc.For Tyqpes 304 and 316 Stainless Steel [5. p. 31]: F,,, =exp (0.935 -T* wheret[5, pp. 25 and 31]: Fe, = fatigue life correction factor T* = 0 for T < 200'C= 1 for T> 200 0 C T = fluid service temperature
(&deg;C)F,* = 0 for strain rate, z > 0.4%/sec= ln(E/0.4) for 0.0004 _< F _< 0.4%/sec= ln(0.0004/0.4) for F < 0.0004%/sec 0* = 0.260 for dissolved oxygen, DO < 0.05 parts per million (ppm)= 0.172 for DO > 0.05 ppm Bounding F 1 ,, values are determined or, where necessary, computed for each load pair in the detailed fatigue calculation for each component.
The environmental fatigue is then determined as Uenv = (U)(Fen), where U is the original fatigue usage and Unv is the environmentally assisted fatigue (EAF)usage factor. All calculations can be found in Excel spreadsheet "VY-16Q-303 (Env. Fat. Calcs).xls" associated with this calculation.
From Reference
[7], for the BWR, typical DO levels range from just over 200 ppb for normal water chemistry (NWC) conditions to less than 10 ppb for hydrogen water chemistry (HWC) conditions.
Typical HWC system availabilities are greater than 90%. Based on VY-specific water chemistry input for Entergy [8], which is also contained in Appendix A of this calculation, the input shown in Table I is defined for use in this calculation.
The water chemistry input covers several portions of the RPV, as well as the feedwater and recirculation lines. Although these regions encompass more areas than needed to address the two components of interest in this calculation, environmental fatigue multipliers are developed for all of these regions in this calculation for potential use in other evaluations associated with this project.Therefore, based on Table I and for the purposes of this calculation, the following is assumed:* Over the 60-year operating life of the plant, HWC conditions exist for 47% of the time, and NWC conditions exist for 53% of the time." All operation through 11/1/2003 was assumed as NWC using the dissolved oxygen values from the "Pre-NMCA" column in Appendix A, and all operation after 11/1/2003 was assumed as HWC using the maximum oxygen values from the "Post-NMCA
+ HWC (OLP)", "Post-NMCA
+ HWC (EPU)", and "Future Operation" columns in Appendix A.* Recirculation line DO is 122 ppb pre-HWC and 48 ppb post-HWC.* Feedwater line DO is 40 ppb for pre-HWC and 40 ppb for post-HWC conditions.
* RPV Upper Region DO is 114 ppb pre-HWC and 97 ppb post-HWC.* RPV Beltline DO is 123 ppb pre-HWC and 46 ppb post-HWC.* RPV Bottom Head Region DO is 128 ppb pre-HWC and 69 ppb post-HWC.File No.: VY-16Q-303 Page 5 of 24 Revision:
0 e k 'tLah15 VU1d P UjJ P jtLLL y filkr l lttJfiie F0306-OIRO NEC066002 Structural Integrity Associates, Inc.Based on the above typical DO levels, bounding Fen multipliers for each of the three applicable I materials (carbon, low alloy, and stainless steels) are shown in Tables 2 through 6 for the various RPV and piping regions.The projected number of cycles used in this calculation is based on the number of cycles actually experienced by the plant in the past and forward-projected with some additional margin for 60 years of operation, as documented in Reference
[9]. In addition, the latest governing stress analysis for I each location was utilized, and any relevant effects of Extended Power Uprate (EPU) operation were incorporated as necessary.
With these assumptions, the cumulative usage factor (CUF) values documented in this calculation are considered applicable for sixty years of operation including all I relevant EAF and EPU effects.I 4.0 CALCULATIONS The analyses for the NUREG/CR-6260 locations identified in Section 2.0 are provided in this U section. As previously noted, the fatigue calculations for 60 years for all locations make use of the 60-year projected cycles for VY from Reference
[9], and incorporate EPU effects.Since the Fen methodology documented in References
[4] and [5] is relatively "new" technology, it is intended to apply to "modern-day" fatigue analyses, i.e., applied to fatigue analyses that use current ASME Code fatigue curves, etc. Therefore, to be consistent with this approach, the evaluation for the all locations will also utilize modern-day fatigue calculation methodology using the 1998 Edition, 2000 Addenda of the ASME Code [ II ]. This involves applying a Young's Modulus correction factor (i.e.,
to the calculated stresses, applying K, where appropriate, and utilizing the 2000 Addenda fatigue curve.NOTE: It is recognized that some of the ref'erences used in this calculation are not the latest revision;for example, Reference
[12] (VYC-378, Revision 0) has been revised. However, the details necessary to peiform the evaluations in this calculation are not necessarily contained in the latest revision of all documents.
Therefore, wherever necessary, the I appropriate revision of the governing document is referenced in order to obtain all appropriate inputs necessary to performn the EAF calculations.
So, it should be recognized that, despite using what appear to be outdated revisions of some references, use of these I references isJbr input data use only. All calculations represent the latest available analyses for all locations.
NOTE: Hand calculations may yield results slightly different than the values shown in the tables of this calculation due to round-off based on the significant figures utilized by the spreadsheet used for these calculations.
I File No.: VY-16Q-303 Page 6 of 24 R e v i s io n : 0 e. ..VIrie n r PT r u p i i ct u y F0306-01 RO NEC066003 Structural Integrity Associates, Inc.4.1 RPV Lower Head The 60-year CUF value (without EAF effects) for the RPV shell/bottom head location was reported in Table 4.3-3 of the VY LRA submittal to be 0.400. The EAF CUF estimated by Entergy for this location was 0.98, based on an overall Fe, of 2.45. Based on this result, further refined analysis would no~t normally be necessary to show acceptable EAF CUF results for this component.
However, the calculation for this location is updated in this section to reflect the updated water chemistry information supplied for this project.The CUF value reported in the VY LRA for the RPV shell/bottom head location is 0.400. This value is the original design basis CUF from the RPV Stress Report, as noted on page B8 of Reference
[12].However, as noted on page A61 of Reference
[ 12), this CUF corresponds to Point 8, which is located on the outside surface of the RPV bottom head at the Junction with the support skirt. Therefore, this location is not exposed to the reactor coolant, and EAF effects do not apply. Based on this, evaluation of the limiting location along the inside surface of the RPV bottom head was performed.
Based on a review of the primary plus secondary stresses tabulated for all locations along the bottom head on page A52 of Reference
[12], Point 14 was selected for EAF evaluation.
Per Section 3.2.1.2 of Reference
[13], none of the CUF values for the RPV bottom head region were evaluated for the effects of EPU, as the CUF values are below the EPU screening criteria value of 0.5. Therefore, as a part of the evaluation for this location, EPU effects were included.
Per References
[14] and [19], the RPV shell material is low alloy steel (A-533, Grade B).The new CUF calculation for Point 14 for 40 years, which includes the use of updated methodology and incorporates EPU effects [ 14], is shown at the top portion of Table 7. The CUF for 40 years (without EAF effects) is 0.0057.The fatigue calculation for 60 years for the RPV shell/bottom head location is also shown in Table 7.The results show a CUF (without EAF effects) of 0.0085 for 60 years. The fatigue calculation for 60 years makes use of the 60-year projected cycles for VY from Reference
[9].The resulting environmental fatigue calculation for the RPV shell/bottom head location is shown in Table 7. Bounding Fen multipliers were applied in the calculations.
RPV bottom head water chemistry conditions from Tables I and 6 are used for this location.
The results show an EAF adjusted CUF of 0.0809 for 60 years, which is acceptable (i.e., less than the allowable value of 1.0).The CUF determined for Point 14 is very low. Comparison to other locations of the RPV shell/bottom head region indicates it is not the limiting location from a fatigue perspective.
Review of the CUF values in Table 3-1 of Reference
[15] reveals that the shroud support (at vessel wall junction) location is potentially more limiting, so EAF evaluation of that location is also performed.
Per page S3-99f of Reference
[16], the design basis CUF of 0.06 is for Point 9. Page S3-85 of Reference
[ 16] reveals that this point is on the RPV shell at the junction of the shroud support plate.Per References
[14] and [19], the RPV shell material is low alloy steel (A-533, Grade B).Pile No.: VY-16Q-303 Page 7 of 24 Revision:
0 F0306-OIRO NEC066004 C Structural Integrity Associates, Inc.The revised and updated CUF calculation for Point 9 for 40 years, which includes the use of updated methodology and incorporates EPU effects, is shown at the top portion of Table 8. The CUF for 40 years (without EAF effects) is 0.0549. This CUF value is more limiting than the RPV shell/bottom head location evaluated in Table 7, so it is considered to be the governing location for VY with respect to the equivalent NUREG/CR-6260 RPV shell/bottom head location.The fatigue calculation for 60 years for the RPV shell/shroud support location is also shown in Table 8. The results show a CUF (without EAF effects) of 0.0774 for 60 years. The fatigue calculation for 60 years makes use of the 60-year projected cycles for VY from Reference
[9].The resulting environmental fatigue calculation for the RPV shell/shroud support location is shown in Table 8. Bounding F,, multipliers were applied in the calculations.
RPV bottom head water chemistry conditions from Table 6 are used for this location.
The results show an EAF adjusted CUF of 0.7364 for 60 years, which is acceptable (i.e., less than the allowable value of 1.0).I I I I I I I I I I I I I I I I I I I File No.: VY-16Q-303 Revision:
0 Page 8 of 24 F0306-01 RO Lcntain~ '.'ZflJC~
t~1 U~JJ ~ ic~tc~ 1 1~at1on NEC066005 Structural Integrity Associates, Inc.4.2 RR Inlet Nozzle For conservatism due to the different materials involved, two locations are evaluated for the RR inlet nozzle: (1) the limiting location in the nozzle forging, and (2) the limiting location in the safe end.The 60-year CUF value (without EAF effects) for the RR inlet nozzle in the VY LRA submittal is 0.610. However, that analysis used conservative transient definitions and cyclic projections for 60 years of operation that have since been updated. The applicable CUF values are those shown in Table 3-1 of Reference
[15] (0.1058 for the safe end, and 0.03 for the nozzle for 40-years), except that these values are pre-EPU.For the RR inlet nozzle forging, the governing CUF calculation is shown on page B28 of Reference
[12], where a value of 0.03 was obtained.
From pages A269 and A270 of Reference
[12], the CUF calculation corresponds to Point 12 in the nozzle forging, which is on the outside surface of the nozzle on the outboard end of the nozzle transition.
Although this location is not exposed to the reactor coolant, it will be conservatively evaluated for EAF effects as it is the bounding fatigue location in the nozzle forging. As a part of the evaluation for this location, EPU effects were included.
Per page I-$8-4 of Reference
[17], the RR inlet nozzle material is low alloy steel (A-508 Class II).The new CUF calculation for Point 12 for 40 years, wlhich includes the use of updated methodology and incorporates EPU effects [14], is shown at the top portion of Table 9. The CUF for 40 years (without EAF effects) is 0.0433.The fatigue calculation for 60 years for the RR inlet nozzle forging location is also shown in Table 9.The results show a CUF (without EAF effects) of 0.0650 for 60 years. The fatigue calculation for 60 years makes use of the 60-year projected cycles for VY from Reference
[9].The resulting environmental fatigue calculation for the RR inlet nozzle forging location is shown in Table 9. Bounding F,,, multipliers were applied in the calculations.
RPV beltline water chemistry conditions from Table 5 are used for this location.
The results show an EAF adjusted CUF of 0.5034 for 60 years, which is acceptable (i.e., less than the allowable value of 1.0)For the RR inlet nozzle safe end, the governing CUF calculation is shown on page B27 of Reference[12], where a value of 0.1058 was obtained.
From pages A257 and A259 of Reference
[12], the CUF calculation corresponds to Line 6 at the inside surface of the safe end. Page A238 of Reference[12] reveals that this location is location at the nozzle-to-safe end weld. Per Section 3.2.1.2 of Reference
[ 13], the CUF value for the RR inlet nozzle safe end was evaluated for the effects of EPU, since the original CUF calculated in Reference
[18] was 0.551 (which was adjusted downward to 0.1.058 by Entergy in Reference
[1.2] based on further refined evaluation).
Therefore, as a part of the evaluation for this location, EPU effects were included.
Per page 8 of Reference
[18], the RR inlet nozzle safe end material is 316L stainless steel.File No.: VY-16Q-303 Page 9 of 24 Revision:
0.............
d.r P oprietFi y I306- tmt F0306-0 t R0 NEC066006 Structural Integrity Associates, Inc.The new CUF calculation for the RR inlet nozzle safe end for 40 years, which includes the use of updated methodology and incorporates EPU effects [14], is shown at the top portion of Table 10.The CUF for 40 years (without EAF effects) is 0.00 17.The fatigue calculation for 60 years for the RR inlet nozzle safe end location is also shown in Table 10. The results show a CUF (without EAF effects) of 0.0017 for 60 years. The fatigue calculation for 60 years makes use of the 60-year projected cycles for VY from Reference
[9].The resulting environmental fatigue calculation for the RR inlet nozzle safe end location is shown in Table 10. Bounding Fen multipliers were applied in the calculations.
Recirculation line water chemistry conditions from Table 2 are used for this location.
The results show an EAF adjusted CUF of 0.0199 for 60 years, which is acceptable (i.e., less than the allowable value of 1.0)I I I I I I I I I I I I I I I I I File No.: VY-16Q-303 Revision:
0 Page 10 of 24 F0306-0 I RO C~mt~lii-i:5
"~hUor Pfopriztary infcrrnat.oa I I NEC066007 Structural Integrity Associates, Inc.5.0 RESULTS OF ANALYSIS The final environmental fatigue results contained in Sections 4.1 and 4.2 (and associated Tables 7 through 10) for the RPV shell/bottom head and RR inlet nozzle locations are summarized in Table 11.
 
==6.0 CONCLUSION==
S AND DISCUSSION In this calculation, EAF calculations were performed in accordance with the GALL Report [2] for the following VY locations: " RR inlet nozzle, consisting of the following bounding locations:
o Nozzle forging (low alloy steel)o Safe end (stainless steel)* RPV shell/bottom head, consisting of the following bounding locations:
o Limiting bottom head shell inside surface location (low alloy steel)o Limiting RPV shell/shroud support location (low alloy steel)The above locations were selected based on the locations identified in NUREG/CR-6260 for the older vintage GE plant and plant-specific fatigue calculations that determined the limiting locations for VY. Calculations for the remaining NUREG/CR-6260 locations will be documented in other analyses performed under this project.The EAF results for the locations identified above are shown in Table 11. These results indicate that the fatigue usage factors, including environmental effects, are within the allowable value for 60 years of operation for all locations evaluated.
The calculations for all locations make use of the 60-year projected cycles for VY and incorporate EPU effects. Therefore, no additional evaluation is required for these components, and the GALL requirements are satisfied.
File No.: VY-16Q-303 Revision:
0 Page 11 of 24 Containc 'Jenclc~ ifi oprictary 1 t 1 f 0 1 F0306-01RO NEC066008 Structural Integrity Associates, Inc.
 
==7.0 REFERENCES==
 
I. NUREG/CR-6260 (INEL-95/0045), "Application of NUREG/CR-5999 Interim Fatigue Curves to Selected Nuclear Power Plant Components," March 1995. I 2. NUREG-1801, Revision 1, "Generic Aging Lessons Learned (GALL) Report," U. S. Nuclear Regulatory Commission, September 2005. I 3. USAS B31.1.0 -1967, USA Standard Code for Pressure Piping, "Power Piping," American Society of Mechanical Engineers, New York.4. NUREG/CR-6583 (ANL-97/18), "Effects of LWR Coolant Environments onl Fatigue Design Curves of Carbon and Low-Alloy Steels," March 1998.5. NUREG/CR-5704 (ANL-98/3 1), "Effects of LWR Coolant Environments on Fatigue Design Curves of Austenitic Stainless Steels," April 1999.6. EPRI/BWRVIP Memo No. 2005-27 1, "Potential Error in Existing Fatigue Reactor Water Environmental Effects Analyses," July 1, 2005.REDACTED I I a 8. "Vermont Yankee Dissolved Oxygen (DO) Levels for Use in EAF Evaluations," page 11 of Entergy Design Input Record (DIR) EC No. 1773, Revision 0, "Environmental Fatigue Analysis I for Vermont Yankee Nuclear Power Station," 7/3/07, SI File No. VY- 16Q-209.9. "Reactor Thermal Cycles for 60 Years of Operation," Attachment I of Entergy Design Input Record (DIR) EC No. 1773, Revision 0, "Environmental Fatigue Analysis for Vermont Yankee Nuclear Power Station," 7/3/07, SI File No. VY-16Q-209.
: 10. VY LRA, page 1-4 (included as Appendix B to this calculation).
: 11. American Society of Mechanical Engineers Boiler & Pressure Vessel Code, Section III, Rules for Construction of Nuclear Facility Components, and Section II, Materials, Part D, "Properties (Customary)," 1998 Edition including the 2000 Addenda.12. Yankee Atomic Electric Company Calculation No. VYC-378, Revision 0, "Vermont Yankee Reactor Cyclic Limits for Transient Events," 10/16/85, SI File No. VY-05Q-21 1.REDACTEDI_ II File No.: VY-16Q-303 Page 12 of 24 Revision:
0 3"C 0'h2ihL Vepndor prepi Jnfnrm athon_F0306-0 RO NEC066009 V Structural Integrity Associates, Inc.14. GE Nuclear Energy Certified Design Specification No. 26A6019, Revision 1, "Reactor Vessel -Extended Power Uprate," June 2, 2003, SI File No. VY-05Q-236.
: 15. Structural Integrity Associates Report No. SIR-01-130, Rev. 0, "System Review and Recommendations for a Transient and Fatigue Monitoring System at the Vermont Yankee Nuclear Power Station," February 2002, SI File No. W-VY-05Q-401.
: 16. CB&1 RPV Stress Report, Section S3, Revision 4, "Stress Analysis, Shroud Support, Vermont Yankee Reactor Vessel, CB&I Contract 9-6201," 2-3-70, SI File No. VY-16Q-203.
: 17. CB&I RPV Stress Report, Section S8, Revision 4, "Stress Analysis, Recirculation Inlet Nozzle, Venriont Yankee Reactor Vessel, CB&I Contract 9-620 1," 2-3-70, S1 File No. VY-16Q-203.
: 18. GE Nuclear Energy Certified Stress Report No. 23A4292, Revision 4, "Reactor Vessel -Recirculation Inlet Safe End Nozzle," March 12, 1986, SI File No. VY- 16Q-203.19. Entergy Drawing No. 5920-5752, Revision 3 (CB&I Drawing No. R15, Revision 1), "Vessel &Attachments Mat'l. Identifications," 1/20/88, SI File No. VY-16Q-209.
File No.: VY-16Q-303 Revision:
0 Page 13 of 24 L.satain~.'Vc~~du~
lt upi iut~ti y iiiiG~ mat~cn F0306-01 RO NEC066010 V Structural Integrity Associates, Inc.Table 1: Water Chemistry Calculations Date of HWC Implementation:
Availability of HWC System Since HWC Implementation:
Projected Future HWC System Availability:
Recirculation Line DO pre-HWC: post-HWC: Feedwater Line DO pre-HWC: post-HWC: RPV Upper Region DO pre-HWC: post-HWC: RPV Beltline Region DO pre-HWC: post-HWC: RPV Bottom Head Reqion DO 11/01/2003 (seeAppendixA) 98.54% (see Appendix A)98.5% (see Appendix A, assume same as recent experience) 122 48 40 40 114 97 ppb (see Appendix A)ppb (see Appendix A)ppb (see Appendix A)ppb (see Appendix A)ppb (see Appendix A)ppb (see Appendix A)pre-HWC: post-HWC: 123 ppb (see Appendix A)46 ppb (see Appendix A)128 ppb (see Appendix A)69 ppb (see Appendix A)?2/1972 (see Appendix B)1.61 years (calculated, includes leap years.)30/2007 3.49 years (calculated, includes leap years.)4.90 years (calculated, includes leap years.)I I I I I I I I I I I I U I I Plant Startup Date: Time at pre-HWC Conditions:
Date of Calculations:
Time Since HWC Implementation:
Projected Future Time for HWC Operation:
Overall HWC Availability:
03/~3 04/r 2 47%Note: All operation through 11/1/2003 was assumed as NWC using the dissolved oxygen values from the "Pre-NMCA" column in Appendix A, and all operation after 11/1/2003 was assumed as HWC using the maximum oxygen values from the "Post-NMCA
+ HWC (OLP)", "Post-NMCA
+ HWC (EPU)", and "Future Operation" columns in Appendix A.File No.: VY-16Q-303 Revision:
0 Page 14 of 24-.... ;-, " --,N EC, Propri.tary
...o.. a.. o.NEC066O1 1 F0306-01 RO V Structural Integrity Associates, Inc.Table 2: Bounding Fen Multipliers for Recirculation Line Low Alloy Steel: F_, = exp(0.898
-0.10lS'T-0%'
1 Assume S* = 0.015 (maximum)Assume t,* = ln(0.001)
= -6.908 (minimum)For a BWR with HWC environment (post-HWC implementation):
DO = 48 ppb -0.048 ppm DO < 0.050 ppm, so 0* = 0 Thus: T (&deg;C) T (&deg;F) F_.0 32 2.45 50 122 2.45 100 212 245 150 302 2.45 200 392 2.45 250 482 2.45 288 550 2.45 For a BWR with NWC environment (pre-HWC implementation)
DO = 122 ppb = 0.122 ppm, so 0* = ln(0.122,10.04)
= 1.115 Thus: T (&deg;C) T (&deg;F) F,, 0 32 2.45 50 122 2.45 100 212 2.45 150 302 2.45 200 392 4.40 250 482 7.89 288 550 12.29 Thus, maximum F_, 2.45 [T*= IT-150) to, T, 150'C]Thus, maximum Fn 12.29 Carbon Steel: For a BWR with HWC environment (post-HWC implementation):
DO = 48 ppb , 0.048 ppm DO < 0.050 ppm, so 0' = 0 Thus: T (&deg;C) T (Ff) F_, 0 32 1.74 50 122 1.74 100 212 1.74 150 302 1.74 200 392 1.74 250 482 1.74 288 550 1.74 Fe = exp(O.554
-0.101S0T'Ogc*)
AssumeS* = 0.015 (maximum)Assume l = In(0.001)
= -6.908 (minimum)For a BWR with NWC environment (pre-HWC implementation)
DO = 122 ppb = 0.122 ppm, so 0' = ln(0. 122/0.04)
-1115 Thus: T (&deg;C) T (-F) Fe_0 32 1.74 50 122 1.74 100 212 1.74 150 302 1.74 200 392 3.12 250 482 5.59 288 550 8.71 Thus, maximum F_, 1.74 [T'= (T- 150) for T > 150'C]Thus, maximum F,, 8.71 Stainless Steel: Fn = exp(0.935
-T'cO)For a BWR with HWC environment )post-HWC implementation):
For a BWR with NWC environment (pre-HWC implementation):
DO = 48 ppb , 0.048 ppm < 0.050 ppm, so 0* = 0.260 DO = 122 ppb = 0.122 ppm > 0.05ppm, so 0* = 0.172 Conservatively use T* = 1 for T > 200'C Conservatively use T' = 1 for T > 200'C Thus: Thus:= 0 for f > O.4%/sec so F. 2.55 so F,,, 2.55 C = In(e/0.4) for 0.0004 <= F, <= 0.4%/sec so F_, ranges from 2.55 so F., ranges from 2.55 to 15.35 to 8.36 c* = ln(0.0004/0.4) for t: < 0.0004%/sec so F,, = 15.35 so F., = 8.36 Thus, maximum F,, = 15.35 Thus, maximum F,, = 8.36 File No.: VY-16Q-303 Revision:
0 Page 15 of 24 Contain7; VodrPo-itr'Ifrnt-c F0306-0 I RO NEC066012 Structural Integrity Associates, Inc.Table 3: Bounding Fen Multipliers for Feedwater Line Low Alloy Steel: Fe = exp)0.898
-0.101S'T'O7,)
Assume S" = 0.015 (maximum)Assume :. = tn(O.001)
= -6.908 (minimum)For a BWR with HWC environment (post-HWC implementation):
DO = 40 ppb = 0.040 ppm < 0.050 ppm so O* = 0 Thus: T (&deg;C) T (-F) Fen 0 32 2.45 50 122 2.45 100 212 2.45 150 302 2.45 200 392 2.45 250 482 2.45 288 550 2.45 For a BWR with NWC environment (pre-HWC implementation):
DO 40 ppb = 0.040 ppm < 0.050 ppm so 0* = 0 Thus: T (&deg;C) T ('F) F_0 32 245 50 122 2.45 100 212 2.45 150 302 2.45 200 392 2.45 250 482 2.45 288 550 2.45 Thus, maximum Fen =2.45 [T*= (T-1 50) for T a 1s0C)Thus, maximum F.,, 2.45 Carbon Steel: I_= esp(0.554
-0.10tS'T'OV;)
Assume S' = 0.015 (maximum)Assume r;. = ln(0.001)
= -6.908 (minimum)I I I I I I I I I I I For a BWR with HWC environment (post-HWC implementation):
DO = 40 ppb = 0.040 ppm < 0.050 ppm so O0 = 0 Thus: T (&deg;C) T (0 F) F_, 0 32 1.74 50 122 1.74 100 212 1.74 150 302 1.74 200 392 1.74 250 482 1.74 288 550 1.74 For a BWR with NWC environment (pre-HWC implementation):
DO = 40 ppb = 0.040 ppm < 0.050 ppm so 0 = 0 Thus: T (-C) T )&deg;F) Fee 0 32 1.74 5o 122 1.74 100 212 1.74 150 302 1.74 200 392 1.74 250 482 1.74 288 550 1.74 Thus, maximum Fe =1,74 [T'= (T-150) for T t 150&deg;C]Thus, maximum F- , 1.74 There is no stainless steel in the Class t feedwater line.File No.: VY-16Q-303 Revision:
0 Page 16 of 24 F0306-01 RO (Jontacos V on ci or Vropriotary intormator I I NEC066013 Structural Integrity Associates, Inc.Table 4: Bounding Fn Multipliers for RPV Upper Region Low Alloy Steelt F_ =, exp(O.898
-0. 101S TPO'.r:/, Assume S" = 0015 (maximum)Assume -, = ln(0.001)
= -6.908 (minimum)For a BWR with HWC environment (post-HWC implementation):
D0 = 97 ppb = 0.097 ppm, so O0 = ln(0.097/0.04)
= 0.886 For a BWR with NWC environment (pre-HWC implementation):
DO = 114 ppb = 0. 114 ppm, so O; = Inf0.114/0.041
= 1.047 Thus: Thus: T (0C) T (&deg;F) Fen 0 32 2.45 50 122 2.45 100 212 2.45 150 302 2.45 200 392 3.90 250 482 6.20 288 550 8.82 T (&deg;C) T (&deg;F) F_, 0 32 2.45 50 122 2.45 100 212 2.45 150 302 2.45 200 392 4.25 250 482 7.35 288 550 11.14 Thus, maximum F,, =8.82 P= (T-150) for T,> 150C Thus. maximum F,, 11.14 Carbon Steel: F= exp(0.554
-0.101S'T'O'c*)
AssumeS* = 0.015 (maximum)Assume vo = ln(O.001)
= -6.908 (minimum)For a BWR with HWC environment (post-HWC implementation):
DO = 97 ppb = 0.097 ppm, so 0* = ln(0.097/0.04)=
0.886 Thus: T (oC) T ('F) F_, 0 32 1.74 50 122 1.74 100 212 1.74 150 302 1.74 200 392 2.77 250 482 4.40 288 550 6.25 For a BWR with NWC environment (pre-HWC implementation):
DO = 114 ppb = 0114 ppm, so 0* = ln(O 114/0.04)
= 1.047 Thus: T (-C) T (-F) F., 0 32 1.74 50 122 1.74 100 212 1.74 150 302 1.74 200 392 3.01 250 482 5.21 288 550 7.90 Thus, maximum Fn =6.25 [T'= (T-150) for T>, 150oC]Thus, maximum F., 7.90 Stainless Steel: FIn = exp(0.935
-T'cO*)For a BWR with HWC environment (post-HWC implementation):
For a BWR with NWC environment (pre-HWC implementation):
DO = 97 ppb = 0.097 ppm a 0.050 ppm, so O0 = 0.172 DO = 114 ppb = 0.114 ppm > 0.05 ppm, so 0* = 0.172 Conservatively use T' = 1 for T > 200'C Conservatively use T' = 1 for T > 2000C Thus: Thus:= 0 for r. > 0.4%/sec so F,, = 2.55 so F_, = 2.55 Sln(r./0.4) for 0.0004 <= F. <= 0.4%/sec so F_, ranges from 2.55 so F,, ranges from 2.55 to 8.36 to 8.36 c*= ln(0.0004/0.4) for r, < 0.0004%/sec so F-, = 8.36 so F. = 8.36 Thus, maximum Fn = 8.36 Thus, maximum F., = 8.36 File No.: VY-16Q-303 Revision:
0 Page 17 of 24 C,,Ju aitnu-' r/tixduu P-1 u 5 ic futjtnt&#xfd;.o F0306-OIRO NEC066014 V Structural Integrity Associates, Inc.Table 5: Bounding F,, Multipliers for RPV Beltline Region Low Alloy Steel: Fen, = exp(0.898
-0.101S'T`O*,)
For a BWR with HWC environment (post-HWC implementation):
DO = 46 ppb = 0.046 ppm DO < 0.050 ppm, so 0* = 0 Thus: T (-C) T (&deg;F) Fen 0 32 2.45 50 122 2.45 100 212 2.45 150 302 2.45 200 392 2.45 269.45 517.01 2.45 288 550 2.45 Assume S" = 0.015 (maximum)Assume t,- = In(0.001)
= -6.908 (minimum)For a BWR with NWC environment (pre-HWC implementation):
DO = 123 ppb = 0.123 ppm, so O0 = tn(0.123/0.04)
= 1.123 Thus: T (&deg;C) T (F) Fn 0 32 2.45 50 122 2.45 100 212 2.45 150 302 2.45 200 392 4.42 269.45 517.01 10.00 288 550 12.43 Thus, maximum Fn, 2.45 [T*= (T-150) for T, 150oq Thus, maximum Fn = 12.43 Carbon Steel; esp(0.554
-0.101STOu)
Carbon Steel.Fen= exp(0.554
-0.101 S'T*O*e*)Assume S* = 0,015 (maximum)Assume F. = In(O.001)
= -6.908 (minimum)For a BWR with HWC environment (post-HWC implementation):
DO = 46 ppb = 0.046 ppm DO < 0.050 ppm, so O0 = 0 Thus: T (&deg;C) T (-F) Fen 0 32 1.74 50 122 1.74 100 212 1.74 150 302 1.74 200 392 1.74 250 482 1.74 288 550 1.74 For a BWR with NWC environment (pre-HWC implementation):
DO = 123 ppb = 0.123 ppm, so 0* = In(0.123/0.04)
= 1123 Thus: T (-C) T (&deg;F) Fen 0 32 1.74 50 122 1.74 100 212 1.74 150 302 1.74 200 392 3.13 250 482 5.64 288 550 8.81 I I I I I I I I I I I I I I I I Thus, maximum Fen -1.74 fT'= (T- 150) fc, T , 150-Cl Thus, maximum Fn 8.81 Stainless Steel: Fen = exp(0.935
-T',*O")For a BWR with HWC environment (post-HWC implementation):
For a BWR with NWC environment (pre-HWC implementation):
DO = 46 ppb = 0.046 ppm < 0.050 ppm, so O* 0.260 DO = 123 ppb = 0.123 ppm > 0.05 ppm, so 0= 0.172 Conservatively use T* = 1 for T > 200&deg;C Conservatively use T* = 1 for T > 2000C Thus: Thus:* = 0 for , > 0.4%/sec so F 0 n = 2.55 so Fn= 2.55= ln(&#xfd;/0.4) for 0.0004 <= v <= 0.4%/sec so Fen ranges from 2.55 so Fen ranges from 2.55 to 15.35 to 8.36= ln(0.0004/0.4) foret- < 0.0004%/sec so Fen = 15.35 so Fn = 8.38 Thus, maximum Fen = 15.35 Thus, maximum Fen 8.36 File No.: VY-16Q-303 Revision:
0 Page 18 of 24 F0306-OIRO NEC066015
, Structural Integrity Associates, Inc.Table 6: Bounding Fen Multipliers for RPV Bottom Head Region Low Alloy Steel: Fn= exp(0.898
-0. 101 S-TOr,-)Assume S* = 0.015 (maximum)Assume u- = ln(0.001)
= -6.908 (minimum)For a BWR with NWC environment (pre-HWC implementation):
DO = 128 ppb = 0.128 ppm, so 0* = In(0.128/0.04)
= 1.163 Thus For a BWR with HWC environment (post-HWC implementation):
DO = 69 ppb = 0.069 ppm, so 0' = In(0.069/0.04)
= 0.545 Thus: T (0C) T )&deg;F) Fen 0 32 2.45 50 122 2.45 100 212 2.45 150 302 2.45 200 392 3.27 250 482 4.34 288 550 5.39 T (-C) T (0 F) Fen 0 32 2.45 50 122 2.45 100 212 2.45 150 302 2.45 200 392 4.51 250 482 8.29 288 550 13.17 Thus, maximum Fen 5.39 [T'= (T-150) for T, 15O0C]Thus, maximum Fen 13.17 Carbon Steel: = exp(0.554
-0.101ST0' 0')Carbon Steel.Fen= exp(0.554
-0.101 S*T*O*c*)AssumeS* = 0.015 (maximum)Assume o:* = In(0.001)
= -6.908 (minimum)For a 6WR with HWC environment (post-HWC implementation):
DO = 69 ppb = 0.069 ppm, so O" = In(0.069/0.04)
= 0.545 Thus: T (-C) T (-F) Fen 0 32 1.74 50 122 1.74 100 212 1.74 150 302 1.74 200 392 2.31 250 482 3.08 288 550 3.82 For a BWR with NWC environment (pre-HWC implementation):
DO = 128 ppb = 0.128 ppm. so 0* = In(0.128/0.04)
= 1163 Thus: T (-C) T (-F) F 0 0 0 32 1.74 50 122 1.74 100 212 1.74 150 302 1.74 200 392 3.20 250 482 5.88 288 550 9.34 Thus, maximum F., =3.82 FT'= (T-150) for T, 150,C Thus, maximum Fen 9.34 Stainless Steel: F,, = exp(O.935
-T*r,'O*)For a BWR with HWC environment (post-HWC implementation):
For a BWR with NWC environment (pre-HWC implementation):
DO = 69 ppb = 0.069 ppm > 0.050 ppm, so 0* = 0.172 DO = 128 ppb = 0.128 ppm > 0.05 ppm, so 0' &#xfd; 0.172 Conservatively use T' = 1 for T > 2000C Conservatively use T' = 1 for T > 2000C Thus: Thus: c = 0 for .> 0.4%!sec so Fen = 2.55 so Fen= 2.55 c* = ln(f./0.4) for 00004 <= -= 0.4%/sec so Fen ranges from 2.55 SO Fen ranges from 2.55 to 8.36 to 8.36= in(O.0004i0.4) for ,: < 0.0004%/sec so F_ = 8.36 so Fen = 8.36 Thus, maximum F~n = 8.36 Thus, maximum Fen = 8.36 File No.: VY-16Q-303 Revision:
0 Page 19 of 24 C= E) 14 -A do P 1 4rita qnpn t F0306-01R0 NEC066016 V Structural Integrity Associates, Inc.Table 7: EAF Evaluation for RPV Shell/Bottom Head Location Component:
RPV Shell/Bottom Head NUREG/CR-6260 CUF: 0.032 (for reference only)
 
==Reference:==
 
NUREG/CR-6260, p. 5-102 Stress Report CUF: 0.0057 (for Point 14, see below)Material:
Low Alloy Steel (Material=A-533 Gr. B per References
[14] and [19])Design Basis CUF Calculation for 40 years: Elatigue cure/Eanalysis
=Power Uprate =K, =m =n=S,,=1.149 1.0067 1.000 2.0 0.2 26,700 Conservatively used minimum E of 26. 1 from Section S2 Appendix of RPV Stress Report.=(549 -100) 1'(546 -100) per 4.4.1.b of 26eA6019.
Rev. 1 14]stress concentration factor NB-3228.5 of ASME Code, Section Ill [11]NB-3228.5 of ASME Code, Section III [I1]psi (ASME Code, Section II, Part D [111)SL+Pe+Q (see Note 1) K. (see Note 2) Salt (see Note3) n (see Note 4) N (see Note 5) U 44,b26 1.00 25,762 200 35,300 0.0057 1 Total, U 4 0 = 0.0057 Notes 1. Pt +PR +o is obtained for Point 14 from p. A52 of VYC-378, Rev. 0.2. K, computed in accordance mith NB-3228.5 of ASME Code, Section III.3. S,, = 0.5
* K "K, E *"Power Uprate "IPL +P6 +Q).4. n for 40 years is the number of Heatup-Cooldown cycles, per p. 38 of VYC-378. Rev. 0.5. N obtained from Figure 1-9.1 of Appendix I of ASME Code, Section Ilif 6. n for 60 years is the projected number of Heatup-Cooldown cycles.I I I I U I I I I I I I I Revsed CUF Calculation for 60 Years: PL+Ps+Q (see Note 1) K. (see Note 2) Salt (see Note3) n (see Note 6) N (see Note 4) U 44,526 1.00 25,762 300 35,300 0.0085 Total, U 6 0 = 0.0085 Envronmental CUF Calculation for 60 Years: Maximum Fen.HWC Multiplier for HWC Conditions
= 5.39 (from Table 6)Maximum F,.aNWC Multiplier for NWC Conditions
= 13.17 (from Table 6)U.w60 = U 6 0 x Fe.rNWC x 0.53 + U 6 0 x FenHWC X 0.47 = 0.0809 Overall Multiplier
= Uenv.6 0/U6 0= 9.51 File No.: VY-16Q-303 Revision:
0 Page 20 of 24 F0306-OIRO WG~~~ 8 1 4t -Ii itlr rp irtar y nomto I I NEC066017 W Structural Integrity Associates, Inc.Table 8: EAF Evaluation for Limiting RPV Shell/Shroud Support Location Component:
RPV Shell at Shroud Support NUREG!CR-6260 CUF: 0.032 (for reference only)
 
==Reference:==
 
NUREG!CR-6260, p. 5-102 Stress Report CUF: 0.0549 (for Point 9, see below)Material:
Low Alloy Steel (Material
= A-533 Gr. B per References
[14] and [19t)Desian Basis CUF Calculation for 40 vears: Hydrotest r', = 26,240 psi p, S3-97ofRPVStress Report)Hydrotest Or = -1,250 psi (p. S3-97of RPVStress Report)Stress Concentration Factor, Kr = 2.40 Hydrotest K,, = 62,976 Improper Startup r5- = 28,060 Improper Startup a, = -1,025 Improper Startup Skin Stress = 156,099 Improper Startup K,,; + Skin Stress = 223,443 Warmup -= -5.707 Warmup n,= -102 Warmup Ktq, = -13.696 Eiattgug cuavteiEanaty s = 1.0417 Power Uprate 1.0067 m= 2.0 n= 0.2 S, = 26,700 (p. S3-99d of RFV Stress Report)psi (p S3-97 o/ RPV Stress Report)psi fp. S3-98 of RPV Stress Report)psi (p. S3-98 of RPV Stress Report)psi (p. S3-98 of RPV Stress Report)psi (p. S3-98 of RPV Stress Report)psi tp. S3-99a of RPV Stress Report)psi (p. S3-99a of PPV Stress Report)psi (p. S3-99a of RPV Stress Report)30.0 128,8 per $3-99f of RPV Stress Report and ASME Code fatigue curve=(549 100)/(546-roo) per4.4.1.bof26A6019.
Roe. 1[14]NB-3228.5ofASME Code. Section Ittt1tt NB-3228. 5 of ASME Code. Section t III[tt psi (ASME Code, Section (I, Part DC Qr t)PL+ PB+Q (see Note 1) Events Ke (see Note 2) Sat (see Note 3) n (see Note 4) N (see Note 5) U 34,690 Improper Startup -Warmup 1.00 124,825 5 332 0.0151 33,095 Hydrotest
-Warmup 1.00 40,804 322 8,095 0.0398 Total, Uo 0.0549 Notes: 1. P, &#xf7;P +Q ts compuaed for Point 9 based on thef ( n, -cJ,) '..,, (a. -Ca,) ,,,2 ] stress intensity 2. K.. computed in accordance vdth NB-3228.5 of ASME Code. Section it.4. n for 40 years is the number of cycles as follos per p. S3-99e and S3-99f of the RPV Stress Report: Improper Startup = 5 cycles Hydrotest
= 2 cycles Isothermal at 70SF and t.000 psi= 120 cyc!es (same as number of Startup events)Warmup-Cooldovm
= 199 cycles Warmup-Blovvdovr=
t cycle TOTAL = 327 cycles 5. N obtained from Figure 1-9. 1 of Appendix I of ASME Code. Section lIl 6. n for 60 years is the projected number of cycles as follows: Improper Startup = t cycles Hydrotest
= t cycles Isothermal at 7 0oF and 1,000 psi = 300 cycles (same as number of Startup events)Warmup-Cooldown
= 300 cycles Warmup-Glo-do-e
= t cycle TOTAL = 603 cycles Revised CUP Calculation for 60 Years: PL+ PB+Q (see Note t) Ke (see Note 2) Sar (see Note 3) n (see Note 61 N (see Note 4) U 341690 Improper Startup -Warmup 1.00 124,825 1 332 0.0030 33,095 Hydrotest
-Warmup 1.00 40,804 602 8,095 0.0744 Total, U6s = 0.0774 Environmental CUF Calculation for 60 Years: Maximum Fse-awc Multiplier for HWC Conditions Maximum Fe-NeWc Multiplier for NWC Conditions Uen 5.6 0 = U 6 0 x Fen.rtWc X 0.53 r- U 6 0 x Fen.HWc X 0.47 Overall Multiplier
= Uenv-6o/Uuo
-5.39 (from Table 6)13.17 (from Table 6)0.7364 9.51 File No.: VY-16Q-303 Revision:
0 Page 21 of 24 F0306-0 I RO NEC066018 U Structural Integrity Associates, Inc.Table 9: EAF Evaluation for RR Inlet Nozzle Forging Location Component:
Recirculation Inlet Nozzle Forging NUREG/CR-6260 CUF: 0.310 (for reference only)
 
==Reference:==
 
NUREG/CR-6260.
: p. 5-105 Stress Report CUP: 0.0433 (updated for Point 12, see belowf Material:
Low Alloy Steel (Material
=A-508 Cl. 1t per p. I-58-4 of CBIN Stress Report Section S8)Design Basis CUF Calculation for 40 years: Etaliguecure/Eanalysis 1.1278 =30.O/26.6(perpI -SS-24 of CBIN Stress Report Section S8 and ASME Code fatigue curve)Power Uprate = 1.0067 -(549- 100) (546- 100) per 4.4.1.b ot26A6019, Rev. 1[141 K, = 1.660 stress concentration factor (p&#xfd; A270 of VYC-378, Rev. 0 [12])m = 2.0 NB-3228.5ofASME Code. Section 1tt[l it n = 0.2 NB-3228.5 ofASMECode, Section Ill/It[]St,, = 26,700 psi (ASME Code, Section t1 Part Oft [))PL+PB+Q (see Note 1) Skin Stress (see Note 2) K, (see Note 3) Salt (see Note 4) n (see Note5) N (see Note 6) U 43.110 15,145 1.00 49,224 200 4,614 0.0433 1 Total, U 4 , 0.0433 Notes: I. P, +P, o0 is obtained for Point 12 from p. A270 of VYC-378, Rev. 0.2. Skin Stress is obtained for Point t2 from p. A270 of VYC-378, Rev. t.3. K computed in accordance with NB-3228.5 of ASME Code, Section Ill.4. = 05 ' K, "E '., ...E,,,,,,, Power Uprate f[ (PI +Pe, +Q) K, + Skin Stress].5. n for 40 years is the number of Heatup-Cooldovn cycles, per p. 828 of lYC-378, Rev. 0 6. N obtained from Figure /-9. 1 of Appendix I of ASME Code, Section It.7. n for 60 years is the projected number of Heatup-Cooldown cycles.Revised CUF Calculation for 60 Years: PL+PO+Q (see Note 1) Skin Stress (see Note 2) Ke (see Note 3) S., (see Note 4) n (see Note 7) N (see Note 6) U 43.110 15,145 1.00 49,224 300 4,614 0.0650 I Total, U. = 0.0650 Environmental CUF Calculation for 60 Years: Maximum Fen-1.WC Multiplier for HWC Conditions
= 2.45 (from Table 5)Maximum FeNwc Multiplier for NWC Conditions
= 12.43 (from Table 5)Uenv-6o = U6o x Fen.NWC X 0.53 + U6 0 x Fen.HWC X 0.47 = 0.5034 Overall Multiplier
= Ue--6doUeo
= 7.74 I I I I I I I I I I I I I I I I I I I File No.: VY-16Q-303 Revision:
0 Page 22 of 24 F0306-O1 RO Cc~ntair 0: '~~~~tdur Pr opi ietto y Itt fuc oo~t~cn NEC066019 V Structural Integrity Associates, Inc.Table 10: EAF Evaluation for RR Inlet Nozzle Safe End Location Component:
NUREG/CR-6260 CUF:
 
==Reference:==
 
Stress Report CUF: Material: Recirculation Inlet Nozzle Sale End 0.310 (for reference only)NUREG/CR-6260, p. 5-105 0.0017 (updated for Location 6-I, see below)Stainless Steel (316L per p. 8 of 23A4292, Rev. 4)Design Basis CUF Calculation for 40 years: Etatig ue curveEanalys 1.1076 =28.3/25.55 (perp. 62 ofReference[18]
andASME Code fatigue curve)Power Uprate 1.0067 =(549- 1oo)1(546-100)per 4.4. t.b of 26A6019. Rev. 1[14]K= 1.280 stress concentration factor (p. 627 of VYC-378, Rev. 0 (12])m = 1.7 NB-3228.5ofASME Code, Section 111[11]n = 0.3 NB-3228.5 of ASME Code, Section III t[1]S= 16,600 psi (ASME Code. Section It. Part D[11])Ke (see Note 3) Salt (see Note 4) n (see Note 5) N (see Note 6) U 1.00 26,385 2,076 1,242,266 0.0017 I Total, U40 = 0.0017 PL+ PB+O (see Note 1)47,183 P+Q+F (see Note 2)36,972 Notes: I. P L'+P +Q is obtained for Surface I (after weld overlay) from p. 117of Reference
[18].2. P+Q+F is obtained for Point 6-1 from p. 118 of Reference
[18] (BEFORE weld overlay).3. K, computed in accordance with NB-3228.5 of ASME Code. Section 11.4. Sai = 0.5
* K
* E, ..... 'Power Uprate ([ (P&#xf7;Q+F) K, ].5. n for 40 years is the number of cycles as follows per p. 826 of VYC-378, Rev. 0: Design Hydrotest
= 130 Loss of Feed umps Composite:
Startup/Shutdown
= 290 SRV Blovdor = 8 Loss of Feedwater Pumps 30 10 events x 3 up'down cycles per event SCRAM = 270 Normal -/- Seismic = I1 10 cycles of upset seismic, plus 1 Level C seismic event Normal = 739 = Sum of all of above events Zeroload = 598 = Startup/Shutdown
+ SRVBtovwdown
+ Scram + LOFP Total number of cycles = 2:076 6. N obtained from Figure 1-9.2 of Appendix I of ASME Code. Section I/1.7. n for 60 years is the projected number of cycles as follows: Design Hydrotest
= 120 Loss of Feedoumps Composi .te: Startup/Shutdown
= 300 SR V B/ovdosn = I Loss of Feedwater Pumps 30 10 events x 3 up'down cycles per event SCRAM = 289 All remaining scrams Normal -/- Seismic= I t Assume the same Normal = 751 = Sum of all of above events Zeroload = 620 = Startup/Shutdown
+ SRV Blovdown + Scram + LOFP Total number of cycles = 2,122 Revised CUF Calculation for 60 Years: PL+ PB+O (see Note 1) P+Q-+F (see Note 2) Ke (see Note 3) Salt (see Note 4) n (see Note 5) N (see Note 7) U 47,183 36,972 1.00 26,385 2,122 1,242.266 0.0017 Total, U., = 0.0017 Environmental CUF Calculation for 60 Years: Maximum Fen.HWc Multiplier for HWC Conditions
=Maximum Fen.NWC Multiplier for NWC Conditions
=Uenv.6o = U 6 o x Fen.NWC X 0.53 + U 6 , x Fen.HWC X 0.47 =Overall Multiplier
= Uenv.6o/U60
=15.35 8.36 0.0199 11.64 (from Table 2)(from Table 2)File No.: VY-16Q-303 Revision:
0 Page 23 of 24 Contains ~r~-j~= Ps o~r>Qtnry Informt~t~cn F0306-0 I RO NEC066020
&#xfd;&#xfd; Structural Integrity Associates, Inc.Table 11: Summary of EAF Evaluation Results for VY 40-Year 60-Year Overall 60-Year No. Component Material (2) Environmental Environmental Design CUF CUF Multiplier CUF (2,3)1 RPV Shell/Bottom Head Low Alloy Steel 0.0057 0.0085 9.51 0.0809 2 RPV Shell at Shroud Support Low Alloy Steel 0.0549 0.0774 9.51 0.7364 3 Recirculation Inlet Nozzle Safe End Stainless Steel 0,0017 0.0017 11.64 0.0199 4 Recirculation Inlet Nozzle Forging Low Alloy Steel 0.0433 0.0650 7.74 0.5034 Notes: 1. Updated 40-year CUF calculation based on recent ASME Code methodology and design basis cycles.2. CUF results using updated ASME Code methodology and actual cycles accumulated to-date and projected to 60 years.3. An Fen multiplier was used for each respective component with the following conditions:
+ 47% HWC conditions and 53% NWC conditions I I I I I I I I I U I I I i I I I I I File No.: VY-16Q-303 Revision:
0 Page 24 of 24 U-4aFrtfttlll YCTICIOr H;0prietfffy 1lntCTTrrZTtt@&#xfd;
-R F0306-01 RO NEC066021 V Structural Integrity Associates, Inc.APPENDIX A VY WATER CHEMISTRY INFORMATION
[8]File No.: VY-16Q-303 Revision:
0 Page A I of A2 CCriLLh>, V~~~clor Prc~1 ictary Information F0306-OI RO NEC066022 V Structural Integrity Associates, Inc.Pre-NMCA Post-NMCA
+ HWC Post-NMCA
+ HWC Future Operation 1593 MWth (OLP) 1593 MWth (OLP) 1912 MWth (EPU) Post-NMCA
+ HWC 1912 MWth (EPU)Location Average Average Average Availability 98.5&deg;%.; Availability 98.5% Availability 99%Implementation Date NMCA Application EPU Implementation
= 11/1972 Date = 04/27`2001 Date = 5/2006 HWC Implementation Date = 11/01/2003 FW Line 40 ppb 4O ppb 40 ppb 40 ppb Recirc. Line 122 ppb 48 ppb 34 ppb 34 ppb RPV Bottom 128 ppb 69 ppb 55 ppb 55 ppb Head **RPV Upper 114 ppb 97 ppb 90 ppb 90 ppb Region RPV Beltline 123 ppb 46 ppb 31 ppb 31 ppb Region I** RPV Bottom head at "Lower Plenum, Downflow" (i.e. outside core support columns)File No.: VY-16Q-303 Revision:
0 Page A2 of A2 F0306-01 RO~Contain.~
Vcudui Fi upi letal y I~~f~1 NEC066023 v Structural Integrity Associates, Inc.APPENDIX B VY LICENSE DATE [10]File No.: VY-16Q-303 Revision:
0 Page B I of B2 Con)1tai Vcd I OP T~ru i i l y inf-i MaIVIdIU F0306-0IRO NEC066024 U Structural Integrity Associates, Inc.Vermont Yarkee Nu::ear Power S.ut-on License Renewal A  Michael A. BaIduzzi Vice President
-Pilarim N Liclear Power Station Fred R_ Dacimo Vice President
-Indian Point Energy Center Randall K. srdington Vice President
-Operations Support Christocher J. Soitwarz Vice Presidemi
-Operations Suppor Theodore A. S n.li'._n VIce President
-Fivzpatrid Nuclear Power Station Jay K. Thfayer%,ice Presideni-Vermont Yankee Nuclear Power Station Pilarim NuLclear Power Station 600 Rocky Hill Road Plymouth, Mass achusetts 02360 Indian Point Energy Center BleakJley Av-enue & Broadway Buchaanon.
New York 105I11 Cooper Nuclear Paoer Station 1200 Prospect Road PC. Box 98 Brownsville, NebraskRa 68321 Entergy Nuclear COpera.ions, Inc 440 Hamilton Avenue White Plains, New 'Yorkl, 10601 Fitzpatrick Nuclear Power Station 268 LalUe RBo'd East Lycomina, New Yorlk 13093 Entergy Nucl-ai ",-;ermnos Yank;ee corporate ONfire 185 Old Ferry Road Braitle'ro, V7 0-5302-05010 I I I I I I I I I I I I I I I I I I I 1.1.5 Class and Perio~d of License SOurlht ENO requests renewal of the facility operza.ing license for VYMPS (faciliti operatino license DPR.-28`; fora period of 2 i years- The license ',,as issued under Section i 4l of t'he Atomic Snergy Act of 1954 as amended. License renewal would extend the facility operating license froim nIdnIgh i FMFarch: 2 O1, &#xfd; lto 2i dnh glt _2.2 This applicason also applies: to renewal of Those NRC source nmaterals, srrc'al nuclear nnaterial, and by-roduct material licenses that are subsumed or combined wih the fanity oper;.ltng license.1.1.6 Alteration Schedule ENSO does iot propose to consruct or alter any production or utilization facility in connection with this renew,,'al application.Administri.rive
&#xfd;rformaton F'ae 1-4 File No.: VY-16Q-303 Revision:
0 Page B2 of B2 F0306-01 RO eMu I iI iItr vScii 3~ Proprictary
~ 1 natio~NEC066025 Structural Integrity Associates, Inc. File No.: VY-16Q-304 CALCULATION PACKAGE Project No.: VY-16Q NEC-JH_07 PROJECT NAME: Environmental Fatigue: Analysis of VYNPS CONTRACT NO.: 10150394 CLIENT: PLANT: Entergy Nuclear Operations, Inc Vermont Yankee Nuclear Power Station CALCULATION TITLE: Recirculation Outlet Nozzle Finite Element Model Affected Project Manager Preparer(s)
Document Revision Description Approval Checker(s)
Revision Pages Signature
& Date Signatures
& Date 0 1-6, Initial Issue Terry J. Herrmann Minghao Qin Appendix: AIA07/12/2007 7/12/2007 A1-A20 Jennifer E. Smith 7/12/2007 Page 1 of 6 F0306-0 I RO Structural Integrity Associates, Inc.Table of Contents 1.0 OBJECTIVE
................................
.........................................
.........
3 2.0 GEOMETRY / MATERIAL PROPERTIES
....... .................................................................
.... 3 3.0 PROGRAM INPUT ....... ............
.................................
3
 
==4.0 REFERENCES==
 
........................................................
4 APPEN DIX A RON_VY.IN P ......................................................................................................
A l I I I I I I I I I I I List of Tables Table 1: M aterial Properties
@ 300'F ..........................................................................................
5 List of Figures Figure 1: AN SYS Finite Elem ent M odel ....................................................
.........................................
6 File No.: VY-16Q-304 Revision:
0 Page 2 of 6 F0306-01 RO Structural Integrity Associates, Inc.I 1.0 OBJECTIVE The objective of this calculation is to create a finite element model of the Vermont Yankee Nuclear Power Station recirculation outlet nozzle. This model will be used to develop a Green's Function to be used in a subsequent fatigue analysis.2.0 GEOMETRY / MATERIAL PROPERTIES A 2-D axisymmetric finite element model (FEM) of the nozzle was developed with element type PLANE182.
The developed model includes the safe end, the nozzle forging, a portion of the vessel* shell, and cladding.
The model used the vessel radius multiplied by a factor 2.0 due to the model being axisymmetric.
The 2-D axisymmetric FEM was constructed using the dimensions and information from References
[4 and 5] based on ANSYS [2] finite element software.
Figure 1 shows the resulting finite element model.I The materials of the various components of the model are listed below: Safe End- SA182 F316 [4] (l6Cr-l2Ni-2Mo)
,0 Piping -SA376 TP316 [7] (l6Cr-12Ni-2Mo)
* Nozzle Forging -sA508 Class 2 [5] (3/4Ni-1/2Mo-1/3Cr-V)
* Vessel -SA533 Grade B [6] (Mn-I/2M0-1.2Ni)
* Cladding SA240 Type 304 [1, Sheet 7] (18Cr-8Ni)
I Material properties for these materials are based upon the 1998 ASME Code, Section 11, Part D, with 2000 Addenda [3] and are shown in Table 1. The properties are taken at an average temperature of 300 0 F. This average temperature is'based on a thermal shock of 500OF to 100&deg;F which will be applied to the FEM model for Green's Function development.
 
===3.0 PROGRAM===
INPUT.The input file, RONVY.INP (included in Appendix A),. creates the finite element model for the recirculation outlet nozzle.I I I File No.: VY-16Q-304 Page 3.of 6 Revision:
0 F0306-01 RO Structural Integrity Associates, Inc.
 
==4.0 REFERENCES==
: 1. GE. Stress Report No. 23A4316, Revision 0, "Reactor Vessel Recirculation Outlet Safe End," SI File No. VY- 16Q-204.2. ANSYS, Release 8.1 (w/Service Pack 1), ANSYS, Inc., June 2004.3. American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section II, Part D, 1998 Edition, 2000 Addenda.4. Vermont Yankee Drawing 5920-06623, Rev. 0, (Hitachi, Ltd. Drawing No IOR290-127),"Recirc. Outlet Safe End," SI File No. VY-16Q-204.
: 5. Vermont Yankee Drawing 5920-00238, Rev. 4, (Chicago Bridge & Iron Company, Contract No. 9-6201, Drawing No. 21), "36"x28" Nozzles Mk NIA/B," SI File No. VY-16Q-204.
: 6. Vermont Yankee Drawing 5920-05752, Rev. 3, "Vessel & Attachments Material Identifications," SI File No. VY-16Q-209.
: 7. SI File No. VY- 16Q- 103, "Vermont Yankee Comments on VY- 16Q-304." I I I I I I I I I I I I I I I I I I I File No.: VY-16Q-304 Revision' 0 Page 4 of 6 F0306-OIRO V Structural integrity Associates, Inc.Table 1: Material Properties
@ 300'F (1)SA533 Grade B SA508 Class 2 SA240 Type SA182 F3161 Material (Mn-l/2Mo-(314Ni-1/2Mo-304 SA376 TP316 1/2Ni) ll3Cr-V) (18Cr-8Ni)
(16Cr-12Ni-2Mo)
Modulus of-28.0 26.7 27.0 27.0 Elasticity, e-6 psi Coefficient of Thermal Teml,7. .7 7.3 9.8 9.8 Expansion, e-6, in/in/&deg;F Thermal Conductivity, 23.4 23.4 9.8 9.3 Btu/hr-ft-&deg;F Thermal Diffusivity, 0.401 0.401 0.160 0.150 ft 2/hr 0.401 0.4010_1600.15 Specific Heat, Btu/lb-OF (2) 0.119 0.119 0.125 0.127 Density, lb/in 3  0.283 0.283 0.283 0.283 Poisson's Ratio 0.3 0.3 0.3 0.3 Notes: 1. The material properties applied in the analyses are taken from ASME Section II Part D 1998 Edition with 2000 Addenda. This is consistent with information provided in the Design Input Record (page 13 of VY EC No. 1773, SI File No. VY-16Q-209).
The use of a later code edition than that used for the original design code is acceptable since later editions typically reflect more accurate material properties than was published in prior Code editions.
Material Properties are evaluated at 300'F from the 1998 ASME Code,.Section II, Part D, with 2000 Addenda, except for density and Poisson's ratio, which are assumed typical values.2. Calculated as fk/(pd)]/12 3.File No.: VY-16Q-304 Revision:
0 Page 5 of 6 F0306-0I RO V Structural Integrity Associates, Inc.Figure 1: ANSYS Finite Element Model File No.: VY-16Q-304 Revision:
0 Page 6 of 6 F0306-01 RO V Structural Integrity Associates, Inc.I APPENDIX A RONVY.inp File No.: VY-16Q-304 Revision:
0 Page Al of A20 F0306-01 RO Structural Integrity Associates, Inc. .finish/clear,start
/prep7/title, Recirc Outlet Nozzle Finite Element Model/com, PLANE 182, 2-D Solid et, l,PLANE182,,, I" !Axisymmetric
/com, **************
/com, Material Properties
@T=300F/com, ****************************
/COM, Material #1 (Safe-End and Piping) SA-182 F316 (16Cr-12Ni-2Mo) mplex, 1,27E&#xf7;06 mp,alpx, 1,9.8E-06 mp,kxx, 1,9.3/3600/12 I mp,c, 1,0. 127 mp,nuxy, 1,0.3 mp,dens, 1,0.283/COM, Material #2 (Nozzle Forging) SA-508 Class 2 (3/4Ni-1/2Mo-1/3Cr-V) mp,ex,2,26.7E+06 mp,alpx,2.,7.3E-06.
mp,kxx,2,23.4/3600/12 mp,c,2,0.119.
mp,nuxy,2,0.3 i mp,dens,2,0.283
/COM, Material #3 (Cladding)
SA-240 Type 304 (18Cr-8Ni) mp,ex,3,27E+06 mp,alpx,3,9.8E-06 mp,kxx,3,9.8/3600/12 mp,c,3,0.125 I mp,nuxy,3,0.3
-mp,dens,3,0.283
/COM, Material #4 (Vessel) SA-533, GR. B (Mn- 1/2Mo- l/2Ni)mp,ex,4,28.OE+06 mp,alpx,4,7.7E-06 mpkxx,4,23.4/3600/12 mp,c,4,0.119 mp,nuxy,4,0.3 mp,dens,4,0.283
*AFUN,DEG/com, *** Geometric Parameters
****set,vira,(103+3/16)
!Actual Vessel Inner Radius to base metal used for model*set,vir,2.0*vira
!2.0 time of Vessel Inner Radius to base metal used for model i*settvw,5+5/8-3/16
!Vessel Wall Thickness*set,ri 1,25.75/2*setro 1,28.375/2 i*set,LI,5*setjro2,28.375/2 File No.: VY-16Q-304 Page A2 of A20 Revision:
0 F0306-OIRO I
I :.Structural Integrity Associates,*
Inc.I I*set,L2,4.25
**set,ro3,28.875/2
*set,ro4,48.75/2
*set,L3,1.5
*set,L4,5.25
*set,L5,7+l/16
*set,L6,12+13/16
*set,1L7,9+/--7/8
*setL8,9+3/8
*set,L9,3 1+15/16*set,LIO L9- 2-13/16-tvw
*set,ra,7*set,rb, 1*set,rc,5.25
*set,rd,2.5
-*set,tv,3/16
*set,dipmA,vir-(tv*2.0)+L9+
11 +L 1*set,L21,1
*set,L22,4.25
*set,ri2l,(25+
15/16)/2 Vessel Centerline to End of Safe End used for model/com, Geometry local, 13,0,,dimA....
csys, 13/com, Begin at end of Safe-End -Carbon Section k, 1, ri o, -1l*(dimA) k, 2, ril +tv, -1 *(dimA)k, 3, ro 1, -1 *(dimA)k, 41, r -I*(dimA-L 1)k, 5, ri l+tv, -I *(dimA-L1L) k, 6, ro3, -l*(dimA-L1) k, 7, ri 1, -T*(dimA-L I-L2)k, 8, ri I +tV, -I *(dimA-L I -L2)k, 9, ro2, -1*(dimA-L8-L2) k, 10, ri5, -I*(dimA-LI-L2-L3) k, 11l, ri I +tv, -I *(dimA&#xfd;L I -L2-L3)k, 12, ro3, -a*(dimA-L I-L2-L3)k, 13, ri 1, -I *(dimA-L I -L2-L3-L4) k, 14,2ri+tv,-1*(dimA-L1-L2-L3-L4) k, 15, to3, -1 *(dimA-L I -L2-L3-L4) k, 16, ri 1, -1*(dimA-L l-L2-L3-L4-L5) k, 17, ri l+tv, -l1*(dimnA-L I-L2-L3-L4-L5) k, 18, ro3, -I*(dimA-L I-L2-L3-L4-L5) k,1 9, *ro4,- l*(dimA-L I-L2-L3-L4-L5-L7)!
Temporary Point 1,19,18 1,18,15 lfiilt, l,2,ra k,22, ro4+(L8+6)*tan(15), -*(dimA-L 1-L2-L,3-L4-L5-L7-(L8+6))
1,19,22 File No.: VY-16Q-304 Revision:
0 Page A3 of A20 F0306-O1 RO
! S .truc tu~ral Integrity Associates, Inc.LFILLT, 1,4,rb k, 25, ri 1, -1 *(dimA-L , &#xfd;L2-L-L4-L6) k, 26, ril+tv, -I *(dimA-LII-2-L3L4-L6) k, 27, ri 1+(L 10+tvw+tv+4)*tan(l 5), -I*(vir-tv-4) k, 28, ri I +tv+(L 10+tvw+tv+4)*tan(l 5), -1 *(vir-tv-4) k,29, (vir+tvw+tv)*sin(45), -1*(vir+tvw+tv)*cos(45) k,30, 0, -l*(vir+tvw+tv)
! Temporary Point k,3 1, 0, 0 ! Temporary Point larc,29,30,3 I,vir+tvw+tv k,32, (vir+tv)*sin(45), -l*(vir+tv)*cos(45) i k,33, 0, -l*(vir+tv)
!Temporary Point 1arc,32,33,3 l,vir+tv k,34, vir*sin(45), -1 *vir*cos(45) k,35, 0, -l*vir ! Temporary Point larc,34,35,3 1,vir LSTR, 4, 5 LSTR, 5, 6 LSTR, 6, 9 i LSTR, 9, 12 LSTR, 12, 15*LSTR, 5, 8 LSTR, 4, 7 LSTR, 7, 10 LSTR, 8, 11 LSTR, 11, 14I LSTR, 10, 13 LSTR, 13, 16 LSTR, .14, 17 LSTR, 16, 25 LSTR, 17, 26 LSTR, 26, 28 LSTR, 25, 27 I LSTR, 4, 1 LSTR, 1, 2 LSTR, 2, 3 LSTR, 3, 6 LSTR, 5, 2 LSTR, 7, 8 LSTR, 8, 9 I LSTR, 12, I1 LSTR, 11, 10 LSTR, 13, 14 LSTR, 14, 15 FLST,2,2,4,0RDE,2 FITEM,2,4 FITEM,2,6 LPTN,P5 IX File No.: VY-16Q-304 Page A4 of A20 i Revision:
0 F0306-0I RO U Structural Integrity Associates, Inc.FLST,2,2,4,ORDE,2 FITEM,2,8 FITEM,2,25 LPTN,P51X FLST,2,2,4,ORDE,2 FITEM,2,7 FITEM,2,24 LPTN,P53X FLST,2,6,4,ORDE,6 FITEM,2,6 FITEM,2,25 FITEM,2,37 FITEM,2,40 FITEM,2,42 EITEM,2,44 LDELE,P5 IX,, ,I LFILLT,4,4 1,rd,, 1*S LFILLT,43,8,rd,, LFILLT,39,38,rc,, I FLST,2,3,4,ORDE,3 FITEM,2,1 FITEM,2,3 I FITEM,2,5 LCOMB,P51 X, ,0 LSTR, 16, 17 LSTR, 17, 21 LSTR, 25, 26 LSTR, 26, 24 LSTR, 22, 30 I LSTR, 30, 35 LSTR, 27, 28 LSTR, 28, 33 LSTR, 29, 32 I LSTR, 32, 34 k,39, 0, -1*(vir+tvw+tv)
I .!Create Areas FLST,2,4,4 FITEM,2,27 I FITEM,2,30 FITEM,2,26 FITEM,2,9 AL,P51X FLST,2,4,4 FITEM,2,28 FITEM,2,29 File No.: VY-16Q-304 Page A5 of A20 Revision:
0 F0306-0 I RO Structural Integrity Associates, Inc.FITEM,2,30 FITEM,2,30 AL,P5 IX FLST,2,4,4 I FITEM,2, I1 FITEM,2,32 FITEM,2,10 FITEM,2,14 AL,P5 IX FLST,2,4,4 FITEM,2,15 FITEM,2,14 FITEM,2,9 FITEM,2,31 AL,P51X FLST,2,4,4 FITEM,2,32 FITEM,2,33
* FITEM,2,12I FITEM,2,17 AL,P51X FLST,2,4,4 FITEM,2,16
.FITEM,2,17 FITEM,2,31 I FITEM,2,34 AL,P51X FLST;2,4,4 FITEM,2,36.
FITEM,2,13 FITEM,2,33 FITEM,2,18 U AL,P51X FLST,2,4,4 FITEM,2,19 FITEM,2,18 FITEM,2,35 FITEM,2,34 AL,P51X I FLST,2,4,4 FITEM,2,2 FITEM,2,5 FITEM,2,36 FITEM,2,21 ALP5 I X FLST,2,4,4 i FITEM,2,20 FITEM,2,21 FITEM,2,3 FITEM,2,35 I AL,P51X FLST,2,4,4 FITEM,2,1 n FITEM,2,37 FITEM,2,23 File No.: VY-16Q-304 Page A6 of A20 i Revision:
0 F0306-O I RO V Structural Integrity Associates, Inc..FITEM,2,5 AL,P51X FLST,2,4,4 FITEM,2,22 FITEM,2,23 FITEM,2,25 FITEM,2,3 AL,P51X FLST,2,4,4 I FITEM,2,38 FITEM,2,42 EITEM,2,37 I,.FITEM,2,8 AL,P5 IX FLST,2,4,4 FITEM,2,4 FITEM,2,8 FITEM,2,25 FITEM,2,40 AL,P51X FLST,2,4,4 FITEM,2,24 FITEM,2,45 I FITEM,2,7 FITEM,2,42 AL,P51X FLST,2,4,4 FITEM,2,6 FITEM,2,7 FITEM,2,44 I FITEM,2,40 AL,P5 IX FLST,2,4,4 FITEM,2,41 FITEM,2,43 FITEM,2,47 FITEM,2,44 AL,P51X FLST,2,4,4 FITEM,2,39 FITEM,2,46 I .FITEM,2,45 FITEM,2,43 AL,P5 IX I ..define materials FLST,5,8,5,ORDE,2 FITEM;5,1 I FITEM,5,-8 CM,_YAREA ASEL .... P51X I CM,_YI,AREA CMSEL,S,_Y CMSEL,S,_YI I File No.: VY-16Q-304 Page A7 of A20 Revision:
0 F0306-01 RO Structural Integrity Associates, Inc.AAT1, J,, 1, 0, CMSELS,S_Y CMfDELEY CMDELE,-_
I FLST,5,5,5,ORDE,5 FITEM,5,9 FITEM,5,11 FITEM,5,13 FITEM,5,15 FITEM,5,8 1 CM,_YAREA ASEL .... P51X CM,_YI,AREA CMSEL,S,_Y 1*CMSEL,S,_Yl AATT, 2,, i, .0, CMSEL,S,_Y
.CMDELE,_Y CMDELE,_YI FLST,5,5,5,ORDE,5 FITEM,5,10 FITEM,5,12 FITEM,5,14 FITEM,5,16 FITEM,5,-
17 CM,_YAREA ASEL .... P51X CM,_YIAREA CMSEL,S,_Y CMSEL,S,_Y AAT/', 3,, 1, 0, CMSEL,S,_Y I CMDELE,_Y CMDELE,_YI
!/com, Map mesh areas FLST,5,10,4,ORDE,10 FITEM,5,5 1 FITEM,5,10 FITEM,5,28 FITEM,5,32 I FITEM,5,-33 FITEM,5,36 FITEM,5,-37 FITEM,5,42 FITEM,5,45 FITEM,5,-46 CM,_YLINE I LSEL .... P51X CM,_YILINE File No.: VY-16Q-304 Page A8 of A20 Revision:
0 F0306-01 RO i Structural Integrity Associates, Inc.CMSEL,,_Y LESIZE,_YI, ,15; .... I FLST,5,10,4,ORDE, 10 IFITEM,5,3 FITEM,5,9 FITEM,5,25 FITEM,5,27 I FITEM,5,31 FITEM,5,34 FITEM,5,-35 i FITEM,5,40 FITEM,5,44 FITEM,5,47 CM,_YLINE I LSEL .... P51X CM,_Y1,LINE CMSEL,,_Y 1*LESIZE,_YI,,,2,,,.,!
1*1 FLST,5,3,4,ORDE,3 I FITEM,5,39 FITEM,5,41 FITEM,5,43 CM,_YLINE LSEL ...P51X CM,_YI,LLNE CMSEL,,_Y LESIZE,_YI
... 80 ..... 1 FLST,5,3,4,ORDE,3 FITEM,5,6 FITEM,5,-7 FITEM,5,24 I CM,_YLINE LSEL .... P51X CM,_YI,L1NE I CMSEL,,_Y LESIZE,_Y 1,,,20 ..... 1 1*I FLST,5,3,4,ORDE,3 FITEM,5,4 FITEM,5,8 FITEM,5,38 CM,_YL[NE LSEL, ;,,P5 IX CM,_Y1,LINE CMSEL,,_Y LESIZE,_Y
.,,,40 ..... I 1*File No.: VY-16Q-304 Page A9 of A20 Revision:
0 F0306-01 RO Structural Integrity Associates, Inc.FLST,5,3,4,ORDE,3 i FITEM,5,1 FITEM,5,22 FITEM,5,-23 I CM,_YLINE LSEL .... P51X CM,_YI,LINE CMS EL,,_Y 1*LESIZE,_YI, ,,30 ..... I FLST,5,6,4,ORDE,6 FITEM,5,2 FITEM,5,20 FITEM,5,-21 FITEM,5,26 FITEM,5,29 FITEM,5,-30 CM,_YLINE LSEL... P51X CM,_YI,LINE CMSEL,,_Y 1*LESIZE,_YI,,,40, .... 1 FLST,5,9,4,ORDE,2 FITEM,5, 11 FITEM,5,-19 CM,_YLINE LSEL .... P51X CM,_Y1 ,LINE CMSEL,,_Y 1*LESIZE,_Y, 1, ,20,, , ,'* i Meshing FLST,5,18,5,ORDE,2 FITEM,5,1 i FITEM,5,-18 CM,_YAREA ASEL .... P51X CM,_YI,AREA CHKMSH,'AREA' CMSEL,S,_Y MSHKEY, 1 AMESH,_Y1 MSHKEY,O CMDELE,_Y CMDELE,_YI CMDELE,_Y2 File No.: VY-16Q-304 Page AlO of A20 I Revision:
0 F0306-OIRO I
N Structural Integrity Associates, Inc.!Modify the safe end ID FLST,2,6,5,ORDE,2
* FITEM,2,1 FITEM,2,-6 ACLEAR,P5 IX FLST,2,6,5,ORDE,2 FITEM,2,1 FITEM,2,-6 ADELE,P51X FLST,2,9,4,ORDE,7 FITEM,2,9 FITEM,2,14 FITEM,2,-17 FITEM,2,26 FITEM,2,-27 FITEM,2,30 I FITEM,2,-31 LDELE,P51X,,,1 FLST,2,3,4,ORDE,3 FITEM,2,1O FITEM,2,28 FITEM,2,32 I LDELE,P5 IX, , FLST,3,2,3,ORDE,2 FITEM,3,3 FITEM,3,6 KGEN,2,P5 IX,, ,-ro2+ri21
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0 F0306-0IRO Structifral Integrity Associates, Inc..FLST,2,4,3 n FITEM,2,23 FITEM,2,8 FITEM,2,9 n FITEM,2,41 A,P51X FLST,2,4,3 FITEM,2,8 FITEM,2,7 FITEM,2,6 FITEM,2,9 A,P51X FLST,2,4,3 FITEM,2,7 FITEM,2,5 FITEM,2,3 FITEM,2,6 A,P51X FLST,2,4,3 FITEM,2,10 FITEM,2,20.
FITEM,2,23 FITEM,2,11 A,P51X FLST,2,4,3 I FITEM,2,20 FITEM,2,4 FITEM,2,8 FITEM,2,23 A,P51X FLST,2,4,3 FITEM,2,4 I FITEM,2,2 FITEM,2,7 FITEM,2,8 A,P51X I FLST,2,4,3 FITEM,2,2 FITEM,2,1 FITEM,2,5 FITEM,2,7 A,P51X FLST,5,8,5,ORDE,4 I FITEM,5,1 FITEM,5,-6 FITEM,5,19 I FITEM,5,-20
*CM,_YAREA ASEL .... P51X CM,_YIAREA I CMSEL,S,_Y.CMSE.LS,-Y 1 AATT, 1,, 1, 0, CMSEL,S, Y File No.: VY-16Q-304 Page A12 of A20 I Revision:
0 F0306-01RO I
V Structural Integrity Associates, Inc.ICMDELE_Y CMDELE,_YI IFLST,5,4,4,ODE,4 FITEM,5,15 FITEM,5,-
16 FITEM,5,26 FITEM,5,28 CM,_YLINE LSEL,, I ,P5IX CM,_YI,LINE CMSEL,,_Y I LESIZE,_YI
,,15,, ,,!FLST,5,4,4,ORDE,4 I FITEM,5,31 FITEM,5,48 FITEM,5,50 FITEM,5,52 CM,_YLINE LSEL .... P51X ,CM,_YI,LINE I * *CMSEL,,_Y LESIZE,_YI, , ,2 .... ,1 I*FLST,5,6,4,ORDE,6 FITEM,5,9 FITEM,5,-
10 I FITEM,5,12.
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CMSEL,_Y LESIZE,_YI,,, 12....1 1*FLST,5,3,4,ORDE,3 FITEM,5,27 FITEM,5,29 I File No.: VY-16Q-304 Page A13 of A20 Revision:
0 F0306-01 RO Structural Integrity Associates, Inc.FITEM,5,51 CM,_Y,LINE LSEL .... P51X CM,_YI,LINE CMSEL,,_Y 1*LESIZE,_YI,, ,25,,.. 1 FLST,5,8,5,ORDE,4 FITEM,5,1 FITEM,5,-6 I FITEM,5,19 FITEM,5,-20 CM,_YAREA ASEL .... P51X CM,_YI,AREA CHKMSH,'AREA' CMSEL,S_-Y 1*I MSHKEY, .AMESH,_YI MSHKEY,0 1*CMDELE,_Y CMDELE,_Y2 CFLST,2,2,5,ORDE,2
* FITEM,2,17 FITEM,2,-
18 ACLEAR,P51X i csys,0.* k, 51,62/2,0,0 k, 52,62/2,60,0 I LSTR, 51, 52"FLST,2,2,5,ORDE,2 FITEM,2,17 FITEM,2,-
18 ADELE,P51X lplo FLST,2,4,4,ORDE,4 FITEM,2,39 FITEM,2,41 FITEM,2,43 FITEM,2,53 LPTN,P51X FLST,2,2,4,ORDE,2 FITEM,2,60 i FITEM,2,-61 LDELE,P51X,, ,1 FLST,2,4,4 FITEM,2,54 FITEM,2,62 File No.: VY-16Q-304 Page A14 of A20 Revision:
0 F0306-01RO V Structural Integrity Associates, Inc.I FITEM,2,55 FITEM,2,44 I AL,P51X FLST,2,4,4 FITEM,2,55 FITEM,2,63 FITEM,2,58 FITEM,2,45 AL,P51X E FLST,2,4,4 FITEM,2,63 FITEM,2,56 FITEM,2,57 FITEM,2,46 AL,P51X FLST,2,4,4 I FITEM,2,47 FITEM,2,59 FITEM,2,57 FITEM,2,62 AL,P51X CM,_YAREA E ASEL.... 18 CM,_YI,AREA CMSEL,S,_Y I CMSEL,S,_Y1 AATT, 2,, 1, 0, CMSEL,S,_Y I CMDELE,_Y CMDELE,_YI FLST,5,2,5,ORDE,2 I .FITEM,5,17 FITEM,5,22 CM,_YAREA E ASEL .... P51X CM,_YI,AREA CMSEL,S,-Y 1*I CMSEL,S,_Y I AATT, .3,, 1,. 0, CMSEL,S,_Y I CMDELE_-Y CMDELE_-Y1 1*CM,_YAREA* ASEL.... 21 CM,_YI,AREA CMSEL,S,_Y
*CMSEL,S,_Y1 AATT, 4,, 1, 0, CMSEL,S,_Y I File No.: VY-16Q-304 Page A15 of A20 Revision:
0 F0306-OIRO Structural Integrity Associates, Inc.CMDELE,_Y CMDELE,_Y1 FLS T,5 ,3 ,4,0R-DE,3 FITEM,5,54 FITEM,5,-55 FITEM,5,58 CM,_YLINE LSEL .... P5IX CM,_YILINE CMSEL,,_Y LESIZE,_YI,,,8
..... I FLST,5,3,4,ORDE,3 FITEM,5,56 FITEM,5,-57 FITEM,5,59 U.CM,_YLINE LSEL .... P51X CM,_YILINE CMSEL,,_Y LESIZE,_YI,, ,40 ..... 1 SFLST,5,2,5,OR-DE,2 FITEM,5,17 FITEM,5,-
18 CM,_Y,AREA I ASEL .... P5IX CM,_YIAREA M CHKMSH,'AREA' I CMSEL,S,_Y MSHKEY,1 AMESH,_YI MSHKEY,O*CMDELE,_Y CMDELE,_Y I CMDELE,_Y2 FLST,5,2,5,ORDE,2 FITEM,5,21
*FITEM,5,-22 CM,_YAREA ASEL .... P51X CM,_YI ,AREA CHKMSH,'AREA' CMSEL,S,Y I MSHKEYJ,1 AMESH,_Y1 MSHKEY,O 1*File No.: VY-16Q-304 Page A16 of A20 I Revision:
0 F0306-OlRO
* I VStructural Integrity Associates, Inc.CMDELE,_Y CMDELE,.YI I CMDELE,_Y2 1*!Simulating Butter FLST,2,2,5,ORDE,2 FITEM,2,9 FITEM,2,-
10 I ACLEAR,P5 IX FLST,2,2,5,ORDE,2 FITEM,2,9 I FITEM,2,-10 ADELE,P51 X KGEN,2,15
.... 1 1/16,, ,0 I KGEN,2,44, ,, ,-0.25, ,0 KGEN,2,14
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0 F0306-01 RO Structural Integrity Associates, Inc.FLST,2,4,4i FITEM,2,39 FITEM,2,5 FITEM,2,2 FITEM,2,53 AL,P51X FLST,2,4,4 FITEM,2,20 FITEM,2,60 ,FITEM,2,53 FITEM,2,41 I AL,P5IX FLST,2,4,4 FITEM,2,72 FITEM,2,68 FITEM,2,69 FITEM,2,41 AL,P51X i FLST,2,4,4 FITEM,2,2!
FITEM,2,60 FITEM,2,36 FITEM,2,43 AL,P5 IX FLST,2,4,4 FITEM,2,66 FITEM,2,69 FITEM,2,35 FITEM,2,43 AL,P5IX CM,_YAREA*ASEL....
10 CM,_YI,AREA CMSEL,S,_Y 3 CMSEL,S,_Y1 AATT, 2,, 1, 0,.CMSEL,S,_Y I CMDELE,_Y CMDELE;_YI FLST,5,3,5,ORDE,3 FITEM,5,9 FITEM,5,23 FITEM,5,-24 I CM,_YAREA ASEL .... P5IX CM,_YIAREA CMSEL,S,.Y, 1*CMSEL,S,_Yl
' AATT, 3,, 1, 0, CMSEL,S, Y* CMDELE,_Y File No.: VY-16Q-304 Page A18 of A20 i Revision:
0 F0306-0I RO I V Strulctural Integrity Associates, Inc.I CMDELE_,2Yl FLST,5,2,5,ORDE,2.
FITEM,5,25 FITEM,5,-26 CM,_Y,AREA ASEL ...P51X CM,_YI,AREA CMSEL,S,_Y I*CMSEL,S,_Yl AATT, , 1 1, 0, CMSEL,S,_Y CMDELE,_Y CMDELE,_Y1 I FLST,5,3,4,ORDE,3 FITEM,5,2 FITEM,5,39 FITEM,5,67 CM,_Y LINE LSEL .... P51X CM,_YI,LINE.CMSEL,,_Y LESIZE,_YI, ,., 10,,,, 11 i FLST,5,6,4,ORDE,6 FITEM,5,20 FITEM,5,-21 i FITEM,5,41 FITEM,5,43 FITEM,5,66.FITEM,5,72 CM,_YLINE LSEL .... P51X CM,_YI,LINE i CMSEL,,_Y LESIZE,_Y, 1, ,2 ..... 1 i FLST,5,2,5,ORDE,2 FITEM,5,9 FITEM,5,-
10 i CM,_YAREA ASEL, .... P51X CM,_YIAREA CHKMSH,'AREA' I CMSEL,S,_Y 1*MSHKEY, 1 AMESH,_Y1 MSHKEY,0 1*CMDELE,_Y I File No.: VY-16Q-304 Page A19 of A20 Revision:
0 F0306-OIRO V Structural Integrity Associates, Inc.CMDELE,_Y1 CMDELE,_Y2 1*FLST,5,4,5,ORDE,2 FITEM,5,23 FITEM,5,-26 CM,_YAREA ASEL .... P51X CM,_YI,AREA CHKMSH,'AREA' CMSEL,S,_Y MSHKEY, I AMESH,_YI MSHKEY,O 1*CMDELE,_Y CMDELE,_Y1 CMDELE,_Y2 save finish I I I I I I I I I I I I I I I I I I I File No.: VY-16Q-304 Revision:
0 Page A20 of A20 F0306-OI RO Structural lIntegrity Associates, Inc. File No.: VY-16Q-305 NEC-JH 08 CALCULATION PACKAGE Project No.: VY-16Q PROJECT NAME: Environmental Fatigue Analysis of VYNPS CONTRACT NO.: 10150394 CLIENT: PLANT: Entergy Nuclear Operations, Inc. Vermont Yankee Nuclear Power Station CALCULATION TITLE: Recirculation Outlet Stress History Development for Nozzle Green Function Project Manager Preparer(s)
&Document Affected Revision Description Approval Checker(s)
Revision Pages Signature
& Date Signatures
& Date 0 1-29, Initial Issue Terry J. Herrmann Jennifer E. Smith Appendix:
07/18/2007 07/18/2007 Al-A2 Minghao Qin 07/18/2007 Page 1 of 29 F0306-OIRO V Structural Integrity Associates, Inc.Table of Contents 1.0 OBJECTIVE..............................................................................................
4 2.0 RECIRCULATION OUTLET NOZZLE MODEL ...................................................
4 3.0 APPLIED LOADS.......................................................................................
4 4.0 THERMAL AND PRESSURE LOAD RESULTS....................................................
7
 
==5.0 REFERENCES==
..........................................................................................
10 APPENDIX A FINITE ELEMENT ANALYSIS FILES ................................................
Al List of Tables Table 1: Material Propertie~s
@ 300'F.............
................
1 Table 2: Pressure Results....................................................................................1.I1 Table 3: 0% Flow Regions 1 and 3 Heat Transfer Coefficients..........................................
12 Table 4: 0% Flow Region 5 Heat Transfer Coefficient
...................................................
13 I I I I I I I I I I I I I I I I I I I File No': VY-16Q-305 Revision:
0 Page 2 of 29 F0306-01I RO SStructural Integrity Associates, Inc.List of Figures Figure 1: ANSYS Finite Element Model .....................................................
14 Figure 2: Recirculation Outlet Nozzle InternalPressure Distribution.......................
15 Figure 3: Recirculation Outlet Nozzle Pressure Cap Load .............................
16 Figure 4: Recirculation Outlet Nozzle Vessel Boundary Conditions
..........................................
17*Figure 5: Nozzle and Vessel Wall Thermal and Heat Transfer Boundaries
.................
18 Figure 6: Safe End Critical Thermal Stress Location ........................................
19 Figure 7: Safe End Limiting Linearized Stress Paths .....................................
20 Figure 8: Blend Radius Limiting Pressure Stress Location...
......................................................
21 Figure 9: Blend Radius Linearized Stress Path......................................
.....................................
22 Figure 10: Safe End 100% Flow Total Stress Intensity
..............................................................
23 Figure 11: Blend Radius 100% Flow Total Stress Intensity
.............................................................
23 Figure 12: Safe End Total Stress History for 100% Flow ...........................................................
24 Figure 13: Safe End Membrane Plus Bending Stress History for 100% Flow .............................
24 Figure 14: Safe End TotalStress History for 50% Flow ............................................................
25 Figure 15: Safe End Membrane Plus Bending Stress History for 50% Flow ...............................
25 Figure 16: Safe End Total Stress History for 0% Flow .................................................................
26 Figure 17: Safe End Membrane Plus Bending Stress History for 0% Flow .....................................
26 Figure 18: Blend Radius Total Stress History for 100% Flow .....................................................
27 Figure 19: Blend Radius Membrane Plus Bending Stress History for 100% Flow ......................
27 Figure 20: Blend Radius Total Stress History for 50% Flow ........................................................
28 Figure 21: Blend Radius Membrane Plus Bending Stress History for 50% Flow .......................
28 Figure 22: Blend Radius Total Stress History for 0% Flow ..................................
29 Figure 23: Blend Radius Membrane Plus Bending Stress History for 0% Flow .........................
29 FileNo.: VY-16Q-305 Revision:
0 Page 3 of 29 F0306-O1 RO Structural Integrity Associates, Inc.1.0 OBJECTIVE The objective of this calculation*
is to compute the pressure stresses, thermal stresses, and the Green's Functions for high (100%), mid (50%), and no (0%) flow thermal loading of the Vermont Yankee Nuclear Power Station recirculation outlet nozzle.2.0 RECIRCULATION OUTLET NOZZLE MODEL An axisymmetric finite element model of the recirculation outlet nozzle was developed in Reference[1] using ANSYS [2]. The geometry and model in Reference
[1] is used in this calculation.
The material properties are taken at an average temperature of 300'F. This average temperature is based on a thermal shock of 5007F to 1007 which will be applied to the FE model for Green's Function development.
Table I listed the material properties at 300TF. The meshed model is shown in Figure 1.3.0 APPLIED LOADS Both pressure and thermal loads will be applied to the' finite element model.3.1 Pressure Load A uniform pressure of 1000 psi was applied along the inside surface of the recirculation outlet nozzle and the vessel wall. A pressure load of 1000 psi was used because it is easily scaled up or down to account for different pressures that occur during transients.
In addition, a cap load was applied to the piping at the end of the nozzle. This cap load was calculated as follows: Pa. P~ (Di2)2~I where: P = Pressure = 1,000 psi Di = Inner Radius = 12.96875 in D, = Outer Radius = 14.18750 in Pcap = Tension stress on the end of the nozzle. (psi)Therefore, the cap load is 5081.7 psi. The calculated value was given a negative sign in order for it to exert tension on the end of the model. The ANSYS input file VYRON_P.INP, in the computer files, applies the pressure loading to the geometry in file RON_VY.INP.
Figures 2, 3, and 4 show the internal pressure distribution, cap load, and symmetry condition applied to the vessel end of the model, respectively.
FileNo.: VY-16Q-305 Page 4 of 29 Revision:
0 F0306-OI RO Structural Integrity Associates, Inc.3.2 Thermal Load Thermal loads are applied to the recirculation outlet nozzle model. The heat transfer coefficients after power uprate were determined by scaling the values from Reference
[4]. These values were determined for various regions of the finite element modelandfor 100% (28,294 GPM, converted from 12.3 Mlbm/hr [7]), 50% (14,147 GPM), and 0% (0 GPM) flow rates. The temperatures used are based upon a thermal shock from 500OF to 100'F. The calculated heat transfer coefficients for each region are shown below. The GPM values are calculated from the Mlbm/hr values at an average temperature of 300 0 F.3.2.1 Heat Transfer Coefficients; The heat transfer coefficients for the 100% flow and 50% flow cases were calculated from Reference[4] as follows: 0 p)0826 )0.hDf =h 3 0  25_ 26 Where: hDf= the heat transfer coefficient at a Diameter and flow rate h 3 0 0 = the heat transfer coefficient from Reference
*[4] at 300'F fDf= the flow rate corresponding to hDf (fi/sec)DDf = the diameter corresponding to hDf (in)The heat transfer coefficients for 0% flow were calculated in spreadsheet Htcoeffs.xls for natural convection and are shown in Tables 3 and 4.As shown in Figure 5, the following heat transfer coefficients were applied: Region I The heat transfer coefficient, h, for 100% flow is 4789 1-3 3577.8 BTU/hr"ft 2"6F at 300 0 F. [4]where 17.364 ft/sec is converted from 28,294 GPM and 25.8 in ID.The heat transfer coefficient, h, for 50% flow is 4789 8.-8) 2054.9 BTU/hr-ft 2-&deg;F at 300&deg;F. [4]where 8.682 ft/sec is converted from 14,147 GPM and 25.8 in ID.The heat transfer coefficient, h, for 0% flow is 112.34 BTU/hr-ft 2-&deg;F at 300TF. [Table 3, for natural convection]
File No..: VY-16Q-305 Page 5 of 29 Revision:
0 F0306-OI RO Structural Integrity Associates, Inc.Region 2 The heat transfer coefficient for Region 2 is linearly transitioned from the value of the heat transfer coefficient used in Region 1 to the value used for Region 3.I I I I I I I Region 3 (the point between Region 2 and Region 4)0. 8 0 .2 The heat transfer coefficient, h, for 100% flow is 4789 17.364) .*26 =3361 BTU/hr-ft 2-&deg;F at 300 0 F. [4]where the flow rate is the same as that for Region 1, and the ID is 35.49 in.The heat transfer coefficient, h, for 50% flow is 4789 8.62 0-. 26 0.21930.9 25 35.49 BTU/hr-ft 2-&deg;F at 300 0 F. [4]where the flow rate is the same as that for Region 1, and the ID is 35.49 in.The heat transfer coefficient, h, for 0% flow is 112.34 BTU/hr-ft 2-&deg;F at 300TF. using the same HTC as Region 1 [Table 3, for natural convection]
Region 4 Per Reference
[1], the heat transfer coefficient for Region 4 (Nozzle Blend Radius) is linearly transitioned from the value of the heat transfer coefficient used in Region 3 to the value used in Region 5.Region 5 The heat transfer coefficient, h, for 100% flow is 0.5 x 3577.8 1788.9 BTU/hr-ft 2'-F at 300&deg;F. [4]The heat transfer coefficient, h, for 50% flow is 0.5 x 2054.9 1027.4 BTU/hr-ft 2--F at 300&deg;F. [4]The heat transfer coefficient, h, for 0% flow is 101 BTU/hr-ft 2-&deg;F at 300 0 F. [Table 4, for natural convection]
by using 40 in. hydraulic diameter [4].I ,I I I I I I I I I I I File No.: VY-16Q-305 Revision:
0 Page 6 of 29 F0306-O1RO 3 Structural Integrity Associates, Inc.SRegion_ 6 The heat transfer coefficient, h, is 0.4 BTU/hr-ft 2-OF [4].3 3.2.2 Boundary Fluid Temperatures For the Green's Functions, a 500'F to 100 0 F thermal shock is run to determine the stress response to a one-degree change in temperature.
The following temperatures are valid when there is water flow. Values between definedpoints are linearly interpolated.
For the 100%, 50%, and 0% flow Scases, the thermal shock is run as follows: Regions 1 to 5 T =500OF -100 0 F Region 6 T= 120&deg;F 4.0 THERMAL AND PRESSURE LOAD RESULTS The three flow dependent thermal load cases outlined in Section 3.0 were run on the finite element model. Appendix A contains the thermal transient input files VYRON T 100I.NP, VYRONT_50.INP, and VY_RONT_0.LNP for 100%, 50%, and 0% flow rates, respectively.
The three flow dependent input files for the stress runs are also included in Appendix A. The stress filenames are VYRONS_100.INP, VYRONS_50.NP, and VY_RONS_0.INP for 100%, 50%, and 0% flow rates, respectively.
* The critical safe end location was chosen as node 6395, which has the highest stress intensity due to.thermal loading under high flow conditions.
As shown in Figures 6 and 7, Node 6395 is located on the inside diameter of the nozzle safe end of the model and the maximum stress occurs at 5.1* seconds.The critical blend radius location was chosen, based upon the highest pressure stress. Assumed the l .cladding has cracked, therefore, as shown in Figures 8 and 9, the critical location is selected as node 3829 at base metal of the nozzle.The stress intensity for use in the Green's functions are calculated from the component stresses (X, Y, and Z) and compared to the stress intensity reported by ANSYS. As seen in Figure 10, the Y-X calculated total stress intensity best matches the ANSYS reported stress intensity for 100% flow at the safe end. Therefore, the Y-X stress will be used for the total and membrane plus bending Green's functions for all flow rates for the safe end. As seen in Figure 11, the Z-X calculated total stress intensity best matches the ANSYS reported stress intensity for 100% flow at the blend radius 3 in very beginning.
Therefore, the Z-X stress will be used for the total and membrane plus bending Green's functions for all flow rates for the blend radius.I File No.: VY-16Q-305 Page 7 of 29 Revision:
0 F0306-01 RO VStructural Integrity Associates, Inc.The stress time history for the critical paths was extracted during the stress run for 100% flow rate.This produced two files, HFSE.OUT and HFBR.OUT, which contain the thermal stress history. The membrane plus bending stresses and total stresses for the Green's Functions were extracted from these files to produce the files HFSEInside.RED and HFBRInside.RED, where SE and BR corresponded to the safe end and blend radius locations, respectively.
The total stress intensity (SI)was extracted from these files to produce the files HFSE.CLD and HFBR.CLD, where SE and BR corresponded to the safe end and the blend radius, respectively.
The stress time history for the critical paths was extracted during the stress run for 50% flow rate.This produced two files, MFSE.OUT and MFBR.OUT which contains the thermal stress history..The membrane plus bending stresses and total stresses for the Green's Functions were extracted from the file to produce the file MFSE Inside.RED, where SE corresponds to the safe end location.The stress time history for the critical paths was extracted during the stress run for 0% flow rate.This produced two files, LFSE.OUT and LFBR.OUT which contain the thermal stress history. The membrane plus bending stresses and total stresses for the Green's Functions were extracted from the file to produce the file LFSEInside.RED, where SE corresponds to the safe end location.
3 The stress time history for the recirculation outlet nozzle during 100% flow, 50% flow, and 0% flow are shown in Figures 12 to 23. The data for the Green's Functions is included, in the files HFBRM+B-Green.xls, HFBRT-Green.xls, HFSE_M+B-Green.xls, HFSET-Green.xls, MFBRM+B-Green.xls, MFBRTGreen.xls, MFSEM+B-Green.xls, MFSET-Green.xls, LFBRM+B-Green.xls, LFBRT-Green.xls, LFSEM+B-Green.xls, and LFSE_T-Green.xls in the project Files. Where HF, MF, and LF corresponded to 100% flow, 50% flow, and 0% flow rate, respectively.
M+B and T corresponded to membrane plus, bending stress and total stress, respectively.
The pressure stress intensities for the path were extracted during the pressure run. The pressure stresses were extracted along the nodal path as shown in Figures 7 and 9. This produced two files, I PSE.OUT and PBR.OUT for the safe end and blend radius locations, respectively.
For the pressure loading specified (1000 psig), the total stress intensities at Node 6395 and Node I 3829 were determined to be 11490 psi and 31300 psi, respectively.
The membrane plus bending stress intensities at Node 6395 and Node 3829 were determined to be 11350 psiand 33640 psi, respectively.
Table 2 shows the final pressure results.lResults were also extracted from the vessel portion of the model to verify the accuracy of the results obtained from the ANSYS model, and to check the results due to the use of the 2.0 multiplier on the vessel radius. These results are contained in the file PVESS.OUT.
The radius of the finite element model (FEM) was multiplied by a factor of 2.0 [1] to account for the fact that the vessel portion of the 2D axisymmetric model is a sphere but the true geometry is the intersection of two cylinders.
File No.: VY-16Q-305 Page8 of 29 Revision:
0 F0306-01 RO 1 Structural Integrity Associates, Inc.The equation for the membrane hoop stress for a sphere is: (Pressure) (radius)2 x thickness Considering a vessel base metal radius, R, of 105.906 inches increased by a factor of 2.0, a vessel base metal thickness, t, of 5.4375 inches, and an applied pressure, P, of 1,000 psi, the calculated stress for a sphere is PR/(2t) = 19,477 psi. This compares very well with the remote vessel wall membrane hoop stress from the ANSYS result file, PVESS.OUT, of 19,540 psi. Thus, considering the peak total pressure stress of 31,300 psi reported above, the stress concentrating effect of the nozzle comer is 31,300/19,477
= 1.61. In other words, the peak nozzle comer stress is 1.61 times higher than nominal vessel wall stress for the 2D axisymmetric model.The equation for the membrane hoop stress in a cylinder is: (pres~sure) x (radius))thickness Based on the previous dimensions, the calculated stress for a cylinder without the 2.0 factor is 19,477 psi. Increasing this by a factor of 1.61 yields an expected peak nozzle comer stress of 31,358 psi, which would be expected from a cylindrical geometry that is representative of the nozzle configuration.
Therefore, the result from the ANSYS file for the peak nozzle comer stress (31,300 psi) is close to the peak nozzle comer stress for a cylindrical geometry because of the use of the 2.0 multiplier.
This is consistent with SI's experience where a factor of two increase in radius is typical for representing the three-dimensional (3D) effect in a 2D axisymmetric model.File No.: VY-16Q-305 Revision:
0 Page 9 of 29 F0306-O1 RO Structural Integrity Associates, Inc.
 
==5.0 REFERENCES==
: 1. SI Calculation No. VY-16Q-304, Revision 0, "Recirculation Outlet Nozzle Finite Element Model" 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 II, Part D, 1998 Edition, 2000 Addenda.4. CB&I, RPV Stress Report Section: T9 "Thermal Analysis Recirculation Outlet Nozzle Vermont Yankee Reactor Vessel." 9-620 1, S1 document, VY- 16Q-204.5. J. P. Holman, "Heat Transfer," 4th Edition, McGraw-Hill, 1976.6. J. P. Holman, "Heat Transfer," 5th Edition, 1981.7. Entergy Nuclear Northeast Engineering Report, Report No. VY-RPT-05-00022, "Task TO 100 Reactor Heat Balance EPU Task Report for ER-04-1409," SI File No. VY-16Q-205.
U I I I I I I I I I I 1 I I I I I I I File No.: VY-16Q-305 Revision:
0 Page 10 of 29 F0306-0 I RO U Structural Integrity Associates, Inc.Table 1: Material Properties
@ 300F(l)SA-533 Gr B SA-508 Cl 2 SA-240 SA-182 F3161 Material (Mn-I/2Mo-(3/4Ni-1/2Mo-Type 304 SA 376 TP316 1/2Ni) Il3Cr-V) (!8Cr-8Ni) (lGCr-12NM
-_________
2Mo)Modulus of Elasticity, e- 28.0 26.7 27.0 27.0 psi 28._2.7270_7.
Coefficient of Thermal 77 73 9.8 9.8 Expansion, e6, in/in/0 F _.7_7.3_9.8_9.
Thermal Conductivity, 23.4 23.4 9.8 9.3 Btu/hr-ft-OF Thermal Diffusivity, ft2/hr 0.401 0.401 0.160 0.150 Calculated Specific Heat, Btu/lb-OF
: 12) 0.119 0.119 0.125 0.127 Density, lb/in 3  0.283 0.283 0.283 0.283 Poisson's Ratio 0.3 0.3 0.3 0.3 Notes: (')The material properties applied in the analyses are taken from ASME Section II Part D 1998 Edition with 2000 Addenda. This is consistent with information provided in the Design Input Record (page 13 of VY EC No. 1773, SI File No. VY-16Q-209).
The use of a later code edition than that used for the original design code is acceptable since later editions typically reflect more accurate material properties than was published in prior Code editions.
Material Properties are evaluated at 300'F from the 1998 ASME Code, Section II, Part D, with 2000 Addenda, except for density and Poisson's ratio, which are assumed typical values.(2) Calculated as fk/(pd)j/12 3.Table 2: Pressure Results Membrane Plus Total Stress Location Bending Stress Intensity (psi)Intensity (psi)Safe End 11350 11490 Blend Radius 33640 31300 File No.: VY-16Q-305 Revision:
0 Page 11 of 29 F0306-01 RO Structural Integrity Associates, Inc.Table 3: 0% Flow Regions 1 and 3 Heat Transfer Coefficients Pipe Inside Diameter, D = 2S H, inches = 2.150 ft= 0.655 m Outer Pipe, Inside radius, r. = 12.9 inches = 1.075. ft 0.328 m Inner Pipe Outside Diameter, D = na inches = 0.000 ft= 0.000 m Inner Pipe, Outside radius, r = 0 inches 0.000 ft 0.000 m Fluid Velocity, V = 17.364 ft/sec = 8A?9 5 gpm=Characteristic Length, L = D = 2.150 ft= 0.655 m Ttuid -Tsurf&#xfd;., AT 8,40 12.00 24.00 36.00 4.67 6.67 13.33 20.00 000 (Outside 12.3 Mib/hr 48.00 60.00 26.67 33.33 72.00 &deg;F 40.00 C Value at Fluid Temperature, T [3]Units Conversion 70 100 200 300 400 500 600 -F Water Property Factor f1l 21.11 37.78 93.33 148.89 204.44 260.00 315.56 C k 1.7307 0.5997 0.6300 0.6784 0.6836 0.6611 0.6040 0.5071 W/m-&deg;C..hm ncv 0.3465 0.3640 0.3920 0.3950 0.3820 0-3490 0.2930 Btu/hr-ft-&deg;F CP 4.1869 4.185 4.179 4.229 4.313 4.522 4.982 6.322 kJ/kg-&deg;C (Sp.ficHeat) 1.000 0.998 1.010 1.030 1.080 1.190 1.510 Btu/Ibm-&deg;F p 16.018 997.1 994.7 962.7 917.8 858.6 784.9 679.2 kg/m 3 (Density) 62.3 62.1 60.1 57.3 53.6 49.0 42.4 Ibm/ft 3 1 1.8 1.89E-04 3.24E-04 6.66E-04 1.01E-03 1.40E-03 1.98E-03 3.15E-03 m 3/m 3-.c (Volumetric Rate of Expansion) 1.05E-04 1.80E-04 3.70E-04 5.60E-04 7.80E-04 1.10E-03 1.75E-03 ft 3/ft 3-&deg;F 9 0.3048 9.806 9.806 9.806 9.806 9.806 .9.806 9.806 mIS 2 (Gravitational Constant) 32.17 32.17. 32.17 32.17 32.17 32.17, 32.17 .tts 2.. 1.4881 9.96E-04 6.82E-04 3.07E-04 1.93E-04 1.38E-04 1.04E-04 8.62E-05 kg.rn-s...........
py.namic_
q ... 6.69E-04 4.58E-04 2.06E-04 1.30E-04 9.30E-05 7.00E-05 5.79E-05 Ibm/ft-s Pr 6.980 4.510 1.910 1.220 0.950 0.859 1.070 -(Prandtl Number)Calculated Parameter Formula 70 100 200 300 400 500 600 -F Reynold's Number, Re pVD/p 3473691 5061789 10891437 16454670 21515912 26132199 27337904 -Grashof Number, Gr gPATL 3/(Wp)2  2441754517 1.2697E+10 2.417E+11 1.252E+12 3.977E+12 1.034E+13 2.16049E+13
-Grashof Number, Gr 6  gpAT(r.-ri) 3/(p.P)3  3.05E+08 1.59E+09 3.02E+10 1.57E+11 4.97E+11 1.29E+12 2.70E+12 -Rayleigh Number, Ra .GrPr 17043446531 5.7265E+10 4.616E+11 1.528E+12 3.778E+.12 8.883E+12 2.31172E+13
-Rayleigh Number, Ra Gr 6 Pr 2.13E+09 7.16E+09 5.77E+10 1.91E+11 4.72E+11 1.11E+12 2.89Et12 From [1:..Inside Surface Forced Convection Heat Transfer Coefficient:
Hforced 0:023Re&deg;pr&deg;-
4 1D 7,823.02 9,326.34 13,148.12 15,405.24 16,705.40 17,126.15 16,275.32 W/m 2-&deg;C 1,377.74 1,642.50 2,315.56 2,713.07 2,942.05 3,016.15 2,866.31 Btu/hr-ft 2-&deg;F From [1]: Inside Surface Natural Convection Heat Transfer Coefficient:
Case: Enclosed cylinder C = n 5 Hfe C(GrPr)nk/L 161.85 258.65 469.34 637.89 773.57 875.17 933.22 W/m 2-&deg;C 32.03 45.55 82.66 1123412 .136.24 154.13 164.35 Btu/hr-ft 2-&deg;F I I I I I I I I I I I I I I I I I File No.: VY-16Q-305 Revision:
0.Page 12 of 29 F0306-OI RO I *Structural Integrity Associates, Inc.Table 4: 0% Flow Region 5 Heat Transfer.
Coefficient Heat Transfer Coefficients
 
==References:==
: 1. J. P. Holman, "Heat Transfer, -4th Edition, McGraw-Hill, 1976.2. J. P. Holman, "Heat Transfer,'
5th Edition, 1981.3. N. P. Cheremisinoff, "Heat Transfer Pocket Handbook," Gulf Publishing Co., 1984.(Required Inputs are Shaded!)Title = _ ". , Pipe Inside Diameter, D =4 dQOO inches = 3.333= 1.016 Outer Pipe, Inside radius, r. = 20 inches = 1.667 0.508 Inner Pipe Outside Diameter, D = f, inches = 0.000= 0.000 Inner Pipe, Outside radius, r = 0 inches 0.000 ft m ft m ft m ft C).oC' I <Fluid Velocity, V =Characteristic Length, L = D =(Outside)
Tluid -Tu,-ram, AT 8.40= 4.67 7.224 3.333 12.00 6.67 0.000 m fllsec = -2g8293 E pm=ft= 1.016 m 24.00 36.00 4 13.33 20.00 2 12.3 Mlb/hr ,8.00 60.00 6.67 33.33 72.00 -F 40.00 &deg;C Value at Fluid Temperature, T [3]Units Conversion 70 100 200 300 400 500 600 'F Water Property Factor [1] 21.11 37.78 93.33 148.89 204.44 260.00 315.56 'C k 1.7307 0.5997 0.6300 -0.6784 0.6836 0.6611 0.6040 0.5071 W/m-'C (Thermal Conductivit0).
..... .0*3465 0.3640 0.3920 0.3950 0.3820 0.3490 0.2930 Btu/hr-ft-*F P 4.1869 4.185 4.179 4.229 4.313 4.522 4.982 6.322 kJ/kg-'C (SpeificHeat.)
.1000 0.998 1.010 1.030 1.080 1.190 1.510 Btu/Ibm-'F p 16.018 997.1 994.7 962.7 .917.8 858.6 784.9 679.2 kg/m 3 (Density) 62.3 62.1 60.1 57.3 53.6 49.0 42.4 .Ibm/f.3 1.8 1.89E-04 3.24E-04 6.66E-04 1.01E-03 1.40E-03 1.98E-03 3.15E-03 m 3/m3-&deg;C (Volumetric Rate of Expansion) 1.05E-04 1.80E-04 3.70E-04 5.60E-04 7.80E-04 1.10E-03 1.75E-03 ft 3/ft 3-oF 9 0.3048 9.806 9.806 9.806 9.806 9.806 9.806 9.806 m/s 2 (Gravitational Constant) 32.17 32.17 .32.17 32.17 32.17 32.17 32.17 ft/s 2 1.4881 9.96E-04 6.82E-04 3.07E-04 1.93E-04 1.38E-04 1.04E-04 8.62E-05 kg/m-s...... yaicsLcs ....... 6.69E-04 4.58E-04 2.06E-04 1.30E-04 9.30E-05 7.00E-05 5.79E-05 lbm/tt:s Pr 6.980 4.510 1.910 1.220 0.950 0.859 1.070 ---(Prandtl Number) 'Calculated Parameter Formula 70 100 200 300 400 500 600 'F Reynold's Number, Re pVD/1 t 2240531 3264854 7024977 10613262 13877763 16855268 17632948 --Grashof Number, Gr gp3ATL 3/(P/p)2  9099611606 4.732E+10 9.01E+11 4.667E+12 1.48E+13 3.85E+13 8.05143E+13 Grashof Number, Gr* g0AT(r-_r) 3/(p/p)3 1.14E+09 5.91E+09 1.13E+11 5.83E+11 1.85E+12 4.82E+12 1.01E+13 --Rayleigh Number, Ra GrPr 6.3515E+10 2.134E+11 1.72E+12 5.694E+12 1.41E+13 3.31E+13 8.61503E+13 Rayleigh Number, Ra GrbPr 7.94E+09 2.67E+10 2.15E+11 7.12E+11 1.76E+12 4.14E+12 1.08E+13 --From [1]: Inside Surface Forced Convection Heat Transfer Coefficient:
Htor~,,j 0.023Re 0 ePro&deg;k/D 3,552.89 4,235.64 5,971.33 6,996.42 7,586.90 7,777.99 7,391.58 W/m 2-&deg;C 625.71 745.95 1,051.63.
1,232.17 1,336.16 1,369.81 1,301.76 Btu/hr-ft 2-&deg;F From [1]: Inside Surface Natural Convection Heat Transfer Coefficient:
Case:. Enclosed cylinder C = 55! , n = , .Hree .C(GrPr)nk/L 162.97 231.79 420.60 571.66 693.25 784.30 836.32 W/m 2-&deg;C 28.70 40.82 74.07 g0.v8Y, 122.09 138.13 147.29 Btu/hr-ft 2-&deg;F File No.: VY-16Q-305 Revision:
0 Page 13 of 29 F0306-O1 RO VStructural Integrity Associates, Inc.ELEMENTS Recirc Outlet Nozzle Finite Element Model APR 19 2007 13:03:51 Figure 1: ANSYS Finite Element Model File No.: VY-16Q-305 Revision:
0 Page 14 of 29 F0306-01 RO C Structural Integrity Associates, Inc.EL EMENT S CF PRES- NORMI ANN, APR 19 2007 13:29:35-5082-3730-30,541-2379-1703-1027&#xfd;-351.496 324.252 1000 IZ Recirc Outlet Nozzle Finite Element Model Figure 2: Recirculation Outlet Nozzle Internal Pressure Distribution File No.: VY-16Q-305 Revision:
0 Page 15 of 29 F0306-01 RO V Structural Integrity Associates, Inc.00 7 34 7 I I Figure 3: Recirculation Outlet Nozzle Pressure Cap Load File No.: VY-16Q-305 Revision:
0 Page 16 of 29 F0306-0 1 RO VStructural Integrity Associates, Inc.Figure 4: Recirculation Outlet Nozzle Vessel Boundary Conditions File No.: VY-16Q-305 Revision:
0 Page 17 of 29 F0306-01 RO V Structural Integrity Associates, Inc.AREAgS S MAT: NUM Region 5 APR 19 2007 13:35:14 Region 6 Region 4 Region 2 Region 3 I Region 1 x Recirc Outlet Nozzle Finite Element Model, Figure 5: Nozzle and Vessel Wall Thermal and Heat Transfer Boundaries File No.: VY-16Q-305 Revision:
0 Page 18 of 29 F0306-01 RO V Structural Integrity Associates, Inc.NODAL SOLUTION STEP=322 SUB =1 TIME=5.1 SINT (AVG)DMX =.810882 SMN =169.035 SMX =121100 AN Y,.APR 24 2007 09:05:10~iW~7' ~169.035 27043 53916 13606 40479 Recirc Outlet Nozzle Finite Element Model 67353 80790 94226 107663 121100 Figure 6: Safe End Critical Thermal Stress Location File No.: VY-16Q-305 Revision:
0 Page 19 of 29 F0306-01RO V Structural Integrity Associates, Inc.ELEMENTS MAT NUM PATH AN7 APR 19 2007 13:57:29 Node 6395 Recirc Outlet Nozzle Finite Element Model Figure 7: Safe End Limiting Linearized Stress Paths File No.: VY-16Q-305 Revision:
0 Page 20 of 29 F0306-0 IRO V Structural Integrity Associates, Inc.Figure 8: Blend Radius Limiting Pressure Stress Location File No.: VY-16Q-305 Revision:
0 Page 21 of 29 F0306-OI RO C Structural Integrity Associates, Inc.I I Figure 9: Blend Radius Linearized Stress Path File No.: VY-16Q-305 Revision:
0 Page 22 of 29 F0306-O I RO HStructural Integrity Associates, Inc.I Total Stress Intensity 03 Time (sec)Figure 10: Safe End 100% Flow Total Stress Intensity Total Stress Intensity C,,.Time (sec)Figure 11: Blend Radius 100% Flow Total Stress Intensity File No.: VY-16Q-305 Revision:
0 Page 23 of 29 F0306-01 RO VStructural Integrity Associates, Inc.140000 (J2 200 400 600 800 Time (sec)1000 Figure 12: Safe End Total Stress History for 100% Flow 80000 a 0 100 200 300 400 500 600 700 800 900 1000 Time (sec)Figure 13: Safe End Membrane Plus Bending Stress History for 100% Flow File No.: VY-16Q-305 Page 24 of 29 Revision:
0 F0306-OI RO Structural Integrity Associates, Inc.--u11 I _ _ __ _I__ _ _ __ _ _ I_ _ I_ _-sY-sx 60000 Q- 40000 U,-' A I F +/- -l + F -I I 20000 4-4----------
+ -N------ F + 1 4 F F I UI 0 100 200 .300 400 500 600 700 800 Time (sec)Figure 14: Safe End Total Stress History for 50% Flow 900 1000-sy-sx 60000 40000 I 20000 41 0____ F F F F ______2UUIU0 I F I-40000-60000-60000 0 100 .200 300 400 500 Time (sec)600 700 800 900 1000 Figure 15: Safe End Membrane Plus Bending Stress History for .50% Flow File No.: VY-16Q-305 Revision:
0 Page 25 of 29 F0306-OI RO Structural Integrity Associates, Inc.==.=100 200 300 400 500 600 700 800 Time (sec)Figure 16: Safe End Total Stress History for 0% Flow 900 1000 30000 Ce 100 200 300 400 500 Time (sec)600 700 800 900 1000 Figure 17: Safe End Membrane Plus Bending Stress History for 0% Flow File No.: VY-16Q-305 Revision:
0 Page 26 of 29 F0306-01 RO C Structural Integrity Associates, Inc.0 1000 2000 3000 4000 5000 6000 Time (sec)7000 8000 Figure 18: Blend Radius Total Stress History for 100% Flow 40000 a 0 1000 2000 3000 4000 5000 6000 7000 8000 Time (sec)Figure 19: Blend Radius Membrane Plus Bending Stress History for 100% Flow File No.: VY-16Q-305 Page 27 of 29 Revision:
0 F0306-01 RO V Structural Integrity Associates, Inc.0~0-~U, II I I I I I I I I I 0 1000 2000 3000 4000 5000 6000 Time (sec)7000 8000 Figure 20: Blend Radius Total Stress History for 50% Flow 30000 U, 0 1000 2000 3000 4000 5000 6000 7000 Time (sec)8000 Figure 21: Blend Radius Membrane Plus Bending StressHistory for 50% Flow File No.: VY-16Q-305 Revision:
0 Page 28 of 29 F0306-O1RO I I I I I I I I I I I I I I I I V Structural Integrity Associates, Inc.35000 30000 25000 C.U, 20000 15000 10000 5000 0 0 1000 2000 3000 4000 5000 6000 7000 8000 Time (sec)Figure 22: Blend Radius Total Stress History for 0% Flow 20000 _____ _____/10000 5000 0-5000--- i i i i i+/- _____-10000 0 1000 2000 3000 4000 5000 6000 7000 8000 Time (sec)Figure 23: Blend Radius Membrane Plus Bending Stress History for 0% Flow File No.: VY-16Q-305 Revision:
0 Page 29 of 29 F0306-OI RO V Structural Integritj Associates, Inc.APPENDIX A FINITE ELEMENT ANALYSIS FILES File No.: VY-16Q-305 Revision:
0 Page A l of A2 F0306-OI RO I ,Structural Integrity Associates, Inc.RON VY.INP Input File for Pressure Load In Computer files VY RON T 00.INP Input File for 100% Flow Thermal Analysis In Computer files VY RON S 100.INP Input File for 100% Flow Stress Analysis In Computer files VY RON T 50.INP Input File for 50% Flow Thermal Analysis In Computer files VY RON T 50.INP Input File for 50% Flow Stress Analysis In Computer files VY RON 0.INP Input File for 0% Flow Thermal Analysis In Computer files VY RON 0.INP Input File for 0% Flow Stress Analysis In Computer files PVESS.OUT Stress Output across the shell with Pressure Load In Computer files PSE.OUT Stress Output at. Safe End with Pressure Load In Computer files PBLEND.OUT Stress Output at Blend Radius with Pressure Load In Computer files#FSE.OUT Stress Output at Safe End In Computer files#FBR.OUT Stress Output at Blend Radius In Computer files#FSE INSIDE.RED Stress Extracted at Safe End In Computer files#FBR INSIDE.RED Stress Extra&ted at Blend Radius In Computer files#FSE T-Green.XLS Green Function with Total Stress at Safe End In Computer files#FSE_M+B-Green.XLS Green Function with Membrane plus Bending Stress In Computer files at Safe End HFBRT-Green.XLS Green Function with Total Stress at Blend Radius'at In Computer files 100% flow HFBRM+B-Green.XLS Green Function with Membrane plus Bending Stress In Computer files at Blend Radius at 100% flow Where # is H, M, L meaning 100%, 50%, and 0% flow rate, respectively.
File No.: VY-16Q-305 Revision:
0 Page A2 of A2 F0306-01 RO Structural Integrity Associates, Inc. File No.: VY-16Q-306 NEC-JH 09 CALCULATION PACKAGE Project No.: VY-16Q PROJECT NAME: Environmental Fatigue Analysis of VYNPS CONTRACT NO.: 10150394 CLIENT: PLANT: Entergy Nuclear Operations, Inc. Vermont Yankee Nuclear Power Station CALCULATION TITLE: Fatigue Analysis of Recirculation Outlet Nozzle Document Affected Project Manager Preparer(s)
&Revision Pages Revision Description Approval Checker(s)
Signature
& Date Signatures
& Date 0 134, Initial Issue Terry J. Herrmann J. E. Smith Appendix:
7/27/2007 7/27/2007 Al-Al Minghao Qin 7/27/2007 Page 1 of 34 F0306-01 RO Structural Integrity Associates, Inc.Table of Contents 1.0 O B JE C T IV E ..................................................................................................................................
4 2.0 M ETH O D O LO G Y ..........................................................................................................................
4 3.0 ANALYSIS ..................................
........................
7 4.0 CALCULATION OF THERMAL STRESSES FOR TRANSIENT 9 ......................
11 5.0 FA TIGUE U SAG E RESULTS ..............................................................................
s .................
14 6.0 ENVIRONMENTAL FATIGUE ANALYSIS .................................
.....I ....... 14 7.0 R E FE R EN C E S ...........................................................................................................................
15 APPENDIX A
 
==SUMMARY==
OF OUTPUT FILES ....................................
.............................
Al List of Tables I I I I I I I I I I I I i Table 1: Table 2: Table 3: Table 4: Table 5: Table 6: Table 7: Table 8: Maximum Piping Stress Intensity Calculations
............................................................
16 B lend R adius Transients..................................................................................................
17 Safe End Transients
...............................................
....... 18 Blend Radius Stress Summary ..........................................
19 Safe End Stress Sum m ary .....................................................................................
.........
20 Fatigue Results for Blend Radius (60 Years) ...................................................................
21 Fatigue Results for Safe End (60 Years) ...................................
23 Material Properties (For.Transient
: 9) .............................................................................
25 File No.: VY-16Q-306 Revision:
0 Page 2 of 34 F0306-01 RO I I ,"Structural integrity Associates, Inc.List of Figures Figure 1: External Forces and Moments on the Recirculation Outlet Nozzle ...............................
26 Figure 2: Nozzle and Vessel Wall Thermal and Heat Transfer Boundaries for Transient 9 ...... 27 Figure 3: Transient 1 -Normal Startup at 100&deg;F/hr .................................
28 Figure 4: Transient 2 -Turbine Roll and Increase to Rated Power ..............................................
28 Figure 5: Transient 3 -Loss of Feedwater Heaters and Turbine Trip 25% Power ............
29 Figure 6: Transient 4 -Loss of Feedwater Pumps .........
I .................................
29 Figure 7: Transient 5 -Turbine Generator Trip ...............................................
30 Figure 8: Transient 6 -Reactor Overpressure
............
...... ..........................................................
.30 Figure 9: Transient 7 -SRV Blowdown .......................................................................................
31 Figure 10: Transient 8 -SCRAM Other .......................................................................................
31 Figure 11: Transient 9 -Im proper Startup .....................................................................................
32 Figure 12: Transient 10 -Shutdow n ...........................................................................................
....... 32 Figure 13: Typical Green's Functions for Thermal Transient Stress ................................................
33 Figure 14: Typical Stress Response Using Green's Functions
....................................................
34 File No.: VY-16Q-306 Revision:
0 Page 3 of 34 F0306-01 RO Structural Integrity Associates, Inc.1.0 OBJECTIVE The purpose of this calculation is to perform a revised fatigue analysis for the Entergy Vermont Yankee (VY) reactor pressure vessel (RPV) recirculation outlet nozzle. Two locations will be analyzed for fatigue acceptance:
the safe end (SA182 F316) and the nozzle inner comer blend radius (SA508 Class 2). Both locations are chosen based on the highest overall stress of the analysis performed in Reference
[I].. Fatigue usage will be determined for each location, the nozzle forging and safe, end, respectively.
An environmental fatigue usage factor will also be determined for each of these locations.
 
==2.0 METHODOLOGY==
In order to provide an overall approach and strategy for evaluating the recirculation outlet nozzle, the Green's Function methodology and associated ASME Code stress and fatigue analyses are described in this section.Revised stress and fatigue analyses are being performed for the recirculation outlet nozzle using ASME Code, Section III methodology.
These analyses are being performed to address license renewal requirements to evaluate environmental fatigue for this component in response to Generic Aging Lessons Learned (GALL) Report [14] requirements.
The revised analysis is being performed to refine the fatigue usage so that an environmental fatigue factor can be determined for subsequent license renewal efforts.Two sets of rules are available under ASME Code, Section III, Class 1 [13]. Subparagraph NB-3600 of Section III provides simplified rules for analysis of piping components, and NB-3200 allows for more detailed analysis of vessel components.
The NB-3600 piping equations combine by absolute sum the stresses due to pressure, moments and through wall thermal gradient effects, regardless of where within the pipe cross-section the maximum value of the components of stress are located. By considering stress signs, affected surface (inside or outside) and azimuthal position, the stress ranges may be significantly reduced. In addition, NB-3600 assigns stress indices by which the stresses are multiplied to conservatively incorporate the effects of geometric discontinuities.
In NB-3200, stress indices are not required, as -the stresses are calculated by finite element analysis and consider* applicable stress concentration factors. In addition, NB-3200 methodology accounts for the different locations within a component where stresses due to thermal, pressure or other mechanical loading are a maximum. This generally results in a net reduction of the stress ranges and consequently, in the calculated fatigue usage. Article 4 [17] methodology was originally used to evaluate the recirculation outlet nozzle. NB-3200 methodology, which is the modem day equivalent to Article 4, -is used in this analysis to be consistent with the Section III design bases for this component, as well as to allow a more detailed analysis of this component.
In addition, several of the conservatisms originally used in the original recirculation outlet nozzle evaluation (such as grouping of transients) are removed in the current evaluation so as to achieve a more accurate CUF.For the recirculation outlet nozzle evaluated as a part of this work, stress histories will be computed by a time integration of the product of a pre-determined Green's Function and the transient data.File No.: VY-16Q-306 Page 4 of 34 Revision:
0 F0306-01 RO 1 Structural Integrity Associates, Inc.This Green's Function integration scheme is similar in concept to the Duhamel theory used in structural dynamics.
A detailed derivation of this approach and examples of its application to specific plant locations is contained in Reference
[15.]. A general outline is provided in this section.The steps involved in the evaluation are as follows:* Develop finite element model: Develop heat transfer coefficients and boundary conditions for the finite element model* Develop Green's Functions e .Develop thermal transient definitions
: Perform stress analysis to determine stresses for thermal transients
* Perform fatigue analysis A Green's Function is derived by. using finite-element methods to determine the transient stress response of the component to a step change in loading (usually a thermal shock). The critical location in the component is identified based on the maximum stress, and the thermal stress response over time is extracted for this location.
This response to the input thermal step is the "Green's Function." Figure 13 shows a typical set of two Green's Functions, each for a different set of heat transfer coefficients (representing different flow rate conditions).
I To compute the thermal stress response for an arbitrary transient, the loading parameter (usually local fluid temperature) is deconstructed into a series of step-loadings.
By using the Green's Function, the response to each step can be quickly determined.
By the principle of superposition, these can be added (algebraically) to determine the response to the original load history. The result is demonstrated in Figure 14. The input transient temperature history contains five step-changes of varying size, as shown in Figure 14. These five step changes, produce the five successive stress responses in the second plot shown in Figure 14. By adding all five response curves, the real-time stress response for the input thermal transient is computed.The Green's Function methodology produces identical results .compared to running the input transient through the finite element model. The advantage of using Green's Functions is that many individual transients can be run with a significant reduction of effort compared to running all transients through the finite element model. The trade-off in this process is that the Green's Functions are based on constant material properties and heat transfer coefficients.
Therefore, these parameters are chosen to bound all transients that constitute the majority of fatigue usage, i.e., the heat transfer coefficients at 300'F bound the cold water injection transient.
In addition, the instantaneous value for the coefficient of thermal Sexpansion is used instead of the mean value for the coefficient of thermal expansion.
This conservatism
* is more than offset by the benefit of not having to analyze every transient, which was done in the VY reactor recirculation outlet nozzle evaluation.
Once the stress history is obtained for all transients using the Green's Function approach, the remainder of the fatigue analysis is carried out using traditional methodologies in accordance with ASME Code, Section III requirements.
File No.: VY-16Q-306 Page 5 of 34 Revision:
0 F0306-OIRO Structural Integrity Associates, Inc.Fatigue calculations are performed in accordance with ASME Code, Section III, Subsection NB-3200 methodology.
Fatigue analysis is performed.
for the two limiting locations (one in the. safe end and one in the nozzle forging, representing the two materials of the nozzle assembly) using the Green's Functions developed for these three Recirculation flow conditions and 60-year projected cycle counts.Three Structural Integrity utility computer programs are used to facilitate the fatigue analysis process: STRESS.EXE, P V.EXE, and FATIGUE.EXE.
The first program, STRESS.EXE, calculates a stress history in r'esponse to a thermal transient using a Green's Function.
The second program, P-V.EXE, reduces the stress history to peaks and valleys, as required by ASME Code fatigue evaluation methods. The third program, FATIGUE.EXE, calculates fatigue from the reduced peak and valley history using ASME Code, Section ili range-pair methodology.
All three programs are explained in detail and have been independently verified for generic use in the Reference
[5]calculation.
In order to perform the fatigue analysis, Green's Functions are developed using the finite element model. Then, input files with the necessary data are prepared and the three utility computer programs are run. The first program (STRESS.EXE) requires the following three input files: Input file "GREEN.DAT":
This file contains the Green's Function for the location being evaluated.
For each flow condition, two Green's Functions are determined:
a membrane plus bending stress intensity Green's Function and a total stress intensity Green's Function.
This allows computation of total stress, as well as membrane plus bending stress, which is necessary to compute K, per ASME Code, Section III requirements.
* Input file "GREEN.CFG":
This file is a configuration file containing parameters that define the Green's Function (i.e., number of points, temperature drop analyzed, etc.).* Input file "TRANSNT.INP":
This file contains the input transient history for all thermal transients to be analyzed for the location being evaluated.
Pressure and piping stress intensities are also included for each transient case, based on pressure stress results from finite element analysis and attached piping load calculations.
The second program (P-V.EXE) simply extracts only the maxima and minima stress (i.e., the peaks and valleys) from the stress histories generated by program STRESS.EXE.
The third program (FATIGUE.EXE) performs the ASME Code peak event-pairing required to calculate a fatigue usage value. The input data consists of the output peak and valley history from program P-V.EXE and a configuration input file that provides ASME Code configuration data relevant to the fatigue analysis (i.e., K, parameters, Sin, Young's modulus, etc.). The output is the final fatigue calculation for the location being evaluated.
The Green's Function methodology described above uses standard industry stress and fatigue analysis practices, and is the same as the methodology used in typical stress reports. Special approval for the use of this methodology is therefore not required.The 10 transients to be analyzed are described in Reference
[2], for the recirculation outlet nozzle.Transients 11 and 12 are hydrostatic tests that have only a small temperature change and are not File No.: VY-16Q-306 Page 6 of 34 i Revision:
0 F0306-01 RO i H structural Integrity Associates, Inc.i modeled. Transients 1 to 10 are shown in Figures 3 -12. The analysis of transient 9 is an exception to this process because there are two different thermal shocks at the nozzle and vessel regions.Transient 9 is analyzed separately using ANSYS instead of STRESS.EXE and P-V.EXE. The results from ANSYS are input directly into FATIGUE.EXE with the other transient stress results.I *3.0 ANALYSIS The fatigue analysis involves preparing the input files and running the three programs.
The programs STRESS.EXE and P-V.EXE are run together through the use of a batch file. The program FATIGUE.EXE is run after processing the output from P-V.EXE. The ANSYS results from transient 9 are added to the P-V.EXE results for the other transients and input into FATIGUE.EXE.
The steps associated with this process are described in the following sub-sections.
 
===3.1 Transient===
 
Definitions (for program STRESS.EXE)
* The program STRESS.EXE requires the following three input files for analyzing an individual transient:
i GREEN.DAT.
There are 12 stress history functions (Green's Functions) obtained from Reference[I]. They represent the membrane plus bending and total stress intensities at the blend radius and safe end locations.
The blend radius and the safe end have three stress history functions for the 100% flow, 50%, and no-flow conditions.
* GREEN.CFG is configured as described in Reference
[5].i Several TRANSNT.INP files are created to simulate the transients shown on Reference
[2]. Tables 2 and 3 show the thermal history used to simulate each transient for the blend radius and safe end locations, respectively.
The aforementioned transient information for each location is contained in i EXCEL files BlendRadiusTransients.xls and Safe End Transients.xls, which are contained in the computer files. Transients are split into the following groups based upon flow rate:* Transients 2, 3, 5, 6, 7, and 8 are run at 100% flow Green's Function* Transients I and 10 are run at 50% flow Green's Function* Transient 4 is run at no flow, 50% flow, and 100% flow Green's Functions, as shown in Tables 2 and 3., Transient 9 is simulated by ANSYS [11] model and the thermal results are taken from ANSYS directly.
See Section 4 for details.* Transients 11 and 12 have only small temperature change (70&deg;F to 100&deg;F). Therefore, the thermal stresses for these two transient are ignored. Only the piping load and the pressure load are considered in these two transients.
* The loss of feedwater heaters (Feedwater Heater Bypass) event has a negligible I temperature, change (526 'F to 516 'F) associated with it. Therefore this transient is ignored.I File No.: VY-16Q-306 Page 7 of 34 Revision:
0 F0306-OIRO Structural Integrity Associates, Inc.3.2 Peak and Valley Points of the Stress History (for program P-V.EXE) I After STRESS.EXE runs are completed, the program P-V.EXE is run to extract only the peaks and valleys from the STRESS.OUT stress history file produced by the STRESS.EXE program. The only input-required for this program-is the stress history file (STRESS.OUT), and the program outputs all of the resulting peaks and valleys to output file P-V.OUT. The resulting peak and valley stress I summaries for all transients are summarized in Tables 4 and 5 for both locations.
Columns 2 through 5 of Tables 4 (for the blend radius) and 5 (for the safe end) show the final peak and valley output. These final peaks and valleys were selected from the total stress and membrane plus bending I stress intensities that were calculated by STRESS.EXE and screened with P-V.EXE.3.3 Pressure Load I The pressure stress associated with a 1,000 psi internal pressure was determined in Reference
[1].These values are as follows: I Pressure stress for the safe end:* 11,350 psi membrane plus bending linearized stress intensity.
* 11,490 psi total stress intensity.
Pressure stress for the blend radius:* 33,640 psi membrane plus bending linearized stress intensity.
* 31,300 psi total stress intensity.
The pressure stress intensity values for each transient were linearly scaled based on the pressure.The actual pressure for column 6 of Tables 4 and 5 is obtained from Tables 2 and 3, respectively.
The scaled pressure stress values are shown in columns 7 and 8 of Tables 4 and 5.The pressure stress is combined with the peak and valley points to calculate the final stress values used for fatigue analysis.3.4 Attached Piping Loads I Additionally, the piping stress intensity (stress caused by the attached piping) was determined.
These piping forces and moments are determined as shown in Figure 1.The following formulas are used to determine the maximum stress intensity in the nozzle at the two locations of interest.
From engineering statics; the piping loads at the end of the model can be translated to the first and second cut locations using the following equations: (Mx), Mx -FL, For Cut1: : M I (My), :My + F, L, File No.: VY-16Q-306 Page 8 of 34 Revision:
0 F0306-OI RO Structural Integrity Associates, Inc.(M.,)2 = M. -- FYL2 For Cut II: (My)2 = My + FL 2 The total bending moment and shear loads are obtained using the equations below: M XY&#xfd;(M. 12+ (MY) 2 For Cut I: Fx,=/ (Fx), 2 +(Fy), 2 M = (M)22+(MY)2 2 For Cut II: Fy (F,)2 2 +(F,)2 2 The distributed loads for a thin-walled cylinder are obtained using the equations below: 1RN L2 RNj q = -- F -ME 7rN L NJ To determine the primary stresses, PM, due to internal pressure and piping loads, the following equations are used.For Cut 1, using thin-walled equations:
Pa, Nz)z =- +_2 tN tN PaN (PM)v -G tN qN SIAX = =2 (PM)O_ (P_)R.2 +_(r ) 2.or SIMIX= 2 (P11)z 2-(PIR), + (CM ) 2 File No.: VY-16Q-306 Page 9 of 34 Revision:
0 F0306-01 RO Structural Integrity Associates, Inc.Because pressure was considered separately in this analysis, the equations used for Cut I are valid for Cut II.where: L, = The length from the end of the nozzle where the piping loads are applied to the location of interest in the safe end.L2 The length from the end of the nozzle where the piping loads are applied to the 3 location of interest in the blend radius.Mxy = The maximum bending moment in the xy plane.Fyx = The maximum shear force in the xy plane.= The normal force per. inch of circumference applied to the end of the nozzle in the z direction.
qN = The shear force per inch of circumference applied to the nozzle.RN= The mid-wall nozzle radius.Since. the pressure was considered separately in this analysis, the equations can be simplified as follows: NZI (PM), = -3 t N (PM)d = 0 rMn = q0 iN.SIAx = 2(rM )O or S ~ ~ 2 (1 1 2 _r +/- ~ 2I Per Reference
[7], the recirculation outlet nozzle piping loads (Total thermal, weight and seismic loads) are as follows: F, = 20,000 lbs K = 2,004,000 in-lb Fy = 20,000 lbs, my = 3,000,000 in-lb F, = 30,000 lbs M,-= 2,004,000 in-lb L, is equal to 4.25 inches and the L 2 is equal to 42.77 inches. The calculations for the safe end and blend radius are shown in Table 1. The first cut location is the same as the Green's Function cross section per [1] at the safe end, and the second cut is from Node 3829 (inside) to Node 3809 (outside).
This gives the maximum ID and minimumOD for the cross section calculation.
The maximum stress intensities due to the piping loads are 570889 psi at the safe end and 280.16 psi at maxmu stress intens i Ties due to th iiglasae50.9piattesf n n 8.6pia the blend radius. The' iping load sign is set as the same as the thermal stress sign.File No.: VY-16Q-306 Page 10 of 34 I Revision:
0 F0306-OI RO Structural Integrity Associates, Inc.These piping stress values are scaled assuming no stress occurs at an ambient temperature of 70'F, and the full values are reached at reactor design temperature, 575TF [6]. The scaled piping stress values are shown in columns 9 and 10 of Tables 4 and 5. Columns 11 and 12 of Tables 4 and 5 show the summation of all stresses for each thermal peak and valley stress point.3.5 Fatigue Analysis (for program FATIGUE.EXE)
The number of cycles projected for the 60-year operating life is used for each transient
[2]: Column 13 in Tables 4 and 5 shows the number of cycles associated with each transient.
The number of cycles for 60 years was obtained from Reference
[2] unless otherwise noted.The program FATIGUE.EXE performs the "ASME Code style" peak event pairing required to calculate a fatigue usage value. The input data for FATIGUE.CFG is as follows: i Blend Radius Safe End Parameters m andn for 2.0 & 0.2 (low 1.7 & 0.3 (stainless Computing K, alloy steel) [13] steel) [13]Design Stress Intensity 26700 psi [9] 17000 psi [9]Values, Sm @ 600&deg;F @ 600-F Elastic Modulus from 30.0x10 6 psi [13] 28.3x10 6 psi [13]Applicable Fatigue Curve _ _ _ _ _ psi__13]________psi
__13 Elastic Modulus Used in 6 Finite Element Model. 26.7x10 psi [1] 27.0x10 6 psi [1]'The Geometric Stress 1.0 1.53 [3]Concentration Factor Kt 1.0_1.53_[3]
The results of the fatigue analyses are presented in Tables 6 and 7 for the blend radius and safe end for 60 years, respectively.
The fatiguerun inputs described are contained in EXCEL files BRresults.xls and SEresults.xls, which are contained in the computer files.4.0 CALCULATION OF THERMAL STRESSES FOR TRANSIENT 9 Per Tables 2 and 3, the thermal shocks are from 526TF to 268TF and from 526TF to 130TF at the blend radius and-the safe end, respectively.
Therefore, the average temperatures for these two locations are about 400TF and 330TF. Since.there are two different temperature shocks in the same model, ANSYS [10] will be used to calculate stresses directly.
In this section, ANSYS [10] is used to simulate this transient and the results will then be used as input to FATIGUE.EXE, as shown in I Tables 4 and 5. This case corresponds to the downhill (RPV) side of the blend radius.An additional case was also run to simulate the uphill (RPV) side of the blend radius, where the* thermal shocks are from 526TF to 130TF at the safe end, and no temperature change at the blend File No.: VY-16Q-306 Page 11 of 34 Revision:
0 F0306-OIRO Structural Integrity Associates, Inc. I radius. This case at the uphill side of the blend radius was found to produce lower stresses than the I previously mentioned downhill case. Due to this, the downhill case was used for the rest of the analysis in this calculation.
I 4.1 Thermal Load Since the average temperatures in the blend radius and safe end respectivelyare 400'F and 330 0 F, I the material properties for 400'F are used for the blend radius, cladding and vessel. Table 8 shows the material properties at 400TF. The flow rate at this transient is 3395.2 GPM (calculated from 12%of max flow rate [2]) and is shown in Tables 2 and 3.Heat transfer coefficients listed on Reference
[4] are forpre power uprate. The heat transfer coefficients can be scaled by power uprate flow rate and diameter to values corresponding to the flow and location conditions.
Referring to Figure 2, heat transfer coefficients were applied as follows: 3 Region 1 Per [4], the heat transfer coefficient at 500 0 F, h, for 3395.2 GPM (2.084 ft/s) flow is 0.8 4911 -2.084 = 672.8 BTU/hr-ft 2-&deg;F.25 Per [4], the heat transfer coefficient at 100&deg;F, h, for 33395.2 GPM (2.084 f-t/s) flow isi 22'50 -(k2.85 )]&deg; =_ 308.24 BTU/hr-ft2-F The fluid temperature shock is: T= 526 0 F -130&deg;F -526 0 F Region2 2 Per [4], the heat transfer coefficient at 500F, h, for 3395.2 GPM (2.084 ft/s) flow is 4911-.(2"084&deg;8(, 25 0..2 632.21 BTU/hr-ft 2_OF.Per [4], the heat transfer coefficient at 300'F, h, for 3395.2 GPM (2.084 ft/s) flow is 4789Q(2" 0 8 4&deg;( 26  4789. 2.084 0.85 ) = 616.57 BTU/hr-ft 2_-&deg;F.File No.: VY-16Q-306 Page 12 of 34 Revision:
0 F0306-OIRO U Struetural Integrity Associates, Inc.IThe fluid temperature shock is: T = 526 0 F -268 0 F -526 0 F Region 3 Per [4], the heat transfer coefficient at 500'F, h, for 3395.2 GPM flow is I 672.8(0.5)
= 336.4 BTU/hr-ft 2-OF.Per [4], the heat transfer coefficient at 300 0 F, h, for 3395.2 GPM flow is 336. 44789) 328.04 BTU/hr-ft 2-OF.The fluid temperature shock is: Case 1: T = 526'F -268&deg;F -526 0 F Case 2: T = 526 0 F Region 4 The heat transfer coefficient, h, is 0.4 BTU/hr-ft 2-OF [4].The temperature is: T = 120&deg;F 4.2 Thermal Results I The flow dependent thermal load case outlined in Section 4.1 was run on the finite element model.Appendix A contains the thermal transient input file VYRONTT9.INP for 3395.2 GPM flow rate. The flow dependent input files for the stress run is also included in Appendix A. The stress filename is VYRONST9.INP for 3395.2 GPM flow rate.* The critical safe end and blend radius locations are defined in Reference
[1] at nodes 6395 and 3829, respectively.
The stress time history for the critical paths was extracted during the stress run. This produced two files, T9SE.OUT and T9BR.OUT, which contain the thermal stress history. The membrane plus bending stresses and total stresses were extracted from these files to produce the files T9SEInside.RED and T9BRJnside.RED, where SE and BR~corresponded to the safe end and blend radius locations, respectively.
I File No.: VY-16Q-306 Page 13 of 34 Revision:
0 F0306-OI RO Structural Integrity Associates, Inc.The data for the stress results is included in the files T9BRM+B.xls, T9BR_T.xIs, T9SE_M+B.xls, and T9SE_.T.xls in the project Files. Where SE and BR corresponded to. the safe end and blend radius locations, respectively.
M+B and T corresponded to membrane plus bending stress and total stress, respectively.
 
===5.0 FATIGUE===
USAGE RESULTS The blend radius cumulative usage factor (CUF) from system cycling is 0.0108 for 60 years (Table 6). The safe end CUF is 0.0015 for 60 years (Table 7).6.0 ENVIRONMENTAL FATIGUE ANALYSIS The Recirculation Outlet nozzle has three materials:
a Ni-Cr-Fe dissimilar metal weld (DMW), a low alloy steel forging, and a stainless steel safe end. To ensure the maximum CUF considering environmental effects was identified, locations in the safe end and nozzle forging were selected.
This selection produces bounding environmental fatigue results for the entire nozzle assembly for the following reasons:* The highest thermal stresses from the FEM analysis occur in the stainless steel safe end. Stainless steel Fen multipliers are significantly higher than Ni-Cr-Fe multipliers (Fen values are 2.55 or higher for stainless steel [12] vs. a constant value of 1.49 for Ni-Cr-Fe [16]). Therefore, evaluation of the safe end bounds the Ni-Cr-Fe weld material.* The highest pressure stresses from the FEM analysis occur in the low alloy steel nozzle forging.Low alloy steel Fen multipliers are higher than Ni-Cr-Fe multipliers (Fen values are 2.45 or higher for low alloy steel [12] vs. a constant value of 1.49 for Ni-Cr-Fe [16]). Therefore, evaluation of the nozzle forging bounds the Ni-Cr-Fe weld material.Per Reference
[12], the dissolved oxygen (DO) calculation shows the overall hydrogen water chemistry (HWC) availability is 47%. This means the time ratio under normal water chemistry (NWC, or pre-HWC) is 53%.For the safe end location, the environmental fatigue factors for post-HWC and pre-HWC are 15.35 and 8.36 from Table 5 of Reference
[12]. These result in an EAF adjusted CUF of (15.35 x 47% +8.36 x 53%) x 0.0015 = 0.0175 for 60 years, which is acceptable (i.e., less than the allowable value of 1.0). The overall environmental multiplier is 11.6453.For the blend radius location, the environmental fatigue factors for post-HWC and pre-HWC are 2.45 and 12.43 from Table 5 of Reference
[12]. These result in an EAF adjusted CUF of (2.45 x 47% +12.43 x 53%) x 0.0 108 = 0.08358 for 60 years, which is acceptable,(i.e., less than the allowable value of 1.0). The overall environmental multiplier is 7.739.File No.: VY-16Q-306 Page 14 of 34 Revision:
0 F0306-0I RO Structural Integrity Associates, Inc..
 
==7.0 REFERENCES==
: 1. Structural Integrity Associates Calculation No. VY-16Q-305, Revision 0, "Recirculation Outlet* Nozzle Green's Functions." 2. Entergy Design Input Record (DIR), Rev. 1, EC No. 1773, Rev. 0, "Environmental Fatigue Analysis for Vermont Yankee Nuclear Power Station," 7/26/07, SI File No. VY-16Q-209.
: 3. CB&I, RPV Stress Report Section: S9 "Stress Analysis Recirculation Outlet Nozzle Vermont Yankee Reactor Vessel." 9-6201, SI document, VY-16Q-204.
: 4. CB&I, RPV Stress Report Section: T9 "Thermal Analysis Recirculation Outlet Nozzle Vermont Yankee Reactor Vessel." 9-6201, SI document, VY-16Q-204.
: 5. Structural Integrity Associates Calculation (Generic)
No. SW-SPVF-OIQ-301, Revision 0,"STRESS.EXE, P-V.EXE, and FATIGUE.EXE Software Verification." 6. VY Drawing, 5920-06623 Rev. 0, (Hitachi, Ltd. Drawing No IOR290-127, Revision 0), "Recirc.Outlet Safe End," SI File No. VY-16Q-204.
: 7. GE. Stress Report No. 23A4316, Revision 0, "Reactor Vessel Recirculation Outlet Safe End," SI File No. VY-16Q-204.
: 8. VY Drawing 5920-00238 Rev. 4, (Chicago Bridge & Iron Company, Contract No. 9-6201, Drawing No. 21, Revision 4), "36"x28" Nozzles Mk N lA/B," SI File No. VY-16QQ-204.
: 9. ASME Boiler and Pressure Vessel Code, Section II, Materials, Part D, Properties, 1998 Edition with 2000 Addenda.10. ANSYS, Release 8.1 (w/Service Pack 1), ANSYS, Inc., June 2004.11. Structural Integrity Ass6ciates Calculation No. VY-16Q-304, Revision 0, "Recirculation Outlet Nozzle Finite Element Model." 12. Structural Integrity Associates Calculation No. VY-16Q-303, Revision 0, "Environmental Fatigue Evaluation of R'actor Recirculation Inlet Nozzle and Vessel Shell/Bottom Head." 13. American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section III, Subsection NB, 1998 Edition, 2000 Addenda.14. NUREG-1801, Revision 1, "Generic Aging Lessons Learned (GALL) Report," U. S. Nuclear Regulatory Commission, September 2005..15. Kuo, A. Y., Tang, S. S., and Riccardella, P. C., "An On-Line Fatigue Monitoring System for Power Plants, Part I -Direct Calculation of Transient Peak Stress Through Transfer Matrices and Green's Functions," ASME PVP Conference, Chicago, 1986.* 16. EPRI Report No. TR-105759, "An Environmental Factor Approach to Account for Reactor Water Effects in Light Water Reactor Pressure Vessel and Piping Fatigue Evaluations," December 1995.17. American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section III, Subsection A, 1965 Edition with Winter 1966 Addenda.I File No.: VY-16Q-306 Page 15 of 34 Revision:
0 F0306-01 RO V Structural Integrity Associates, Inc.Table 1: Maximum Piping Stress Intensity Calculations I Blend Radius External Piping Loads Safe End External Piping Loads Parameters Fx= 20.00 kips Fy = 20.00 kips Fz = 30.00 kips Mx= 2004.00 in-kips my 3000.00 in-kips Mz= 2004.00 in-kips OD= 55.88 in ID= 37.368 in RN= 23.31 in L 42.77 in tN = 9.25 in (M,)2= 1148.54 in-kips (My)2 = 3855.46 in-kips Mxy = 4022.90. in-kips Fxy = 28.28 .kips Nz = 2.56 kips/in qN= -0.20 kips/in Primary Membrane Stress Intensity PMz 0.28 ksi E = -0.02 ksi SImax = 0.28 ksi Slmax 280.16 J psi Parameters Pa..00 kits.Fx= 20.00 kips Fy = 20.00 kips Fz = 30.00 kips Mx= 2004.00 in-kips my= 3000.00 in-kips Mz= 2004.00 in-kips OD= 28.38 in ID= 25.938 in RN 13.58 in L 4.25 in tN 1.22 in (M.), = 1919.00 in-kips (my), = 3085.00 in-kips My = 3633.15 in-kips Fxy = 28.28 .kips Nz = 6.62, kips/in qN= -1.07 kips/in Primary Membrane Stress Intensity PMz = 5.43 ksi t = -0.88 ksi Simax = 5.71 J ksi S!max = .5708.89 psi I I I I I I I I I I I I I I I I I Note: The locations for Cut I and Cut II were defined paths, respectively.
in Reference
[1] for safe end and blend radius File No.: VY-16Q-306 Revision:
0 Page 16 of 34 I I F0306-OIRO
!Structural Integrity Associates, Inc.I Table 2: Blend Radius Transients Transient Time Temp Time Stop Pressure Flow Rate Transient Time Temp Time Step Pressure Flow Rate Number s F s (pjsi (GePMl Number [9 (FJ (s) (I93)91 IGPM 1. Normal Startup with 0 100 0 14147.0 6. Reactor Overpressure 0 526 1010 .28294 Hesatup at 100lF/hr 16164 549 16164 1010 (50%). 1 Cycle 2 526 2 1375 (100%)'300 Cycles 22164 549 6000 1010 32 526 30 940 2. Turbine Roll and 0 549 1010 28294 1832 526 1800 940 Increase to Rated Power 1 542 1 1010 (100%). 2252 549 420 1010 300 Cycles 601 542 600 1010 2312 549 60 1010 602 526 1 1010 2313 542 1 1010 6602 526 6000 1010 '2913 542 600 1010 3. Loss of Foedwater 0 526 1010 28294 2914 526 1 1010 Heaters 1800 542 1800 1010 (100%)' 8914. 526 6000 1010 Turbine Trip 25% Power 2100 542 300 1010 7. SRV Slowdown 0 526 .1010 26294 10 Cycles 2460 526 360 .1010 1 Cycle. 600 375 600 170. (100n/o), 3060 526 600 1010 11580 70 10980 50 3960 542 900 1010 17580 70 6000 50 4260 542 300 1010 8. SCRAM Other 0 526 1010 28294 6060 526 1800 1010 228 Cycles 15 526 15 940 (100%).12060 526 6000 1010 1815 526 1800 940 4. Loss of Feedwater 0 526 1010 0 2235 549 420 1010*Pumps 3 526 3 1190 (0/o), 2295 549 60 1010 10 Cycles 13 526 10 1135 2296 542 1 1010 233 300 220 1135 2356 542 60 1010 2213 500 1980 1136 .2357 526 1 1010 2393 300 180 885 8357 526 6000 1010 6773 500 4380 1135 9. Improper Startup 0 526 1010 3395 7193 300. 420 675 14147 1 Cycle 1 268 0 1 1010 (12%)'7493 300 300 675 (50%) 27 268 0' 26 1010 11093 400 3600 240 28 526 1 1010 16457 549 5364 1010 6028 526 6000 1010 16517 549 60 1010 10. Shutdown 0 549 1010 14147 16518 542 1 1010 28294 300 Cycles 6264 375 6264 170 (50%)17118 542 600 1010 (100%) 6864 330 600 88 17119 526 1 1010 16224 70 9360 50 23119 526 6000 1010 1 22224 70 6000 50 6. Turbine Generator Trip 60 Cycles 0 10 15 30 1830 2250 2310 2311 2911 2912 8912 526 526 526 526 526 549 549 542 542 526 526 10 5 15 1800 420 60 1 600.*1 6000 1010 1135 1135 940 940 1010 1010 1010 1010 1010 1010 28294 11. Design Hydrostatic (100%)' Test 120 cvcles 100 50 1563 50 1981 (7%)12. Hydrostatic Test o- 100 -- 0 1981 1 Cycle 1100 " (79/6)1 1 50 Notes: 1.The instant temperature change is assumed as 1 second time step.2. The number of cycles is for 60 years (2].3. 268&deg;F is the blend radius temperature for this transient.
The safe end has a different temperature for Transient
: 9. [2)File No.: VY-16Q-306 Revision:
0 Page 17 of 34 F0306-O1RO V Structural Integrity A ssociates, Inc.I I I Table 3: Safe End Transients Transient Time Temp Time Step Pressure Flow Rate Transient Time Tomp Time Step Pressure Flow Rate Number W F (psjl) (GPM) Number fs) sFf jsJ jps) IGPMI 1. Normal Startup with 0 100 0 14147.0 6. Reactor Overpressure 0 526 1010 28294 Heatup at lO0F/hr 16164 549 16164 1010 (50%)- 1 Cycle 2 526 2 1375 (100%).300 Cycles 16864 549 700 1010 32 526 30 940 2. Turbine Roll and 0 549 1010 28294 1832 526 1800 940 Increase to Rated Power 1 542 1 1010 (100%)' 2252 549 420 1010 300 Cycles 601 542 600 1010 2312 549 60 1010 602 526 1 1010 2313 542 1 1010 1302 526 700 1010 2913 542 600 1010 3. Loss of Feedwater 0 526 1010 28294 2914 526 1 1010 Heaters 1800 542 1800 1010 (100%). 3614 526 700 1010 Turbine Trip 25% Power 2100 542 300 1010 7. SRV Blowdown 0 526 1010 28294 loCycles 2460 526 360 1010 1 Cycle 600 375 600 170 (100%).3060 526 600 1010 11580 70 10980 50 3960 542 900 1010 12280 70 700 50 4260 542 300 1010 8. SCRAM Other 0 526 1010 28294 6060 526 1800 1010 228 Cycles 15 526 15 940 (100%)'6760 526 700 1010 1815 526 1800 940 4. Loss of Feodwater 0 526 1010 0 2235 549 420 1010 Pumps 3 526 3 1190 (0%)' 2295 549 60 1010 10 Cycles 13 526 10 1135 2296 542 1 1010 233 300 220 1135 2356 542 60 1010 2213 500 1980 1135 2357 526 1 1010 2393 300 180 885 3057 526 700 1010 6773 500 4380 1135 9. Improper Startup 0 526 1010 3395 7193 300 420 675 14147 1 Cycle 1 130" 1 1010 (12%)'7493 300 300 675 (50%)' 27 130 26 1010 11093 400 3600 240 28 526 1 1010 16457 549 5364 1010 728 526 700 1010 16517 549 60 1010 10. Shutdown 0 549 1010 14147 16518 542 1 .1010 28294 300 Cycles 6264 375 6264 170 (50%)'17118 542 600 1010 (100%)' 6864 330 600 88 17119 526 1 1010 16224 70 9360 50 17819 526 700 1010 16924 70 700 50 I I I I U I I I 6. Turtine Generator Tnp 60 Cycles .0 10 15 30 1830 2250 2310 2311 2911 2912 3612 526 526 526 526 526 549 549 542 542 526 526 10 5 15 1800 420 60 1 600 1 700 1013 1135 1135 940 940 1010 1010 1010 1010 1010 1010 28294 (I00%)'11. Design Hydrostatic Test 120 Cycles-I 100 0 1100 50 1981 (7%)'12. Hydrostatic Test 100 -50 1,981 I Cycle 1563 (7,%)'1 1 50 1 Notes: 1. The instant temperature change is assumed as 1 second time step.2. The number of cycles is for 60 years [2].3. 130'F is the safe end temperature for this transient.
The blend radius has a different temperature for Transient
: 9. [2]Note: These transients are the same as in Table 2 with the exception of the 700 second steady state time increment that is used The transients in Table 2 are plotted using a 6000 second steady state increment.
The difference is due to the length of the Green's Function for the safe end which.is shorter compared to the blend Radius.I I I I I I File No.: VY-16Q-306 Revision:
0 Page 18 of 34 F0306-O1 RO I Structural Integrity Associates, Inc.Table 4: Blend Radius Stress Summary 1 2 1 3 14 15 7 81 9 1 10 11 12 13 Transient&i,,nier Time Total M+B Stress Stress temperature1pj) F Pressure fpsig)Total Pressure Stress 0 31613 31613 31613 31613 31613 31613 I 22164 90.0 1 94+301 4071 366&5691 2977 2955 1834 4425 170E 24811.54.2435 53, M+B Pressure Stress, 0 33976.4 33976.4 33976.4 33976.4 33976.4 33976.4 33976.4 33976.4 33976.4 33976.4 33976.4 33976.4 33976.4'Total Piping Stress M*8 Piping Stress (psi)Total Total Stress 47 Total.MWe Stress (880i 3481 521-1 101(101(101(101(101(1i 01 (TOM1(252.97541 252.9754 28113.0!34591.7'34972.7, 35953.8!35556.0U 37756.9E 34842.91 34824.9f 33708.8!36290.9i 33580.8!35836.9i 34830.91 34330.9(39964.9f 38243.4f 53982.31 30C Number Of Cycles (60 years)300 300 300 300 300 300 300 3974.40 10601 6070.801 3971 2551 11-U-1(1 (12060.00 2965 185'521 31613 4 1 01 2465 -7031 526.00 1010 31613 33976.'3 2465-70: 526.04 119(37247 40031.61 252.97541-252.9754 39075.6'&#xfd;-70" 1135 35525.51 38181.41 252.9754 -252.9754 37225.42 V 969(13996 542.0(17247 526.0(23111 3010.1(8912.00 6 0.00 2.00 32.00 2271.50 3022.00 8914.00 7 0.00 615.10 2 17580.00 8 0.00 15.G0 2254.50 2491.20 8357.00 9 0 0.52 28 2: 1 425 2971 2959 2959 2959 ill 4407 2959 2959 2959 2959 29631 29!59 4479 4407 22959 11 279" 2963&#xfd;18551 526.0(113!1131 88!101C 101C 101(101Z 101C 101C 1135 94C 101C 101C 101C 101C 35525.!38181.41 158.87741 15&.8774-232.6952 34123.80 35350.70 1c* 31613 3161Z 35525.E 29422 31613 31613 31613 31613 33976.4 143.3538-236.9137 129.2122 261.8518 252.9754 252.9754 252.9754 252.9754 252.9754 265.7352 252.9754 252.9754 252.9754 252.9754 252.9754 40606.851 36609.7!1c 38737.481
.40283.3E GC 48030.2f UC 184c 526.0(33976.41 252.9754 32633.98 33723.58 I 31989.74 34537.14 36272-981 36808.38 1 1 1849.52E 1010 31613 33976.4 1849 526 940 29422 31621.61 295 1851 54E 5_!2_5&#xfd;2_E 1010 1010 1010 1010 1010 1010 1010 1010 31613 31613 31613 31613 31613 31613 31613 31613 33976.4 265.7352 265.7352 33976.4 252.9754 252.9754 33976.41 252.9754 252.9754 31989.74 35657.98 34828.96 33923.86 33821.75 55601.05 33385.70 33923.86 34645.74 20654.77"11988.04 12180.21 12400 2058 8791 525.8 33976.41 252.86451 10 27671 2176 549 1010 31613 33976.4 265.7352T 6643 4158 445.775 441 13803.31 14835.241 208.469 34537.14 36463.38 36080.38 35190.26 34963.15 37405.45 34840.10 35108.26 36416.14 19201.71 9562.84 8345.13 1802.00 16.64 37020.64 1698.64 1698.64 52595.96.1698.64 1 1 1 228 228 228 228 228 1 1-1 1-1 300 300 300 300 11 12 100 100 100 0 0 50 15651 16821 16.643121 16.64312: NOTES: Column 1: Transient number identification.
Column 2: Time during transient where a maxima or minima stress intensity occurs from P-V.OUT output file.-Column 3: Maxima or minima total stress intensity from P-V.OUT output file.Column 4: Maxima or minima membraneplus bending stress intensity from P-V.OUT output file.Column 5: Temperature per total stress intensity.
Column 6: Pressure per Table 2.Column 7: Total pressure stress intensity from the quantity (Column 6 x 31300)/1000.
Column 8: Membrane plus bending pressure stress intensity from the quantity (Column 6 x 33640)/1000.
Column 9: Total external stress from calculation in Table 1, 280.16 psi*(Column 5-70'F)/(575&deg;F
-70'F).Column 10: Same as Column 9, but for M+B stress.Column 11: Sum of total stresses (Columns 3, 7, and 9).Column 12: Sum of membrane plus bending stresses (Columns 4, 8, and 10).Column 13: Number of cycles for the transient (60 years).I File No.: VY-16Q-306 Revision:
0 Page 19of34 F0306-01 RO V .Structural Integrity Associates, Inc.Table 5: Safe End Stress Summary 1 1 2 1 3 1 4 [ 6 1 G 7 8 9 10 11 12 13 Total M&#xf7;B Stress Stress Pressure ITtal M&#xf7;B Pressure Pressure Stress Stress Tot.l Piping Stress M&#xf7;B Piping Stress Total Total Stress Z .T"Total M&#xf7;B Stress (psi)Number of Cycles (GO years)Transient Time Temperature I I I I I I I I I I I I I I I I I I I NOTES: Column 1: Transient number identificationm Column 2: Time during transient where a maxima or minima stress intensity occurs from P-V.OUT output file.Column 3: Maxima or minima total stress intensity from P-V.OUT output file.Column 4: Maxima or minima membrane plus bending stress intensity from P-V.OUT output file.Column 5: Temperature per total stress intensity.
Column 6: Pressure per Table 3.Column 7: Total pressure stress intensity from the quantity (Column 6 x 1 1490)/1000.
Column 8: Membrane plus bending pressure stress intensity from the quantity (Column 6 x 11350)/1000.
Column 9: Total external stress from calculation in Table 1, 5708.89 psi*(Column 5-70&deg;F)/(575&deg;F
-70'F).Column 10: Same as Column 9, but for M+B stress.Column 11: Sum of total stresses (Columns 3, 7, and 9).Column 12: Sum of membrane plus bending stresses (Columns 4, 8, and 10).Column 13: Number of cycles for the transient (60 years).File No.: VY-16Q-306 Revision:
0 Page 20 of 34 F0306-0I RO V Structural Integrity Associates, Inc.Table 6: Fatigue I tesults for Blend Radius (60 Years)LOCATION = LOCATION NO. 2 -- BLEND RADIUS FATIGUE CURVE = 1 (1 = CARBON/LOW ALLOY, 2 =. STAINLESS STEEL)m =2.0 n= .2 Sm 26700. psi Ecurve : 3.000E+07 psi Eanalysis
= 2.670E+07 psi Kt = 1.00 MAX 55601.53822.51017.48939.46249.40607.39965.38737.38243.37757.37757.36291.36291.36273.36273.35954 35954.35954.35954.35954.35837.35658.35658.35556.35556.35279.34973.34973.34843.34843.34843.34843.34837.34834.34834.34831.34829.34829.34829.34829.34829.34825.34825.MIN RANGE MEM+BEND Ke Salt Napplied Nallowed 17.17 17.17.17.17.17..17.17.17)476.476.1582.1582.1582.1582.1 5 8 2 *1582 1844.1926.1926.1926.11988.11988.12180.12180.12180.20655.20655.25750.27368.28113.28113.28113.28113.28113.28113.29216.31990.31990.31990.31990.31990.55584.53806.51001.48922.46233.40590.39948.38721.38227.37740.37281.35815.34709.34691.34691.34372.34372.34372.34110.34028.33911.33732.23670.23568.23376.23099.22793.14318.1418.8.9093.7475.6730.6.724.6721.6721.6718.6716.5613.2839.2839.2839.2835.2835.37389. 1.0.00 48014. 1.000 44054. 1.000 52579. 1.000 48340. 1.000 36593. 1.000 39059. 1.000.40267. 1.000 37209. 1.000 37702. 1.000 37314. 1.000 36492. 1.000 35198. 1.000 35110.. 1.000 35110. 1.000 35021. 1.000 35021. 1.000 35021 1.000 34858. 1.000 34917. 1.000 34978. 1.000 34661. 1.000 26901. 1.000.27109. 1.000 28326. 1.000 27958. 1.000 27831. 1.000 16974. 1.000 16887. 1.000 17221. 1.000 5178. 1.000 3789. 1.000 3785. 1.000 3784. 1.000 3784. 1.000 3782. 1.000 3781. 1.000 1808. 1.000 1543. 1.000 1543. 1.000 1543. 1.000 1541. 1.000 1541. 1.000 31227. 1.000E+00 30228. 1.OOOE+01 28652. 1.OOOE+01 27484. 1.OOOE+00 25974. 1.O00E+00 22803. 1.OOOE+01 22443. 1.OOOE+01 21753. 6.OOOE+01 21476. 1.000E+01 21202. 7.OOOE+00 20945. 2.930E+02 20121. 7.OOOE+00 19500. 3.OOOE+00 19490. 6.OOOE+01 19490. 1.0.00E+00 19310. 5.600E+01 19310. 1.000E+00 19310. 1.000E+00 19163. 1.OOOE+00 19117. 2.410E+02 19051. 1.OOOE+01 18951. 4.900E+01 13298. 1.790E+02 13240. 1.210E+02 13133. 1.790E+02 12977. 1.000E+01 12805. 1.11OE+02 8044. 1.890E+02 7971. 1.110E+02 5108. 1.OOOE+00 4199. 1.OOOE+01 3781. 1.780E+02 3777. 1.000E+01 3776 6.000E+01 3776 1.0OOE+00 3774 1.000E+01 3773. 4.100E+01*3153 1.000E+01 1595. 6.000E+01 1595. 1.000E+00 1595. 1.160E+02 1593. 1.000E+01 1593. 6.OOOE+01 1.951E+04 2. 161E+04 2. 547E+04 2.894E+04 3.44 E+04 5. 217E+04 5. 647E+04 6.59-2E+04 7.025E+04 7.486E+04 7. 954E+04 9. 705E+04 1. 096E+05 1.098E+05 1.098E+05 1. 135E+05 1. 135E+05 1. 135E+05 1. 167E+05 1. 177E+05 i. 191E+05 1.2:14E+05
: 5. 728E+05 5.955E+05 6.4 11E+05 7.138E+05 8.050E+05 7. 421E+07 7.983E+07 1.OOOE+20 1.OOOE+20 1.OOOE+20 1. OOOE+20 1.000E+20 1. OOOE+20 1. 000E+20 1. OOOE+20 1. 000E+20 1. OOOE+20 1. 000E+20 1.000E+20 1. OOOE+20 1.000E+20 U.0001..0005.0004.0000.0000..0002..0002.0009.0001.000~1.0037.0001.00900.0005..0000.0005.00090.0000.0000.0020.0001.0004.0003.0002.0003.0000.0001.0000.0000..0000.0000.0000.0000.0000.0000.0000.0000~.0000.0000.0000.0000.0000.0000 File No.: V.Revision:
0 Y-16Q-306 Page 21 of 34 F0306-01 RO Structural Integrity Associates, Inc.34825.34825.34825.34825.34825.34825.34646.34646.34646.34646.34646.34646.34646.34646.34646.34646.34646.31990.31990.31990.32634.32634.32634.32634.33386.33581.33709.33822.33924.33924.34124.34331.34447.34592.2835.2835.2835.2191;2191.2191 2012 1260 1065 937 824 722.722.522.315.199.54.1541.1541.1541.2355.2355.2355.2695.1578.1120.1137.1455.1228.1310.1067.3398.-603.-130.1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1593.1593.1593.1231.1231.1231.1130.708.598.526.463.406.406.293.177.112.30.1. O00.E+00 1. OOOE+00 4 .OOOE+01 6. OOOE+01 1. OOOE+00 1.270E+02 1.010E+02 1. OOOE+00 1.OOOE+01 1. OOOE+01 1.OOOE+00 1.OOOE+00 1. OOOE+00 1.OOOE+01 1.OOOE+01 1.200E+02 3. 500E+01 1.OOE+20 1.OOOE+20 1.OOOE+20 1.OOOE+20 1.OOOE+20 1.00OE+20 1. OOOE+20 1.00OE+20 1.OOOE+20 1. OOOE+20 1. OOOE+20 1.000E+20 1.O00E+20 1.OOOE+20 1.OOOE+20 1.000E+20 1. OOOE+20.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0108 TOTAL USAGE FACTOR =I I I I I I I I I I I I I I I I I I File No.: VY-16Q-306 Revision:
0 Page 22 of 34 F0306-0I RO Structural Integrity Associates, Inc.II Table 7: Fatigue Results for Safe End (60 Years).LOCATIC FATIGUE C URV S Ecurv Eanalysi K N = LOCATION NO. 1 -- SAFE END TE = 2 (1 = CARBON/LOW ALLOY, 2 = STAINLESS STEEL)m = 1.7 n= .3 m 17000. psi e 2.830E+07 psi s= 2.700E+07 psi= 1.53 MAX MIN RANGE MEM+BEND Ke Salt Napplied Nallowed U 82580.31546.31546..25988.2.5730.18521.18298.17956.17956.17956.17952..17948.17948.17948.13174.12978.6956.5393.5393.5393.5393.5393.4762.4605.4605.4605..4518 4198.4130.3911.3486.3485.3419.3292.3292.3292.3292.3292.3292.3292.3292.3135.3086.-7469.-7469.-5010.-2934.-2934.-2934.-2934.-2*934.-2741.-1264.-1264.-1264.-157.-157.-157.-157.-157.-157.-133.136.136.136.136.136 339 909 909 909.909.909.909.909.909.909.909.909.914.914.914.1029.1376.1376.1376.90049.39015.36556.28922.28664.21455.21232.20890.20697.19220.19216.19212.18104.18104.13331.13135.7112.5550.5526.5258.5258.5258.4626.4469.4266.3697.3609.3290.3222.3003.2578.2577.2511.2384.2384.2384.2378.2378.2378.2264.1916.1759.1710.66991.33.281.28040.*24217.23354.9572.21370.9197.8846..7194.7191.7189.6096.6096.10909.13020.7125.-1219.-1293.-2126.-2126.-2126.3924.3153.3526.3332.3576.3673.3479..2870.2947.2942.3179.2472.2472.2472.2098.2098.2098.2247.1389.1452.1361.2.045 1..000 1..000 1.000.1.000 1.000 1.000 1.000 1.0.00 1..000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1. 000 1.000 1. 000 1. 000 1.000 1. 000 1. 000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 134573.29691.26947.21884.21509.13903.1 17063.13502.13304.12071.12068.12065.11181.11181.10016.10500.5706.2570.2537.2165.2165.2165.3514.3218.3215.2863.2885.2744.2655.2371.2170.2168.2199.1936.1936.1936.1829.1829.1829.1810.1390.1325.1274.1. OOOE+00 9. OOOE+00 1. OOOE+00 1. OOOE+01 1.OOOE+01.2.280E+02
: 1. OOOE+00 5. 100E+01 1. 000E+00 2.480E+02 1.OOOE+01 4.200E+01 1. 800E+0i 1.OOOE+00 1. OOOE+00 1.200E+02 1.00 OE+00 1. 590E+02 1. OOOE+00 6. OOOE+01 1. OOOE+00 7. 900E+01 1. OOOE+01 1. 390E+02 1.200E+02 4. 100E+01 1. OOOE+01 6. OOOE+01 1.OOOE+01 1. OOOE+01 1.OOOE+00 1. OOOE+00 1. OOOE+01 6. OOOE+01 1. OOOE+00 9. 600E+01 1. 200E+02 1. OOOE+00 1.OOOE+00 1. OOOE+00 9. OOOE+00 1.OOOE+01 2. 280E+02 6. 765E+02 6. 857E+05 1. 160E+06 2. 383E+06 2. 566E+06 9.-710E+08
: 7. 876E+06 1. OOOE+20 1.OOOE+20 1.000E+20 1.OOOE+20 1.000E+20 1.OOOE+20 1.000E+20 1. OOOE+20 1.OOOE+20 1 .OOOE+20 1.OOOE+20 1.OOOE+20 1.000E+20 1.000E+20 1. OOOE+2&#xfd;0 1. OOOE+20 1.000E+20 1.OOOE+20 1. 000E+20 1.OOOE+20 1.OOOE+20 1. OOOE+20 1. 00.OE+20 1.OOOE+20 1.OOOE+20 1.OOOE+20 1. OOOE+20 1. OOOE+20 1.OOOE+20 1. OOOE+20 1. OOOE+20 1. OOOE+20 1.OOOE+20 1. OOOE+20 1. OOOE+20 1.000E+20.0015.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000 0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000..0000.000 0.0000.0000.0000.0000 File No.: VY-16Q-306 Revision:
0 Page 23 of 34 F0306-O I RO Structural Integrity Associates, Inc.2809.2783.2783.2783.2783.2783.2783.2780.2780.2780.2780.2780.2780.2763.2762.2762.2762.2762.2762.2762.2496.2496.2491.2487.2487.1376.1376.1732.1793.1958.1958.1958.1958.2104.2352.-2352.2352.2352.2352.2352.2352.2441.2441.2441.2441.2441.2445.2445.2445.2487.1433.1407.1051.990.825.825.825.822.676.428.428.428.428.411.410.410.321.321.321.321.55.51.46.42.0.1091.1.187.860.208.811.811.811.808.576.416.416.416.416.403.403.403.443.443.443.443.177.181.178.175.0..1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1054.1067.790.576.658.658.658.655.514.340.340.340.340.327.327.327.291.291.291.291.78.77.74.71.0.1. OOOE+01 4. 300E+01 1.000E+01 1. 000E+01 6.OOOE+01 1. OOOE+00 1. 040E+02 1.240E+02 1.000E+01 1. 660E+02 1.000E+01 6.000E+01 1.000E+00 1.000E+01 1. OOOE+01 4. 300E+01 1. 700E+01 1. 000E+00 1. 000E+00 2. 28E+02 5, 300E+01 2. 470E+02 1.000E+01 4. 300E+01 1.700E+01 1.000E+20 1.000E+20 1.000E+20 1.000E+20 1.000E+20 1.000E+20 1.000E+20 1.000E+20 1.000E+20 1.000E+20 1.000E+20 1.000E+20 1. OOOE+20 1.000E+20 1.000E+20 1.000E+20 1.000E+20 1 .000E+20 1.000E+20 1.000E+20 1.000E+20 1.000E+20 1.000E+20 1.000E+20 1.000E+20.0000.0000.0000.0000.0000.0000.0000.0000.0000 0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0015 TOTAL USAGE FACTOR I I I I I I I I I I I I I I I I I I File No.: VY-16Q-306 Revision:
0 Page 24 of 34 F0306-01 RO Structural Integrity Associates, Inc.Table 8: Material Properties (For Transient 9)(1)SA-533 Gr B SA-508 Cl 2 SA-240 SA-182 F316 Material @400 OF @400 'F Type 304 @300 OF (Mn-ll2Mo-(3/4Ni-1/2Mo-
@400 'F (16Cr-12Ni-l12Ni) *l3Cr-V) (18Cr-8Ni) 2Mo)Modulus of Elasticity, e-6 27.4 26.1 265 27.0 psi.Coefficient of Thermal Expansion, e-6, in/in/&deg;F 8.0 7.7 10.2 9.8 Thermal Conductivity, 23.1 23.1 10.4 9.3 Btu/hr-ft-&deg;F Thermal Diffusivity, ft 2/hr 0.378 0.378 0.165 0.150 Specific Heat, Btu/Ib-&deg;F(2) 0.125 0.125 0.129 0.127 Density, lb/in 3  0.283 0.283 0.283 0.283 Poisson's Ratio 0.3 0.3 0.3 0.3 Notes: () Material Properties are evaluated at 400 0 F from the 1998 ASME Code, Section II, Part D, with 2000 Addenda, except for density and Poisson's ratio, which are assumed typical values. This is consistent with information provided in the Design Input Record (page 13 of VY EC No. 1773, SI File No. VY- 16Q-209).
The use of a later code edition than that used for the original design code is acceptable since later editions typically reflect more accurate material properties than was published in prior Code editions.
The safe end material properties were used for 300'F, the Code table values closest to the average temperature for the safe end for transient 9.(2) Calculated as [k/(pd)]/12 3.File No.: VY-16Q-306 Revision:
0 Page 25 of 34 F0306-01 RO Structural Integrity Associates, Inc.F,, Figure 1: External Forces and Moments on the Recirculation Outlet Nozzle File No.: VY-16Q-306 Revision:
0 Page 26 of 34 F0306-OIRO V Structural Integrity Associates, Inc.AREAS K M.AT Nti Region 3 Region 2 IMN APR 19 2007 13:35:14 Region 4 I* / Region I Transition Regions x Recirc Outlet Nozzle Finite Element Model Figure 2: Nozzle and Vessel Wall Thermal and Heat Transfer Boundaries for Transient 9 File No.: VY-16Q-306 Revision:
0 Page 27 of 34 F0306-O I RO Structural Integrity Associates, Inc.('F) --Pressure (psig) ]I-Temp (-F) --Pressure (psig)j 600 500 400 200 1001 1100 1050 1000 950 900 0)0., 0 3000 6000 9000 12000 15000 Time (seconds)Figure 3: Transient 1 -Normal Startup at 100&deg;F/hr[-Temp f) --Pressure I 555 550 545 540 E 535 1120 1040 960 880 800 720 640-560-480 400 320 240 160-80 IL 530 525 520 0 300 350 400 450 500 0 50 100 150 200 250 Time (seconds)Figure 4: Transient 2 -Turbine Roll and Increase to Rated Power File No.: VY-16Q-306 Revision:
0 Page .28 of 34 F0306-OI RO Structural Integrity Associates, Inc.I I- Temp (F) -,-- Pressure (psig)600 1 550 500 -450 400-3 5 0 300 4. 250 200 150 100 50 0 1080 1040 1000 960.920-880-840.800-760-720.680.640.600 -560 -520 480 440 a-400 360 320.280.240 200 160 120 80 40 0 2000 4000 6000 8000 10000 Time (seconds)Figure 5: Transient 3 -Loss of Feedwater Heaters and Turbine Trip 25% Power 600 500 400 300 200 100 0[- Temp (-F) --Pressure (psig)//1280 1240 1200 1160 1120 1080 1040 1000 960 920 880 80 tOO 760 7 320 680 640 600 560 520-480 f 440 400 360 320 280 240-160]-80 S40 0 a, a.a-//\\ ,/2 0 2000 4000 6000 6000 10000 12000 Time (seconds)14000 16000 18000 20000 22000 Figure,6:
Transient 4 -Loss of Feedwater Pumps File No.: VY-16Q-306 Revision:
0 Page 29 of 34 F0306-O1 RO Structural Integrity Associates, Inc.I- Temp (F) --Pressure (psig) I 555 550 545 540 E 535 I-I ---530 525 520 0 500 1000 1500 2000 2500 Time (seconds)Figure 7: Transient 5 -Turbine Generator Trip-Temp (f) --Pressure (psig)600 500 .. --" ---400 300 0 500 1000 1500 2000 2500 30 Time (seconds)Figure 8: Transient 6 -Reactor Overpressure 1200 1150 1100 1050 1000 950 900 850 800 750 700 " 650--600 E-550 =-500* C-450-400-350 300 250 200 150 100 50 0* 3000 1500 I1400 S1300 1200 1100 1000 8 0 0 700 600 5o00 400 300-200 100 0 00 File No.: VY-16Q-306 Revision:
0 Page 30 of 34 F0306-01 RO
.V Structural Integrity Associates, Inc.I 600-Temp (&deg;F) --Pressure (psig)500 E I--1100 4- 1000 9O 0 800 700 600 500 400 300 200 100 a-I I I I 100-12000 2000 4000 6000 Time (seconds)8000 10000 Figure 9: Transient 7 -SRV Blowdown I--Temp (*F) --Pressure (psig) I 600 500 400 300 E 200 100 0l1100 1000 900 800-700-600 Soo.400 300 200 100 0 0 1000 2000 3000 4000 5000 Time (seconds)Figure 10: Transient 8 -SCRAM Other File No.: VY-16Q-306 Revision:
0 Page 31 of 34 F0306-OlRO Structural Integrity Associates, Inc.j-Temp (F) --Pressure (psig)]600- 1100 I 1000 9002 I 400 700 300 Blend Radius .I 500 2004 Safe End 300 3 100 .200 100 0 "0 0 10 20 30 40 50 60 70 80 90 100 Time (seconds)Figure 11:, Transient 9 -Improper Startup[-Temp (F) -Pressure (psig)600 1100 1000 I.500 900 800 400 700 U -..* 600 ooo6 I-300 -* 400I 200 I 300 100 .200 100 0 100 0 2000 4000 6000 8000 10000 12000 14000 16000 Time (seconds)I Figure 12: Transient 10 -Shutdown File No.: VY-16Q-306 Page 32 of 34 m Revision:
0 F0306-OI RO Structural Integrity Associates, Inc.IL 0)0)~0 Q (I)0~C,)U)4-C,)400 Time (sec)92825rO Note: A typical set of two Green's Functions is shown, each for a different set of heat transfer coefficients (representing different flow rate conditions).
Figure 13: Typical Green's Functions for Thermal Transient Stress File No.: VY-16Q-306 Revision:
0 Page 33 of 34 F0306-01 RO V Structural Integrity Associates, Inc.11250.Tbm me: I.,tS" o-to Lm 0.::iO" ..ZOO] 64W 00 100M Iwo 1ZW140 0 0 W Z1UG.Figure 14: Typical Stress Response Using Green's Functions File No.: VY-16Q-306 Revision:
0 Page 34 of 3 4 F0306-01 RO I Structural Integrity Associates, Inc.APPENDIX A
 
==SUMMARY==
OF OUTPUT FILES VY RON T T9.INP Input File for Transient 9 Thermal Analysis In Computer files VY RON S T9.INP Input File for Transient 9 Stress Analysis In Computer files LFSE.OUT Stress Output at Safe End In Computer files LFBR.OUT Stress Output at Blend Radius In Computer files LFSE INSIDE.RED Stress Extracted at Safe End In Computer files LFBR INSIDE.RED Stress Extracted at Blend Radius In Computer files LFSE T.XLS Stress Results with Total Stress at Safe End In Computer files LFSEM+B.XLS Stress Results with Membrane plus Bending Stress at Safe In Computer files End LFBR T.XLS Stress Results with Total Stress at Blend Radius In Computer files LFBRM+B.XLS Stress Results with Membrane plus Bending Stress at Blend In Computer files Radius T9SE.OUT Transient 9 Safe End stress output In Computer files T9BR.OUT Transient 9 Blend Radius stress output In Computer files T9SE Inside.RED Transient 9 Stress Extracted at Safe End In Computer files T9BR Inside.RED Transient 9 Stress Extracted at Blend Radius In" Computer files T9BRM+B.xls Transient 9 Stress Results with Membrane plus Bending In Computer files Stress at Blend Radius T9BR T.xls Transient 9 Stress Results with Total Stress at Blend Radius In Computer files T9SE_M+B.xls Transient 9 Stress Results with Membrane plus Bending In Computer files Stress at Safe End T9SE T.xls Transient 9 Stress Results with Total Stress at Safe End In Computer files FATIGUE.OUT Output file from FATIGUE.EXE In Computer files FATIGUE.inp Input file for FATIGUE.EXE In Computer files TRANSNT XX.inp Input files for STRESS.EXE In Computer files P-V XX.OUT Output file fromP-V.EXE In Computer files File. No.: VY-16Q-306 Revision:
0 Page Al of Al F0306-OI RO Structural Integrity Associates, Inc. File No.: VY-16Q-307 CALCULATION PACKAGE Project No.: VY-16Q NEC-.IH 10 PROJECT NAME: Environmental Fatigue Analysis of VYNPS CONTRACT NO.: 10150394 CLIENT: PLANT: Entergy Nuclear Operations, Inc. Vermont Yankee Nuclear Power Station CALCULATION TITLE: Recirculation Class 1 PipingFatigue and EAF Analysis Document Affected Project Manager Preparer(s)
&Reviint PAgesd Revision Description Approval Checker(s)
Signature
& Date Signatures
& Date 0 1-16 Initial Issue A I A51 131-135T.
J. Herrmann Computer Files 07/27/2007 R.V. Perry 07/27/20017 K.R. Evon 07/27/2007 P. Hirschberg 07/27/2007 C.J. Fourcade 07/27/2007 Page 1 of 16 F0306-01 RO V Structural Integrity Associates, Inc.Table of Contents 1.0 O B JE C T IV E ...............................
.................................................................................
... 3 2.0 M ET H O D O LO G Y ...................................................
...................................................................
3 2.1 B ackground
............................................................................................
...............................
3 2.2 Design Transients and Fatigue Analysis ...................................
4 3.0 ASSUM PTIONS/DESIGN INPUTS ...........................................................................................
4 4.0 ANALYSIS ..........................................................
12 5.0 RESU LTS O F AN A LY SIS ...................................................................................................
14
 
==6.0 REFERENCES==
 
.......................................................
15 APPENDIX A PIPESTRESS INPUT FILES ..............................................................................
Al APPENDIX B PIPESTRESS OUTPUT ......................................................................................
BI List of Tables Table 1: Material Properties
[1] [3].........................
.......................
6 Table 2: Recirculation and RHR Piping Segment Numbers ...............................................
...............
7 Table 3: VY Thermal Transients
.....................................................................
9 Table 4: Recirc/RHR Piping Size Information
[3] ...................................
12 Table 5: Therm al Cycle Load Sets ................................................................................................
13 List of Figures Figure 1. Recirculation and RHR Piping Diagram .......................................................................
8 I I I I I I 1 I I I I I I I I File No.: VY-16Q-307 Revision:
0 Page 2 of 16 F0306-01RO V Structuralintegrity Associates, Inc.1.0 OBJECTIVE The purpose of this calculation is to perform an ASME Section 111, NB-3600 fatigue usage calculation (including environmental fatigue) for the Loop A NUREG/CR-6260 locations in the Reactor Recirculation (RR) and Residual Heat Removal (RHR) piping.The fatigue calculation performed herein is not a certified ASME Code NB-3600 stress and fatigue analysis.
Rather, it is an evaluation for the purposes of establishing fatigue usage to accommodate fatigue monitoring of the subject B3 1.1 piping. Although the PIPESTRESS program implements all ASME Code NB-3600 equations, only the fatigue usage results are utilized.
All stress limit checks, although calculated by the program, are ignored since satisfactory stress limit checks were performed as a part of the already existing governing B3 1.1 stress analyses for all piping systems.2.0 METHODOLOGY
 
===2.1 Background===
Since ASME Section III Design Specifications do not exist for the subject piping systems, SI developed transient definitions and expected number of cycles for the subject piping in a previous evaluation.
These definitions are based on SI's experience in piping analysis at other BWR'plants, as well as review of VY-specific operating procedures, and are appropriate for BWR-4 plants and tailored specifically to VY. Those transient definitions will reflect current plant operating conditions as shown in references
[7 through 10]. Using the PIPESTRESS computer code [5], heat transfer analysis will be performed for the transients defined to establish the necessary parameters for use in an NB-3600 fatigue evaluation.
This will result in a detailed usage factor calculation for the RR and RHR NUREG/CR-6260 locations from which to base the environmental fatigue evaluation.
File No.: VY-16Q-307 Revision:
0 Page 3 of 16 F0306-O1RO Structural Integrity Associates, Inc. 1 I 2.2 Design Transients and Fatigue Analysis The temperature time histories are obtained from the reactor thermal cycle diagrams [7] [8]. These diagrams also provide the changes in flow rate and system pressures.
These temperatures and 3 pressures were updated to account for EPU [9].The computer program PIPESTRESS
[5] was used, which is a full function, verified piping analysis package. The ASME Code methodology for fatigue analysis of Class I piping systems requires determination of the through-wall thermal gradient terms AT, (linear gradient), AT 2 (nonlinear gradient), and Ta-Tb (transition gradient) for each transient containing a non-trivial ramp rate.PIPESTRESS calculates these terms for each thermal transient.
Load sets were then developed for the critical time points of the transients, that include loads due to pressure, thermal expansion, OBE seismic, and thermal gradient stresses.
PIPESTRESS was then used to determine the range of primary plus secondary plus peak stresses for each load set pair, and calculate the cumulative fatigue.usage for the design numbers of cycles.3.0 ASSUMPTIONS/DESIGN INPUTS The Code of construction for VY is ANSI B31.1, 1967 Edition [3, 10]&#xfd; In order to take advantage of improvements in the ASME Code that'result in a lower calculated fatigue usage, this evaluation is done to the ASME Boiler and Pressure Vessel Code, Section 1II, 1998 Edition with 2000 Addenda I[1]. The 1998 Edition of Section III (with 2000 Addenda) has been accepted by the US NRC for use in design analyses.
Although there are a few restrictions on the application of this Edition, they involve the use of optional increased allowables that are not being used in this calculation.
The piping analysis input information was based on references provided by VY. The ADLPIPE input file [6] was the source for the piping geometry, and pipe support locations and types. Additional I piping support information was obtained from plant drawings [ 15]. The pipe size, schedule, insulation, and weight per foot, were obtained from [3] (page 10). The flow element located between the pump and RHR return tee was not included in the model. The weight of the element would have no significant impact on the analysis and the element is remote from any areas of severe thermal transients such as the RHR return tee. The weight of the contents was automatically added by the PIPESTRESS program. The design temperature and piping materialwas obtained from reference
[3](page 9). Table 1 summarizes the material properties used in this analysis.!U Reference
[6] contains an SSE response spectrum.
This spectrum was conservatively used as the OBE spectrum in this analysis.
Code case N-411 damping is utilized and directional loading is combined by. SRSS [3] (page 20). 3 l File No.: VY-16Q-307 Page 4 of16 i Revision:
0 F0306-O1RO I
HI Structural Integrity Associates, Inc.I Per Reference
[9] (Item 14, section 3.2.1), the normal recirculation flow per loop, post EPU, is I 12.3Mlbm/hr (at 526'F). Flow is converted to gpm as follows: Q :12,300,000 Ibm t (7.48gal( hr 32,36gpm hr &#xfd;47.45-bm) f 3 F 60mi J U Where flow is stopped, a flow rate that gives an equivalent natural convection heat transfer coefficient is calculated.
The applicable transients to consider for the RR and RHR Systems are shown in the thermal cycle diagrams [7] and [8]. Level C transients are not required to be included in the fatigue analysis per NB-3224.4.
Reference
[3] describes which transientsare considered level C. Note that a transient Ifor RHR initiation is not accounted for onthese diagrams.
In order toaccount for this transient, RHR temperature data from RFO 25 [11] was used to conservatively determine an appropriate temperature
* change while reference
[12] was used to determine flow rates and pressures.
Table 2 describes each fl section and Figure 1 shows the piping model with node numbers. Table 3 contains a list of applicable transients. (Note that the transient RHR initiation contains a section 3B. This section accounts for the portion of the recirculation pump discharge piping that is affected by this transient.)
OBE cycles are not listed in Table 3 but are included as Load Set 26 for +OBE and Load Set 27 for -OBE. A review of shutdown cooling mode operation since the recirculation piping was replaced in 1986 was performed by the station and the number of cycles per loop was conservatively estimated to be 150 through year 60 [10]. Based on this, the cycle counts for the Recirculation piping were reduced by a factor of 150/300 (50%) for all transients with the exception of transients that have fewer than 10 Stransient cycles.To ensure this cycle reduction adequately considered the potential impact on carbon steel RHR piping, the full number of transient cycles [7] was initially applied to the PIPESTRESS model and the highest CUF for the carbon steel portion of the RHR piping, which has not been replaced, was lower than the value obtained for the recirculation piping with reduced cycles. The Recirculation and RHR line sizes are specified in reference
[3] and are shown in Table 4.I I File No.: VY-16Q-307
.Page 5 of 16 Revision:
0 F0306-O1RO V Structural Integrity Associates, Inc. -Table 1: Material Properties
[11 [3]ASTM A-106 Grade B (C-Si)Coefficient of Linear Mean Coefficient Design Young's Thermal Thermal Thermal of Thermal Stress Yield Temperature Modulus Conductivity Diffusivity Expansion.
Expansion (10-6 Intensity Strength (0 F) (xl0 6 psi) (Btu/hr-fl-&deg;F) (ft 2/hr) (in/100 ft) /in/in./F) (ksi) (ksi)70 29.5 27.5 0.529 0.00 6.40 20.0 35.0 100 29.3 27.6 0.512 0.20 20.0 35.0 200 28.8 27.6 .0.486 1.00 20.0 32.1 300 28.3 27.2 0.453 1.90 20.0 31.0 400 27.7 26.7 .0.428 2.80 20.0 29.9 500 27.3 25.9 0.398 3.70 18.9 28.5 600 26.7 25.0 0.374 4.70 17.3 26.8 ASME SA-376 TP 316 (l6Cr-12Ni-2Mo)
Coefficient of Linear Mean Coefficient Design Young's Thermal Thermal Thermal of Thermal Stress Yield Temperature Modulus Conductivity Diffusivity Expansion Expansion (10-6 Intensity Strength (0 F) (x10 6 psi) (Btu/hr-fl-&deg;F) (ft 2/hr) .(in/] 00 ft) /in/in/-F) (ksi) (ksi)70 28.3 8.2 0.139 0.00 8.50 20.0 30.0 100 28.1 8.3
* 0.140 0.30 20.0 30.0 200 27.6 .8.8 0.145 1.40 20.0 .25.9 300 27.0 .9.3 0.150 2.50 20.0 23.4.400. 26.5 9.8 0.155 3.70 19.3 21.4 500 25.8 10.2 0.160 5.00 18.0 20.0 600 25.3 10.7 0.165 6.30 17.0 18.9 ASME SA-403 WP 316 (16Cr-12Ni-2Mo)
Coefficient of Lineai Mean Coefficient Design Young's Thermal Thermal Thermal of Thermal Stress Yield Temperature Modulus Conductivity Diffusivity Expansion Expansion (10-6 Intensity Strength (TF) (x 10 6 psi) (Btulhr-fl-0 F) (ft 2/hr) (inilO0 ft) /iniini 0 F) (ksi) (ksi)70 28.3 8.2 0139 0.00 8.50 20.0 30.0 100 .28.1 8.3 0.140 0.30 20.0 30.0 200 *27.6 8.8 0.145 1.40 20.0 25.9 300 27 9.3. 0.150 2.50 20.0 23.4 400 26.5 9.8 0.155 3.70 18.7 21.4 500 25.8 10.2 0.160 5.00 17.5 20.0 600 25.3 10.7 0.165 6.30 16.4 18.9 I I I I I I I I I I I I I The material properties applied in the analyses are taken from ASME Section II Part D 1998 Edition with 2000 Addenda. This is consistent with information provided in the Design Input Record (page 13 of VY EC No. 1773, SI File No. VY- 16Q-209).
The use of a later code edition than that used for the original design code is acceptable since later editions typically reflect more accurate material properties than was published in prior Code editions.I I I I File No.: VY-16Q-307 Revision:
0 Page 6 of 16 F0306-O1RO I
U Structural Integrity Associates, Inc.Table 2: Recirculation and RHR Piping Segment Numbers Piping Node Points Region Start End Description 1 3 500 Outlet 2 500 50 Pump suction 3 150 210 Pump discharge 3B* 188 210 Down Stream of RHR Return 210 340 Inlet Header 210 320 Inlet Header 5A 340 365 Riser 5B 340 345 Riser 5C 210 334 Riser 5D 320 325 Riser 5E 320 315 Riser 6A 365 366 Inlet Nozzle 6B 345 346 Inlet Nozzle 6C 334 336 Inlet Nozzle 6D 325 326. Inlet Nozzle 6E 315 316 Inlet Nozzle 7A 500 550 RHR Supply; tee to valve 7B 550 565 RHR Supply; valve to penetration 8 152 176 4" Bypass 9A 600 660 , RHR Return; valve to tee 9B 660 675 RHR Return, penetration to valve*Only applicable for RHR initiation File No.: VY-16Q-307 Revision:
0 Page 7 of 16 F0306-0I RO V
Integrity Associates, inc.I I.04'.Figure 1. Recirculation and RHR Piping Diagram I File No.: VY-16Q-307 Revision:
0 I I I I I I V Structural Integrity Associates, Inc.Table 3: VY Thermal Transients*
1 1 __________
TlseooTh Condidioan 141171 (8j [z] Peo No.TC.n7enl Dewdptk"I Pipiog Opo. 1 T- T_ I Ti-o R F"ow j ..... I o"l &deg;'o l I C.w J I Regk,7n FTemp.('8)] (iF0 [ () I (s.) I ('F ) w(o, (ig j (psig) CyCl.o1181 I 100 70 100 1800 60 2.262 0 j.10 2 00 70 100 1800 60 2,262 0 1.100 3 100 70 106 I800 60 2,262 0 1G100 4 5 00 70 00 800 60 905 0 1.100 5 Z00 70 100 1800 60 452 0 1,100 Desigo Hlydeosess (Leak Test) + 6 00 70 100 1800 60 452 0 1.100 60 7A 100 70 100 1800 60 0 0 1.100 78 0OO 70 100 :800 60 0 0 120 8 100 70 100 1800 60 0 0 1.100 9A 100 70 100. 1800 60 0 0 1.100 9B 100 70 I 00 1800. 60 0 -0 1.100 I )00 100 100 1000 0 2,262 1.100 s0 2 100 100 100 1800 0 -2.262 1,100 50 3 10t 100 100 1800 0 2,262 1.100 50 4 100 100 100 1000 0 .905 .1t00 50 5 00 :00 1 402 I,000 50 2 Design Hy&. 5 00 0s90 2 (Lek T..)'- 6 100 100 100 1800 0 452 1.100 50 60 7A 1000 0 0 100 1800 0 0 1,100 50 78 100 100 100 1800 0 0 120 50 8 0 IO0 100 0000 0 0 100 0 0 9A 100 100 100 1800 0 0 1,100 5o 9B 1 .100 I0 10 1800 0 0 1.100 50 I 549 00 4 16164 10 1 00 s1010 2 549 100 549 16164 100 16,158 50 1,010 3 040 100 040 16164 100 16,158 50 1,035 4 549 100 549 16164 :00 6.463 500 1.035 5 549 100 549 16164 100 3.232 50 1.035 3 Slosup 6 549 100 549 .16164 100 3.232 50 1,035 250 7A 54B 100 549 16164 100 300 50 1,010 78 150 100 Bo 16 64 0 .0 50 120 8 549 100 549 16164 1oo 168 50 1.035 9A 549 100 549 16164 t00 0 50 .1.035 9B 1I2 100 150 16164 II 0 1 50 1,035 I 542 549 942 0 STEP 32,316 12010 1,010 2 542 549 542 8 STEp 32.516 1.010 I,00 3 542 549 542 0 STEP 32,316 1,035 1.035 4 542 549 542 0 STEP 12,926 1.035 1.035 T4rcine Ro& 5 542 549 042 0 STEP 6,463 .1.035 1.035 tnceose 10 Ra6ed 4 +SCRAM 6 542 049 542 0 STEP 6.463 1.055 1.035 290-7A 042 549 042 0 STEP 364 .1,010 1,010 7 0 50 ISO 0 STEP 0 120 120 8 542, 549 542 0 STEP 335 1.035 1,035 9A 542 049 542 0 STEP 520 1.035 1,035 913 150 150 I IS0 0 STEP o 1,035 1.035 I 526 542 526 0 STEP 32,316 1,010 1,010 2 526 042 526 0 STEP 32,316 I100 1,010 3 526 542 526 0 STEP 52,316 1.035 2035 4 026 542 526 0 STEP 12,926 1,035 1,035 T1-l- Ro& t' 5 526 542 526 0 STEP 6.463 1,035 1.035 5 onrease so lRoted Po5 +SCA 6 526 542 526 0 STEP 6,463 1.035 1.005
* 290 Pow-- SCRAM 5 1 4 "6 0 SE .6 ,3-2 7A 526 542 .526 0 STEP 358 1,010 1,010 740 I50 I50 1 0 STEP
* 0 120 120 8 026 542 526 6 0 STEP 333 1.035 1,035 9A 526 542 526 0 STEP 5I 1030 1,035 9B IS0 15O 150 0 STEP 0 1,035 1,035 I 542 526 542 900 64 32.316 1,010 1,010 2 542 526 542 900 64 32.316 1,010 1,0 3 542 526 542 900 64 32,316 1,035 1,035 4 302 526 542 900 64 12.926 1,035 1,O35 Loss of 5 542 526 542 900 64 6,463 1.035 1,035 6 Peedoolere Iaree, 6 542 526 542 900 64 .6,463 1.035 1,035 5x'2 TurbiseTrip(4-)
7A 542 526 042 900 64 358 1,010 .1,010 76 ISO I50 10 900 0 0 120 120 8 542 526 542 900 64 330 1.035 1,035 9A 542 526 542 900 64 5I 1.035 1,033 9B 150 150 150 900 60 0 1,035 1,005 I 526 542 326 360 160 32,316 1.010 12010 2 526 542 026 360 160 32,316 --,015 1.0LO 3 526 542 526 360 160 32,316 10035 1,035 4 526 042 526 360 160 12.26 1,035 1,035 Less of S 026 542 526 360 160 6.463 1,035 1.035 7 Feedwate leisee 6 '26 542 526 360 160 6,463 1.030 1.035 5 2 Tobine Tip (-) 7A 526 542 526 360 160 356 1,010 1,010 7B I50 I50 I50 360 0 6 120 120 4 526 542 526 360 160 335 1,035 ,035 7A 526 542 526 360 160 5164 1,035 1,035 971 150 520 00 360 0 0 1,005 1,030 File No.: VY-16Q-307 Revision:
0 Page 9 of 16 F0306-O1RO VStructural Integrity Associates, Inc.I I Table 3: VY Thermal Transients (continued)
Thermal Conditi-os
[41 [71 189 [10 [1 N:.Tnss.s, D-Hf..nl n "Pi..g j Op".r. T. TTn. Rl m 3 IniMul T r.I f CR.go. J .F3 (OF) (se.) (&#xfd;Fsr) p (gpm) (p.isg (psig) Cycle 1101 1 516 526 516 0 STEP 32,316 10010 1.010 2 516 526 516 0 STEP 32,316 1,01O 1,010 3 516 526 516 0 STEP 32,316 .035 1,035 4 .516 526 516 0 STEP 12,926 1-035 ".035 Loss of 5 516 526 536 0 STEP 6.463 .035 1.035 8 P ariala, Hmaa t 6 $16 526 536 0 STEP 6,463' 1,035 1,035 35 P40431 PW Ii-,SE 001e Bypass(- 7A 516 326 516 0 STEP 351 1.010 1,030 7B 1So 3 50 10 So 0 STEP 0 IN 120 8 516 526 516 0 STEP 335 1.035 1.035 9A 516 526 516 0 STEP 502 1.035 * ,035 9B ISO 150 150 0 STEP 0 1.035 1,035 1 I 526 516 526 0 STEP 32,316 1,010 I.m10 2 526 516 526 0 STEP 32,316 1.010 1,010 3 526 516 526 0 STEP 32,336 3.035 1.035 4 526 516 526 0 STEP 12.926 1.035 1,035 Loss of 5 526 516 526 0 STEP 6.463 1,035 1.035 9 Fdw Heaer 6 526 5"16 526 0 STEP 6.463 1.035 1.035 35 Partial FW H-.t Bypass ( 7 7A 526 536 526 0 STEP 351 1,010 1.010 7B 150 150 150 0 STEP 0 120 120 8 526 516 526 0 STEP 335 1,035 1.035 9A 526 516 526 0 STEP 502 1035 1.035 9B 150 150 150 0 STEP 0 1,035 1,035 I 300 526 $00 220 3698 600 ,:190 I,135 2 300 526 300 220 3698 600 1,190 1.135 3 300 526 30$ 220 3698 600 1.213 1.160 Loss of 4 300 526 300 220 3698 400 1.213 13,60 Foedwater Pumps 5 300 526 300 220 3698 200 1.215 1.:60 30 o(03o0 Vals- 6 300 526 300 220 3693 200 1.215 1.160 6 Cl.ol I" step 'A 300 520 300 220 3693 306 1.$90 1,135 down 7B I50 s 50 13$ 0.03 0 0 120 120 8 300 326 30$ 22$ 3698 6 1.215 1.160 9A 300 526 300 220 3690 437 1.215 1,160 9B 150 150 150 0.01 0 0 1.215 1,160 I 500 300 500 1980 364 600 085 1.1335 2 500 300 500 1980 364 600 005 1.135 3 300 $00 500 1980 364 600 910 1.160 Lossof 4 500 300 0 13980 364 400 910 1,160 Feod wate, P uops 5 500 300 500 1980 364 200 9$0 1.160 (Imlaon Vatv- 6 500 300 500 1980 364
* 200 910 1.160 5 X 2 Close) IsI & 2.d 7A 500 300 500 1980 364 301 .885 1.135 stop o 71 50. 350 I 150 0.01 0 0 120 120 8 500 $00 500 1980 364 6 910 1.160" 9A 500 300 500 3980 364 429 910 1.160 9B 15$. 150 150 .0.01
* 0 0 910 1,160 I 300 500 300 10 4000 600 .13$5 675 2 300 500 300 180 4000 600 I.135 675 3 300 500 300 180 4000 600 1.160 700 Loss of 4 300 .500 300 180 4000 400 ,1360 700 Feedoaler Pumps 5 300 500 300 180 4000 200 .160 700 12 (Isolaion ValvM 6 300 500 300 180 4000 200 1.160 700 5 X 2 Close) 2nd & 3,e 7A $00' 500 $30 10 4000 301 1.135 675 stIpdown 7B 150 150 150 0.01 0 0 120 121 8 300 500 300 100 4000 69 1,00 700 9A 300 500 300 180 4000 429 1,160 700 90 150 150 150 0.01 0 0 1,160 700 I 349 300 549 8964 0.10 16.130 240 1.010 2 549 300 549 8964 100 16,150 540 1.010 5 349 $00 549 8964 300 16358 265 1.,035 Loss of 4 "549 $00 549 964 100 6.463 265 1.035 F edwter Pumps 0 549 300 $49 8964 100 3.232 265 1.055 13 0sola6on Valves 6 549 .300 549 8964 100 3.232 265 1.035 5 Close) ls- s-SP 7A 549 300 549 8964 10$ 310 240 1.010 op 70B 10 330 150 8964 100 0 120 120 0 549 300 549 8%4 100 168 265 1,035 9A 549 300 549 8964 100 443 265 1.035 9B3 150 150 150 8967 300 0 265 1.035* 5349 526 549 0 STEP 32.316 1.010 1,010 2 549 576 549 0 STEP 32,316 13010 -1.010 3 549 526 549 0 S sTEP 32.316 1.035 1.035 4 549 526 549 0 STEP 12,926 1,035 1.035 5 549 526 549 0 STEP 6,463 1,035 :0,35 14 0 6 549 526 549 0 STEP 6.463 1,035 3.035 150 7A 549 526 549 0 STEP 360 1.010 .O030 7B 150 150 150 0 STEP 0 120 120 8 549 526 549 0 STEP 335 1,035 3,035 9A 549 526 549 0 STEP 514 3,035 3.035 9B 150 150 350 0 STEP 0 1.035 1.035 File No.: VY-16Q-307 Revision:
0 I I I I I I I I I I I I I I I Pg10o16 I F0306-01IRO I
I Structural Integrity Associates, Inc.Table 3: VY Thermal Transients (continued) 1 1 ~~~Th-eno Condition, 14[1[7[1 (8101 orN.T n-l n e ip flo o ,J P iping O p r T -[ &#xfd; T Im o R IO N Flo -[ 91 W IWIo M .1n of Rlgi.. Tempt. Ff) .,F) I- ' F (gpm) I (psig) (p"s 1 lOI I 375 149 375 6164 100 16,158 1.010 170 2 375 549 375 6264 00 16.158 .,1O 170 3 375 049 575 6264 00 16.158 105 195 4 375 549 375 6264 100. 6.463 10S5 195 5 375 549 375 6264 00 3.232 .035 195 15 Sholdono 1 6 375 549 375 6264 100 3,232 ,035 195 150 7A 375 549 375 6264 100 320 .,035 170 7B 150 1 0 -580 0.01 0 0 120 120 8 575 549 375 6264 100 168 1.035 195 9A 375 549 3 375- 6264 100 458 1,035 195 9B ]SO 150 150 0.01 0 0 1,035 195 1 530. 375 550 600 270 16.150 170 90 2 330 375 350 600 270 16.151 170 90 5 330 570 500
* 600 270 16.1518 195 111 4 330 575 330 600 270 6.463 195 111 5 330 375 330 600 270 3.232 195 115 16 Shutdow2 6 330 375 330 600 270 3.252 195 115 7 330 375 330 600 270 282 170 90 7B so 150 0ISO 600 0 0 120 90 8 370 375 330 600 270 161 195 115 9A. 350 375 330 600 270 403 195 110 9B ISO 150 150 600 0 0 195 11[I 225 .330 225 5700 O 0 16,15 90 0 .2 225 530 225 5700 100 16.158 90 0 3 200 530 225 3700 100 16,158 115 25 4 225 530 225 3780 100 6.463 115 20 5 225 330 225 3780 100 3,232 115 25 17 S hdo wn 3 "6 2 2 5 330 22 5 37800 0 5.2 3 2 11 2 5 ISO 7A 225 330 225 3780 100 260 90 0 7B ]SO 150 ISO 0 0 0 9 ' 0 8 225 330 225 37 10 100 16 S .5 25 9A 225 330 225 3700 100 260 .115 25 9. Iso ISO 150 0 0 0 115 25 100 225 100 4500 100 22.850 0 0 2 100 225 100 4500 100 816.15 0 0 3 100 225 1 4500 100 16,158 25 25 3B 100 225 I00 4500 100 22,058 25 25 4 l 00 225 100 4500 :00 9.143 25 25 Shuldoo- 4 1 1 Is (1 S51d7 5 F100 225 100 4500 I00 4.572 25 25 ISO isO) 6 100 225 100 4500 100 4.572 25 25 7A 100 225 100 4500 100 6,700 0 0 70 100 225 100 0500 100 6.700 0 0 8 100 225 100 4500 100 168 25 25 9A 100 225 100 4500. 0OO 6,700 100 100 90 100 225 100 4500 100 6,700 100 100 I 100 ;00 100 0.01 0 2.262 .25 1,560 2 100 100 100 0.01 0 2.262 25 1.363 3 100 100 100 0.01 0 2.262 25 1,560 0 100 100 100 0 01 0 905 25 1.563 5 10 00 00 0.01 0 452 25 1.565 19 Code lydro 6 100 100 I00 0.01 0 452 25 1.563 7A 100 100 100 0.01 0 I58 25 1.563 7B 0000 I000 I 0.01 0 0 0 450 0 100 0 lO 000 0.01 0 23 25 1.,563 9A 100 100 100 0.01 0 220 25 1.563 9B 100 100 100 001 0 0 25 1.563 1 225 225 225 0.0 , 0 22.858 0 0 2 225 225 225 0.01 0 16.150 0 0 3 225 225 225 0.01 0 16'158 25 25 3B 225 180 225 60 2700 22,858 25 25 4 225 180 220 60 .2700 9,145 25 '25 20 R R tR Wi aion 5 225 180 225 60 2700 4,572 25 25 (1) 6 225 180 225 60 2700 4,572 25 25 7A 225 225 225 60 0 6.700 0 0 7B 225 150 225 60 4500 6.700 0 0 8 225 225 225 0.01 0 237 25 25'A 225 70 225 60 9300 6,710 20 25 90 225 70 225 60 9300 6,700 25 25 21 (-)1 2 3 4 5 6 7A 9A 9B 225 225 225 180 110.180 1800 225 70 70 225 225 225 225 225 225 225 225 IS5 225 225 150 225 225 225 t800 180 180 180 225 150 225 70 70 0.01.001 0.01 60 60 60 60 60 0.01 0.01 60 60 0 0 2700 2700 2700 2700 0 0 0 9300 1290 22,858 16,1 5 16,:588 22,858 9,143 4,572 4.572 6,700 6,700 237 6,700 25 25 25 25 25 0 25 25 0 0 25 25 25 25 25"0 0 25 25 150 File No.: VY-16Q-307 Revision:
0 Page 11 of 16 F0306-OI RO Structural Integrity Associates, Inc.Table 4: Recirc/RHR Piping Size Information
[31 Regions 1,2 3 4 5 6 7A, 7B 8 9A, 9B Piping Nom. O.D. (in.) 28.169 28.339 21.878 1.2.748 14.17 20 4.5 24 Piping Nom. Wall (in.) 1.244 1.339 1.043 0.685 1.395 1.031 0.3385 1.217 Pipe Weight' (lb/ft) 386.1 415.1 257.2 103.4 207.5 221.9 23.2 316.5 Note: 1. Weight of contents automatically added by the PIPESTRESS Program.4.0 ANALYSIS Through-wall thermal gradient terms were calculated by the PIPESTRESS program for all of the transients.
Thermal transient cases were modeled for each transient, as shown in Table 3. Some transients were similar in nature and were lumped together and the number of cycles added together.Listings of the PIPESTRESS input files are included as Appendix A.The forces and moments due to thermal expansion need to be included in the fatigue evaluation.
The thermal expansion cases as analyzed by the piping program, PIPESTRESS, correspond to the end temperature and pressure of the transient.
Table 5 lists the thermal expansion cases.The material properties were obtained from the ASME Code Section III, 1998 Edition, Appendix I, with 2000 Addenda [1]. E and x are taken at 70'F, and k, p, and cp are taken at the average temperature over the range of the individual transients.
The internal heat transfer coefficient h for the transients with flow occurring in the pipe is calculated based on the following relation for forced convection
[131: h 0.023 Re 0 8 Pr 0 4 k/D Where Re= Reynolds number Pr = Prandtl number k -Thermal conductivity D = Pipe diameter I I I I I I I I I I File No.: VY-16Q-307 Revision:
0 Page 12 of 16 F0306-01 RO 1 ~Structural Integrity Associates, Inc.The heat transfer coefficients were calculated by PIPESTRESS using the above relation.
The flow rates described for each transient in Section 3 were used. For the transients where flow is stopped, the natural convection heat transfer coefficient was used. The formula for h is [13]: h= 0.55 (Gr Pr)&deg; &#xfd;k/L Where Gr Grashof Number L Pipe diameter PIPESTRESS only, has the forced convection heat transfer formula built in, so an equivalent flow rate was determined that would give the same heat transfer coefficient as the free convection coefficient.
Since the replacement of the Recirculation piping [10], HWC conditions exist for 39% of the time, and NWC conditions exist for 61% of the time. This is based on 17.5 years of operation with NWC between March and July 1.986 when the piping was replaced and November 2003 when HWC was implemented and the 46 years from March 1986 to the end. of the period of extended operation in March 2032. Using the bounding EAF multipliers (8.36 for HWC and 15.35 for NWC) [14], an overall multiplier may be calculated as follows: (15.35)0.61
+ (8.36)0.39 12.62 Table 5: Thermal Cycle Load Sets Rcgion Tanperatums IVF)Lad Set C-s I 2 3 3B 4 5 6 1 7A 7B .8 9A 9B I I 0 I4O I00 -o0o 100 00 100 100 1 00 100 100.2 2 1 0 tO0 10 -100 10 0 100 100 00 100 100 I004 3 3 549 549 549 -549 549 " 549 549 150 549 549 150 4 4 542 542 542 542 542 542 542 " 50 542 542 150 5 5 526 526 526 5 226 526 526 526 150 526 526 150 6 6 542 542 542 -542 542 542 542 150 542 542 150 7 7 526 526 526 -526 526 526 526 150 526 526 150 8 8 516 516 516 -516 516 516 516 150 516 516 :50 9 9 526 526 526 -526 526 526 "526 150 .526 526 150 10 10 300 300 305 300 300 300 300 150 300 300 150 II I11 55O 500 500 -500 500 500 500 150 500 500 .150 12 12 300 300 300 -300 305 300 300 150 300 300 150 13 13 549 549 549 -. 549 549 549 549 150 549 549 150 14 14 549 549 549 -549 549 549 549 150 549 .549 ISO Is 15 375 375 375 -375 375 375 375 150 375 375 I50 16 16 530 330 350 3305 330 550 330 IS0 330 530 IS0 17 17 225 225 225 225 225 225. 225 ISO 225 225 IS0 is 18 100 100 loo 100 100 '10 100 100 100 100 IO 10 .00 19 19 100 100 100 -0Go 100 100 0 0 100 100 " O S0 100 20 20 225 225 225 225 225 225 225 225 225 225 225 225 21 21 225 225 225 ISO 4 10 190 1SO 225 150 225 70 70 Region Pre-s-res (psig)1,2, 7A 6, 9B 7B I 3B I,100 50 1,010 1,010 1,010 1,010 1,010 t,010 1,010 1,135 1,1355 675 1010 1,010 170 90 0 1563 0 45 1,100 50 1,035 1,035 1,035 1,035 1,035 1,035 1,035 1,160 1,160 700 1,035 1,035 195 115 25 25 1,563 25 25 120 50 120 120: 20 120 120 120 120 120 120 121 120 120 120 90 0 0 450 0 0 25 25 25 File No.: VY-16Q-307 Revision:
0 Page 13 of 16 F0306-O1 RO Structural Integrity Associates, Inc.5.0 RESULTS OF ANALYSIS To perform the fatigue analysis, program PIPESTRESS
[5] was used. PIPESTRESS calculates the thermal expansion and seismic moments,*the ASME Code Equation 10, 12, and .13 stresses, perf6rms the thermal stress ratchet check, and performs fatigue analysis per Equation 11 and 14. For each operating state of the recirculation/RHR piping, load sets are created. A load set includes the coincident pressure, thermal expansion moment, through-wall thermal.gradient terms, number of cycles, and temperature at which the allowable Sm is taken. In general, the pressures and thermal expansion moments are taken at the end point of the transient, the thermal gradients taken at the point of maximum total thermal gradient stress during the transient, and the Sm allowable is initially conservatively taken at the highest temperature of the transient.
Table 5 lists the inputs to the load sets. 3 In calculating fatigue, the range of stress in going from one load set to another is determined.
Since the Code assumes that any transient could follow any other, all pairs of load sets are evaluated to determine the range of stresses for the Code stress equations.
The number of allowable cycles for each load set pair is determined.
The incremental fatigue usage is obtained by dividing the number of design cycles by the allowable cycles. The incremental fatigue usages for all load set pairs are then summed to obtain the total fatigue usage.The cumulative fatigue usage for the Loop A recirculation RIR return isolation valve-to-pipe location (Node 641), prior to considering environmental effects, is 0.0128. Taking into account environmental effects, the bounding multiplier for stainless steel is 12.62. This results in a total fatigue usage of 0. 1615. (Note that since the RHR carbon steel piping has not been replaced, these.results represent the full projected 60 year cycle count.).The cumulative fatigue usage for the RHR return tee (Node 600), prior to considering environmental effects, is 0.0590. Taking into account environmental effects, the bounding multiplier for stainless steel is 12.62. This results in a total fatigue usage of 0.7446.Appendix A contains the PIPESTRESS input files. Appendix B contains the fatigue usage summary for both locations.
I I I File No.: VY-16Q-307 Page 14 of 16 Revision:
0 F0306-01RO Ii 1 Structural Integrity Associates, Inc.I
 
==6.0 REFERENCES==
: 1. ASME Boiler and Pressure Vessel Code, Section III, 1998 Edition with 2000 Addenda.2. ASME Boiler and Pressure Vessel Code, Section XI, 1998 Edition.3. Vermont Yankee Calculation 23A5569, "Recirculation System Stress Analysis Loop A", Revision 0, SI File No. VY-05Q-227.
: 4. Email from Jim Fitzpatrick (Entergy) to Terry Herrmann (SI), "RE: RHR Thermal Transients," dated: June 29, 2007 11:19AM, SI File Number VY-09Q-209.
: 5. Program PIPESTRESS, Version 3.5.1+26, DST Computer Services, S.A., June 2004.6. ADLPIPE Model Input Listing, Vermont Yankee Calculation VYC-2030, Rev. 0, "Temporary Shielding Recirculation
&RHR Piping Loop A," File c2030n2, SI File No. W-VY-05Q-227.
: 7. "Reactor Thermal Cycles for 60 Years of Operation," Attachment 1 of Entergy Design Input I .Record (DIR) Revision 1, EC No. 1773, Revision 0, "Environmental Fatigue Analysis for Vermont Yankee Nuclear Power Station," SI File No. VY-16Q-209.
I 8. "Nozzle. Thermal Cycles (Recirculation Outlet)," Attachment 1, page 4, of Entergy Design Input Record (DIR) Revision 1, EC No. 1773, Revision 0, "Environmental Fatigue Analysis for i *Vermont Yankee Nuclear Power Station," SI File No. VY-16Q-209.
: 9. Entergy Nuclear Report VY-RPT-05-00022, "Task TO 100 Reactor Heat Balance EPU Task I Report for ER-0401409", Revision 0, SI File No. VY-16Q-205.
: 10. Design Input Record (DIR) Revision 1, EC No. 1773, Revision 0, "Environmental Fatigue Analysis for Vermont Yankee Nuclear Power Station," SI File No. VY-16Q-209.
: 11. "RHR Shutdown Cooling Temperature Data," page 8, of Entergy Design Input Record (DIR) EC I No. 1773, Revision 1, "Environmental Fatigue Analysis for Vermont Yankee, Nuclear Power Station," SI File No. VY-16Q-209.
: 12. "RHR Shutdown Cooling Flow Rate and Pressure Data," page 9, of Entergy Design Input Record (DIR) Revision 1, EC No. 1773, Revision 0, "Environmental Fatigue Analysis for Vermont Yankee Nuclear Power Station," SI File No. VY- 16Q-209.13 Holman, J.P., Heat Transfer, Fifth Edition, McGraw-Hill, 1981.File No.: VY-16Q-307 Page 15 of 16 Revision:
0 F0306-OIRO VStructural Integrity Associates, Inc.14. SI Calculation, "Environmental Fatigue Evaluation of Reactor Recirculation Inlet Nozzle and Vessel Shell/Bottom Head," Revision 0, SI File Number VY-16Q-303.
: 15. VY Drawings, SI File No. VY-16Q-205:
: a. 5920-6801, Sheet 1, Revision 1.b. 5920-6802, Sheet 1, Revision 2, Sheet2, Revision 2, Sheet3, Revision 3, Sheet 4, Revision 2, Sheet 5, Revision 2, Sheet 6, Revision 2.c. 5920-6808 Sheet 1, Revision 0.I I I I I I I I I I I I I I I I I.File No.: VY-16Q-307 Revision:
0 Page 16 of 16 I F0306-OIRO I
v Structural Integrity Associates, Inc.APPENDIX A PIPESTRESS Input Files Input File Description Recirc_15.fre Piping model and general input-for reduced cycle count RHR 15.fre. Piping model and general input-for 60 year cycle count Regl.inp Region 1 transient definitions Reg2.inp Region 2 transient definitions Reg3.inp Region 3 transient definitions Reg4.inp Region 4 transient definitions Reg5.inp Region 5 transient definitions Reg6.inp Region 6 transient definitions Reg7A.inp Region 7A transient definitions Reg7B.inp Region 7B transient definitions Reg8.inp Region 8 transient definitions Reg9A.inp Region 9A transient definitions Reg9B.inp Region 9B1 transient definitions File No.: VY-16Q-307 Revision:
0 Page Al of A51 F0306-01 RO VStructural Integrity Associates, Inc.Recirc 15.fre IDEN. JB=3 *Job number (I to 9999)CD=l *I=ASME Class 1 GR=-Y *Direction of gravity VA=O *0=Calculate IU=l *Input units OU=l *Output units CH=$ *Delimiter character AB=T *FREE errors abort PL=$Vermont Yankee$EN=$RVP$TITL BL=3 *Modeling option: 2=Verify 1=USA 1=USA* 3 = uniform mass for static analysis* lumped mass for dynamic analysis*
* rotational inertia ignored GL=1 *Report forces/moment 0=Global SU=l *Support summary 0=No CV=I5 *Code version -See Manual HS=l *Highest 20 stress ratios, for each case MD=l *Hot modulus J6=l *File generated by program TI=$Vermont Yankee Recirculation
$$Fatigue Analysis$FREQ RF=l RP=8 FR=36 MP=20 RC=0'MX=70 TI=$SEISMIC$
l=Local l=Yes 2--G et L I I I I I I I I I I I I I I I THERMAL CYCLE LOAD CASES****LCAS LCAS.LCAS LCAS LCAS LCAS LCAS LCAS.LCAS LCAS LCAS LCAS LCAS LCAS LCAS LCAS LCAS LCAS LCAS LCAS LCAS LCAS LCAS LCAS LCAS RF=0 RF=0 RF=0 RF=0 RF=0 RF=0 RF=0 RF=0 RF=0.RF=0 RF=0 RF=0 RF=0 RF=0 RF=0 RF=0 RF=0 RF=0 RF=0 RF=0 RF=0 RF=0 RF=0 RF=0 RF=0 CA=1 CA=2 CA=3 CA=4 CA=5 CA=6 CA=7 CA=8 CA=9 CA=I0 CA=I1 CA=12 CA=13 CA=14 CA=I5 CA=16.CA=17 CA=18 CA=l 9 CA=20 CA=21 CA=22 CA=23 CA=24 CA=25 TY=0 TY=0 TY=0 TY=0 TY=0 TY=0 TY=0 TY=0 TY=0 TY=0 TY=0 TY=0 TY=0 TY=0 TY=0 TY=0 TY=0 TY=0 TY=0 TY=0 TY=0 TY=O TY=0 TY=0 TY=0 TI=$LC-l$TI=$LC-2$TI=$LC-3$TI=$LC-4$TI=$LC-5$TI=$LC-6$TI=$LC-7$TI=$LC78$TI=$LC-9$TI=$LC-10$
TI=$LC-11$
TI=$LC-12$
TI=$LC-13$
TI=$LC-14$
TI=$LC-15$
TI=$LC-16$
TI=$LC-17$
TI=$LC-18$
TI=$LC-19$
TI=$LC-20$
TI=$LC-21$
TI=$LC-22$
TI=$LC-23$
TI=$LC-24$
TI=$LC-25$
*TC-1*TC-2*TC-3*TC-4*TC-5*TC-6*TC-7*TC-8*TC-9*TC-10*TC-11*TC-12*TC13*TC-14*TC-15*TC-16*TC-17*TC-18*TC-19*TC-20*TC-21*TC-22*TC-23*TC-24*TC-25**** WEIGHT CASES****LCAS CA=I01 LCAS CA=102 RF=l TY=3 RF=2 TY=4 TI=$OPERATING WEIGHT$TI=$HYDROTEST WEIGHT$I I I I File No.: VY-16Q-307 Revision:
0 Page A2 of A51 F0306-OIRO V Structural Integrity Associates, Inc.******* *************
************* THERMAL TRANSIENT CASES****** *** * * ** *** ** * *** ** ** ** * ** *** **TCAS TCAS TCAS TCAS TCAS TCAS TCAS TCAS TCAS TCAS TCAS TCAS TCAS TCAS TCAS TCAS TCAS TCAS TCAS TCAS TCAS TCAS TCAS TCAS TCAS CA=201 CA=202 CA=203 CA=204 CA=205 CA=206 CA=207 CA=208 CA=2 09 CA=210 CA=211 CA=212 CA=213 CA=214 CA=215 CA=216 CA=217 CA=218 CA=219 CA=220 CA=221 CA=222 CA=223 CA=224 CA=225 TI=$Design Hydrotest
(+TI=$Design Hydrotest
(-TI=$Startup TI=$TRoll
& Inc. PWR1 TI=$TRoll
& Inc. PWR2 TI=$LOFWH+TT PWRI TI=$LOFWH+TT PWR2 TI=$LOFWH+PFWHTR Bypl TI=$LOFWH+PFWHTR Byp2 TI=$LOFWP, ISO Cl DN 1 TI=$LOFWP, ISO Cl UP 1 TI=$LOFWP, ISO Cl DN 2 TI=$LOFWP, ISO Cl UP 2 TI=$Reduction to 0% PWR TI=$Shutdownl TI=$Shutdown2.TI=$Shutdown3 TI=$Shutdown4 TI=$Code Hydrotest TI=$RHR Initiation UP TI=$RHR Initiation DN TI=$Inadvert.
Inj.. DOWN TI=$Inadvert.
Inj. UP TI=$Sihgle Relief BD DN TI=$Single Relief BD UP))** SEISMIC CASES****RCAS CA=103 EQ=3 EV=l TY=l SU=l LO=l**** LOAD COMBINATION CASES *FX=l FY=l FZ=l TI=$OBE INERTIA$CCAS RF=I CA=104 CCAS RF=l CA=401 SS=l CCAS RF=I CA=402 SS=1 CCAS RF=l CA=403 SS=l**** LOAD SETS***** ** * ** **** ******ME=l FL=l ME=I EQ=3 ME=3 Fl=l ME=3 Fl=-l C1=103 C1=10.l C1=103 C1=103 CY=10 C2=103 C2=1 C2=1 TI=$OBE$TI=$EQUATION
.9 LEVEL B$TI=$NORMAL+OBE$
TI=$NORMAL-OBE$
LSET LSET LSET.LSET LSET LSET LSET LSET LSET LSET LSET LSET LSET LSET RF=I RF=2 RF=3 RF=3 RF=4 RF=4 RF=4 RF=5 RF=5 RF=5 RF=I1 RF=I1 RF=3 RF=3 FC=0 FC=0 FC=0 FC=0 FC=0 FC=0 FC=0 FC=0 FC=0 FC=0 FC=0 FC=0 FC=0 RP=1 RP=1 RP=1 RP=1 RP=1 RP=I RP=1 RP=l RP=l RP=l RP=l RP=I RP=l CY=60 CY=60 CY=150 CY=290 CY=290 CY=I0 CY=I0 CY=35 CY=35 CY=5 CY=I0 CY=10 CY=5 PR=1 PR=2 PR=3 PR=4 PR=5 PR= 6 PR=7 PR=8 PR=9 PR=I0 PR=lI PR=I2 PR=13 MO=l MO=2 MO=3 MO=4 MO=5.MO=6 MO=7 MO=8 MO=9 MO=I0 MO=ll MO=12 MO=13 TR=201 TR=-202 TR=203 TR=-204 TR=-205 TR=206 TR=-207 TR=-208 TR=209 TR=-210 TR=211 TR=-212 TR=213 TI=$Design Hydrotest
(+)LS-I$TI=$Design Hydrotest
(-)LS-2$TI=$Startup LS-3$TI=$TRoll
& Inc. PWRI LS-4$TI=$TRoll
& Inc. PWR2 LS-5$TI=$LOFWH+TT PWRI LS-6$TI=$LOFWH+TT PWR2 LS-7$TI=$LOFWH+PFWHTR Bypl LS-8$TI=$LOFWH+PFWHTR Byp2 LS-9$TI=$LOFWP, ISO Cl DN 1 LS-10$TI=$LOFWP, ISO Cl UP 1 LS-II$TI=$LOFWP, ISO Cl DN 2 LS-125 TI=$LOFWP, ISO Cl UP 2. LS-13$FC=0 RP=l CY=150 PR=14 MO=14 TR=214 TI=$Reduction to 0% PWR LS-14$File No.: VY-16Q-307 Revision:
0 Page A3 of A51 F0306-OIRO CStructural Integrity Associates, Inc.LSET LSET LSET LSET LSET LSET LSET LSET LSET LSET LSET RF=5 RF=15 RF=I16 RF=2 0 RF=1 9 RF=20 RF=20 RF=5 RF=5 RF=23 RF=24 FC=0 FC=0 FC=0 FC=0 FC=0 FC=0 FC=0 FC=0 FC=0 FC=0 FC=0 RP=I RP=I RP=I RP=1 RP=1 RP=I RP=I RP=1 RP=I RP=1 RP=I CY=150 CY=150 CY=150 CY=150 CY=1 CY=150 CY=150 CY=0 CY=0 CY=0 CY=o PR=15 PR=16 PR=17 PR=18 PR=19 PR=20 PR=21 PR=22 PR=23 PR=24 PR=25 MO=15 MO=16 MO=17 MO=18 MO=19 MO=20 MO=21 MO=22 MO=2 3 MO=2 4 MO=2 5 TR=-215 TR=-216 TR=-217 TR=-218 TR=219 TR=220 TR=-221 TR=-222 TR=223 TR=-224 TR=225 TI=$Shutdownl TI=$Shutdown2 TI=$Shutdown3 TI=$Shutdown4 TI=$Code Hydrotest TI=$RHR Initiation UP TI=$RHR Initiation DN TI=$Inadvert.
Inj. DOWN TI=$.Inadvert.
Inj. UP TI=$Single Relief BD DN TI=$Single Relief BD UP LS-15$LS-16$LS-17$LS-18$LS-19$LS-20$LS-21$LS-22$LS-23$LS-24$LS-25$LSET RF=2 FC=O CY=5 FL=I PR=2 MO=402 TI=$NORMAL+OBE LS-26$LSET RF=2 FC=0 CY=5 FL=I PR=2 MO=403 TI=$NORMAL-OBE LS-27$*FATG AT=500 AF=502*FATG AT=600 AF=602**** RESPONSE SPECTRA****
SPEC FS=OBE EV=I ME=3 FP=0 TI=$RESPoNSE$
LV=I DX=1 DY=1 DZ=1 DI=X 0.30/0.100 0.40/0.100 0.90/0.20 3.30/0.700 4.40/0.750 4.41/0.90 8.70/1.600 12.00/0.650 17.00/0.40 DI=Y 0.30/0.030 0.40/0.030 0.50/0.05' 2.00/0.220 2.40/0.350 3.50/0.35' 8.25/0.330 8.75/0.250 17.50/0.25' DI=Z 0.30/0.100 0.40/0.100 0.50/0.13' 1.90/0.600 3.50/0.600 3.75/0.70' 8.50/1.500 12.50/0.500 20.00/0.35' I I I I I I I U I I I I I U I 0 0 0 0 0 0 0 0 0 1.25/0.400 4.75/1.100 20.00/0.350 0.60/0.075 3.60/0.300 25.00/0.120 0.90/0.150 4.40/0.700 30.00/0.350 2.25/0.450 5.20/1.100 30.00/0.350 1.00/0.075 5.30/0.300 30.00/0.120 1.00/0.250 4.50/0.800 36.00/0.350 2.30/0.700 5.80/1.600 36.00/0.350 1.20/0.100 5.75/0.330 36.00/0.120 1.60/0.250 6.25/1.500
**** MATERIAL PROPERTIES
**** ASTM C MATH CD=106 MATD TE=70 MATD TE=100 MATD TE=200 MATD TE=300 MATD TE=400 MATD TE=500 MATD TE=600* ASME SA-376 MATH CD=376.31 MATD TE=70 MATD TE=100 MATD TE=200 MATD TE=300 MATD TE=400 MATD TE=500 MATD TE=600* ASME SA-403 rade B, PIPE *EX=0 T EH=29.5 E EH=29.3 E EH=28.8 E.EH=28.3 E: EH=27.7 E: EH=27.3 E EH=26.7 E Grade TP316, P 6 EX=0 T EH=28.3 .E EH=28.1 E: EH=27.6 E: EH=27.0 E EH=26.5 E EH=25.8 E)EH=25.3 E}Grade WP316, El Y=1 X=0. 0 X=0.20 X=l. 00 X=l. 90 X=2.80 X=3.70 X=4.70 IPE *Y=4 X=0.0 X=0.30 X=1.40 X=2. 50 X=3.70<=5. 00 K=6.30 LBOWS *(=4&#xfd;=0. 0*C-Si SM=20.0 SM=2 0. 0 SM=20.0 SM=2 0.0 SM=20. 0 SM=18. 9 SM=17 .3 SY=35 SY=35 SY=32. 1 SY=31 SY=29. 9 SY=28.5 SY=26. 8*16Cr-12Ni-2Mo SM=20.0 SY=30.0 SM=20.0 SY=30.0 SM=20.0 SY=25.9 SM=20.0 SY=23.4 SM=19.3 SY=21.4 SM=18.0 SY=20.0 SM=17.0 SY=18.9*16Cr-12Ni-2Mo SM=20.0 SY=30.0 MATH CD=403.316 EX=0 MATD TE=70 EH=28.3 TE E>I I I I File No.: VY-16Q-307 Revision:
0 Page A4 of A51 F0306-01 RO S structural Interity Associates, Inc.MATD TE=l(MATD TE-=2(MATD TE=3(MATD TE=4(MATD TE=5(MATD TE=6(*** Cross CROS CD=l CROS CD=2 CROS CD=3 CROS CD=4 CROS CD=5 CROS CD=7 CROS CD=8 CROS CD=ll CROS CD=13 CROS CD=14 CROS CD=15 CR0S CD=16 CROS CD=17 CROS CD=18 CROS CD=19 CROS CD=20 CROS CD=25 CROS CD=26 CROS CD=27 CROS CD=28 CRoS CD=29 CROS CD=30 CROS CD=40 CROS CD=41 CROS CD=42 EH=28 .1 EH=27. 6 EH=27 .0 EH=26. 5 EH=25.8 EH=2 5.3 EX=0. 30 EX=I. 40 EX=2. 50 EX=3.70 EX=S.00 EX=6. 30 SM=20.0 SM=20.0 SM=20. 0 SM=18.7 SM=17.5 SM=16.4 SY=30.0 SY=25. 9 SY=23. 4 SY=21.4 SY=2 0.0 SY=18. 9 Sectional Properties OD=50.0 WT=8.87 MA=3977.2
*CALC. PER GE SPEC. NO. 23A5569 SO=1 OD=37.85 SO=1 OD=28.875 SO=1 OD=28. 638 SO=1 OD=28.169 SO=1 OD=28. 166 SO=1 OD=42. 507 SO=. 001 OD=6. 625 SO=0. 001 OD=28.339 S0=I OD=28.339 SO=1 OD=12.748 SO=1 OD=14.17 S0=1 OD=15.5 SO=I OD=21. 88 SO=1 OD=28.25 SO=1 OD=21. 878 SO=1 OD=20 SO=1 OD=20 SO=1 OD=4 .5 SO=l1 oD=4. 5 SO=I OD=24 SO=1 OD=2 4 SO=1 OD=4. 5 SO=0.001 OD=2.875 SO=0.001 OD=28.339 ST=l. 0 WT=6. 1 ST=I. 0 WT=l.56 ST=I. 0 WT=l.45 ST=l. 0 WT=l.244 ST=1. 0 WT=2.125 ST=l. 0 WT=2.486 ST=. 001 WT=0.432 ST=0. 001 WT=l. 339 ST=l WT=2. 67 ST=1 .0 WT=0. 685 ST=l. 0 WT=1. 395 ST=l. 0 WT=2 ST=l .0 WT=4.06 ST=l.0 WT=7.25 ST=I. 0 WT=l. 043 ST=l. 0 WT=l.031 ST=1 WT=1. 875 ST=1 WT=0. 3385 ST=1 WT=0. 67 ST=I WT=1.217 SrT=1 WT=2.43 ST=1 WT=0.3385 ST=0. 001 WT=0. 276 ST=0.001 WT=l. 339 MA=2122.2 MA=4 84.9 MA=450. 4 MA=386. 1 MA=0. 001 KL= -1 MA=0.001 KL=1 MA=0. 001 KL=l MA=415. 1 MA=0. 001 KL=1 MA=103.4 MA=207 .5 MA=307 .7 MA=803.2 MA=1673.1 MA=257.2 MA=221. 9 MA=0. 001 KL=I MA=23.2 KL:I MA=0. 001 KL=1 MA=316. 5 MA=0. 001 KL=1 MA=0. 001 KL=l MA=0. 001 KL=l MA=0. 001*RECIRCULATION OUTLET NOZZLE*CALC. PER GE SPEC. NO. 23A5569*CALC. PER GE SPEC. NO. 23A5569*CALC. PER GE SPEC. NO. 23A5569*CALC. PER GE SPEC. NO. 23A5569*VALVE*PUMP*PUMP RIGID STRUTS[3][3][.3][3][3]*CALC. PER GE SPEC. NO. 23A5569 [3]*VALVE*CALC.*CALC.*CALC..* CALC.*CALC.*CALC.*CALC.*VALVE PER PER PER PER PER PER PER GE GE GE GE GE GE GE SPEC.SPEC.SPEC.SPEC.SPEC.SPEC.SPEC.NO.NO.NO.NO.NO.NO.NO.23A5569 23A5569 23A5569 23A5569 23A5569 23A5569 23A5569[3][3][3][3][3][3][3]*CALC. PER GE SPEC. NO. 23A5569 [3]*4 inch bypass line*VALVE V2-54A*CALC. PER GE SPEC.*VALVE NO. 23A5569 [3]*4 inch bypass STRUTS*STRUT RDAI, RDA5, & VBAI*RIGID FROM RECIRC ELBOW TO RDAl STRUT SO=0.001 ST=0.001 KL=I* STRUCTURE AND LOADS******** **************
File No.: VY-16Q-307 Revision:
0 Page A5 of A51 F0306-01 RO V Structural Integrity Associates, Inc.* ------------------------
7----------------------------------
DESN TE=575.0 PR=1250.0
*Reference 12 GE Design Requirements Rpt VY-05Q-227
*--7----------------------------
-----------------------------
------*-------------------------------------------
*BEGIN REGION 1 TRANSIENT CARDS & GEOMETRY FROM RHR SUPPLY TO TEE---------------------------------------------------
INCL FN=Z:\SISJ-PROJECTS\VY-16Q\RevO\REG1.INP.
*RUN 1 FROM ANCHOR TO REACTOR VESSEL N3B*GROUP 1 FROM ANCHOR TO REACTOR VESSEL N3B*NOTE*NOTE NODE 003 -RECIRC SUCTION NOZZLE NIA (EL. 279'5 INCH)*NOTE NODE 003 IS AT THE SAFE END TO VESSEL NOZZLE CONNECTION
*NOTE*NOTE SAFE END FROM NODES 003 TO 808*NOTE CONNECTION TO VESSEL AT NODE 003*NOTE OD AND WALL THICKNESS FOR SAFE END TAKEN FROM GE CALC*NOTE WEIGHT FOR SAFE END BASED ON THICKNESS*NOTE MATL CD=376.316 CROS CD=1 COOR PT=3 AX=0 AY=0 AZ=0 ANCH PT=3 AMVT CA=I AMVT CA=2 AMVT CA=3 AMVT CA=4 AMVT CA=5 AMVT CA=6 AMVT CA=7 AMVT CA=8 AMVT CA=9 AMVT CA=10 AMVT CA=11 AMVT CA=12 AMVT CA=I3 AMVT CA=14 AMVT CA=15 AMVT CA=16 AMVT CA=17 AMVT CA=18 AMVT CA=19 AMVT CA=20 AMVT CA=21 AMVT CA=22 AMVT CA=23 AMVT CA=24 PT=3 PT=3 PT=3 PT=3 PT=3 PT=3 PT=3 PT=3 PT=3 PT=3 PT=3 PT=3 PT=3 PT=3 PT=3 PT=3 PT=3 PT=3 PT=3 PT=3 PT=3 PT=3 PT=3 PT=3 DX=0. 0000 DX=0. 0000 DX=0. 0000 DX=0.0000 DX=0.0000 DX=0. 0000 DX=0. 0000 DX=0. 0000 DX=0.0000 DX=0.0000 DX=0. 0000 DX=0.0000 DX=0.0000 DX=0. 0000 DX=0. 0000 DX=0.0000 DX=0. 0000 DX=0. 0000 DX=0.0000 DX=0.0000 DX=0. 0000 DX=0. 0000 DX=O 0000 DX=0. 0000 DY=0. 0176 DY=0. 3141 DY=0.3112 DY=0. 2995 DY=0. 3112 DY=0.2 995 DY=0. 2922 DY=0.2 995 DY=0. 1422 DY=0.2807 DY=0. 1422 DY=0. 3141 DY=0. 3141 DY=0. 1928 DY=0. 1624 DY=0.0946 DY=0.0176 DY=0. 0176 DY=0. 0946 DY=0. 0946 DY=0. 0361 DY=0. 2995 DY=0. 1928 DY=0. 0176 DZ=-0.0201 DZ=O. 3602 DZ=-0. 3568 DZ=-0. 3434*DZ=-0.3568 DZ=-0. 3434 DZ=-0. 3350 DZ=-0. 3434 DZ=-0. 1630 DZ=-0* 3218 DZ=-0. 1630 DZ=-0.3602 DZ=-0. 3602 DZ=-0.2521 DZ=-0. 1986 DZ=-0. 1084 DZ=-0. 0201 DZ=-0. 0201 DZ=-0..1084 DZ=70.1084 DZ=-0. 0413 DZ=-0. 3434 DZ=-0.2521 DZ=-0. 0201 I I I I I I I I I I I I I I I I I TANG CROS TANG CROS TANG CROS TANG CROS PT=805 DZ=-1.017 EW=1 CD=2 PT=806 DZ=-0.823 EW=1 CD=3 PT=807 DZ=-0.58 EW=1 CD=4 PT=808 DZ=-0.47 CD=5 TANG PT=5 DZ=-5.59 EW=1 FileNo.: VY-16Q-307 Revision:
0 Page A6 of A51 I I F0306-OI RO U Structural Integrity Associates, Inc.MATL CD=403.316 BRAD PT=7 RA=3.5 EW=I MATL CD=376.316 TANG PT=9 .DY=-6.69 EW=1 TANG PT=500 DY=-2.31*END REGION 1 GEOMETRY FROM RHR SUPPLY TO TEE-----------------------------------
------------------------------------------------------
*BEGIN REGION 2 TRANSIENT CARDS & GEOMETRY FROM RHR SUPPLY TEE TO PUMP* ----------------------------------------------------
-*GROUP 2 RHR SUPPLY TEE TO PUMP INCL FN&#xfd;Z:\SISJ-PROJECTS\VY-16Q\RevO\REG2.INP TANG CROS TANG TANG TANG TANG MATL BRAD MATL TANG CROS VALV JUNC VALV JUNC RIGD LUMP JUNC CROS TANG TANG TANG MATL BRAD MATL CROS TANG.LUMP*TANG TANG TANG LUMP TANG PT&#xfd;II DY=-2.22 EW=I CD=5 PT=12 DY=-I.78 PT-20 DY=-6.77 PT=22 DY=-3.25 PT=25 DY=-15.49 EW=1 CD=403.316 PT=26 RA=3.5 EW=1 CD=376.316 PTh27 DX=-3.3 DZ=I.27 EW=1 CD=7 PTh30 DX=-2.28 DZ=0.89 MA=l0.368 PL=l PT=30 PT=40 DX=-2.31 DZ=0.9 PL=2 EW=1*PT=30 PT=35 DY=7 PT=35 MA=I.132 PT=40 CD=5 PT=42"DX=-1.18 DZ=0.46 PT=43 DX=-0.55 DZ=0.21 PT=44 DX=-3.31 DZ=I.28 EW=1 CD=403.316 PT=46 RA=2.33 EW=I CD=376.316 CD=8 PT=50 DY=4.33 EW=O PT=50 MA=28. *NOTE WEIGHT OF PUMP FLOODI PT=75 DY=0.5 PT=83 DY=2.13 PT=86. DY=3.38 PT=86 MA=32 *NOTE TOTAL WEIGHT OF PUMP PT=90 DY=4.08 *TOP OF PUMP ED 28K (EXCLUDIN MOTOR 32000 LBS G MOTOR)*NOTE SNUBBERS ON TOP OF PUMPS WERE DELETED DURING*NOTE THE RECIRC PIPE REPLACEMENT PROJECT*NOTE -RIGID LINKS FOR CONSTANT SUPPORTS AT PUMP FOLLOW* --------------------
*END REGION 2 GEOMETRY FROM RHR SUPPLY TEE TO PUMP--------L-------------
-------------------------------
*BEGIN REGION 3 TRANSIENT CARDS & GEOMETRY FROM PUMP DISCHARGE TO HEADER* ----------------------------------------
*GROUP 3 FROM PUMP DISCHARGE TO HEADER INCL FN=Z:\SISJ-PROJECTS\VY-16Q\RevO\REG3.INP FileNo.: VY-16Q-307 Revision:
.0 Page A7 of A51 F0306-OI RO Structural Integrity Associates, Inc. " JUNC PT=50 CROS CD=8 RIGD PT=54 DX=l.06 DZ=I.06 RIGD PT=56 DX=l.06 DY=0.75 DZ=I.06 JUNC PT=50 RIGD PT=66 DZ=-3.83 RIGD PT=69 DY=l JUNC PT=50 CROS CD=8 RIGD PT=60.DX=-3.83 RIGD PT=63 DY=1*
* CODING.FOR PUMP RIGID STRUTS* CODED FROM PUMP CENTERLINE CROS CD=1I JUNC PT=66 RIGD PT=15 DY=0.7071 DZ=-0.7071
*NOTE CONSTANT SUPPORT HA3 AT NODE 56*NOTE CONSTANT SUPPORT HA4 AT NODE 69*CONSTANT SUPPORT HAS AT NODE 63 FOLLOW ***JUNC PT=60 RIGD PT=16 DX=-0.7071 DY=0.7071* *** END OF CODING FOR PUMP SUPPORTS ****PUMP INLET CROS CD=8 JUNC PT=50 TANG PT=150 DX=-2.17 BRAN PT=151 DZ=2 333 TE=I*NOTE PUMP DISCHARGE CONNECTION TO PIPE AT NODE 151 CROS CD=13 TANG PT=152 DZ=I.25 TANG PT=155 DZ=I EW=l CROS CD=14 VALV PT=160 PL=I DX=0.0 DY=0.0 DZ=2.52 MA=6.8285 JUNC PT=160 RIGD PT=163 DX=0.0 DY=7.12 DZ=0.0 LUMP PT=163 MA=0.9715 JUNC PT=160 VALV PT=I70 PL=2 DX=0.0 DY=0.0 DZ=6.18 EW=I CROS CD=13 MATL CD=403.316 BRAD PT=175 RA=3.5 EW=l MATL CD=376.316 TANG PT=I76 DY=5.95 TANG PT=177 DY=4.42*NOTE ***WEIGHT OF-FLOW ELEMENT NOT INCLUDED***
*NOTE ***REF. DWG. 5920-6800 FOR DIMENSIONS***
TANG PT=184 DY=4.42 TANG PT=186 DY=3.02 TANG PT=I88 DY=1.51 TANG PT=189 DY=0.74 TANG PT=190 DY=I.15 EW=I TANG PT=600 DY=I.06 I I U I I I I I I I I I I I I I***INPUT FILE TO INCLUDE EFFECTS OF RHR INITIATION INCL FN=Z:\SISJ-PROJECTS\VY-16Q\RevO\REG3B.INP ON LINE NEAR RHR RETURN TO HEADER JUNC PT=600 TANG PT=I95 DY=2.08 EW=I TANG PT=210 DX=0.0 DY=I.83 DZ=0.0 KL=I *CENTER OF CROSS, RECIRC HEADER*MUST HAVE INDI CARD FOR EACH MEMBER CONNECTED TO CROSS CENTER File No.: VY-16Q-307 Page A8 of A51 Revision:
0 I I F0306-OI RO Structural Integrity Associates, Inc.I*END REGION 3 GEOMETRY FROM PUMP DISCHARGE TO HEADER---------------------
------------------------------
*BEGIN REGION 5 TRANSIENT CARDS & GEOMETRY RISER TO NOZZLE NODE 336* ------------------------------
*GROUP 5 RISER TO NOZZLE NODE 336 INCL FN=Z:\SISJ-PROJECTS\VY-16Q\RevO\REG5.INP
*NOTE CROSS AND REDUCER DIMENSIONS TAKEN FROM 5920-6632 SHT.3 CROS CD=13 MATL TANG CRED CROS TANG TANG MATL BRAD CD=376. 316 PT=215 DX=0.0 DY=2.59 DZ=0.0 EW=0 PT=220 DY=1.29 AN=30 EW=1 *AL=$CONC.
REDUCERS CD=15 PT=330 DY=4.58 PT=335 DY=3.29 EW=1 CD=403.316 PT=334 RA=1.5 EW=1* --------------------
*END REGION 5 GEOMETRY RISER TO NOZZLE NODE 336---------------------
* ------------------------------
*BEGIN REGION 6 TRANSIENT CARDS & GEOMETRY TO-------------------------------
-*GROUP 6 TO NOZZLE NODE 336 INCL FN=Z:\SISJ-PROJECTS\VY-16Q\RevO\REG6.INP NOZZLE NODE 336 MATL TANG CROS TANG CROS TANG CROS TANG CROS TANG NOZZ AMVT AMVT AMVT AMVT AMVT AMVT AMVT AMVT AMVT AMVT AMVT AMVT AMVT AMVT AMVT AMVT AMVT AMVT AMVT CD=376. 316 PT=838 DX=3.875 CD=16 PT=837 DX=0.875 EW=1 CD=17 PT=836 DX:0.37 EW=1 CD=18 PT=835 DX=0.53 EW=1 CD=19 PT=336 DX=0.704 EW=1 PT=336 CA=1 CA=2 CA=3 CA=4 CA=5 CA=6 CA=7 CA=8 CA= 9 CA=10 CA=11 CA=12 CA=13 CA=14 CA=15 CA=f 6 CA=17 CA=18 CA=1 9 PT=336 PT=336 PT=336 PT=336 PT=336 PT=336 PT=336 PT=336 PT=336 PT=336 PT=336 PT=336 PT=336 PT=336 PT=336 PT=336 PT=336 PT=336 DX=-0. 0201 DX=-0.3602 DX=-0. 3568 DX=-0. 3434 DX=-0. 3568 DX=-0 3434 DX=-0.3350 DX=-0. 3434 DX=-0. 1630 DX=-0. 3218 DX=-0. 1630 DX=-0.3602 DX=-0. 3602 DX=-0 .2193 DX=-0. 1862 DX=-0. 1084 DX=-0. 0201 DX=-0. 0201 DX=-0. 1084 DY=0.0246 DY=0. 4398 DY=0. 4316 DY=0. 4152 DY=0.4050 DY=0.2940 DY=O0.3229 DY=0. 2700 DY=0.1991 DY=0. 1626 DY=0. 0246 DY=0.4398 DY=0. 4316 DY=0. 4152 DY=0.4050 DY=0. 2940 DY=0.3229 DY=0.2700 DZ=0.0000 DZ=0.0000 DZ=0.0000 DZ=0.0000 DZ=0. 0000 DZ=0.0000 DZ=0. 0000 DZ=0. 0000 DZ=0. 0000 DZ=0 .0000 DZ=0. 0000 DZ=0. 0000 DZ=0. 0000 DZ=0. 0000 DZ=0. 0000 DZ=0. 0000 DZ=0.0000 DZ=0. 0000 DY=~0.1991 DZ=~0.0000 File No.: VY-16Q-307 Revision:
0 Page A9 of A51 F0306-0I RO Structural Integrity Associates, Inc.I AMVT CA=20 PT=336 DX=-0.0201 DY=0.1626 DZ=0.0000 AMVT CA=21 PT=336 DX=-0.0413 DY=0.3229 DZ=0.0000 AMVT CA=22 PT=336 DX=-0.3434 DY=0.2700 DZ=0.0000 u AMVT CA=23 PT=336 DX=-0.2211 DY=0.1991 DZ=0.0000 AMVT CA=24 PT=336 DX=-0.0201 DY=0.1626 DZ=0.0000*NOTE SAFE END FROM NODES 838 TO 336*NOTE CONNECTION TO VESSEL AT NODE 336.*NOTE OD AND WALL THICKNESS FOR SAFE END TAKEN FROM GE CALC*NOTE WEIGHT BASED ON THICKNESS---------------------
*END REGION 6 GEOMETRY TO NOZZLE NODE 336---------------------
-------------------------------
*BEGIN REGION 4 TRANSIENT CARDS & GEOMETRY HEADER TO NOZZLE NODE 366* -------------------
*GROUP 4 HEADER TO NOZZLE NODE 366 INCL FN=Z:\SISJ-PROJECTS\VY-16Q\RevO\REG4.INP JUNC PT=210 CROS CD=20 BRAN PT=240 DX=0.1786 DY=0.0 DZ=I.7 TANG PT=250 DX=0.3 DZ=2.853 EW=O BRAD PT=255 RA-4.578 EW=0 *NOTE BEND RADIUS IS 4.578 FEET.TANG PT=340 DX=1.799 DZ=3.108----------------
1------*END REGION 4 GEOMETRY HEADER TO NOZZLE NODE 366---------------------
* ...I,[*--------------------------
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*BEGIN REGION 5 TRANSIENT CARDS & GEOMETRY RISER TO NOZZLE NODE 366-------------------------------
*GROUP 5 RISER TO NOZZLE NODE 366 INCL FN=Z:\SISJ-PROJECTS\VY-16Q\RevO\REG5.INP TANG PT=349 DX=0.71 DZ=I.23 EW=0 CRED PT=347 DX=0.75 DZ=1.3 AN=30 CROS CD=15 TANG PT=343 DX=0.5525 DZ=0.957 EW=1 BRAD PT=410 RA=1.5 EW=l TANG PT=360 DX=3.483 DZ=2.011 EW=I MATL CD=403.316 BRAD PT=361 RA=I.5 EW=1 MATL CD=376.316 CROS CD=15 TANG PT=362 DY=3.18 TANG PT=364 DY=8.56 EW=1l MATL CD=403.316 BRAD PT=365 RA=1.5 EW=1* ---------------------------*END REGION 5 GEOMETRY RISER TO NOZZLE NODE 366----------
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-------------------------------
*BEGIN REGION 6 TRANSIENT CARDS & GEOMETRY TO NOZZLE NODE 366-------*GROUP 6 TO NOZZLE NODE 366 INCL FN=Z:\SISJ-PROJECTS\VY-16Q\RevO\REG6.INP File No.: VY-16Q-307 Page A10 of A51 I Revision:.
0 F0306-0 I RO I V Structural Integrity Associates, Inc.MATL TANG CROS TANG CROS TANG CROS TANG CROS TANG NOZZ AMVT AMVT AMVT AMVT AMVT AMVT AMVT AMVT AMVT AMVT AMVT AMVT AMVT AMVT AMVT AMVT AMVT AMVT AMVT AMVT AMVT AMVT AMVT AMVT CD=376. 316 PT=868 D CD=16 PT=867 D CD=17 PT=866 D CD=18 PT=865 D.CD=19 PT=366 D: PT=366 CA=1 CA=2 CA=3 CA=4 CA=5 CA=6 CA=7 CA= 8 CA=9 CA=10 CA=11 CA=12 CA=13 CA=14 CA=15 CA=16 CA=17 CA=18 CA=19 CA=20 CA=21 CA=22 CA=23 CA=24 X=1.8 DZ=-3.1 X=0.4375 DZ=-0.76 EW=1 X=0.185 DZ=-0.32 EW=1 X=0.265 DZ=-0.46 EW=1 X=0.352 .DZ=-0.61 EW=1 PT=366 PT=366 PT=366 PT=366 PT=366 PT=366 PT=366 PT= 3 66, PT=366 PT=366 PT=366 PT=366 PT=366 PT=366 PT=366 PT=366 PT=366 PT=366 PT=366 PT=366 PT=366 PT=366 PT=366 PT=366 DX=-0.0101 DX=-0.180.0 DX=-0. 1783 DX=-0. 1716 DX=-0. 1783 DX=-0. 1716 DX=-0. 1674 DX=-0. 1716 DX=-0. 0815 DX=-0. 1609 DX=-0. 0815 DX=-0. 1800 DX=-0. 1800 DX=-0. 1097 DX=-0. 0931 DX=-0. 0542 DX=-0. 0101 DX=-0. 0101 DX=-0. 0542 DX=-0. 0101 DX=-0. 0207 DX=-0. 1716 DX=-0. 1105 DX=-0 0101 DY=0.0246 DY=0. 4398 DY=0. 4357 DY=0. 4193 DY=0. 4357 DY=0. 4193 DY=0. 4091 DY=0 4193 DY=0. 1991 DY=0.3930 DY=0. 1991 DY=0. 4398 DY=0. 4398 DY=0. 2678 DY=0. 2275 DY=0. 1324 DY=0. 0246 DY=0. 0246 DY=0. 1324 DY=0. 02.46 DY=0.0505 DY=0. 4193 DY=0.2700 DY=0.0246 DZ=0.0174 DZ=0: 3120 DZ=0. 3091 DZ=0.2974 DZ=0. 3091 DZ=0.2974 DZ=0.2902 DZ=0.2974 DZ=0. 1412 DZ=0. 2788 DZ=0. 1412 DZ=0. 3120 DZ=0. 3120 DZ=0. 1899 DZ=0. 1613 DZ=0.0939 DZ=0 .0174 DZ=0. 0174 DZ=0. 0939 DZ=0 .0174 DZ=0. 0358 DZ=0.2974 DZ=0. 1915 DZ=0.0174* ------------------
*END REGION 6 GEOMETRY TO NOZZLE NODE 366----------------------
-- -*BEGIN REGION 4 TRANSIENT CARDS & GEOMETRY HEADER TO NOZZLES NODE 326 & 316------------------------------
*GROUP 4 HEADER TO NOZZLES NODE 326 & 316 INCL FN=Z:\SISJ-PROJECTS\VY-16Q\RevO\REG4.INP JUNC PT=210 CROS CD=20 BRAN PT=260 DX=0.1786 DY=0.0 DZ=-1.7 TE=2 TANG PT=270 DX=0.3 DZ=-2.853 EW=0 BRAD PT=275.RA=4.578 EW=0 TANG PT=320 DX=1.799 DZ=-3.108---------------------
*END REGION 4 GEOMETRY HEADER TO NOZZLES NODE 326 & 316*---------------------------
-*BEGIN REGION 5 TRANSIENT CARDS & GEOMETRY RISER TO NOZZLE NODE 316------------------------------
File No.: VY-16Q-307 Revision:
0 Page All of A51 F0306-O1 RO V Structural Integrity Associates, Inc.*GROUP 5 RISER TO NOZZLE NODE 316 INCL FN=Z:\SISJ-PROJECTS\VY-16Q\Rev0\REG5.INP TANG PT=319 DX=0.71 DZ=-1.23 EW=1 CRED PT=317 DX=0.75 DZ=-1.3 AN=30 CROS CD=15 TANG PT=313 DX=0.5525 DZ=-0.957 EW=1 BRAD PT,=400 RA=1.5 EW=1 TANG PT=310 DX=3.483 DZ=-2.011 EW=1 MATL CD=403.316 BRAD PT=311 RA=1.5 EW=I MATL CD=376.316 CR0S CD=15 TANG PT=312 DY=4.74 TANG PT=314 DY=6.99 EW=I MATL CD=403.316 BRAD PT=315 RA=1.5 EW=1----------------------
*END REGION 5 GEOMETRY RISER TO NOZZLE NODE 316---------------------
-------------------------------
*BEGIN REGION 6 TRANSIENT CARDS & GEOMETRY TO NOZZLE NODE 316* ---------------------
*GROUP 6 TO NOZZLE NODE 316 INCL FN=Z:\SISJ-PROJECTS\VY-16Q\RevO\REG6.INP MATL CD=376.316 TANG PT=818 DX=1.84 DZ=3.19 CROS CD=16 TANG PT=817 DX=0.4375 DZ=0.76 EW=1 CROS CD=17 TANG PT=816 DX=0.185 DZ=0.32 EW=1 CROS CD=18 TANG PT=815 DX=0.265 DZ=0.46 EW=1 CROS .CD=19 TANG PT=316 DX=0.352 DZ=0.61 EW=I I I I I U I I U I I I I I I U I I NOZZ AMVT AMVT AMVT AMVT AMVT AMVT AMVT AMVT AMVT AMVT AMVT AMVT AMVT AMVT AMVT AMVT AMVT AMVT AMVT AMVT AMVT AMVT PT=316 CA=I CA=2 CA=3 CA=4 CA=5 CA=6 CA=7 CA=8 CA=9 CA=-I 0 CA=11 CA=12 CA=13 CA= 14 CA=15 CA=1 6 CA=I7 CA 18 CA=19 CA 20 CA=21 CA=22 PT=316 PT=316 PT=316 PT=316 PT=316 PT=316 PT=316 PT=316 PT=316 PT=316 PT=316 PT=316 PT=316 PT=316 PT=316 PT=316 PT=316 PT=316 PT=316 PT=316 PT=316 PT=316 DX=-0. 0101 DX=-O. 1800 DX=-0. 1783 DX=-O. 1716 DX=-0. 1783 DX=-O. 1716 DX=-O. 1674 DX=-O. 1716 DX=-O. 08 15 DX=-0. 1609 DX=-0. 0815 DX=-0. 1800 DX=-0. 1800 DX=-0. 1097 DX=-0. 0931 DX=-0. 0542 DX=-0. 0101 DX=-0. 0101 DX=-0.0542 DX=-0.0101 DX=-0. 0207 DX=-0. 1716 DY=0. 0246 DY=0. 4398 DY=0.4 357 DY=0. 4193 DY=0..4 357 DY=0. 4193 DY=0. 4091 DY=0. 4193 DY=0. 1991 DY=0. 3930 DY=0. 1991 DY=0. 4398 DY=0.4398 DY=0 2678 DY=0. 2275 DY=0. 1324 DY=0. 0246 DY=0. 0246 DY=0. 1324 DY=0. 0246 DY=0. 0505 DY=0. 4193 DZ=-O. 0174 DZ=-0.3120 DZ=-0. 3091 DZ=-0. 2974 DZ=-0. 3091 DZ=-0 .2974 DZ=-0.2902 DZ=-0 .2974 DZ=-0. 1412 DZ=-0.2788 DZ=-0. 1412 DZ=-0. 3120 DZ=-0.3120 DZ=-0. 1899 DZ=-0. 1613 DZ=-0.0939 DZ=-0.0174 DZ=-0. 0174 DZ=-0.0939 DZ=-0. 0174 DZ=-0. 0358 DZ=-0 .2974 File No.: Revision: VY-16Q-307 0 Page A12 of.A51 I I F0306-O1 RO IStructural Integrity Associates, Inc.AMVT CA=23 PT=316 DX=-0.1105 DY=0.,2700 DZ=-0.1915 AMVT CA=24 PT=316 DX=-0.0101 DY=0.0246 DZ=-0.0174
*END REGION 6 GEOMETRY TO NOZZLE NODE 316-----------------
---*BEGIN REGION 5 TRANSIENT CARDS & GEOMETRY RISER TO NOZZLE NODE 346----------------------------
*GROUP 5 RISER TO NOZZLE NODE 346 INCL FN=Z:\SISJ-PROJECTS\VY-16Q\RevO\REG5.INP JUNC PT=340 CROS CD=15 BRAN PT=342 DY=1.36 TE=2 TANG PT=344 DY=10.39 EW=0 MATL CD=403.316 BRAD PT=345 RA=1.5 EW=1---------------
----------
*END REG ION 5 GEOMETRY RISER TO NOZZLE-NODE 346---------------------
* ------------------------------
*BEGIN REGION 6 TRANSIENT CARDS & GEOMETRY TO----------------------------
7*GROUP 6 TO NOZZLE NODE 346 INCL FN=Z:\SISJ-PROJECTS\VY-16Q\RevO\REG6.INP MATL CD=376.316 NOZZLE NODE 346 TANG CROS TANG CROS TANG CROS TANG CROS TANG NOZZ AMVT AMVT AMVT AMVT AMVT AMVT AMVT AMVT AMVT AMVT AMVT AMVT AMVT AMVT AMVT AMVT AMVT AMVT AMVT AMVT AMVT PT=848 DX=3.17 DZ=-1.83 CD=16 PT=847 DX=0.758 DZ=-0.4375 EW=1 CD=17 PT=846 DX=0.32 DZ=-0..185 EW=1 CD=18 PT=845 DX=0.46 DZ=-0.265 EW=1 CD=19 PT=346 DX=0.61 DZ=-0.352 EW=1 PT=346 CA=1 CA=2 CA=3 CA= 4 CA=5 CA=6 CA=7 CA= 8 CA=19 CA=10 CA=1I CA-12 CA=13 CA-14 CA=15 CA=' 6 CA=17 CA=18 CA=19 CA=20 CA=21 PT=346 PT=346 PT=346 PT=346 PT=346 PT=346 PT=346 PT=346 PT=346 PT=346 PT=346 PT=346 PT=346 PT=346 PT=346 PT=346 PT=346 PT=346 PT=346 PT=346 PT=346 DX=-0. 0174 DX=-O. 3120 DX=-O. 3091 DX=-0.2974 DX=-0. 3091 DX:-0.2974 DX=-O. 2902 DX=-O.2974 DX=-0. 1412 DX=-0. 2788 DX=-0.1412 DX=-0 .3120 DX=-0. 3120 DX=-0. 1899 DX=-0.1613 DX=-0. 0939 DX=-0. 0174 DX=-0. 0174 DX=-0. 0939 DX=-0. 0174 DX=-0. 0358 DY=0. 0246 DY=0. 4398 DY=0. 4357 DY=0. 4193 DY=0. 4357 DY=0. 4193 DY=0. 4091 DY=0. 4193 DY=0. 1991 DY=0 3930 DY=0. 1991 DY=0. 4398 DY=0. 4398 DY=0.2678 DY=0. 2275 DY=0. 1324 DY=0.0246 DY=0. 0246 DY=0. 1324 DY=0.0246 DY=0.0505 DZ=0. 0101 DZ=0. 1800 DZ=0. 1783 DZ=0. 1716 DZ=0. 1783 DZ=0. 1716 DZ=0 1674 DZ=0.1716 DZ=0. 0815 DZ=0. 1609 DZ=0.0815 DZ=0. 1800 DZ=0. 1800 DZ=0.1097 DZ=0.0931 DZ=0. 0542 DZ=0.0101 DZ=0.0101 DZ=0. 0542 DZ=0.0101 DZ=0.0207 File No.: VY-16Q-307 Revision:
0 Page A13 of A51 F0306-O1 RO V Structural Integrity Associates, Inc.AMVT CA=22 PT=346 DX=-0.2974 DY=0.4193 DZ=0.1716 AMVT CA=23 PT=346 DX=-0.1915 DY=0.2700 DZ=0.1105 AMVT CA=24 PT=346 DX=-0.0174 DY=0.0246 DZ=0.0101*END REGION 6 GEOMETRY TO NOZZLE NODE 346---------------------
------------------------------
*BEGIN REGION 5 TRANSIENT CARDS & GEOMETRY RISER TO NOZZLE NODE 326-------------------------------
*GROUP 5 RISER TO NOZZLE NODE. 326 INCL FN=Z:\SISJ-PROJECTS\VY-16Q\Rev0\REG5.INP JUNC PT=320 CROS CD=15 BRAN PT=322 DY=1.42 TE=2 TANG PT=324 DY=10.33 EW=1 MATL CD=403.316 BRAD PT=325 RA=1.5 EW=1*--------------------------
*END REGION 5 GEOMETRY RISER TO NOZZLE NODE 326---------------------
*----------------------------
*BEGIN REGION 6 TRANSIENT CARDS & GEOMETRY TO* ------------------------------
*GROUP 6 TO NOZZLE NODE 326 INCL FN=Z:\SISJ-PROJECTS\VY-16Q\RevO\REG6.INP NOZZLE NODE 326 I I I I I I I I I I I I I I I I I MATL TANG CROS TANG CROS TANG CROS TANG CROS TANG NOZZ AMVT AMVT AMVT AMVT AMVT AMVT AMVT AMVT AMVT AMVT AMVT AMVT AMVT AMVT AMVT AMVT AMVT AMVT AMVT AMVT CD=376. 316 PT=828 DX=3.18 DZ=1.84 CD=16 PT=827 DX=0.758 DZ=0.4375 EW=1 CD=17 PT=826 DX=0.32 DZ=0.185 EW=1 CD=18 PT=825 DX=0.46 DZ=0.265 EW=1 CD=19 PT=326 DX=0.61 DZ=0.352 EW=1 PT=326 CA=1 CA=2 CA=3 CA=4 CA=5.CA=6 CA=7 CA=8 CA=9 CA=10 CA=11 CA=12 CA=13 CA=14 CA=1 5 CA=1 6 CA=17 CA=18 CA=1 9 CA=20 PT=326 PT=326 PT=326 PT=326 PT=326 PT=326 PT=326 PT=326 PT=326 PT=326 PT=326 PT=326 PT=326 PT=326 PT=326 PT=326 PT=326 PT=326 PT=326 PT=326 DX=-0.0174 DX=-0.3120 DX=-0. 3091 DX=-0.2974 DX=-0. 3091 DX=-0.2974 DX=-0.2902 DX=-0.2974 DX=-0. 1412 DX=-0. 2788 DX=-0. 1412 DX=-0.3120 DX:-0.3120.
DX=-0. 1899 DX=-0. 1613 DX=-0.0939 DX=-0.0174 DX=-0. 0174 DX=-0.0939 DX=-0. 0174 DY=0. 0246 DY=0. 4398 DY=0.4357 DY=0.4193 DY=0.4357 DY=0.4193 DY=0. 4091 DY=0. 4193 DY=0.1991 DY=0.3 930 DY=0.1991 DY=0. 4398 DY=0. 4398 DY=0.2678 DY&#xfd;=0. 2275 DY=0. 1324 DY=0. 0246 DY=0.0246 DY=0.1324 DY=0.0246 DZ=-0.0101 DZ=-0. 1800 DZ=-0. 1783 DZ=-O. 1716 DZ=-0. 1783 DZ=-0.1716 DZ=-0. 1674 DZ=-0. 1716 DZ=-0. 0815 DZ=-0 .1609 DZ=-0.0815 DZ=-0. 1800 DZ=-0. 1800 DZ=-0.1097 DZ=-0. 0931 DZ=-0. 0542 DZ=-O.0101 DZ=-0.0101 DZ=-0. 0542 DZ=-0.0101 File No.: VY-16Q-307 Revision:
0 Page A14 of A51 I I F0306-O1 RO U Structural Integrity Associates, Inc.AMVT CA=21 PT=326 DX=-0.0358 DY=0.0505 DZ=-0.0207 AMVT CA=22 PT=326 DX=-0.2974 DY=0.4193 DZ=-0.1716 AMVT CA=23 PT=326 DX=-0.1915 DY=0.2700 DZ=-0.1105 AMVT CA=24 PT=326 DX=-0.0174 DY=0.0246 DZ=-0.0101
*END REGION 6 GEOMETRY TO NOZZLE NODE 326*----------------------
! -*BEGIN REGION 7A TRANSIENT CARDS & GEOMETRY TO RHR SUPPLY VALVE NODE 550*GROUP 7 TO RHR SUPPLY VALVE NODE 550 INCL FN=Z:\SISJ-PROJECTS\VY-16Q\Rev0\REG7A.INP MATL CD=376.316 JUNC PT=500* CROS CD=25 BRAN PT=502 DX=1.67 EW=0 TE=1 TANG PT=506 DX=2.53 EW=0 MATL CD=403.316
* BRAD PT=,507 RA=1.67 EW=1 MATL CD=376..316 TANG PT=508 DZ=-4.01 TANG PT=515 DZ=-4.53 EW=1 MATL CD=403.316 BRAD PT=520 RA=1.67 EW=1 MATL CD=376.316 CROS CD=26 VALV PT=525 DX=-3.34 PL=1 JUNC PT=525 VALV PT=530 DX=-1.99 PL=2 EW=1 JUNC PT=525.RIGD PT=526 DY=2.5 LUMP PT=526 MA=7.569 JUNC PT=530 CROS CD=25 TANG PT=540 DX=-1.13 EW=1 CROS CD=26 VALV PT=545 DX=-1.97 PL=1 JUNC PT=545 RIGD PT=547 DY=2.5 LUMP PT=547 MA=7.355 JUNC PT=545 VALV PT=550 DX=-1.98 PL=2 EW=1*END REGION 7A GEOMETRY TO RHR SUPPLY VALVE NODE 550*BEGIN REGION 7B TRANSIENT CARDS & GEOMETRY FROM RHR SUPPLY VALVE* TO PENET. NODE 565------------------------------
*GROUP 17 FROM RHR SUPPLY VALVE TO PENET. NODE 565 INCL FN=Z:\SISJ-PROJECTS\VY-16Q\RevO\REG7B.INP CROS CD=25 MATL CD=106 TANG PT=555 DX=-3.36 EW=1 BRAD PT=556 RA=1.67 EW=I TANG PT=560 DY=-10.17 EW=1 BRAD PT=561 RA=1.67 EW=1 File No.: VY-16Q-307 Page A15 of A51 Revision:
0 F0306-01 RO Structura Integrity Associates, Inc.TANG PT=563 DZ=-6.92 TANG PT=565 DZ=-6.92---------------------
*END REGION 7B GEOMETRY FROM RHR SUPPLY VALVE TO PENET. NODE 565---------------------
-----------------
-------------
*BEGIN REGION 8 TRANSIENT CARDS & GEOMETRY FOR 4 INCH BYPASS-------------------------------
*GROUP 8 4 INCH BYPASS INCL FN=Z:\SISJ-PROJECTS\VY-16Q\RevO\REG8.INP
*NOTE CODING FOR 4 INCH BYPASS STARTS HERE JUNC PT=152 CROS CD=27 MATL CD=376.316 BRAN PT=700 DX=-l.19 TE=4 TANG PT=702 DX=-0.61 TANG PT=703 DX=-I.43 EW=O MATL CD=403.316, BRAD PT=704 RA=0.5 EW=0 MATL CD=376.316 TANG. PT=705 DZ=-5.08*NOTE CONSTANT SUPPORT HAll AT NODE 705 TANG PT=721 DZ=I.12 TANG PT=706 DZ=2.47 TANG PT=707 DZ=I.03 TANG PT=708 DZ=0.34 TANG PT=709 DZ=0.38 JUNC PT=707 BRAN PT=710 DY=0.34 TE=I CROS CD=28 VALV PT=712 DY=0.71 MA=0.3669 PL=I *AL=$Vl VALV PT=715 DZ=-3.5 MA=0.1831 PL=3 JUNC PT=712 VALV PT=714 DY=0.71 PL=2 CROS CD=27 TANG PT=723 DY=4.19 MATL CD=403.316 BRAD PT=716 RA=0.5 MATL CD=376.316 TANG PT=718 DX=I.48 TANG PT=720 DX=0.56 BRAN PT=176 DX=I.19 TE=4************CODING FOR STRUTS RDA5 AND VABI JUNC PT=170 CROS CD=40 *OD=4.5 inch RIGD PT=725 DP=0 DX=-0.583 DY=I,84 *AL=$RD CROS CD=41 *OD=2.875 inch RIGD PT=715 DP=0 DX=-2.67 DY=-0.79 RIGD PT=721 DP=0 DY=-I.05 *AL=$VABI$
*************CODING FOR RDAI STRUT FOLLOWS CROS CD=42 *OD=28.339 inch JUNC PT=I75 RIGD PT=I73 DP=0 DY=-3.5 DZ=0.34 CROS CD=41 *OD=2.875 inch RIGD PT=708 DP=0 DX=-3.21 *AL=$RDAI$
* ---------------------------
*END REGION .8 GEOMETRY FOR 4 INCH BYPASS*-------------------
I I I I I I I I I I I I I I IV2-54A$FOLLOW AS$File No.: VY-16Q-307 Revision:
0 Page A16 of A5l I i F0306-01 RO K Structural Integrity Associates, Inc.I.*----------------------
-* BEGIN REGION 9A TRANSIENT CARDS & GEOMETRY FOR RHR RETURN FROM TEE TO VALVE NODE 660-------------------------------
*GROUP 9 RHR RETURN. FROM TEE TO VALVE NODE 660 INCL FN=Z: \SISJ-PROJECTS\VY-16Q\Rev0\REG9A.
INP*NOTE CODING FOR RHR RETURN STARTS HERE CROS CD=29 JUNC PT=600 MATL CD=376.316 BRAN PT=602 DX=-3.8i23 TE=I MATL CD=403.316 BRAD PT=610 RA=2 EW=1 TANP DY=4 BRAD PT=612 RA=2 EW=I MATL CD=376.316 TANG PT&#xfd;614 DZ=-I0.38 EW=I MATL CD=403.316 BRAD PT&#xfd;615 RA=10 EW=1 S MATL CD&#xfd;376. 316 TANG PT=620 DX=5.98 DZ=-3.45 EW=1*NOTE*NOTE VARIABLE SPRING H104 AT NODE 620* *NOTE 3 *NOTE VALVE V10-81A DATA FROM 5920-4590 WEIGHT -6845.#*NOTE WEIGHT APPLIED AT ESTIMATED CENTER OF GRAVITY (NODE 623)CROS CD&#xfd;30 VALV PT=622 DX=1.98 DZ=-1.15 PL=1 *AL=$VALVE V10-81A$JUNC PT=622 VALV PT=624 DX=1.98 DZ=-1.15 PL=2 EW=1 JUNC PT=622 RIGD PT=623 DY=2.5 LUMP PT=623 MA=7.32 *VALVE ACTUATOR CROS CD=29 JUNC PT=624 TANG PT=625 DX=1.867 DZ=-1.078 TANG PT=-630 DX=2.598 DZ=-1.5 EW=1 MATL CD=403.316 BRAD PT=631 RA=3 EW=--MATL CD=376.316 TANG PT=640 DZ=-4.54 EW=I MATL CD=403.316 BRAD PT=641 RA=2 EW=l MATL CD=376.316
* NOTE VALVE V10-46A DATA FROM 5920-4718 WEIGHT -5295.#CROS CD=30 VALV PT=655 DX=-3.79 PL=1 TA=2 *AL=$VALVE V10-46A$LUMP PT=655 MA=5.77---------------------
*END REGION 9A GEOMETRY FOR RHR RETURN FROM TEE TO VALVE NODE 660*BEGIN REGION 9B TRANSIENT CARDS & GEOMETRY FOR RHR RETURN FROM VALVE NODE 660 TO PENET. NODE 675*GROUP 19 RHR RETURN FROM VALVE NODE 660 TO PENET. NODE 675 INCL FN=Z:\SISJ-PROJECTS\VY-16Q\RevO\REG9B.INP File No.: VY-16Q-307 Page A17 of A51 Revision:
0 F0306-01 RO V Structural Integrity Associates, Inc.*NOTE*NOTE VARIABLE SPRING HI05 AT NODE 655*NOTE VALV PT=660 DX=-1.79 PL=2 EW=1*NOTE SPEC CHANGE TO CARBON STEEL MATL CD=106 CROS CD=29 TANG PT=661 DX=-I TANG PT=663 DX=-3.31 EW=1 BRAD PT=665 RA=2 EW=1 TANG PT=670 DY=-10.5 DZ=0.38 EW=1 BRAD PT=671 RA=2 EW=1 TANG PT=673 DZ=-7.74 TANG PT=675 DZ=-7.74*--------------------------
*END REGION 9B GEOMETRY FOR RHR RETURN FROM VALVE NODE 660 TO PENET. NODE 675--------------------
*--------------------------
***STRESS INDICES AT CROSS POINT--------------------
INDI AT=210 AF=195 B1=0.5 C1=1 INDI AT=210 AF=215 B1=0.5 C1=1 INDI AT=210 AF=240 B1=0.5 C1=1 INDI AT=210 AF=260 B1=0.5 C1=1*--------------------
*** SUPPORTS* ---------------------------
K1=4 K1=4 K1=4 K1=4 B2=2.256 C2=3.024 K2=1 B2=2.256 C2=3.024 K2=1 82=1.805 C2=3.024 K2=1 B2=1.805 C2=3.024 K2=1 C3=1 C3=1 C3=1 C3=1 K3=1 K3=1 K3=1 K3=1 CP=0. 5 CP=0. 5 CP=0.5 CP=0. 5 I I I I I I i I I I I I I I RSTN RSTN RSTN ROTR ROTR ROTR RSTN RSTN RSTN ROTR ROTR ROT.R SNUB SNUB SNUB PT=675 PT=675 PT=675 PT=675 PT=675 PT=675 PT=565 PT=565 PT=565 PT=565 PT=565 PT=565 PT=12 PT=12 PT=190 PT=190 DX=I DY=1 DZ=I RX=1 RY=I RZ=1 DX=I1 DY=1 DZ=I RX=I RY=1 RZ=1 DZ=-I DX=1 DX=-1 DZ=1 SP=16000 SP=16000 SP=23000 SP=300000 SP=300000 SP=340000 SP=16000 SP=16000 SP=23000 SP=300000 SP=300000 SP=340000*RHR*RHR*RHR*RHR*RHR*RHR*RHR*RHR*RHR*RHR*RHR*RHR SUPPLY SUPPLY SUPPLY SUPPLY SUPPLY SUPPLY SUPPLY SUPPLY SUPPLY SUPPLY SUPPLY SUPPLY PENET.PENET.PENET.PENET.PENET.PENET.PENET.PENET.PENET.PENET.PENET.PENET.SP=1000 SP=1000 SP=1000 SP=1000*AL=$SNUBBER
*AL=$SNUBBER
*AL=$SNUBBER
*AL=$SNUBBER SS-7A-I$SS-7A-2$SS-6-Al$SS-6-A2$VSUP PT=20 DY=l FO=24.8 SP=2.664 *AL=$VARI.
SUPT. HA-1$CSUP CSU P CSUP CSUP CS UP CSU P CSUP PT=27 PT=42 PT=56 PT=69 PT=63 PT=160 PT=705 DY=I DY=I DY=I DY=I DY=I DY=-I DY=1 FO=8. 3 F0=8. 3 FO=18.05 FO=18.0 FO=18. 02 FO=11. 8 po=0. 960 KP=0.01 KP=0.01 KP=0.01 KP=0.01 KP=0. 01 KP=0 .01 KP=0.01*AL=$CONST.
*AL=$CONST.
*AL=$CONST.
*AL=$CONST.
*AL=$CONST.
*AL=$CONST.
*AL=$CONST.
SUPT.SUPT.SUPT.SUPT.SUPT.SUPT.SUPT.H-8-Al$H-8-A2$HA3 FOR PUMPS HA4 FOR PUMPS*HA5 FOR PUMP$HA-9 & HA-10S HA-lI ON 4 INCH BYPASS$VSUP PT=184 VSUP PT=343 DY:l FO=36.0 SP=3.542*AL=$VARI.
SUPT. HA-2$*AL=$VARI.
SUPT. HAI3$DY=l FO=7. 1 SP=3. 014 File No.: VY-'16Q-307 Revision:
0 Page AI8 of A51 I I F0306-OI RO V Structural integrity Associates, Inc.VSUP PT=313 DY=l FO=7.1 SP=3.014 *AL=$VARI.
SUPT. HAI4$VSUP VSUP VSUP PT=530 PT=620 PT'=655 DY=l SP=9.420 FO=26.0 DY=l SP=7.084 FO=14.9 DY=l SP=4.710 FO=22.0*AL=$HANGER H109 RHR SUPPLY VALVE$*AL=$HANGER H104 RHR RETURN VALVE$*AL=$HANGER H105 RHR RETURN VALVES RSTN PT=15 RSTN PT=16 ENDP DY=0.7071 DZ=-0.7071 DX=-0.707l DY='0.7071 SP=6000 SP=6000*RECIRC PUMP*RECIRC PUMP RHR 15.inp IDEN JB=3 *Job number (1 to 999 CD=I *I=ASME Class 1 GR=-Y *Direction of gravit VA=0 *0=Calculate IU=l *Input units OU=1 *Output units CH=$ *Delimiter character AB=T *FREE errors = abort PL=$Vermont Yankee$EN=$RVP$TITL BL=3 *Modeling option: 9)y 2=Verify 1=USA l=USA* 3 = uniform mass for static analysis lumped mass for dynamic analysis* rotational inertia ignored GL=I *Report forces/moment
.0=Global SU=l *Support summary 0=No CV=I5 *Code version -See Manual HS=l *Highest 20 stress ratios for each case MD=l *Hot modulus J6=l *File generated by program TI=$Vermont Yankee Recirculation
$$Fatigue Analysis$FREQ RF=l RP=8 FR=36 MP=20 RC=0 MX=70 TI=$SEISMIC$
l=Local l=Yes 2=G et L**** THERMAL CYCLE LOAD CASES****LCAS LCAS LCAS LCAS LCAS LCAS LCAS LCAS LCAS LCAS LCAS LCAS LCAS.LCAS LCAS LcAs LCAS LCAS LCAS LCAS LCAS LCAS RF=0 RF=0 RF=0 RF=0 RF=0 RF=0 RF=0 RF=0 RF=0 RF=0 RF=0 RF=O RF=0 RF=0 RF=0 RF=0 RF=0 RF=0 RF=0 RF=0 RF=0 RF=0 CA=1 CA=2 CA=3 CA=4 CA=5 CA=6 CA=7 CA=8 CA=9 CA=f0 CA=I1 CA=12 CA=13 CA=14 CA=I 5 CA=16 CA=17 CA=18 CA=I 9 CA=20 CA=21 CA=22 TY=0 TY=0 TY=0 TY=0 TY=0 TY=0, TY=0 TY=0 TY=0 TY=0 TY=0 TY=0 TY=0 TY=0 TY=0 TY=0 TY=0 TY=0 TY=0 TY=0 TY=0 TY=0 TI=$LC-l$TI~=$LC-2$
TI=$LC-3$rI=$LC-4$[rI=$LC-5$
TI=-$LC-6$
rI=$LC-7$rI=$LC-8$CI=$LC-9$Tl=$LC-10$
T I=$ LC -11$TI=$LC-12$
TI=$LC-13$
TI=$LC-14$
TT=$LC-15$
TT=$LC-16$
TI=$LC-1?$
TI=$LC-18$
TI=$LC-19.$
TI=$LC-20$
TI=$LC-21$
TI=$LC-22$
*TC-l*TC-2*TC-3*TC-4*TC-5*TC-6*TC-7*TC&#xfd;8*TC-9*TC-10*TC-II*TC-12*TC-13*TC-14*TC-15*TC-16*TC-17*TC-18*TC-19*TC-20*TC-21*TC-22 File No.: VY-16Q-307 Revision:.
0 Page A19 of A51 F0306-01 RO Structural Integrity Associates, Inc.LCAS RF=0 CA=23 TY=0 TI=$LC-23$
LCAS RF=0 CA=24 TY=0 TI=$LC-24$
LCAS RF=0 CA=25 TY=0 TI=$LC-25$
**** WEIGHT CASES*****TC-23*TC-24*TC-25 LCAS CA=101 LCAS CA=102 RF=I TY=3 TI=$OPERATING WEIGHT$RF=2 TY=4 TI=$HYDROTEST WEIGHT$THERMAL TRANSIENT CASES****TCAS TCAS TCAS TCAS TCAS TCAS TCAS TCAS TCAS TCAS TCAS TCAS TCAS TCAS TCAS TCAS TCAS TCAS TCAS TCAS TcAs TCAS TCAS TCAS TCAS CA=201 CA=202 CA=203 CA=204 CA=205.CA=206 CA=207 CA=208 CA=209 CA=210 CA=211 CA=212 CA=213 CA=214 CA=215 CA=216 CA=217 CA=218 CA=219 CA=220 CA=221 CA=222 CA=223 CA=224 CA=225 TI=$Design Hydrotest
(+)TI=$Design Hydrotest
(-)TI=$Startup TI=$TRoll
& Inc. PWRI TI=$TRo11
& Inc. PWR2 TI=$LOFWH+TT PWRI TI=$LOFWH+TT:PWR2 TI=$LOFWH+PFWHTR Bypl TI=$LOFWH+PFWHTR Byp2 TI=$LOFWP, ISO Cl DN 1 TI=$LOFWP, ISO Cl UP 1 TI=$LOFWP, ISO Cl DN 2 TI=$LOFWP, ISO Cl UP 2 TI=$Reduction to 0% PWR TI=$Shutdownl TI=$Shutdown2 TI=$Shutdown3 TI=$Shutdown4 TI=$Code Hydrotest TI=$RHR Initiation UP TI=$RHR Initiation DN TI=$Inadvert.
Inj. DOWN TI=$Inadvert.
Inj. UP TI=$Single Relief BD DN Ti=$Single Relief BD UP I I I I I I I I I I SEISMIC CASES****RCAS CA=103 EQ=3 EV=l TY= .SU=I LO=l FX=l FY=l FZ=l TI=$OBE INERTIA$** C**************************
**** LOAD COMBINATION CASES *CCAS RF=1 CA=104 ME=l FL=l Cl=103 CY=l0 CCAS RF=I CA=401 SS=l ME=1 EQ=3 Cl=101 C2=103 CCAS RF=l CA=402 SS=I ME=3 F1=1 C1=103 C2=1 CCAS RF=I CA=403 SS=1 ME=3 F1=-I C1=103 C2=1 TI=$OBE$TI=$EQUATION 9 LEVEL B$TI=$NORMAL+OBE$
TI=$NORMAL-OBE$
I I I I I I I I**** LOAD SETS**************
LSET RF=l LSET RF=2 LSET RF=3 LSET RF=3 FC=0 RP=I CY=120 FC=0 RP=I CY=120 FC=0 RP=1 CY=300 FC=0 RP=1 CY=579 PR=I MO=l PR=2 MO=2 PR=3 MO=3 PR=4 MO=4 TR=201 TR=-202 TR=203 TR=-204 TI=$Design Hydrotest
(+)LS-I$TI=$Design Hydrotest
(-)LS-2$TI=$Startup LS-3$TI=$TRoll
& Inc. PWR1 LS-4$File No.: VY-16Q-307 Page A20 of A51 Revision:
0 F0306O01 RO C Structural Integrity Associates, Inc.I LSET RF=4 FC=0 RP=1 CY=579 PR=5 MO=5 LSET RF=4 FC=0 RP=1 CY=20 PR=6 MO=6 T.ET RPFA FC=O PP== CY=2 DPR=7 M0=7 LSET LSET LSET LSET LSET LSET LSET LSET LSET LSET LSET LSET LSET LSET LSET LSET LSET LSET RF=5 RF=5 RF=5 RF=11 RF=11 RF=3 RF=3 RF=5 RF=15 RF=16 RF=20 RF=19 RF=20 RF=2 0 RF=5 RF=5 RF=2 3 RF=2 4 FC=0 FC=0 FC=0 FC=0 FC=0 E'C=0 FC=0 FC=0 FC=0 FC=0 FC=0 FC=0 FC=0 FC=0 FC=0 FC=0 FC=0 FC= 0 RP=I RP=I RP=I RP=I1 RP=1 RP=1 RP=1 RP=I RP=1 RP=I RP=I RP=1 RP:I RP=I RP=1 RP=1 RP=1 RP=I CY=70 CY=70 CY=70 CY=20 CY=20 CY=10 CY=300 CY=300 CY=300 CY=300 CY=300 CY=1 CY-300 CY=300 CY=0 CY=0 CY=0 CY=0 PR=8 PR= 9 PR=10 PR=I1 PR=12 PR=13 PR=14 PR=15 PR=16 PR=17 PR=18 PR=19 PR=20 PR=21 PR=22 PR=23 PR=24 PR=25 MO=8 MO=9 MO=10 MO=II MO=12 MO=13 MO=14 MO=15 MO=16 MO=17 MO=18 MO=19 MO=20 MO=21 MO=22 MO=23 MO=24 MO=25/I TR=-205 TR=206 TR=-207 TR=-208 TR=209 TR=-210 TR=211 TR=-212 TR=213 TR=214 TR=-215 TR=-216 TR=-217 TR=-218 TR=219 TR=220 TR=-221 TR=-222 TR=223 TR=-224 TR=225.TI=$TRoll
& Inc. PWR2 LS-5$TI=$LOFWH+TT PWRI LS-6$TI=$LOFWH+TT PWR2 LS-7$TI=$LOFWH+PFWHTR Bypl LS-8$TI=$LOFWH+PFWHTR Byp2 LS*-9$TI=$LOFWP, ISO Cl DN 1 LS-10$TI=$LOFWP, ISO Cl UP 1 LS-11$TI=$LOFWP, ISO Cl DN 2 LS-12$TI=$LOFWP, ISO Cl UP 2 LSL-135 TI=$Reduction to 0% PWR LS-14$TI=$Shutdownl LS-15$TI=$Shutdown2 LS-16$TI=$Shutdown3 LS-17$TI=$Shutdown4 LS-18$TI=$Code Hydrotest LS-19$TI=$RHR Initiation UP LS-20$TI=$RHR Initiation DN LS-215 TI=$Inadvert.
Inj. DOWN LS-22$TI=$Inadvert.
Inj. UP LS-23$TI=$Single Relief BD DN LS-24$TI=$Single Relief BD UP LS-255 LSET RF=2 FC=0 CY=5 FL=I PR=2 MO=402 TI=$NORMAL+OBE LSET RF=2 FC=0 CY=5 FL=1 PR=2 MO=403 TI=$NORMAL-OBE
*FATG AT=500 AF=502*FATG AT=600 AF=602 LS-26$LS-275**** RESPONSE SPECTRA****
SPEC FS=OBE EV=I ME=3 FP=0 TI=$RESPONSE$
LV=I DX=I DY=I DZ=1 DI=X 0.30/0.100 0.40/0.100 0.90/0.20(3.30/0.700 4.40/0.750 4.41/0.90 8.70/1.600 12.00/0.650 17.00/0.40(DI=Y 0.30/0.030 0.40/0.030 0.50/0.05(2.00/0.220 2.40/0.350 3.50/0.35C 8.25/0.330 8.75/0.250 17.50/0.25(0 0 0 0 01 01 1.25/0.400 4.75/1.100 20.00/0.350 0.60/0.075 3.60/0.300 25.00/0.120 0.90/0.150 4.40/0.700 30.00/0.350 2.25/0.450 5.20/1.100 30.00/0.350 1.00/0.075 5.30/0.300 30.00/0.120 1.00/0.250 4.50/0.800 36.00/0.350 2.30/0.700 5.80/1.600 36.00/0.350 1.20/0.100 5.75/0.330 36.00/0.120 1.60/0.250 6.25/1.500 DI=Z 0.30/0.100 1.90/0.600 8.50/1.500 0.40/0.100 3.50/0.600 12.50/0.500 0.50/0.130 3.75/0.700 20.00/0.350 MATERIAL PROPERTIES
**** ***A* ** *G******0B,* ASTM A-106 Grade B, PIPE *MATH MATD MATO MATD MATD MATD MATD MATD CD=106 TE=70 TE=100 TE=200 TE=300 TE=400 TE=500 TE=600 EX=0 EH=29. 5 EH=2 9.3 EH=28.8 EH=2 8.3 EH=2 7.7 EH=27.3 EH=2 6. 7 Grade TP316, TY=1 EX=0. 0 EX=0.20 EX=I.00 EX=l. 90 EX=2.80 EX=3.70 EX=4.70 PIPE *TY=4*C-Si SM=20.0 SM=20. 0 SM=20.0 SM=20.0 SM=20. 0 SM=18. 9 SM=17 .3 SY=35 SY=35 SY=32. 1 SY=31 SY=29. 9 SY=28.5 SY=26. 8* ASME SA-376 MATH CD=376.316 EX=0*16Cr-12Ni-2Mo File No.: VY-16Q-307 Revision:
0 Page A21 of A51 F0306-01RO Structural Integrity Associates, Inc. .MATD TE=70 MATD TE=l00 MATD TE=200 MATD TE=300 MATD TE=400 MATD TE=500 MATD TE=600* ASME SA-403 MATH CD=403.3]MATD TE=70 MATD TE=100 MATD TE=200 MATD TE=300 MATD TE=400 MATD TE=500 MATD TE=600 EH=28.3 EH=28. 1 EH=27. 6 EH=27.0 EH=2 6.5 EH=25. 8 EH=25.3 Grade WP316, 16 EX=0 EH=28.3 EH=28.1 EH=27.6 EH=27.0 EH=26.5 EH=25.8 EH=25.3 EX=0. 0 EX=0. 30 EX=l. 40 EX=2.50 EX=3.70 EX=5.00 EX=6.30 ELBOWS *TY=4 EX=0. 0 EX=0. 30 EX=1. 40 EX=2.50 EX=3.70 EX=5.00 EX=6. 30 SM=20.0 SY=30.0 SM=20.0 SY=30.0 SM=20.0 SY=25.9 SM=20.0 SY=23.4 SM=19.3 SY=21.4 SM=18.0 SY=20.0 SM=17.0 SY=18.9*16Cr-12Ni-2Mo SM=20.0 SY=30.0 SM=20.0 SY=30.0 SM=20.0 SY=25.9 SM=20.0 SY=23.4 SM=18.7 SY=21.4 SM=17.5 SY=20.0 SM=16.4 SY=18.9 I I I I I Cross Sectional Properties CROS CD=1 OD=50.0 WT=8.87 MA=3977.2
*CALC. PER GE SPEC. NO. 23A5569 [3]*CROS CROS CROS CROS CROS CROS CROS CROS CROS CROS CROS CROS CROS CROS CROS CROS CROS CROS CROS CROS CD=2 CD=3 CD=4 CD0=5 CD=7 CD=8 CD=11 CD=13 CD=14 CD=15 CD=16 CD=17 CD=18 CD=19 CD=20 CD=25 CD=26 CD=27 CD=28 CD=29 SO=1 OD=37.85 SO=1 OD=28. 875 SO=l OD=28.638 SO=l OD=28.169 SO=l OD=28.166 SO=1 OD=42, 507 SO=. 001 OD=6. 625 so=o.001 OD=28.339 SO=1 OD=28,339 SO=1 OD=12, 748 50=1 OD=14,17 SO=l OD=15.5 OD=21.88 SO=I OD=28.25 SO=1 OD=21. 878 SO=l OD=20 SO=OD=20 SO=1 OD=4 .5 SO=1 OD=4. 5 SO=OD=24 ST=I. 0 WT=6. 1 ST=I. 0 WT=1.56 ST=I. 0 WT=I.45 ST=I.0 WT=1. 244 ST=1 .0 WT=2.125 ST=I .0 WT=2.486 ST=. 001 WT=0. 432 ST=0.001 WT=1. 339 ST=1 WT=2. 67.ST=1. 0 WT=0. 685 ST=1. 0 WT=1.395 ST=I. 0 WT=2 ST=I .0 WT=4. 06 ST=I .0 WT=7.25 ST=I .0 WT=I.043 ST=1 .0 WT=I.031 ST=I WT=1.875 ST=I WT=0. 3385 SThI WT=0. 67 ST=I WT=I.217 MA=2122.2 MA=484. 9 MA=450.4 MA=386. 1 MA=0. 001 KL=1 MA=0. 001 KL=1 MA=O. 001 KL=I MA=415. 1 MA=0.001 KL=1 MA=I03.4 MA=207. 5 MA=307. 7 MA=8 03.2 MA=1673.1 MA=257 .2 MA=221. 9 MA=0.001 KL=1 MA=2 3.2 KL=I MA=0.001 KL=1 MA=316. 5*RECIRCULATION OUTLET NOZZLE*CALC. PER GE SPEC. NO. 23A5569 [31*CALC. PER GE SPEC. NO. 23A5569 [3]*CALC. PER GE SPEC. NO. 23A5569 [31*CALC. PER GE SPEC. NO. 23A5569 [3]*VALVE*PUMP*PUMP RIGID STRUTS*CALC. PER GE SPEC. NO. 23A5569 [3]*VALVE*CALC.*CALC.*CALC.*CALC.*CALC.*CALC.*CALC.*VALVE PER PER PER PER PER PER PER GE GE GE GE GE GE GE SPEC.SPEC.SPEC.SPEC.SPEC.SPEC.SPEC.NO.NO.NO.NO.NO.NO.NO.23A5569 23A5569 23A5569 23A5569 23A5569 23A5569 23A5569[3][3][3][3][3][3][3]I I I I I I I I I I I*CALC. PER GE SPEC. NO. 23A5569 [3]*4 inch bypass line*.VALVE V2-54A*CALC. PER GE SPEC.NO. 23A5569 [3]SO=I CROS CD=30 OD=24 File No.: VY-16Q-307 Revision:
0 ST=I WT=2.43 MA=0.001 *VALVE Page A22 of A5lI.I I F0306-01 RO Structural Integrity Associates, Inc.[CROS CD=40 CROS CD=41 CROS CD=42 SO=1 OD=4. 5 SO=-0.001.
OD=2. 875 SO=0.001 OD=28.339 SO=0.00l ST=1 KL=1 WT=0.3385 MA=0.001 ST=0.001 KL=1 WT=0.276 MA=0.001 ST=0.001 KL=1 WT=1.339 MA=0.001 ST=0.001 KL=1*4 inch bypass STRUTS*STRUT RDA1, RDA5, & VBAI*RIGID FROM RECIRC ELBOW TO RDAI STRUT* STRUCTURE AND LOADS** *** *** * *** **** * *** **-----------------------------------------------------------
DESN TE=575.0 PR=1250.0
*Reference 12 GE Design Requirements Rpt VY-05Q-227
----------
=-------------------------------------------------
-----------------------------------
I----------------
*BEGIN REGION 1 TRANSIENT CARDS & GEOMETRY FROM RHR SUPPLY TO TEE---------------------------------------------------
INCL FN=Z:\SISJ-PROJECrS\VY-16Q\Rev0\REGI.INP RUN 1 FROM ANCHOR TO REACTOR VESSEL N3B*GROUP 1 FROM ANCHOR TO REACTOR VESSEL N3B*NOTE*NOTE NODE 003 -RECIRC SUCTION NOZZLE NIA (EL. 279'5 INCH)*NOTE NODE 003 IS AT THE SAFE END TO VESSEL NOZZLE CONNECTION
*NOTE*NOTE SAFE END FROM NODES 003 TO 808*NOTE CONNECTION TO VESSEL AT NODE 003*NOTE OD AND WALL THICKNESS FOR SAFE END TAKEN FROM GE CALC*NOTE WEIGHT FOR SAFE END BASED ON THICKNESS*NOTE MATL CD=3 CROS CD=1 COOR PT=3 ANCH PT=3 AMVT C.AMVT C]AMVT C;AMVT C;AMVT Ci AMVT Ci AMVT Ci AMVT Ci AMVT Ci AMVT C)AMVT C)AMVT C)-AMVT C)AMVT C)AMVT C)AMVT C).AMVT C)AMVT C1 AMVT C1 AMVT C7 AMVT C1 AMVT C1 AMVT C1 AMVT Cr 76.316 AX=0 AY=0 AZ=0 A=I A=2 A=3 A=4 A= 5 A=6 A=7 A=8 A=9%=10 A--13 A=I4 A=I5 4=19 4=20 4=21 1=22--23%=24 PT='3 PT=3 PT=3 PT=3 PT=3 PT=3 PT=3 PT=3 PT=3 PT=3 PT=3 PT=3 PT=3 PT=3 PT=3 PT=3 PT=3 PT=3 PT=3 PT=3 PT=3 PT=3 PT=3 PT=3 DX=0. 0000 DX=0. 0000 DX=0. 0000 DX=0. 0000 DX=0. 0000 DX=0. 0000 DX=0. 0000 DX=0. 0000 DX=0. 0000 DX=0. 0000 DX=0. 0000 DX=0. 0000 DX=0. 0000 DX=0.0000 DX=0. 0000 DX=0. 0000 DX=0.0000 DX=O. 0000 DX=0. 0000 DX=0. 0000 DX=0.0000 DX=0. 0000 DX=0. 0000 DX=0. 0000 DY=0. 0176 DY=0. 3141 DY=0.3112 DY=0. 2995 DY=0. 3112 DY=0.2995 DY=0.2922 DY=0.2995 DY=0. 1422 DY=0.2807 DY=0. 1422 DY=0. 3141 DY=0. 3141 DY=0 1928 DY=0. 1624 DY=0. 0946 DY=0. 0176 DY=0. 0176 DY=0. 0946 DY=0. 0946 DY=0. 0361 DY=O0.2995 DY=0. 1928 DY=0. 0176 DZ=-0. 0201 DZ=-0. 3602 DZ=-0. 3568 DZ=-0. 3434 DZ=-0. 3568 DZ=-0. 3434 DZ=-0.3350 DZ=-0 .3434 DZ=-0.1630 DZ=-0.3218 DZ=-0. 1630 DZ=-0.3602 DZ=-0 .3602 DZ=-0.2521 DZ=-0. 1986 DZ=-0. 1084 DZ=-0.0201 DZ=-0.0201 DZ=-0. 1084 DZ=-0. 1084 DZ=-0.0413 DZ=-0. 3434 DZ=-0.2521 DZ=-0. 0201 File No.: V, Revision:
0 Y-16Q-307 Page A23 of A51 F0306-O1RO Structural Integrity Associates, Inc. U I TANG PT=805 DZ=-1.017 EWI=1 CROS CD=2 m TANG PT=806 DZ=-0.823 EW=1 CROS CD=3 TANG PT=807 DZ=-0.58 EW=I1 CROS CD=4 I TANG PT=808 DZ=-o.47 CROS CD=5 TANG PT=5 DZ=-5.59 EW=1 MATL CD=403.316 U BRAD PT=7 RA=3.5 EW=1 MATL CD=376.316 TANG PT=9 DY=-6.69 EW=I l TANG PT=500 DY=-2.31 I-----------------------------------
*END REGION 1 GEOMETRY FROM R-R SUPPLY TO TEE------------------------------------
------------------------------------------------------
*BEGIN REGION 2 TRANSIENT CARDS & GEOMETRY FROM RHR SUPPLY TEE TO PUMP* I---------------------------------
-I*GROUP 2 RHR SUPPLY TEE TO PUMP INCL FN=Z:\SISJ-PROJECTS\VY-16Q\Rev0\REG2.INP TANG PT=11 DY=-2.22 EW=1 CROS CD=5 TANG PT=12 DY=-1.78 TANG PT=20 DY=-6.77 TANG PT=22 DY=-3.25 TANG PT=25 DY=-15.49 EW=l MATL CD=403.316 BRAD PT=26 RA=3.5 EW=1 MATL CD=376.316 TANG PT=27 DX=-3.3 DZ=1.27 EW=1 CROS CD=7 VALV PT=30 DX=-2.28 DZ=0.89 MA=10.368 PL=1 JUNC PT=30 VALV PT=40 DX=-2.31 DZ=0.9 PL=2 EW=1 JUNC PT=30 RIGD PT=35 DY=7 LUMP PT=35 MA=1.132 JUNC PT=40 I CROS CD=5 TANG PT=42 DX=-1.18 DZ=0.46 TANG PT=43 DX=-0.55 DZ=0.21 TANG PT=44 DX=-3.31 DZ=1.28 EW==1 MATL CD=403.316 BRAD PT=46 RA=2.33 .EW=I MATL CD=376.316 CROS CD=8 TANG PT=50 DY=4.33 EW=0 LUMP PT=50 MA=28 *NOTE WEIGHT OF PUMP FLOODED 28K (EXCLUDING MOTOR)TANG PT=75 DY=0.5 TANG PT=83 DY=2.13 TANG PT=86 DY=3.38 LUMP PT=86 MA=32 *NOTE TOTAL WEIGHT OF PUMP MOTOR 32000 LBS TANG PT=90 DY=4.08 *TOP OF PUMP*NOTE SNUBBERS ON TOP OF PUMPS WERE DELETED DURING*NOTE THE RECIRC PIPE REPLACEMENT PROJECT File No.: VY-16Q-307 Page A24 of A51 n Revision:
0 F0306-01 RO i Structural Integrity Associates, Inc., I*NOTE -RIGID LINKS FOR CONSTANT SUPPORTS AT PUMP FOLLOW---------------------
*END REGION 2 GEOMETRY FROM RHR SUPPLY TEE TO PUMP-- --------------
-------------------------------
*BEGIN REGION 3 TRANSIENT CARDS &.GEOMETRY FROM PUMP DISCHARGE TO HEADER----------------
7--------------
*GROUP 3 FROM PUMP DISCHARGE TO HEADER INCL FN=Z:\SISJ-PROJECTS\VY-16Q\RevO\REG3.INP JUNC PT=50 CROS RIGD RIGD JUNC RIGD RIGD JUNC CROS RIGD RIGD CD=8 PT=54 DX=I.06 DZ=1.06 PT=56 DX=1.06 DY=0.75 DZ=l PT=50 PT=66 DZ=-3.83 PT=69 DY=1 PT=50 CD=8 PT=60 DX=-3.83 PT=63 DY=l* *** CODING FOR PUMP RIGID STRu CODED FROM PUMP.CENTERLINE CR0S CD=11 JUNC PT=66 RIGD PT=15 DY=0.7071 DZ=-0.70 JUNC PT=.60 RIGD PT=16 DX=-0.7071 DY=0.70* *** END OF CODING FOR PUMP SUP*PUMP INLET CROS CD=8 JUNC PT=50 TANG PT=150 DX=-2.17 BRAN *PT=151 DZ=2.333 TE=1*NOTE PUMP DISCHARGE CONNECTION CROS CD=13.06 *NOTE CONSTANT SUPPORT HA3 AT NODE 56*NOTE CONSTANT SUPPORT HA4 AT NODE 69*CONSTANT SUPPORT HA5 AT NODE 63 JTS FOLLOW **)71 371'PORTS ***TO PIPE AT NODE 151 TANG TANG CROS VALV JUNC RIGD LUMP JUNC VALV CROS MATL BRAD MATL TANG.TANG PT=I52 PT=155 CD=14 PT=160 PT=160 PT=163 PT=163 PT=160 PT=170 DZ=I. 25 DZ=1 EW=1 PL=1 DX=0.0 DY=0.0 DZ=2.52 MA=6.8285 DX=0.0 DY=7.12 DZ=0.0 MA=0. 9715 PL=2 DX=0.O DY=0.0 DZ=~6.18 EW=I CD=13 CD=403.316 PT=175 RA=3.5 EW=l CD=376.316 PT=176 DY=5.95 PT=177 DY=4.42*'NOTE ***WEIGHT OF FLOW ELEMENT NOT INCLUDED***
*NOTE ***REF. DWG. 5920-6800 FOR DIMENSIONS***
TANG PT=184 DY=4.42 TANG PT=186 DY=3.02 TANG PT=188 DY=1.51 TANG PT=189 DY=0.74 File No.: VY-16Q-307 Revision:
0 Page A25 of A51 F0306-OIRO V Structural Integrity Associates, Inc.TANG PT=I90 DY=l.15 EW=1 TANG PT=600 DY=I.06***INPUT FILE TO INCLUDE EFFECTS OF RHR INITIATION ON LINE NEAR RHR RETURN TO HEADER INCL FN=Z:\SISJ-PROJECTS\VY-16Q\RevO\REG3B.INP JUNC PT=600 TANG PT=I95 DY=2.08 EW=1 TANG PT=210 DX=0.0 DY=l.83 DZ=0.0 KL=l *CENTER OF CROSS, RECIRC HEADER*MUST HAVE INDI CARD FOR EACH MEMBER CONNECTED TO CROSS CENTER---------------------
*END REGION 3 GEOMETRY FROM PUMP DISCHARGE TO.HEADER----------------------
---------------
---------------
*BEGIN REGION 5 TRANSIENT CARDS & GEOMETRY RISER TO NOZZLE NODE 336*--------------------------------
*GROUP 5 RISER TO NOZZLE NODE 336 INCL FN=Z:\SISJ-PROJECTS\VY-16Q\RevO\REG5.INP I I I I U I U I I I I I I I*NOTE CROSS AND REDUCER DIMENSIONS TAKEN FROM 5920-6632 SHT.3 CROS CD=I3 MATL CD=376.316 TANG PT=215 DX=0.0 DY=2.59 DZ=0.0 EW=0 CRED PT=220 DY=1.29 AN=30 EW=l. *AL=$CONC.
REDUCER$CROS CD=I5 TANG PT=330 DY=4.58 TANG PT=335 DY=3.29 EW=l MATL CD=403.316 BRAD PT=334 RA=l.5 EW=l---------------------
*END REGION 5 GEOMETRY RISER TO NOZZLE NODE 336*--------------------------
* ------------------------------
*BEGIN REGION 6 TRANSIENT CARDS & GEOMETRY TO* ------------------------------
*GROUP 6 TO NOZZLE NODE 336 INCL FN=Z: \SISJ-PROJECTS\VY-16Q\RevO\REG6.INP MATL CD=376.316 TANG PT=838 DX=3.875 CROS CD=16 TANG PT=837 DX=0.875 EW=I CROS CD=17 TANG PT=836 DX=0.37 EW=1 CROS CD=18 TANG PT=835 DX=0.53 EW=l CROS CD=19 TANG PT=336 DX=0.704 EW=1 NOZZ PT=336 AMVT CA=I PT=336 DX=-0.0201 DY=0.0246 AMVT CA=2 PT=336 DX=-0.3602 DY=0.4398 AMVT CA=3 PT=336 DX=-0.3568 DY&#xfd;-0.4316 AMVT CA=4 PT=336 DX=-0.3434 DY=0.4152 AMVT CA=5 PT=336 DX=-0.3568 DY=0.4050 AMVT CA=6 PT=336 DX=-0.3434 DY=0.2940 AMVT CA=7 PT=336 DX=-0.3350 DY=0.3229 AMVT CA=8 PT=336 DX=-0.3434 DY=0.2700 AMVT CA=9 PT=336 DX=-0.1630 DY=0.1991 NOZZLE NODE 336 DZ=0.0000 DZ=0.0000 DZ=0.0000 DZ=0.0000 DZ=0.0000 DZ=0.0000 DZ=0.0000 DZ=0.0000 DZ=O.O0000 I I I I I File No.: V Revision:
0 SY-1I6Q-307 Page A26 of A51 F0306-OI RO K Structural Integrity Associates, Inc.I AMVT CA=1I PT=336 DX=-0.3218 DY=O.1626 DZ=0.0000 AMVT CA-11 PT=336 DX=-O.1630 DY=O.0246 DZ=0.0000 AMVT CA=i2 PT=336 DX=-0.3602 DY=0.4398 DZ=0.0000 AMVT CA=l3 PT=336 DX=-0.3602 DY=0.4316 DZ=0.0000 AMVT CA=14 PT=336 DX=-0.2193 DY=0.4152 DZ=O.0000 AMVT. CA=l5 PT=336 DX=-0.1862 DY=O.4050 DZ=0.0000 AMVT CA=I6 PT=336 DX=-0.1084 DY=0.2940 DZ=0.0000 AMVT CA=I7 PT=336 DX=-0.0201 DY=0.3229 DZ=0.0000 AMVT CA=18 PT=336 DX=-0.0201 DY=0.2700 DZ=0.0000 AMVT CA=19 PT=336 DX=-0.1084 DY=0.1991 DZ=0.0000 AMVT CA=20 PT=336 DX=-0.0201 DY=0.1626 DZ=0.0000 AMVT CA=21 PT=336 DX=-0.0413 DY=0.3229 DZ=0.0000 AMVT CA=22 PT=336 DX=-0.3434 DY=0.2700 DZ=0.0000 AMVT CA=23 PT=336 DX=-0.2211 DY=0.1991 DZ=0.0000 AMVT CA-24 PT=336 DX=-0.0201 DY=0.1626 DZ=0.0000*NOTE SAFE END FROM NODES 838 TO 336*NOTE CONNECTION TO VESSEL AT NODE 336*NOTE OD AND WALL THICKNESS FOR SAFE END TAKEN FROM GE CALC i *NOTE WEIGHT BASED ON THICKNESS----------------------
*END REGION 6 GEOMETRY TO NOZZLE'NODE 336---------------------
l*------------------------------
*BEGIN REGION 4 TRANSIENT CARDS & GEOMETRY HEADER TO NOZZLE NODE 366*GROUP 4 HEADER TO NOZZLE NODE 366 INCL FN=Z:\SISJ-PROJECTS\VY-16Q\RevO\REG4.INP JUNC PT=210 CROS CD=20 BRAN PT=240 DX=0.1786 DY=0.0 DZ=I.7 TANG PT=250 DX=0.3 DZ=2.853 EW=0 BRAD PT=255 RA=4.578 EW=O *NOTE BEND RADIUS IS 4.578 FEET TANG PT=340 DX=1.799 DZ=3.108---------------------
*END REGION 4 GEOMETRY HEADER TO NOZZLE NODE 366l**BEGIN REGION 5 TRANSIENT CARDS & GEOMETRY RISER TO NOZZLE NODE 366-------------------------------
iGROUP 5 RISER TO NOZZLE NODE 366 INCL FN=Z:\SISJ-PROJECTS\VY-16Q\RevD\REG5.INP TANG PT=349 DX=D.71 DZ=I.23 EW=D CRED PT=347 DX=0.75 DZ=I.3 AN=30 CROS CD=15 TANG PT=343 DX=.0.5525 DZ=0.957 EW=I BRAD PT=41D RA=l.5 EW=1 TANG PT=360 DX=3.483 DZ=2.011 EW=I MATL CD=403.316 BRAD PT=361 RA=I.5 EW=I MATL CD=376.316 CROS CD=15 TANG PT=362 DY=3.18 TANG PT=364 DY=8.56 EW=l MATL CD=403.316 I File No.: VY-16Q-307 Page A27 of A51 Revision:
0 F0306-O1 RO V Structural Integrity Associates, Inc.BRAD PT=365 RA=1.5 EW=1-------------------
*END REGION 5 GEOMETRY RISER TO NOZZLE NODE 366*----------------
---------------------------------
*BEGIN REGION 6 TRANSIENT CARDS & GEOMETRY TO* ------------------------------
*GROUP 6 TO NOZZLE NODE 366 INCL FN=Z:\SISJ-PROJECTS\VY-16Q\RevO\REG6.INP NOZZLE NODE 366 MATL TANG CROS TANG CD=376. 316 PT~=868 DX~=1.8 DZ=~-3.1 CD=~16 PT=867 DX=0.4375 DZ&#xfd;=-0.76 EW~1 CROS CD=17 I I I I I I I I I I TANG CROS TANG PT=866 DX=0.185 DZ=-0.32 EW=1 CD=18 PT=865 DX=0.265 DZ=-0.46 EW=I CROS CD19 TANG PT=366 DX=0.352 DZ--0.61 EW=1 NOZZ PT=366 AMVT CA=1 AMVT CA=2 AMVT CA=3 AMVT CA=4 AMVT CA=5 AMVT CA=6 AMVT CA=7 AMVT CA=8 AMVT CA=9 AMVT CA=10 AMVT CA11 AMVT CA=I2 AMVT QA=13 AMVT CA=14 AMVT CA=15 AMVT CA=16 AMVT CA=17 AMVT CA=I8 AMVT CA=19 AMVT CA=20 AMVT CA=21 AMVT CA=22 AMVT CA=23 AMVT CA=24 PT=366 PT=366 PT=366 PT=366 PT=366 PT=366 PT=366 PT=366 PT=366 PT=366 PT=366 PT=366.PT=366 PT=366 PT=366 PT=366 PT=366 PT=366 PT=366 PT=366 PT=366 PT=366 PT=366 PT=3666 DX=-0. 0101 DX=-0. 1800 DX=-0. 1783 DX=-0. 1716 DX=-0. 1783 DX=-0. 1716 DX=-0. 1674 DX=-0. 1716 DX=-0. 0815 DX=-0. 1609 DX=-0. 0815 DX=-0. 1800 DX=-0. 1800 DX=-0. 1097 DX=-0. 0931 DX=-0.0542 DX=-0. 0101 DX=-0.0101 DX=-0. 0542 DX=-0. 0101 DX=-0.0207 DX=-0. 1716 DX=-0. 1105 DX=-0.0101 DY=0. 0246 DY=0. 4398 DY=0. 4357 DY=0. 4193 DY=0.4357 DY=0. 4193 DY=0.4091 DY=0. 4193 DY=0. 1991 DY=0. 3930 DY=0. 1991 DY=0.4398 DY=0.4398 DY=0.2678 DY=0.2275 DY=0. 1324 DY=0. 0246 DY=0. 0246 DY=0. 1324 DY=0.0246 DY=0. 0505 DY-.0. 4193 DY=0. 2700 DY=0. 0246 DZ=0.0174 DZ=0.3120 DZ=0. 3091 DZ=0.,2974 DZ=0. 3091 DZ=0. 2974 DZ=0.2902 DZ=0.2974 DZ=0. 1412 DZ=0.2788 DZ=0. 1412 DZ=0.3120 DZ=0.3120 DZ=0. 1899 DZ=0. 1613 DZ=0 .0939 DZ=0. 0174 DZ=0. 0174 DZ=0.0939 DZ==0.0174 DZ=0.0358 DZ=0 .2974 DZ=0. 1915 DZ=0. 0174* --------------------
*END REGION 6 GEOMETRY TO NOZZLE NODE 366---------------------
-------------------------------
*BEGIN REGION 4 TRANSIENT CARDS & GEOMETRY HEADER TO NOZZLES NODE 326 & 316-------------------------------
*GROUP 4 HEADER TO NOZZLES NODE 326 & 316 INCL FN=Z:\SISJ-PROJECTS\VY-16Q\RevO\REG4.INP JUNC PT=210 CROS CD=20 BRAN PT=260.DX=0.1786 DY=0.0 DZ=-1.7 TE=2 I I I I I I I File No.: VY-16Q-307 Revision:
0 Page A28 of A51 F0306-OI RO i SStructural Integrity Associates, Inc.* TANG PT=270 DX=O0.3 DZ=-2.853 EW=0 BRAD PT=275 RA=4.578 EW=O TANG PT=320 DX=1.799 DZ=-3.108* -------------
*END REGION 4 GEOMETRY HEADER TO NOZZLES NODE 326 & 316----------------------
--IBEGIN REGION 5 TRANSIENT CARDS & GEOMETRY RISER TO NOZZLE NODE 316------------------------------
*GROUP 5 RISER TO NOZZLE NODE 316 INCL FN=Z:\SISJ-PROJECTS\VY-16Q\RevO\REG5.INP TANG PT=319 DX=0.71 DZ=-1.23 EW=1 CRED PT=317 DX=0.75 DZ=-1.3 AN=30 CROS CD=15 TANG PT=313. DX=0.5525 DZ=-0.957 EW=I BRAD PT=400 RA=I.5 EW=I TANG PT=310 DX=3.483 DZ=-2.011 EW=l MATL CD=403.316 BRAD PT=311 RA=I.5 EW=l MATL CD=376.316 CROS CD=15 TANG PT=312 DY=4.74 TANG PT=314 DY=6.99 EWe1 MATL CD=403.316 BRAD PT=315 RA=I.5 EW=I---*END REGION 5 GEOMETRY RISER TO NOZZLE NODE 316-------------------
---------------------------
-*BEGIN REGION 6 TRANSIENT CARDS & GEOMETRY TO NOZZLE NODE 316-------------------------------
*GROUP 6 TO NOZZLE NODE 316 INCL FN=Z:\SISJ-PROJECTS\VY-16Q\RevO\REG6.INP MATL CD=376.316 TANG PT=818 DX=I.84 DZ=3.19 CROS CD=16 TANG PT=817 DX=0.4375 DZ=0.76 EW=I CROS CD=17 TANG PT=816 DX=0,185 DZ=0.32 EW=I CROS CD=18 TANG PT=815 DX=0.265 DZ=0.46 EW=I CROS CD=19 TANG PT=316 DX=0.352 DZ=0.61 EW=1 NOZZ PT=316 AMVT CA=I PT=316 DX=-0.0101 DY=0.0246 DZ=-0.0174.
AMVT CA=2 PT=316 DX=-0.1800 DY=0.4398 DZ=-0.3120 AMVT CA=3 PT&#xfd;316 DX=-0.1783 DY=0.4357 DZ=-0.3091 AMVT CA=4 PT=316 DX=-0.1716 DY=0.4193 DZ=-0.2974 AMVT CA=5 PT&#xfd;316 DX=-0.1783 DY=0.4357 DZ=-0.3091 AMVT CA=6 PT=316 DX=-0.1716 DY=0.4193 DZ=-0.2974 AMVT CA=7 PT=316 DX=-0.1674 DY=0.4091 DZ=-0.2902 AMVT CA=8 PT=.316 DX=-0.1716 DY=0.4193 DZ=-0.2974 AMVT CA=9 PT=316 DX=-0.0815 DY=0.1991 DZ=-0.14i2 AMVT CA=10 PT=316 DX=-0.1609 DY=0.3930 DZ=-0.2788 AMVT CA=l1 PT=316 DX=-0.0815 DY=0.1991 DZ=-0.1412 AMT CA=12 PT=316 DX=-0.1800 DY=0.4398 DZ=-0.3120 File No.: VY-16Q-307 Page A29 ofA5l Revision:
0 F0306-01 RO V Structural Integrity Associates, Inc.I I I AMVT CA=I3 PT=316 DX=-0.1800 DY=0D.4398 DZ=-0.3120 AMVT AMVT AMVT AMVT AMVT AMVT AMVT AMVT AMVT AMVT AMVT CA=14 CA=15 CA=16 CA=17 CA=18 CA=19 CA=220 CA=21 CA=22 CA=2 3 CA=24 PT=316 PT=316 PT=316 PT=316 PT=316 PT=316 PT=316 PT=316 PT=316 PT=316 PT=316 DX=-O. 1097 DX=-O.0931 DX=O.0542 DX=-0. 0101 DX=-0. 0101 DX=-O.0542 DX=-0. 0101 DX=-0.0207 DX=-0. 1716 DX=-0. 1105 DX=-0.0101 DY=0.2678 DY=0.2275 DY=0.1324 DY=0. 0246 DY=0.0246 DY=0. 1324 DY=0.0246 DY=0.0505 DY=0. 4193 DY=O0.2700 DY=0. 0246 DZ=-0.1899 DZ=-0. 1613 DZ=-0.0939 DZ=-O. 0174 DZ=-0.0174 DZ=-0.0939 DZ=-0. 0174 DZ=-0 .0358 DZ=-0.2974 DZ=-0. 1915 DZ=-0. 0174*END REGION 6 GEOMETRY TO NOZZLE NODE 316---------------------
-------------------------------
*BEGIN REGION 5 TRANSIENT CARDS & GEOMETRY RISER TO NOZZLE NODE 346-------------------------------
*GROUP 5 RISER TO NOZZLE NODE 346 INCL FN=Z:\SISJ-PROJECTS\VY-16Q\RevO\REG5.INP JUNC PT=340 CROS CD=15 BRAN PT=342 DY=1.36 TE=2 TANG PT=344 DY=10.39 EW=0 MATL CD=403.316 BRAD PT=345 RA=1.5 EW=1---------------------
*END REGION 5 GEOMETRY RISER TO NOZZLE NODE 346*--------------------------
I I I I I I I I I I I* ------------------------------
*BEGIN REGION 6 TRANSIENT CARDS & GEOMETRY TO* ------------------------------
*GROUP 6 TO NOZZLE NODE 346 INCL FN=Z:\SISJ-PROJECTS\VY-16Q\Rev0\REG6.INP MATL TANG CROS TANG CROS TANG CROS TANG CROS TANG NOZZ AMVT AMVT AMVT AMVT AMVT AMVT AMVT AMVT AMVT AMVT AMVT CD=376.316 PT=848 DX=3.17 DZ=-1.83 CD=16 PT=847 DX=0.758 DZ=-0.4375 EW=1 CD=17 PT=846 DX=0.32 DZ=-0.185 EW=1 CD=18 PT=845 DX=0.46 DZ=-0.265 EW=1 CD=19 PT=346 DX=0.61 DZ=-0.352 EW=1 PT=346 NOZZLE NODE 346 DZ=0.0101 DZ=0.1800 DZ=0.1783 DZ=0.1716 DZ=0 .1783 DZ=0.1716 DZ=0. 1674 DZ=0.1716 DZ=0.0815 DZ=0.1609 DZ=0.0815 CA=1 CA=2 CA=3 CA=4 CA=5 CA=6 CA=7 CA=8 CA= 9 CA=10 CA=11 PT=346 PT=346 PT=346 PT=346 PT=346 PT=346 PT=346 PT=346 PT=346 PT=346 PT=346 DX=-0. 0174 DX=-0. 3120 DX=-0. 3091 DX=L0.2974 DX=-0. 3091 DX=-0.2974 DX=-0. 2902 DX=-0.2974 DX=-0. 1412 DX=-0. 2788 DX=-0. 1412 DY=0. 0246 DY=0.4 398 DY=0.4357 DY=0.4193 DY=0. 4357 DY=0. 4193 DY=0. 4091 DY=0. 4193 DY=0. 1991 DY=0. 3930 DY=0. 1991 I I I I I File No.: VY-16Q-307 Revision:
0 Page A30 of A51 F0306-OI RO 1 Structural integrity Associates, Inc.AMVT CA=I12 PT=346 DX='-0.3120 DY=0.4398 DZ=0.1800 AMVT AMVT AMVT AMVT AMVT AMVT AMVT AMVT AMVT AMVT AMVT AMVT CA=13 CA=14 CA=15 CA=16 CA=17 CA=18 CA=19 CA=20 CA=21 CA=22 CA=2 3 CA=24 PT=346 PT=346 PT=34 6 PT=346 PT=346 PT=346 PT=346 PT=346 PT=346 PT=346 PT=346 PT=346 DX=-0. 3120 DX=-0. 1899 DX=-0. 1613 DX=-0.0939 DX=-0. 0174 DX=-0. 0174 DX=-0. 0939 DX=-0.0174 DX=-0. 0358 DX=-0. 2974 DX=-0. 1915 DX=-0. 0174 DY=0.4398 DY=0. 2678 DY=0.2275 DY=0.1324 DY=0.0246 DY=0. 0246 DY=0. 1324 DY=0. 0246 DY=O. 0505 DY=0. 4193 DY=0.2700 DY=0. 0246 DZ=0. 1800 DZ=0. 1097 DZ=0.0931 DZ='0.0542 DZ=0. 0101 DZ=0. 0101 DZ=0 -0542 DZ=0.0101 DZ=0. 0207 DZ=0. 1716 DZ=0.1105 DZ=0. 010i*END REGION 6 GEOMETRY TO NOZZLE NODE 346---------------------
-------------------------------
*BEGIN REGION 5 TRANSIENT CARDS & GEOMETRY RISER TO NOZZLE NODE 326* ------------------------------
*GROUP 5 RISER TO NOZZLE NODE 326 INCL FN=Z:\SISJ-PROJECTS\VY-16Q\RevO\REG5.INP JUNC PT=320 CROS CD=15 BRAN PT=322 DY=1.42 TE=2 TANG PT=324 DY=10.33 EW=1 MATL CD=403.316 BRAD PT=325 RA=1.5 EW=1*--------------------------
*END REGION 5 GEOMETRY RISER TO NOZZLE NODE 326--------------*-------------------------------
*BEGIN REGION 6 TRANSIENT CARDS & GEOMETRY TO* ------------------------------
*GROUP 6 TO NOZZLE NODE 326 INCL FN=Z:\SISJ-PROJECTS\VY-16Q\RevO\REG6.INP NOZZLE NODE 326 MATL TANG CROS TANG CROS TANG CROS TANG CROS TANG NOZZ AMVT AMVT AMVT AMVT AMVT AMVT AMVT AMVT AMVT AMVT CD=376. 316 PT=828 DX=3.18 DZ=1.84 CD=16 PT=827 DX=0.758 DZ=0.4375 EW=1 CD=17 PT=826 DX=0.32 DZ"0.185 EW=1 CD=18 PT=825 DX: CD=19 PT=326 DX: PT=326 CA=1 CA=2 CA=3 CA=4 CA=5 CA=6 CA= 7 CA=8 CA= 9'0.46 DZ=0.265 EW=1:0.61 DZ=0.352 EW=1 PT=326 PT=326 PT=326 PT=326 PT=326 PT=326 PT'326 PT=326 PT=326 DX"-0.0174 DX=-0. 3120 DX=-0.3091 DX=-0. 2974 DX=-0. 3091 DX=-0. 2974 DX=-0.2902 DX=-0.2974 DX=-0. 1412 DY=0.0246 DY=O. 4398 DY=0. 4357 DY=O. 4193 DY=0.4 357 DY=0. 4193 DY=0. 4091 DY=0. 4193 DY=0. 19 91 DY=0.3930 DZ=-0.0101 DZ=-0. 1800 DZ=-0. 1783 DZ=-0..1716 DZ=-0. 1783 DZ=-0. 1716 DZ=-0. 1674 DZ=-0. 1716 DZ=-0. 0815 DZ=-0.1609 CA=10 PT=326 DX=-0.2788 File No.: VY-16Q-307 Revision:
0 Page A31 of A51 F0306-OIRO Structural Integrity Associates, Inc. U I AMVT CA=II PT=326 DX=-0.1412 DY=0.1991.
DZ=-0.0815 AMVT CA=l2 PT=326 DX=-0.3120 DY=0.4398 DZ=-0.1800 AMVT CA=13 PT=326 DX=-0.3120 DY=0.4398 DZ=-0.1800 I AMVT CA=14 PT=326 DX=-0.1899 DY=0.2678 DZ=-0.1097 AMVT CA=I5 PT=326 DX=-0.1613 DY=0.2275 DZ=-0.0931 AMVT CA=16 PT=326 DX=-0.0939 DY=0.1324 DZ=-0.0542 AMVT CA=I7 PT=326 DX=-0.0174 DY=0.0246 DZ=-0.0101 AMVT CA=18 PT=326 DX=-0.0174 DY=0.0246 DZ=-0.0101 AMVT CA=19 PT=326 DX=-0.0939 DY=0.1324 DZ=-0.0542 AMVT CA=20 PT=326 DX=-0.0174 DY=0.0246 DZ=-0.0101 AMVT CA=21 PT=326 DX=-0.0358 DY=0.0505 DZ=-0.0207 AMVT CA=22 PT=326 DX=-0.2974 DY=0.4193 DZ=-0.1716 AMVT CA=23 PT=326 DX=-0.1915 DY=0.2700 DZ=-0.1105 AMVT CA=24 PT=326 DX=-0.0174 DY=0.0246 DZ=-0.0101
*END REGION 6 GEOMETRY TO NOZZLE NODE 326----------------------
--*BEGIN REGION 7A TRANSIENT CARDS & GEOMETRY TO RHR SUPPLY VALVE NODE 550-------------------------------
*GROUP 7 TO RHR SUPPLY VALVE NODE 550 INCL FN=Z:\SISJ-PROJECTS\VY-16Q\Rev0\REG7A.
INP MATL CD=3.76.316 JUNC PT=500 CROS CD=25 BRAN PT=502 DX=I.67 EW=0 TE=1 TANG PT=506 DX=2.53 EW=0 MATL CD=403.316 BRAD PT=507 RA=I.67 EW=l MATL CD=376.316 TANG PT=508 DZ=-4.01 TANG PT=515 DZ=-4.53 EW=I MATL CD=403.316 I BRAD PT=520 RA=I.67 EW=l MATL CD=376.316 CROS CD=26 VALV PT=525 DX=-3.34 PL=I JUNC PT=525 VALV PT=530 DX=-I.99 PL=2 EW=I JUNC PT=525 RIGD PT=526 DY=2.5 LUMP PT=526 MA=7.569 JUNC PT=530 CROS CD=25 TANG PT=540 DX=-I.13 EW=I CROS CD=26 VALV PT=545 DX=-I.97 PL=I JUNC PT=545 I RIGD PT=547 DY=2.5 LUMP. PT=547 MA=7.355 JUNC PT=545 VALV PT=550 DX=-l.98 PL=2 EW=l*END REGION 7A GEOMETRY TO RHR SUPPLY VALVE NODE 550---------------------
*BEGIN REGION 7B TRANSIENT CARDS & GEOMETRY FROM RHR SUPPLY VALVE TO PENET. NODE 565 File No.: VY-16Q-307 Page A32 of A51 I Revision:
0 F0306-OI RO I
" Structural Integrity Associates, Inc.* ----- ------------------------
*GROUP 17 FROM RHR SUPPLY VALVE TO PENET. NODE 565 INCL FN=Z:\SISJ-PROJECTS\VY-16Q\RevO\REG7B.INP CROS CD=25 MATL CD=106 TANG PT=555 DX=-3.36 EW=1 BRAD PT=556 RA=1.67 EW=1 TANG PT=560 DY=-10.17 EW=1 BRAD PT=561 RA=1.67 EW=1 TANG PT=563 DZ=-6.92 TANG PT=565 DZ=-6.92---------------------
*END REGION 7B GEOMETRY FROM RHR SUPPLY VALVE TO PENET. NODE 565-- ---------------
-- ---- -------------------------
*BEGIN REGION 8 TRANSIENT CARDS & GEOMETRY FOR 4 INCH BYPASS-------------------------------
*GROUP 8 4 INCH BYPASS INCL FN=Z:\SISJ-PROJECTS\VY-16Q\RevO\REG8.INP
*NOTE CODING FOR 4 INCH BYPASS STARTS HERE JUNC PT=152 CROS MATL BRAN TANG TANG MATL BRAD MATL TANG CD=27 CD=376. 316 PT=700 DX=-1.19 TE=4 PT=702 DX=-0.61 PT=703 DX=-1.43 EW=0 CD=403.316 PT==704 RA=0.5 EW=0 CD=376.316 PT=705 DZ=5.08*NOTE CONSTANT SUPPORT HA1l AT NODE 705 TANG PT=721 DZ=1.12 TANG PT=706 DZ=2.47 TANG PT=707 DZ=1.03 TANG PT=708 DZ=0.34 TANG PT=709 DZ=0.38 JUNC PT=707 BRAN PT=710 DY=0.34 TE=1 CROS CD=28 VALV PT=712 DY=0.71 MA=0.3669 VALV PT=715 DZ=-3.5 MA=0.1831 JUNC PT=712 VALV PT=714 DY=0.71 CROS CD=27 TANG PT=723 DY=4.19 MATL CD=403.316 BRAD PT=716 RA=0.5 MATL CD=376.316 TANG PT=718 DX=1.48 TANG PT=720 DX=0.56 BRAN PT=176 DX=1.19 TE=4************CODING FOR STRUTS JUNC PT=170 CROS CD=40 *OD=4.5 inch RIGD PT=725 DP=0 DX=-0.583 DY=CROS CD=41 *OD=2.875 inch RIGD PT=715 DP=0 DX=-2.67 DY=-PL=1 PL=3*AL=$VALVE V2-54A$PL=2 RDA5 AND VABI FOLLOW=1.84 *AL=$RDA5$
-0.79 File No.: VY-16Q-307 Page A33 of A51 Revision:
0 F0306-01 RO Structural Integrity Associates, Inc. U~I RIGD PT=721 DP=O DY=-I.05 *AL=$VABI$
*************CODING FOR RDAI STRUT FOLLOWS CROS CD=42 *OD=28.339 inch I JUNC PT=175 RIGD PT=I73 DP=0 DY=-3.5 DZ=0.34 CROS CD=41 *OD=2.875 inch RIGD PT=708 DP=O DX=-3.21 *AL=$RDA1$
------------------
*END REGION 8 GEOMETRY.
FOR 4 INCH BYPASS----------------------
-------------------------------
*BEGIN REGION 9A TRANSIENT CARDS & GEOMETRY FOR RHR RETURN FROM TEE TO VALVE NODE 660* -------------------
*GROUP 9 RHR RETURN FROM TEE TO VALVE NODE 660.INCL FN=Z:\SISJ-PROJECTS\VY-16Q\RevO\REG9A.INP
*NOTE CODING FOR RHR RETURN STARTS HERE CROS CD=29 JUNC PT=600 MATL CD=376.316 BRAN PT=602 DX=-3.8123 TE=I MATL CD=403.316 BRAD PT=610 RA=2 EW=1 TANP DY=4 BRAD PT=612 RA=2 EW=1 MATL CD=376.316 I TANG PT=614 DZ=-10.38 EW=l MATL CD=403.316 BRAD PT=615 RA=10 EW=1 MATL CD=376.316 I TANG PT=620 DX=5.98 DZ=-3.45 EW=1*NOTE*NOTE VARIABLE SPRING H104 AT NODE 620*NOTE*NOTE'VALVE V10-81A DATA FROM 5920-4590 WEIGHT- 6845.#*NOTE WEIGHT APPLIED AT ESTIMATED CENTER OF GRAVITY (NODE 623)CROS CD=30 VALV PT=622 DX=1.98 DZ=-1.15 PL=I *AL=$VALVE V10-81A$JUNC PT=622 VALV PT=624 DX=I.98 DZ=-1.15 PL=2 EW=I JUNC PT=622 .RIGD PT=623 DY=2.5 LUMP PT=623 MA=7.32 *VALVE ACTUATOR CROS CD=29 JUNC PT=624 TANG PT=625 DX=1.867 DZ=-I.078 TANG PT=630 DX=2.598 DZ=-I.5 EW=1 MATL CD=403.316 BRAD PT=631 RA=3 EW=1 MATL CD=376.316 TANG PT=640 DZ=-4.54 EW=I MATL CD=403.316 BRAD PT=641 RA=2 EW=1 MATL CD=376.316 I*NOTE VALVE V10-46A DATA FROM 5920-4718 WEIGHT -5295.#CROS CD=30 VALV PT=655 DX=-3.79 PL=1 TA=2 *AL=$VALVE V10-46A$LUMP PT=655 MA=5 .77 File No.: VY-16Q-307 Page A34 of A51 I Revision:
0 F0306-OIRO I Structural Integrity Associates, Inc.I----------------
*END REGION 9A GEOMETRY FOR RHR RETURN FROM TEE TO VALVE NODE 660-7*BEGIN REGION 9B TRANSIENT CARDS & GEOMETRY FOR RHR RETURN FROM VALVE NODE 660 TO PENET. NODE* 675---------------------------
*GROUP 19 RHR RETURN FROM VALVE NODE 660 TO PENET. NODE 675 INCL FN=Z:\SISJ-PROJECTS\VY-16Q\RevO\REG9B.INP
*NOTE VARIABLE SPRING Hi05 AT NODE 655* NOTE VALV PT=660 DX=-I.79 PL=2 EW=1*NOTE SPEC CHANGE TO CARBON STEEL MATL CD=106 CROS CD=29 TANG PT=661 DX=-I TANG PT=663 DX=-3.31 EW=I BRAD PT=665 RA=2 EW=1 TANG PT=670 DY=-10.5 DZ=0.38 EW=I BRAD PT=671 RA=2 EW=1 TANG PT=673 DZ=-7.74 TANG PT=675 DZ=-7.74*END REGION 9B GEOMETRY FOR RHR RETURN FROM VALVE NODE 660 TO PENET. NODE 675-------------------
* **STRESS INDICES AT CROSS POINT INDI AT=210 AF=195 B1=0.5 C1=1 K1=4 B2=2.256 C2=3.024 K22=1 C3=1 K3=1 CP=0.5 INDI AT=210 AF=215 BI=0.5 C=- K-1=4 B2=2.256 C2=3.024 K2=1 C3=l K3=1 CP=0.5 INDI AT=210 AF=240 B1=0.5 C1=I K1=4 B2=1.805 C2=3.024 K2=1 C3=1 K3=1 CP=0.5 INDI AT=210 AF=260 B1=0.5 C1=1 K1=4 B2=1.805 C2=3.024 K2=1 C3=1 K3=1 CP=0.5-------------------
*** SUPPORTS---------------------------
RSTN PT=675 DX=1 SP=16000 *RHR SUPPLY PENET.RSTN PT=675 DY=1 SP=16000 *RHR SUPPLY PENET.RSTN PT=675 DZ=1 SP=23000 *RHR SUPPLY PENET.ROTR PT=675 RX=1 SP=300000
*RHR SUPPLY PENET.ROTR PT=675 RY=1 SP=300000
*RHR SUPPLY PENET.ROTR PT=675 RZ=1 SP=340000
*RHR SUPPLY PENET.RSTN PT=565 DX=1 SP=16000 *RHR SUPPLY PENET.RSTN PT=565 DY=1 SP=16000 *RHR SUPPLY PENET.RSTN PT=565 DZ=1 SP=23000 *RHR SUPPLY PENET.ROTR PT=565 RX=1 SP=300000
*RHR SUPPLY PENET.ROTR PT=565 RY=1 SP=300000
*RHR SUPPLY PENET.ROTR PT=565 RZ=1 SP=340000
*RHR SUPPLY PENET.SNUB PT=12 DZ=-X SP=1000 *AL=$SNUBBER .SS-7A-2$SNUB PT=12 DX=1 SP=I000 *AL=$SNUBBER SS-7A-2$SNUB PT=190 DX=-I SP=1000 *AL=$SNUBBER SS-6-Al$SNUB PT=190 DZ=1 SP=1000 .*AL=$SNUBBER SS-6-A2$VSUP PT=20 DY=1 FO=24.8 SP=2.664 *AL=$VARI.
SUPT. HA-1$File No.: VY-16Q-307 Page A35 of A51 Revision:
0 F0306-01 RO Structural Integrity Associates, Inc. U CSUP CSUP CSUP CSUP CSUP CSUP CSUP vsuP VSUP VSUP VSUP VSUP VSUP PT=27 PT=42 PT=56 PT=69 PT=63 PT=160 PT=705 PT=184 PT=343 PT=313 PT=530 PT=620 PT=655 DY= 1 DY=1 DY=~1 DY= 1 DY= 1 DY---1 bY=1 DY=1 DY=1 DY=1 DY=1 DY= 1 DY=1 FO=8. 3 FO=8. 3 FO=18.05 FO=18.0 FO=18.02 FO=11. 8 FO=0.960 KP=0.01 KP=0.01 KP=0.01 KP=0 ..01 KP=0.01 KP=0.901 KP=0.01*AL=$CONST.
*AL=$CONST.
*AL&#xfd;$CONST.
*AL=$CONST.
*AL=$CONST.
*AL=$CONST.
*AL=$CONST.
SUPT.SUPT.SUPT.SUPT.SUPT.SUPT.SUPT.H-8-A1$H-8-A2S HA3 FOR PUMPS HA4 FOR PUMPS HA5 FOR PUMPS HA-9 & HA-10S HA-lI ON 4 INCH BYPASS$FO=36.0 FO=7. 1 FO=7 .1 SP=3.542 SP=3.014 SP=3. 014*AL=$VARI.
SUPT. HA-2$*AL$VARI.
SUPT. HA13$*AL=$VARI.
SUPT. HA14$SP=9.420 FO=26.0 SP=7.084 FO=14.9 SP=4.710 FO=22.0*AL=$HANGER H109*AL&#xfd;$HANGER H104*AL&#xfd;$HAN1GER H105 RHR SUPPLY VALVES RHR RETURN VALVE$RHR RETURN VALVES RSTN PT=15 RSTN PT=16 ENDP DY=0.7071 DZ=-0.7071 DX=-0.7071 DY=0.7071 SP=6000 SP=6000*RECIRC PUMP*RECIRC PUMP Regl.inp*BEGIN REGION 1 TRANSIENT CARDS & GEOMETRY FROM RHR SUPPLY TO TEE------------------------------
--------------------
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OPER OPER OPER OPER OPER OPER OPER OPER OPER OPER OPER OPER CA=1 CA=2 CA=3 CA=4 CA=5 CA= 6 CA=7 CA=8 CA= 9 CA=10 CA=11 CA=12 TE=100 TE=100 TE=549 TE=542 TE=526 TE=542 TE=526 TE=516 TE=526 TE=300 TE=500 TE=300 PR=1100 PR=50 PR=1010 PR=1010 PR=1010 PR=1010.PR=1010 PR=1010 PR=1010 PR=1135 PR=1135 PR=675 File No.: VY-16Q-307 Revision:
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*.BEGIN REGION 3 TRANSIENT CARDS & GEOMETRY-------------------------------
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0 Page A39 of A51 F0306-01 RO Structural Integrity Associates, Inc.TRAN CA=224 IS=1 FS=1 IT=526 FT=375 *TT=600 FL=32316 IP=I050 FP=240 TP=TRAN CA=225 IS=1 FS=1 IT=375 FT=I00 TT=9900 FL=32316 IP=240 FP=40 TP=0 PAIRA CA=201 C0=8.3 DI=0.140 EX=8.5 *Tavg=85.0 PAIR CA=202 CO=8.3 DI=0.140 EX=8.5 *Tavg=100.0 PAIR CA=203 CO=9.4 DI=0.151 EX=8.5 *Tavg=324.5 PAIR CA=204 CO=10.5 DI=0.162 EX=8.5 *Tavg=545.5 I PAIR CA=205 CO=10.4 DI=0.161 EX=8.5 *Tavg=534.0 PAIR CA=206 CO=10.4 DI=0.161 EX=8.5. *Tavg=534.0 PAIR CA=207 C0=10.4 DI=0.161 EX=8.5 *Tavg=534.0 PAIR CA=208 C0=I0.3 DI=0.161 EX=8.5 *Tavg=521.0 PAIR CA=209 CO=10.3 DI=0.161 EX=8.5 *Tavg=521.0 PAIR CA=210 CO=9.9 DI=0.156 EX=8.5 *Tavg=413.0 PAIR CA=211 CO=9.8 DI=0.155 EX=8.5 *Tavg=400.0 PAIR CA=212 CO=9 .8 DI=0 155 EX=8.5 *Tavg=400.0I PAIR CA=213 C0=9.9 DI=0.156 EX=8.5 *Tavg=424.5 PAIR CA=214 CO=10.4 DI=0.162 EX=8.5 *Tavg=537.5 PAIR CA=215 CO=10.0 DI=0.158 EX=8.5 *Tavg=462.0" PAIR CA=216 CO=9.5 DI=0.152 EX=8.5 *Tavg=352.5 PAIR CA=217 CO=9.2 DI=0.149 EX=8.5 *Tavg=277.5 PAIR CA=218 CO=8.7 DI=0.143 EX=8.5 *Tavg=162.5 PAIR CA=219 CO=8.3 DI=0.140 EX=8.5.*Tavg=100.0
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*BEGIN REGION 4 TRANSIENT CARDS & GEOMETRY'HEADER TO NOZZLE NODE 366---------------------
I----------
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0 F0306-O1 RO I V Structural Integrity Associates, Inc.I OPER OPER OPER OPER OPER OPER.OPER OPER OPER OPER OPER OPER TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN* TRAN TRAN TRAN TRAN TRAN TRAN CA=14 T CA=15 T CA=16 T CA=17 T CA=18 T CA=19 " T CA=20 T CA=21 T CA=22 T CA=23 T CA=24 T CA=25 T CA=201 CA=202 CA=203 CA=204 CA=205 CA=206 CA=207 CA=208 CA=209 CA=210 E=549'E=375 E=330 E=225 E=100 E=100 E=225 E=180 E=130 E=526 E=375 E=100 IS=1 F IS=1 F IS=1 E IS=1 IS=1 IS=1 IS=1 IS=1 IS=1 IS=1 PR=1035 PR=195 PR=115 PR=25 PR=25 PR=1563 PR=25 PR=25 PR=1035 PR=1035 PR=225 PR=25'S=1 3S=1'S=1 FS=1 FS=1 FS=1 FS=1 FS=1 FS=1 FS=1 IT=70 IT=100 IT=100 IT=549 IT=54 2 IT=-526 IT=542 IT=-52 6 IT=516 IT=52 6 F'T=100 TT=1800 F'T=100 TT=1800 F'T=549 TT=16164 FT=542 FT=526 FT=542 FT=526 FT=516 FT=526 FT=300 TT=0 TT=0 TT=900 TT=360 TT=0 TT=0 TT=220 CA=211 IS=1 FS=1 IT=300 FT=500 TT=1980 CA=212 IS=1 FS=1 IT=500 FT=300 TT=180 CA=213 IS=1 FS=I IT=300 FT=549 TT=8964 CA=214 IS=1 FS=1 IT=526 FT=549 TT=0 CA=215 IS=1 FS=1 IT=549 FT=375 TT=6264 CA=216 IS=1 FS-=1 IT=375 FT=330 TT=600 CA=217 IS=1 FS=1 IT=330 FT=225 TT=3780 CA=218 IS=1 FS=1 IT=225 FT=100 TT=4500*CA=219 IS=1 FS=1 IT=100 FT=100 TT=0 CA=220 IS=1 FS3=I IT=180 FT=225 TT=60 CA=221 IS=1 FS=1 IT=225 FT=180 TT=60*CA=222 IS=1 FS=1 IT=526 FT=130 TT=0 CA=223 IS=1 FS=1 IT=130 FT=526 TT=0 CA=224 IS=1 FS=1 IT=526 FT=375 TT=600 CA=225 IS=1 FS=1 IT=375 FT=100 TT=9900 FL=905 FL=905 FL=6463 FL=12926 FL=12926 FL=12926 FL=12926 FL=12926 FL=12926 FL=400 FL=400 FL=400 FL=6463 FL=12926 FL=6463 FL=6463 FL=6463 FL=9143 FL=905 FL=9143 FL=9143 FL=12926 FL=12926 FL=12926 FL=12926 IP=15" FP=1115 TP=0 IP=1115 FP=65 TP=0 IP=65 FP=1050 TP=0 IP=1050 FP=1050 TP=0 IP=i050 FP=1050 TP=0 IP=1050 FP=1050 TP=0 IP=1050 FP=1050 TP=0 IP=1050 FP=1050 TP=O IP=1050 FP=1050 TP=0 IP=1230 FP=1175 TP=0 IP=925 FP=1175 TP=0 IP1=175 FP=715 TP=0 IP=280 FP=1050 TP=0 IP=1050 FP=1050 TP=0 IP=1050 IP=210 IP=130 IP=40 IP=40 IP=40 IP=40 FP=210 TP=0 FP=130 TP=0 FP=40 TP=0 FP=40 TP=0 FP=15.78 TP=0 FP=40 TP=0 FP=40 TP=0 IP=1050 FP=1050 TP=0 IP=1050 FP=1050 TP=0 IP=1050 FP=240 TP=0 IP=240 FP=40 .TP=0 PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR CA=201 CA=202 CA=203 CA=204 CA=205 CA=206 CA=207 CA=208 CA=209 CA=210 CO=8.3 CO=8.3 CO=9.4 CO=10.5 CO=10.4 CO=10.4 CO=10.4 CO=10.3 CO=10.3 CO=9. 9 DI=0.140 EX=8.5 DI=0.140 EX=8.5 DI=0.151 EX=8.5 DI=0.162 DI=0.161 DI=0.161 DI=0.161 DI=0.161 DI=0. 161 DI=0. 156 EX=8. 5 EX=8. 5 EX=8. 5 EX=8. 5 EX=8. 5 EX=8. 5 EX=8. 5*Tavg=85.
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0 Page A41 of A51 F0306-OI RO V Structural Integrity Associates, Inc.*PAIR CA=222 CO=9.4 DI=0.151 EX=8.5 *Tavg=328.0 PAIR CA=223 CO=9.4 DI=0.151 EX=8.5 *Tavg=328.0 PAIR CA=224 CO=10.0 DI=0.157 EX=8.5 *Tavg=450.5 PAIR CA=225 CO=9.0 DI=0.147 EX=8.5 *Tavg=237.5 ReO5.inp*--B -------------------------------------
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0 Page A42 of A51 F0306-01 RO U Structural Integrity Associates, Inc.TRAN CA=225 IS=1 FS=1 IT=375 FT=100 TT=9900 FL=6463 IP=240 FP=40 TP=0 PAIR PAIR PAIR PAIR*PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR*PAIR PAIR PAIR PAIR CA=201 CA=202 CA=203 CA=204 CA=205 CA=206 CA=207 CA=208 CA=209 CA=210 CA=211 CA=212 CO=8.3 CO8.3 CO=9.4 4 CO=10.5 CO=10. 4 CO= 10.4 CO=10.4 CO=10.3 CO=10.3 CO=9. 9 CO=9.8 CO=9.8 DI=0.140 DI=0. 140 DI=0. 151 DI=0. 162 DI=0.163 DI=0. 161 DI=0. 161 DI=0. 161 DI=0. 161 DI=0. 15i DI=0. 155 D1=0. 155 EX=8.5 *Tavg=85.0 EX=8.5 *Tavg100.0 EX=8.5 *Tavg=324.5 EX=8.5 *Tavg=545.5 EX=8.5. *Tavg=534.0 EX=8.5 *Tavg=534.0 EX=8.5 *Tavg=534.0
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*BEGIN REGION 6 TRANSIENT CARDS & GEOMETRY-------------------------------
TO NOZZLE NODE 336 OPER CA=1 OPER CA=2 OPER CA=3 OPER CA=4 OPER CA=5 OPER CA=6 OPER CA=7 OPER CA=8 OPER CA=9 OPER CA=10 OPER CA=11 OPER CA=12 OPER CA=13 OPER CA=14 OPER CA=15 OPER CA=16 OPER CA=17 OPER CA=18 OPER CA=19 OPER CA=20 OPER CA=21 OPER CA=22 OPER CA=23 OPER CA=24 OPER CA=25 TE=100 TE=100 TE=549 TE=542 TE=526 TE=542 TE=526 TE=516 TE=526 TE=300 TE=500 TE=300 TE=549 TE=549 TE=375 TE=330 TE=225 TE=100 TE=100 TE=225 TE=180 TE=130 TE=526 TE=375 TE=100 PR=1100 PR=50 PR=1035 PR=1035 PR=1035 PR=1035 PR=1035 PR=1035 PR=1035 PR=1160 PR=1160 PR=700, PR=1035 PR=1035 PR=195 PR=115 PR=25 PR=25 PR=1563 PR=25 PR=25 PR=1035 PR=1035 PR=225 PR=25 TRAN CA=201 IS=1 FS=1 IT=70 FT=100 TT=1800 FL=452 IP=15 FP=1115 TP=0 File No.: VY-16Q-307 Revision:
0 Page.A43 of A51 F0306-01 RO V Structural Integrity Associates, Inc.TRAN TRAN.TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN.TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN PAIR PAIR PAIR.PAIR PAIR PAIR PAIR PAIR PAIR PAIR CA=202 CA=2 03 CA=204 CA=205 CA=206 CA=207 CA=208 CA=209 CA=210 CA=211 cA=212 CA=213 CA=214 CA=215 CA=216 CA=217 CA=218 CA=219 CA=220 CA=221 CA=222 CA=223 CA=224 CA=225 CA=201 CA=202 CA&#xfd;203 CA=204 CA=205 CA=206 CA=207 CA=208 CA=209 CA=210 IS=1 FS=1 IT=100 FT=100 IS=1 FS=1 IT=100 FT=549 IS=1 IS=1 IS=1 IS=1 IS=1 IS=1 IS=1 FS=1 FS=1 FS=1 FS=1 FS=I FS=1 FS=1 IT=549 IT=542 IT=526 IT=542 IT=526 IT=516 IT=526 FT=542 FT=526 FT=542, FT=526 FT=516 FT=526 FT=300 IS=1 FS=1 IT=300 FT=500 IS=1 FS=1 IT=500 FT=300 IS=1 FS=1 IT=300 FT=549 IS=1 FS=1 IT=526 FT=549 IS=1 FS=1 IT=549 FT=375 IS=1 FS=1 IT=375 FT=330 IS=1 FS=1 IT=330 FT=225 IS=1 FS=1 IT=225 FT=100 IS=1 FS=1 IT=100 FT=100 IS=1 FS=1 IT=i80 FT=225 IS=1 FS=1 IT=225 FT=180 IS=1 FS=1 IT=526 FT=130 IS=1 FS=1 IT=130 FT=526 IS=1 FS=1 IT=526 FT=375 TT=1800 TT=16164 TT=0 TT=0 TT=900 TT=360 TT=0 TT=0 TT=220 TT=1980 TT=180 TT=8964 TT=0 TT=6264 TT=600 TT=3780 TT=4500 TT=0 TT=60 TT=60 TT=0 TT=0 TT=600 FL=6463 FL=64 63 FL=6463 FL=6463 FL=6463 FL=6463 FL=200 IP=1050 IP=1050 IP=1050 IP=1050 IP=1050 IP=1050 IP=1230 FP=1050 FP=1050 FP=1050 FP=1050 FP=1050 FP=1050 FP=1175 TP=0 TP=0 TP=0 TP=0 TP=0 TP=0 TP=0 FL=452 IP=1115 FP=65 TP=0 FL=3232 IP=65 FP=1050 TP=0 FL=200 IP=925 FP=1175 TP=0 FL=200 IP=1175 FP=715 TP=0 FL=3232 IP=280 FP=1050 TP=0 FL=6463 IP=1050 FP=1050 TP=0 FL=3232 IP=1050 FP=210 TP=0 FL=3232 IP=210 FP=130 TP=0 FL=3232" FL=4572 FL=452 FL=4 572 FL=4572 FL=6463 FL=6463 FL=6463 IP=130 IP=40 IP=40 IP=40 IP=40 IP=1050 IP=1050 IP=1050 FP=40 TP=0 FP=40 TP=0.FP=1578 TP=0 FP=40 TP=0 FP=40 TP=0 FP=1050 TP=0 FP=1050 TP=0 FP=240 TP=0 IS=1 FS=1 IT=375 FT=100 TT=9900 FL=6463 IP=240 FP=40 TP=0 CO=8. 3 CO=8. 3 CO=9. 4 DI=0.140 EX=8.5 DI=0.140 EX=8.5 DI=0.151 EX=8.5*Tavg=85.0
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*Tavg=150.0 Reg8.inp*---------------------------------------
*BEGIN REGION 8 TRANSIENT CARDS & GEOMETRY FOR 4 INCH BYPASS OPER OPER OPER OPER OPER OPER OPER OPER OPER OPER OPER OPER OPER OPER OPER OPER OPER OPER CA= I CA=2 CA=3 CA= 4 CA=5 CA= 6 CA=7, CA= 8 CA= 9 CA=10 CA=11 CA=12 CA=13 CA=14 CA=15 CA=16 CA= 17.CA=18 TE=100 TE=100 TE=549 TE=542 TE=526 TE=542 TE=526 TE=516 TE=526 TE=300 TE=500 TE=300 TE=549 TE=549 TE=375 TE=330 TE=225.TE=100 PR=110.0 PR=50 PR=1035 PR=1035 PR=1035 PR=1035 PR=1035 PR=1035 PR=1035 PR=1160 PR=1160 PR=700 PR=1035 PR=1035 PR=195 PR=115 PR=25 PR=25 File No.: VY-16Q-307 Revision:
0 Page A47 of A51 F0306-01 RO Structural Integrity Associates, Inc.OPER OPER OPER OPER OPER OPER OPER CA=1 9 CA=20 CA=21 CA=22 CA=2 3.CA=24 CA=25 CA=201 CA=202 CA=203 TE=100 TE=225 TE=225 TE=130 TE=526 TE=375 TE=100 PR=1563 PR=25 PR=25 PR=1035 PR=1035 PR=225 PR=25 I I I I I I I TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRA1 TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN IS=i IS=1 IS=1 FS=1 FS=1 FS=I IT=70 IT=100 IT=100 CA=204 IS=]CA=205 IS=]0v=2 06 IS=]CA=207 IS=]CA=268 IS=]OA=209 IS=]CA=2,10 IS=2 CA=211 IS=1 L FS=1 IT=549-FS=1 IT=542 1 FS=1 IT=526-FS=1 IT=542 FS=l IT=526 FS=1 IT=516* FS=1 IT=526 FS=1 IT=300 FT=100 FT=100.FT=549 FT=542 FT=526 FT=542 FT=526 FT=516 FT=526 FT=300 FT=500 TT=1800 TT=1800 TT=16164 TT=0 TT=0 TT=900.TT=360 TT=0 TT=0 TT=220 TT=1980 TT=180 TT=8964 TT=0 TT=6264 TT=600 TT=3780 TT=4500 TT=0 FL=23.5 IP=15 FP=1115 TP=0 FL=23.5 IP=1115 FP=65 TP=0 FL=168 IP=65 FP=1050 TP=0 FL=335 IP=1050 FP=1050 TP=0 FL=335 IP=1050 FP=1050 TP=0 FL=335 IP=1050 FP=1050 TP=0 FL=335 IP=1050 FP=1050 TP=0 FL=335 IP=1050 FP=1050 TP=0 FL=335 IP=1050 FP=1050 TP=0 FL=6 IP=1230 FP=1175 TP=0 FL=6 IP=925 FP=1175 TP=0 FL=6 IP=1175 FP=715 TP=0 FL=167.5 IP=280 FP=1050 TP=0 FL=335 IP=1050 FP=1050 TP=0 FL=167.5 IP=1050 FP=210 TP=0 FL=167.5 IP=210 FP=130 TP=0 FL=167.5 IP=130 FP=40 TP=0 FL=167.5 IP=40 FP=40 TP=0 FL=23.5 IP=40 FP=1578 TP=0 CA=212 IS=_1 FS=1 IT=500 FT=300 CA=213 IS=1 FS=1 IT=300 FT=549 CA=214 IS=1 FS=1 IT=526 FT=549 CA=215 IS=I FS=1 IT=549 FT=375 CA=216 IS=1 FS=1 IT=375 FT=330 CA=217 IS=1 FS=1 IT=330.FT=225 CA=218 IS=1 FS=1 IT=225 FT=100 CA=219 IS=1 FS=1 IT=100 FT=100 CA=220 CA=221 CA=222 *IS=I FS=1 IT=526 FT=130 TT=0 CA=223 IS=1 FS=1 IT=130 FT=526 TT=0 CA=224 IS=1 FS=1 IT=526 FT=375 TT=600 CA=225 IS=1 FS=1 IT=375 FT=100 TT=9900 FL=335 IP=105C FL=335 IP=1050 FL=335 IP=1050 FL=335 IP=240 FP=1050 TP=0 FP=1050 TP=0 FP=240 TP=0 FP=40 TP=0 PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR CA=201 CA=202 CA=203 CA=204 CA=205 CA=206 CA=207 CA=208 CA=209 CA=2 10 CO=8. 3 CO=8. 3 CO=9. 4 CO=10.5 CO=10.4 CO=10.4 CO=10..4 CO=10.3 C0=10.3 C0=9. 9 DI=0. 140 DI=0. 140 DI=0. 151 DI=0. 162 DI=0.161 DI=0.161 Di=0. 161 DI=0.161 DI=0.161 DI=0.156 EX=8.5 *Tavg=85.0 EX=8.5 .*Tavg=100.0 EX=8.5 *Tavg=324.5 EX=8.5 *Tavg=545.5 EX=8.5 *Tavg=534.0 EX=8.5 *Tavg=534
.0 EX=8.5 *Tavg=534.0 EX=8.5 *Tavg=521.0 EX=8.5 *Tavg=521.0 EX=8.5 *Tavg=413.0 I I I I I I I I I I1 CA=211 CO=9.8 DI=0.155 EX=8.5 *Tavg=400.0 CA=212 CO=9.8 DI=0.155 EX=8.5 *Tavg=400.0 CA=213 CO=9.9 DI=0.156 EX=8.5 *Tavg=424.5 CA=214 CO=10.4 DI=0.162 EX=8.5 *Tavg=537.5 PAIR CA=215 CO=10.0 PAIR CA=216 C0=9.5 PAIR CA=217 CO=9.2 PAIR CA=218 CO=8.7 PAIR CA=219 CO=8.3*PAIR CA=220 C0=9.0*PAIR CA=221 CO=9.0*PAIR CA=222 C0=9.4 PAIR CA=223 CO=9.4 PAIR CA=224 CO=10.0 PAIR CA=225 CO=9.0 DI=0.158 EX=8.5 *Tavg=462.0 DI=0.152 EX=8.5 *Tavg=352.5 DI=0.149 EX=8.5 *Tavg=277.5 DI=0.143 EX=8.5 *Tavg=162.5 DI=0.140 EX=8.5 *Tavg100.0 DI=0.146 EX=8.5 *Tavg=225.0 DI=0.146 EX=8.5 *Tavg=225.0 DI=0.151 EX=8.5 *Tavg=328.0 DI=0.151 EX=8.5 *Tavg=328.0 DI=0.157 EX=8.5 *Tavg=450.5 DI=0.147 EX=8.5 *Tavg=237.5 File No.: VY-16Q-307 Revision:
0 Page A48 of A51 U I F0306-01 RO V Structural Integrity Associates, Inc.Reg9A.inp* -------------------
---- --- --- ---- ------*BEG1&#xfd;N REGITON 9A TRANSIENT CARDS K GEOMETRY FOR RHR RETURN FROM TEE TO VALVE NODE 660 OPER CA=1 OPER CA=2 OPER CA=3 OPER CA=4 OPER CA=5 OPER CA=6 OPER CA=7 OPER CA=8 OPER CA=9 OPER CA=10 OPER CA=11 OPER CA=12 OPER CA=13 OPER CA=14 OPER CA=15 OPER CA=16 OPER CA=17 OPER CA=18 OPER CA=19 OPER CA=20 OPER CA=21 OPER CA=22 OPER CA=23 OPER CA=24 OPER CA=25 TE=100 TE=100 TE=549 TE=542 TE=526 TE=542 TE=526 TE=516 TE=526 TE=300 TE=500 TE=300 TE=54 9 TE=54.9 TE=375 TE=330 TE=225 TE=100 TE=100 TE=225 TE=70 TE=130 TE=526 TE=375 TE=100 PR=1100 PR=50 PR=1035 PR=1035 PR=1035 PR=1035 PR=1035 PR=1035 PR=1035 PR=1160 PR=1160 PR=700 PR=1035 PR=1035 PR=195.PR=115 PR=25 PR=100 PR=1563 PR=25 PR=25 PR=1035 PR=1035 PR=225 PR=25 TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN PAIR PAIR PAIR CA=201 CA=202 CA=203 CA=204 CA=205 CA=206 CA=207 CA=208 CA=209 CA=210 CA=211 CA=212 CA=213 CA=214 CA=215 CA=216 CA=217 CA=218 CA=219 CA=220 CA=221 CA=2 22 CA=223 CA=224 CA=225 IS=1 IS=1 IS=1 IS=1 IS=1 IS=1 IS=l Is=1 IS=1 1S=I FS=1 FS=1 FS=1 FS=1 FS=I FS=1 FS=1 FS=1 FS=1 FS=1 IT=70 IT=100 IT=100*IT=549 IT1=542 IT1=52 6 11=542 11T=526 11=51 6 IT=526 FT=100 FT=100 FT=549 FT=542 FT=526 FT=542 FT=526 FT=516 FT=526 FT=300 IS=1 FS=1 IT=300 FT=500 IS=1 FS=1 IT=500 FT=300 IS=1 FS=1 IT=300 FT=549 IS=1 FS=1 IT=526 FT=549 IS=1 FS=1 IT=549 FT=375 IS=1 FS=1 IT=375 FT=330 IS=1 FS=1 IT:330 FT=225 IS=1 FS=1 IT=225 FT=100 IS=1 FS=1 IT=100 FT=100 IS=1 FS=1 IT=70 FT=225 IS=1 FS=1 IT=225 FT=70*IS=1 FS=1 IT=526 FT=130 IS=1 FS=1 IT=130 FT=526 IS=1 FS=1 IT=526 FT=375 IS=1 FS=1 IT=375 FT=100 TT=1800 TT=1800 TT=16164 TT=0 TT=0 TT=900 TT=360 TT=0 TT=0 TT=220 TT=1980 TT=180 TT=8964 TT=0 TT=6264 TT=600 TT=3780 TT=4500 TT=0 TT=60 TT=60 TT=0 TT=0 TT=600 TT=9900 FL=204 IP=15 FP=1115 TP=0 FL=204 IP=1115 FP=65 TP=0 FL=247 IP=65 FP=1050 TP=0 FL=520 IP=1050 FP=1050 TP=0 FL=511 IP=1050 FP=1050 TP=0 FL=511 IP=1050 FP=1050 TP=0 FL=511 IP=1050 FP=1050 TP=0 FL=502 IP=1050 FP=1050 TP=0 FL=502 IP=1050 FP=1050 TP=0 FL=437 IP=1230 FP=1175 TP=0 FL=429 IP=925 FP=1175 TP=0 FL=429 IP=1175 FP=715 TP=0 FL=443 IP=280 FP=1050 TP=0 FL=514 IP=1050 FP=1050 TP=0 FL=458 IP=1050 FP=210 TP=0 FL=403 IP=210 FP=130 TP=0 FL=260 IP=130 FP=40 TP=0 FL=6700 IP=115 FP=115 TP=0 FL=226 IP=40 FP=1578 TP=0 FL=6700 IP=40 FP=40 TP=0 FL=6700 IP=40 FP=40 TP=0 FL=389 IP=1050 FP=1050 TP=0 FL=389 IP=1050 FP=1050 TP=0 FL=458 IP=1050 FP=240 TP=0 FL=334 IP=240 FP=40 TP=0 CA=201 CO=8.3 CA=202 CO=8.3 CA=203 CO=9.4 DI=0.140 DI=0.140 DI=0.151 EX=8.5 *Tavg=85.0 EX=8.5 *Tavg=100.0 EX=8.5 *Tavg=324.5 I File No.: V Revision:
0{-16Q-307 Page A49 of A51 F0306-01 RO Structural Integrity Associates, Inc.I PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR CA=204 CO=10.5 DI=0.162 CA=205 CO=10.4 DI=0.161 CA=206 CO=10.4 DI=0.161 CA=207 CO=10.4 DI=0.161 CA=208 CO=I0.3 DI=O'.161 CA=209 CO=10.3 DI=0.161 CA=210 CO=9.9 DI=0.156 CA=211 CO=9.8 DI=0.155 CA=212 CO=9.8 DI=0.155 CA=213 CO=9.9 DI=0.156 CA=214 CO=10.4 DI=0.162 CA=215 CO=10.0 DI=0.158 CA=216 CO=9.5 DI=0.152 CA=217 CO=9.2 DI=0.149 CA=218 CO=8.7 DI=0.143.CA=219 CO=8.3 DI=0.140 CA=220 CO=8.6 DI=0.142 CA=221 CO=8.6 DI=0.142 EX=8.5 *Tavg=545.5 EX=8.5 *Tavg=534.0 EX=8.5 *Tavg=534.0 EX=8.5 *Tavg=534.0 EX=8.5 *Tavg=521.0 EX=8.5 *Tavg=521.0 EX=8.5 *Tavg=413.0 EX=8.5 *Tavg=400.0 EX=8.5 *Tavg=400.0 EX=8.5 *Tavg=424.5 EX=8.5 *Tavg=537.5 EX=8.5 *Tavg=462.0 EX&#xfd;8.5 *Tavg=352.5 EX=8.5 *Tavg=277.5 EX=8.5 *Tavg=162.5 EX=8.5 *Tavg=100.0 EX=8.5 *Tavg=147.5 EX=8.5 *Tavg=147.5
*PAIR CA=222 CO=9.4 DI=0.151 EX=8.5 *Tavg=328.0 PAIR CA=223 CO=9.4 DI=0.151 EX=8.5 *Tavg=328.0 PAIR CA=224 CO=10.0 DI=0.157 EX=8.5 *Tavg=450.5 PAIR CA=225 CO=9.0 DI=0.147 EX=8.5 *Tavg=237.5* ------------------------------
I I I I I I I I I I I I I I I*BEGIN REGION 9B TRANSIENT CARDS & GEOMETRY 675-------------------------------
FOR RHR RETURN FROM VALVE NODE 660 TO PENET. NODE OPER OPER OPER OPER OPER OPER OPER OPER OPER OPER OPER OPER OPER OPER OPER OPER OPER OPER OPER OPER OPER OPER OPER OPER OPER CA=1 CA=2 CA=3 CA=4 CA=5 CA=6 CA=7 CA=8 CA=9 CA=10 CA=11 CA=12 CA=13 CA=14 CA=15 CA=1 6 CA=17 CA=18 CA=19 CA=20 CA=21 CA=22 CA=2 3 CA=2 4 CA=25 TE=100.TE=100 TE=150 TE=150 TE=150 TE=150 TE=150 TE=150 TE=150 TE=150 TE=150 TE=150 TE=150 TE=150 TE=150 TE=150 TE=150 TE=100 TE=100 TE=225 TE=70 TE=150 TE=150 TE=150 TE=150 PR=1100 PR=50 PR=1035 PR=1035 PR=1035 PR=1035 PR=1035 PR=1035 PR=1035 PR=1160 PR=1160 PR=700 PR=1035 PR=1035 PR=195 PR=115 PR=25 PR=100 PR=1563 PR=25 PR=25 PR=1035 PR=1035 PR=225 PR=25 TRAN TRAN TRAN CA=201 CA=202 CA=203 IS=1 FS=1 IT=70 IS=1 FS=1 IT=100 IS=1 FS=1 IT=100 FT=100 TT=1800 FT=100 TT=1800 FT=150 TT=16164 FL=204 FL=204 FL=247 IP=15 I P=1115 IP=65 FP=1115 FP=65 FP=1050 TP=0 TP=0 TP=0 I TRAN CA=204 TRAN CA=205 File No.: VY-16Q-307 Page A50 of A5 Revision:
0 0 I F0306-O1R V Structural Integrity Associates, Inc.I TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN PAIR PAIR PAIR* PAIR* PAIR*PAIR* PAIR**PAIR*PAIR* PAIR*PAIR PAIR* PAIR*PAIR*PAIR PAIR* PAIR PAIR PAIR PAIR PAIR*PAIR*PAIR PAIR PAIR CA=206 CA=207 CA=208 CA=209 CA=210 CA=211 CA=212 IS=1 FS=1 IT=150 FT=150 CA=213 CA=214 CA=215 CA=216 IS=l FS=1 IT1=50 FT=150 CA=217 CA=218 IS=l FS=1 IT=225 FT=100 q CA=219 IS=1 FS=1 IT=100 FT1=00 CA=220 IS=I FS=I IT=70 FT=225 CA=221 IS=I FS=1 IT=150 FT=70 CA=222 CA=223 CA=224 IS=I FS=1 IT=150 FT=150 CA=225 IS=1 FS=1 IT=150 FT=150 FL=429 IP=1175 FP=715 TP=0 TT=600 FL=403 IP=210 FP=130 TP=0 FL=6700 IP=115 FL=247 .IP=40 FL=6700 IP=40 FL=6700 IP=40 FP=115 TP=0 FP=157.8 TP=0 FP=40 TP=0 FP=40 TP=0 FL=458 IP=1040 FP=240 FL=334 IP=240 FP=40 TP=0 TP=0 CA=201 CA=202 CA=203 CA=204 CA=205 CA=206* CA=207 CA=208 CA=209* CA=210 CA=211 CA=212 CA=2113 CA=214 CA=215 CA=216 CA=217 CO=27..6 CO=27.. 6 CO=27.6 CO=27. 6 CO=27. 6 CO=27. 6 CO=27. 6 CO=27. 6 CO=27. 6 CO=27.6 CO=27 .6 CO=27.6 CO=27 .6 CO=27 .6 CO=27 .6 CO=27 .6 CO=27 .6 DI=0. 521 DI=0. 512 DI=0 .506 DI=0. 49 DI=0.49_DI=O. 49cS DI=0.499 DI=0.49S DI=0.499 DI=0.4 9S DI=0.49S DI=0. 49S DI=0. 499 DI=0.49S DI=0.. 49S DI=0.499 DI=0. 499 EX=6. 4 EX=6. 4 EX=6. 4) EX=6.4) EX=6.4) EX=6.4) EX=6.4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 1 EX=6. 4 1 EX=6. 4 1 EX=6.4 1 EX=6.4*Tavg=85.
0*Tavg=100.0
*Tavg=125.0
*Tavg=150.0
*Tavg=l50.0
*Tavg=150.0
*Tavg=l50.0
*Tavg=150.0
*Tavg=150.0
*Tavg=l50.0
*Tavg=150.0
*Tavg=150.0
*Tavg=150.0
*Tavg=150.0
*Tavg=150.0
*Tavgl150.0
*Tavg=150.0 CA=218 CO=27.6 DI=0.496 EX=6.4 *Tavg=162.5 CA=219 CA=220 CA=221 CA=222 CA=223 CA=224 CA=225 CO=27.6 CO=27 .6 CO=27. 6 CO=27. 6 CO=27.6 CO=27.6 CO=27.6 DI=0.512 DI=0. 500 DI=0.509 DI=0.499 DI=0.499 DI=0.499 DI=0.499 EX=b. 4 EX=6. 4 EX=6. 4 EX=6.4 EX=6.4 EX=6.4 EX=.6. 4*Tavg=100.0
*Tavg=147.5
*Tavg=110.0
*Tavg=150.0
*Tavg=150.0
*Tavg=l50.0
*Tavg=150.0 File No.: VY-16Q-307 Revision:
0 Page A51 of A51 F0306-01 RO Structural Integrity Associates, Inc.APPENDIX B PIPESTRESS Output Description Fatigue results for reduced cycle count Fatigue results for full 60 year cycle count Output File Recirc 15.prf RHR 15.prf File No.: VY-16Q-30.7 Revision:
0 Page B I of B5 F0306-O1 RO l" Structural Integrity Associates, Inc.I Recirc 15.prf D S T C O M P U T ER S E R V I C E S S.A.F-4 .2 PAGE NO. 3947++ DST/PIPESTRESS
++ Vermont Yankee Version 3.5.1+026 PC-EXE Release: Jun CALCULATION NUMBER .3 CODE SECTION III CLASS I ASME-1998 Vermont Yankee Recirculation Fatigue Analysis RVP 2007/07/26 08:42:12 [42 FATIGUE ANALYSIS AT POINT. 600, WELDING TEE 600 TO 602 INDIVIDUAL STRESS RANGE CHECK LOAD SET PAIR I J 11 21 14 19 14 10 14 9 5.2 1 3 6.5 13 8 21 20 27 20 20 20 20 3 26 17 17 18 17 17 SALT EQN. 14 88675.84491.67184.65876.62914.55493.54186.53739.46216.46169.42799.42219.42196.42131.41392.NI 10 0 150 10 1 0 10 5 5 0 5 0 35 0 290 186 60 0 60 55 90 0 10 0 186 36 5 0 35 0 OCCURENCES
-NJ 150 140 140 0 150 149 5 0 149 144 144 139 13.9 104 104 0 150 90 5 0 150 60 60 50 150 0 50 45 45 10-- NUMBER USED 10 140 1 5 45 5 5 35 104 60 5 45 90 10 150 5 35 SETS ELIMINATED DYNAM.21 19 27 10 14 9 20 2 26 3 6 18 13 8 NO. CYCLES TO FAILURE 2801.3359.8221.8900.10868.20012.22574.23541.50502.50782.76939.82911.83156.83864.92408.DELTA Ti IN DEGREES F STRESSES IN PSI USAGE REMARKS FACTOR 0.0036 0.0417 0.0001 0.0006 0.0005 0.0002 0.0016 0.0044 0.0012 0.0001 0.0012 0.0001 0.0018 0.0001 0.0004 File No.: Revision: VY-16Q-307 0
I Structural Integrity Associates, inc.D S T C 0 M P U T E R S E R V I C E S S. A. F-4.2 PAGE NO. 3946++ DST/PIPESTRESS
++ Vermont Yankee Version 3.5.1+026 PC-EXE Release: Jun CALCULATION NUMBER 3 CODE SECTION III CLASS 1 ASME-1998 RVP Vermont Yankee Recirculation Fatigue Analysis FATIGUE ANALYSIS AT POINT 600, WELDING TEE 600 TO 602 INDIVIDUAL STRESS RANGE CHECK 2007/07/26 08:42:12 [421 DELTA TI IN DEGREES F1 STRESSES IN PSI I LOAD SET PAIR r T 7 1 4 4 4 26 17 15 16 is 12 27 5 SALT EQN. 14 41326.38663.35177.34727.25167.23758.2773.10 0 55 0 290 140 140 45 45 35 45 0 35 0------ OCCURENCES
------NT N.T NUMBER SETS USED ELIMINATED DYNAN.10 0 150 95 150 0 95 0 10 0 45 0 36 1 10 55 150 7,17 1 16 NO. CYCLES TO FAILURE 93222.133841.227086.95 10 45 35 15 246096.12 1449206.,27 26 1748766.4 >100000000000.
USAGE REMARKS FACTOR 0.0001 0.0004 0.0007 0.0004 0.0000 0.0000 DYN. RANGE OF EVENT NO.0.0000 0.0590 I I TOTAL USAGE FACTOR I Notes a: Fails f: Weld ISI j: Rupture Location I I I File No.: VY-16Q-307 Revision:
0 I I I lI I I Istructural Integrity Associates, Inc.RHR 15.prf D S T COMPUTER SERVICES S.A.F-4.2 PAGE NO. 401S++ DST/PIPESTRESS
++Vermont Yankee Version 3.5.1+026 PC-EXE Release: Jun CALCULATION NUMBER 3 CODE SECTION III CLASS 1 ASME-1998 Vermont Yankee Recirculation Fatigue Analysis FATIGUE ANALYSIS AT POINT 641, SR ELBOW INDIVIDUAL STRESS RANGE CHECK RVP 640 TO 641 2007/07/26 08:44:06 [4-DELTA TI IN DEGREES F STRESSES IN PSI LOAD SET PAIR I J 10 20 11 21 12 20 20 21 3 21 3 17 13 17 14 18 15 19 1 15 6 15 9 15 4 15 7 27 4 16 SALT EQN. 14 100252.68706.64893.39947.35368.20439.19221.14925.14877.14434.12896.12506.11542.10017.9993.NI 10 0 20 0 20 0 270 0 300 290 290 0 10 0 300 0 300 299 120 0 20 0 70 0 579 490 20 15 490 190 OCCURENCES
------ NUMBER NJ USED 300 10 290 300 20 280 290 20 270 280 270 10 10 10 0 300 290 10 10 10 0 300 300 0 1 1 0 299 120*179 179 20 159 159 70 89 89 89 0 5 5 0 45 300 300 0 SETS ELIMINATED DYNAM, 10 11 20 21 3 13,17 14,18 >19 1 >6 9 >15 >27 >16 >NO. CYCLES TO FAILURE 1788.7511.9456., 112120.219528.3190872.4148766.100000000000.
100000000000.
100000000000.
100000000000.
100000000000.
100000000000.
100000000000.
100000000000.
USAGE REMARKS FACTOR 0.0056.0.0027 0.0021 0.0024 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 File No.: VY-16Q-307 Revision:
0 Structural Integrity Associates, Inc.I1 D S T C O M P U T E R S E R V I C E S S. A. F-4.2 PAGE NO. 402C++ DST/PIPESTRESS
++ Vermont Yankee Version 3.5.1+026 PC-EXE Release: Jun-. -.....- ----. --.-. .-. .-. --. --. --.-. .-. .-. .-. --. --.-. .-. .-. .-. --. --. --. -. .-. .-. --. --. --. -..- ..- .CALCULATION NUMBER 3 CODE SECTION III CLASS 1 ASME-1998 Vermont Yankee Recirculation Fatigue Analysis FATIGUE ANALYSIS AT POINT 641, SR ELBOW INDIVIDUAL STRESS RANGE CHECK RVP 2007/07/26 08:44:06 [41 640 TO 641 DELTA T1 IN DEGREES STRESSES IN PSI LOAD SET PAIR SALT I J EQN.14 2 7 9353.2 5 9353.5 26 8235.26 27 2019.4 5 1570.5 8 1512.NI 120 105 105 0.474 469 45 0 190 0 279 209 OCCURENCES
------ NUMBER NJ USED 15 15 0 579 105 474 5 5 0 45 45 45 0 469 190 279 70 70 0 SETS NO. CYCLES ELIMINATED TO FAILURE DYNAM.7 >100000000000.
2 >100000000000.
26 >100000000000.
,27 26 >100000000000.
4 >100000000000.
8 >100000000000.
USAGE REMARKS FACTOR 0.0000 0.0000 0.0000 0.0000 DYN. RANGE OF EVENT NO.0.0000 0.0000 I I I I I I 0.0128 TOTAL USAGE FACTOR =Motes a: Fails f: Weld ISI j: Rupture Location''I I U File No.: VY-16Q-307 Revision:
0 I I I I I I I Structural Integrity Associates, Inc. File No.: VY-16Q-308"I. NEC-JH_ 11 CALCULATION PACKAGE Project No.: VY-16Q PROJECT NAME: Environmental Fatigue Analysis of VYNPS CONTRACT NO.: 10150394 CLIENT: PLANT: Entergy Nuclear Operations, Inc. Vermont Yankee Nuclear Power Station CALCULATION TITLE: Core Spray Nozzle Finite Element Model Project Manager Preparer(s)
&Document Affected.
Revision Description Approval Checker(s)
Revision Pages Signature
& Date Signatures
& Date 01-7, Initial Issue Terry J. Herrmann Roland Horvath Appendix:
07/19/2007 07/12/2007 A1-A17 John Staples 07/12/2007 Page 1 of 7 F0306-O1 RO V Structural Integrity Associates, Inc.I I I Table of Contents 1.0 OBJECTIVE
...................................................................................................................................
3.2.0 GEOM ETRY / M ATERIAL PROPERTIES
............................................................................
3 3.0 PROGRA M IN PUT.........................................
I .............................................................................
4 4.0 REFEREN CES ............................................................................................................................
5 APPENDIX A VYCSNGEOM.INP
..........................................
Al List of Tables Table 1: M aterial Properties
@ 300'F () ..................................................................................
....... 6 List of Figures I I I I I I I I I I I I I I I Figure 1: AN SYS Finite Elem ent M odel ..........................................................................................
7 File No.: VY-16Q-308 Revision:
0 Page 2 of 7 F0306-0 RO I U Structural Integrity Associates, Inc.I1.0 OBJECTIVE The objective of this calculation is to create a finite element model of the Vermont Yankee Nuclear Power Station Core Spray Nozzle. This model will be used to develop a Green's. Function to be used in a subsequent fatigue analysis.2.0 GEOMETRY I MATERIAL PROPERTIES I A 2-D axisymmetric finite element model (FEM) of the nozzle was developed with element type PLANE82. The developed model includes the part of the pipe, the safe end, the nozzle forging, a portion of the vessel shell, and the cladding.
The radius of the vessel in the finite element model was multiplied by a factor of 2 to account for the fact that the vessel portion of the 2D axisymmetric model is a sphere, but the true geometry is a cylinder.
The equation for the membrane hoop stress I for asphere is: (pressure) x (radius)2 x thickness The equation for the membrane hoop stress in a cylinder is: I (pressure) x (radius)thickness The factor of two was verified in Reference
[I I] where actual stress results were compared to the I results of this analytical form.The 2-D axisymmetric FEM was constructed using the dimensions and information from References
[1 -8] based on ANSYS [9] finite element software.
Figure 1 shows the resulting finite element model.The materials of the various components of the model are listed below:* Safe End -SB 166 [1] (72Ni-I5Cr-8Fe, N06600): 80 x 100 Conc. Reduction-SA312 TP304 [7] (18Cr-8Ni)
I Nozzle Forging -SA508 Class I1 [1] (3/4 Ni-l/2Mo-l/3 Cr-V)* Vessel -SA533 Grade B [7] (Mn-1/2Mo-1/2Ni)
Cladding -SA240 TP 304 [7] (18Cr-8Ni)
Note: In the FEM, the 80 x 100 Conc. Reduction was modeled as a straight pipe with the material properties of the original design [7]. Later, this piping section was replaced by a new material (SA403 T316L) [10]. These two stainless steels have the same modulus of elasticity and thermal coefficient properties.
File No.: VY-16Q-308 Page 3 of 7 Revision:
0 F0306-OIRO Structural Integrity Associates, Inc.Material properties for these materials are based upon the 1998 ASME Code, Section II, Part D, with 2000 Addenda [8] and are shown in Table 1. The properties are taken at an average temperature of 300'F. This average temperature is based on a thermal shock of 500'F to 100'F, which will be applied to the FEM model for Green's Function development.
 
===3.0 PROGRAM===
INPUT The input file, VY CSNGEOM.inp (included in Appendix A), creates the finite element model for the core spray nozzle.I I I I I I I I I I I I I I I I I File No.: VY-16Q-308 Revision:
0 Page 4 of 7 F0306-OI RO Structural Integrity Associates, Inc.
 
==4.0 REFERENCES==
: 1. Reactor 8 In. Dia. Nozzles Mk. N5A & B, 5920-00624 Rev. 8, SI File No. VY-16Q-207.
: 2. Core Spray Nozzle Weld Overlay Profile N5A & N5B, 5920-068i3, Sh. 1 of 2 Rev. 0, SI File No. VY-16Q-206.
: 3. N5A/B Thermal.Sleeve Details, 5920-00898, Rev 1, SI File No. VY-16Q-206.
: 4. Special Safe End Forging for Nozzles N2A/B & N5A/B, 5920-00655, Rev. 6, SI File No. VY-16Q-206.5. Special Forgings for Nozzles N5A & N5B, 5920-00069, Rev 1, SI File No. VY-16Q-206.
: 6. Core Spray Nozzle Weld Overlay Profile N5A & N5B, 5920-06813, Sh. 2 of 2 Rev. 0, SI File No. VY-16Q-204.
: 7. CB&I RPV Stress Report, Section S7, "Stress Analysis Core Spray and Flooding Nozzle, Vermont Yankee Reactor Vessel, CB&I Contract 9-6201, S1 File No. VY-16Q-206.
: 8. American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section II, Part D, 1998 Edition, 2000 Addenda.9. ANSYS, Release 8.1 (w/Service Pack 1), ANSYS, Inc., June 2004.10. "10" x 8" SA403 T316L CONC REDUCER", Page 1.8 of Attachment 2 of Entergy Design Input Record (DIR) EC No. 1773, Revision 0, "Environmental Fatigue Analysis for Vermont Yankee Nuclear Power Station," 7/3/07, SI File No. VY-16Q-209.
: 11. SI Calculation No. VY-16Q-309, Revision 0, "Core Spray Nozzle Green's Functions".
File No.: VY-16Q-308 Page 5 of.7 Revision:
0 F0306-OIRO Structural Integrity Associates, Inc.I I I Table 1: Material Properties
@ 300'F ()Notes: 1. The material properties applied in the analyses are taken from ASME Code, Section I, Part D 1998 Edition, with 2000 information provided in the Design Input Record (page 13 of VY EC No. 1773, SI File No. VY- 16Q-209).
The use of a for the original design code is acceptable, since later editions typically reflect more accurate material properties than wa editions.
Material Properties are evaluated at 300'F from the 1998 ASME Code, 2000 Addenda, Section 11, Part D, except for densi assumed typical values [8].2. In the FEM, the 80 x 100 Cone. Reduction was modeled as a straight pipe with the material properties of the original d was replaced by a new material (SA403 T316L). These two stainless steels have the same modulus of elasticity and thei 3. Calculated as [k/(pd)]/12 3.File No.: VY-16Q-308 Revision:
0!I I I I I I V Structural Integrity Associates, Inc.i I- ,UM AN0.APIR 11&#xfd; 21007 II: 12 :.16 L] ..........................
ELEMENPI3, M4AT. -NUM APR; 11 2007 10:2 f 12:6 Core. 'Siray Nozzle Firnite Elem~ent Model Figure 1: ANSYS Finite Element Model File No.: VY-16Q-308 Revision:
0 Page 7 of 7 F0306-01 RO Structural Integrity Associates, Inc.APPENDIX A VYCSNGEOM.INP File No.: VY-16Q-308 Revision:
0 Page Al of A17 F0306-01 RO I Structural Integrity Associates, Inc.I!finish/clear,start I/prep7 I et,I,PLANE182,,, 1 !Axisymmetric
/com, **************************
/com, Material Properties
@T=300F/com, ****************************
/COM, Material #1 (Nozzle: SA-508 Class 11, 3/4Ni-I/2Mo-1/3Cr-V) mp,ex ,1,26.7E+06 I mp,alpx, 1,7.3E-06 mp,kxx ,1,23.4 /3600/12 mp,c ,1,0.1193277 mp,nuxy, 1,0.3 mp,dens, 1,0.283 I /COM, Material #2 (Safe End: N06600, Inconel 82 Weld Overlay)mp,ex ,2,29.8E+06 mp,alpx,2,7.9E-06 I mp,kxx,2,9.6
/3600/12 mp,c ,2,0.1157407 mp,nuxy,2,0.29 mp,dens,2,0.3
/COM, Material #3 (Vessel: SA-533 Grade B, Mn-1/2Mo-1/2Ni)
I mp,ex ,3,28.00E+06 mp,alpx,3,7.7E-06 mp,kxx ,3,23.4 /3600/12 mp,c ,3,0.1193277 mp,nuxy,3,0.3 mp,dens,3,0.283
/COM, Material #4 (3/16 Clad: SA-240 TP304, 8-10 Diam. Conc. Red.: SA-312 TP 304, Thermal Sleeve: SA-312 TP304)mp,ex ,4,27.OE+/-06 mp,alpx,4,9.8E-06 mp,kxx,4,9.8
/3600/12 rmp,c ,4,0.1252495 mp,nuxy,4,0.3 I mp,dens,4,0.283
* /com, */com, Geometric Parameters
/com, *****AFUJN,deg File No.: VY-16Q-308 Page A2 of A17 Revision:
0 F0306-0 I RO Structural Integrity Associates, Inc./com, pipe parameters
*set, pID, 9.834*set, pOD, 10.815*set, pL, 8 k, 1, pID/2, 0 k, 2, POD/2, 0 k, 3, POD/2, pL k, 4, PID/2, pL 1, 1, 1,2, 1, 3, 2 3 4 1,4, 1*/com,**********
/com, Safe End Parameters
/oom,**********
*set, seBX, pL*set, selDOl, 9.834.*set, seID02, 9.*set, selD03, 9 + 31/32*set, seID04, 11+ 3/4*set, seOD01, 10.815*set, seOD02, 11 + 1/6*set, seOD03, 13 + 27/64*set, seOD04, 10 + 11/16 I I I I I I I I I I I I I I I I.I I I*set, seLO1, 3 + 1/32*set, seL02, 7/8*set, seL03, 1+11/16*set, seL04, 13/32*set, seL05, 4*set, seL06, 3+1/2*set, seLO7, 12+4+/-1/16*set, seL08, seL07-(seLO 1 +seL02+seLO3+seLO4+seLO5+seLO6)
*set, seRO1, 3*set, seR02, 3/4*set, seR03, 1/4*set, seR04, 1/8 k, 5, seOD01/2, seBX+seLO0 k, 6, seOD02/2, seBX+seLO 1 +seL02 File No.: VY-16Q-308 Revision:
0 Page A3 of A17 F0306-0I RO V Structural Integrity Associates, Inc.k, 7, seOD02/2, seBX+seL01
+seL02+seLO3+seLO4
+A496 k, 8, (seOD02+seOD03)/4, seBX+seL01+seLO2+seLO3+seLO4+seLO5/2 k, 9, seOD03/2, seBX+seL01
+seL02+seLO3+seLO4+seLO5 k, 10, seOD03/2, seBX+seL01
+seLO2+/-seLO3+seL04+seLO5+seLO6 k, 11, seID04/2, seBX+seL0 I+seLO2+seLO3+seLO4+seL05+seL06 k, 12, seID04/2, seBX+seL0I+seLO2+seLO3+seLO4+seLO5 k, 13, seOD04/2, seBX+seL01+seL02+seLO3+seLO4+seLO5 k, 14, seOD04/2, seBX+seL07 k, 15, seID03/2, seBX+seL07 k, 16, selD02/2, seBX+seLO0+seLO2+seLO3+seL04+seLO5 k, 17, selD02/2, seBX+seL01
+seLO2+seLO3+seLO4 k, 18, selDO0/2, seBX+seL01
+seL02+seLO3 1,3, 5.1,5,6 1,6,7 1,9, 10 1, 10, 11 1, 11,12 1, 12, 13 1, 13, 14 1, 14, 15 1, 15, 16 1, 16, 17 1, 17,18 1, 18,4 k, 19, seOD02/2+seR01, seBX+seLO I+seL02+seLO3+seLO4
+.496 k, 8, seOD02/2+seRO1, seBX+seL01
+seLO2+seLO3+seLO4+seROI
+.496 larc, 7, 8, 19, seRO1 k, 20, seOD03/2-seRO1, seBX+seLO 1+seL02+seL03+seLO4+seLO5 k, 21, seOD03/2-seRO1, seBX+seLO I+seL02+seLO3
+seLO4+seLO5-seROI larc, 9, 21, 20, seRO1 L2ANG, 19,18,0,0,,, Idele, 20, 21, 1 Ifillt, 5, 6, seR02 Ifillt, 6, 7, seR02 lfillt, 10, 11, seR03 lfillt, 11, 12, seR03 Ifillt, 15, 16, seR04 lfillt, 16, 17, seR04/com, weld 1/8 gap*set, wgap, 1/8 File No.: VY-16Q-308 Page A4 of A17 Revision:
0 F0306-OIRO Structural Integrity Associates, Inc. H k, 40, seOD03/2, seBX+seLOl+seLO2+seLO3+seL04+seL05+seLO6
+ wgap n k, 41, selD04/2, seBX+seLO0+seL02+seL03+seLO4+seLO5+/-seL06
+ wgap 1, 10,40 1,40, 41 1,41,11/com, ***********
/com; Nozzle/com, ***********
*set, nlDO1, seODO1*set, nOD01, seOD03*set, nOD02, 24+1/4*set, nOD03, 2* 12+7.25*set, nOD04, 2* 12+7.25-1-1/8
*set, nLOl, 4+5/16 I**set, nL02, 5+3/8*set, nL03, 5+1/8+5+5/8
*set, nWO1, 1/16 n.*set, wClad, 3/16*Set, wReactor, 5+5/8-wClad
*set, nL04, 7/16* set, nR01, 1/4*set, nR02, 3/16* set, nR03, (8*12+7)*2
*set, nR04, 2.5*set, nR05, nR04-wClad
*set, nR06, 3.5*set, nR07, 3 +7/8.*set, nR08, 0.5 u K, 42, KX(11) + nWO1, KY(11)K, 43, KX(41) + wClad, KY(41)+nLO4+nRO I K, 44, KX(43) + nROI, KY(43)K, 46, KX(44) + nR01 *sin(15), KY(44)-nR01
*cos(15)K, 47, KX(46) + 10*nR01 *cos(15), KY(46)+ 10*nRO I*sin(15)K, 48, KX(43), KY(43) + 24 K, 49, KX(41), KY(41) + 24 K, 50, KX(40), KY(40) + nLO1 K, 51, KX(44) + (nRO I+wClad)*sin(15), KY(44)-(nRO I +wClad)*cos( 15)K, 52, KX(51)+ 10*nROl*cos(15), KY(51)+10*nRO0*sin(15)
K, 53, KX(51) -10*nRO0*cos(15), KY(51)-10*nR01*sin(15)
K, 54, KX(42), KY(42)+wClad*2 larc, 43, 46, 44, nR01 File No.: VY-16Q-308 Page A5 of A7 1 Revision:
0 F0306-01RO Structural Integrity Associates, Inc.L, 46, 47 L, 43, 48 L, 41, 49 L, 40, 50 IL, 53, 52 L, 42, 54 LOVLAP, 35,36 LDELE, 39, 40,,0 LOVLAP, 31,34,38 LDELE, 40,42,2,0 3 Ifillt, 37, 35, nR02 K, 60, nOD02/2, KY(40) + nL01+nL02 K, 61, nOD02/2, KY(40) + nL01+nL02+nLO3 K, 62, 0, KY(40) + nLOl+nLO2+nLO3+nRO3 K, 63, 0, KY(62) -nR03 U K, 64, nR03, KY(62)K, 65, 0, KY(63)-wClad K, 66, nR03+wClad, KY(62)I .K, 67, 0, KY(65)-wReactor K, 68, nR03+wReactor, KY(62)LARC, 63, 64, 62, nR03 LARC, 65, 66, 62, nR03+wClad LARC, 67, 68, 62, nR03+wReactor I L, 64, 66 L, 66, 68 I LOVLAP, 34, 33 LDELE, 46,47 LOVLAP, 32, 38 LDELE, 34 LDELE, 46 LFILLT,45,48,nRO4,, LFILLT,33,47,nRO5,, L, 50, 60 L, 60, 61* LOVLAP, 40,46 File No.: VY-16Q-308 Page A6 of A17 Revision:
0 F0306-OIRO V Structulral integrity Associates, Inc.LDELE, 50, 51 i LFILLT,49,52,nRO6 LFILLT,38,41,nR07 LFILLT,49,38,nRO8
/com, Nozzle and Vessel border K, 80, nODO3/2, KY(60)+/-2*nLO3 K, 81, nOD03/2, KY(60)K, 82, nOD4/2, KY(60)+/-2*nLO3 K, 83, nOD04/2, KY(60)L, 80,81 L, 82,83 LPTN, 53,48 LPTN, 51, 52 LDELE, 56, 59,1,0 LSTR, 76, 75 LPTN, 51, 47 1 KL,40,0.5,, KL,34,0.5,, KL,32,0.5,, LSTR, 78, 79 LSTR, 79, 84 K, 90, KX(73)+wReactor*2*cos(160), KY(73)+wReactor*2*sin( 160)L, 73, 90 I LPTN, 59, 33 LPTN, 63, 45 LDELE, 65 K, 91, KX(71)+wReactor*2*cos(170), KY(7 1)+wReactor*2*sin(170)
L, 71, 91 LPTN, 45, 60 LPTN, 33, 67 LDELE, 69 KCENTER,KP,69,78,70,0 LSTR, 89, 58 LSTR, 89, 57 LPTN, 40, 33, 67 LDELE, 73, 74 L, 58, 56 L, 57, 55 File No.: VY-16Q-308 Page A7 ofA7 i Revision:
0 F0306-OI RO Structural Integrity Associates, Inc.I/com, ***********
/com, Weld Overlay/CON,************
I *set, woA, 3.100*set, woB, 0.781*.set, woC, 2.500 I *set, woD, 3.734*set, woE, 3.480*set, woF, 6.3 10 I *set, woG, 8.313*set, woH, 0.535*set, woR0l, 7/16 i K, 80, KX(40), KY(40)-wgap/2-woA K, 81, KX(80)+woH, KY(80)+woH U K, 83, KX(40), KY(40)-wgap/2+woB/2+woC K, 82, KX(83)+woH, KY(83)-woH I L, 80, 81 L, 81, 82 L, 82,83 I LPTN, 74, 46 I LDELE, 79 LFILLT,78,76,woR0 1,, LSTR, 94, 96/com,/com, Heat transfer coef. points S /tom, *************
* set, tsLO1, 2.25*set, tsL02, 3.5 I K, 100, KX(41), KY(1 1)+seL08+tsLO1 K, 101, KX(4 1)+wClad, KY( 11 )+seLO8+tsLO I K, 102, KX(41), KY(1 1)+seLO8+tsL01
+tsL02 K, 103, KX(41)+wClad, .KY(1 1)+seLO8+tsL01
+tsL02 L, 100, 101 L, 102, 103 I LDELE, 51 LDELE, 47 I File No.: VY-16Q-308 Page A8 of A17 Revision:
0 F0306-01 RO V Structural Integrity Associates, Inc. I K, 104, KX(103)+wReactor*cos(-20), KY(1 03)+wReactor*sin(-20)
U K, 105, KX(101)+wReactor*cos(-
10), KY(101)+wReactor*sin(-
10)L, 103, 104 L, 101, 105 LPTN, 38, 47 LPTN, 76, 51 LDELE, 86 LDELE, 84 LDELE, 65 LDELE, 68 LDELE, 63 LDELE, 45 LDELE, 66 LDELE, 60 LSTR, 43, 101 LSTR, 101, 103 LSTR, 103, 85 LSTR, 86, 102 l LSTR, 102, 100 LSTR, 100, 41 LDIV,30,0.5, ,2,0 K, 106, KX(99)+wReactor*cos(200), KY(99)+wReactor*sin(200)
K, 107, KX(38)+wReactor*cos(160), KY(38)+wReactor*sin(160)
I L, 99, 106 L, 38, 107 LPTN, 66, 84 LPTN, 88, 76 LDELE, 89,90 I LSTR, 99, 38 LDELE, 28 LSTR, 26, .9 LSTR, 29, 16 LTRB, 11,29,0 LCOMB, 11,23,0 I LCOMB,1 11,24,0 LDIV, 11,, ,3,0 K, 110, KX(22)+wReactor*cos(180), KY(22)+wReactor*sin(180)
L, 110, 22 1 LPTN, 15, 89 LDELE, 94 File No.: VY-16Q-308 Page A9 ofA17 i Revision:
0 F0306-01 RO I C Structural Integrity Associates, Inc.LSTR, 28, 111 LSTR, 27, 22 LSTR, 17, 7 K, 112, KX(33)+wReactor, KY(33)L, 33, 112 LPTN, 7, 95 LDELE, 99 K, 114, KX(25)+wReactor*cos(180), KY(25)+wReactor*sin(180)
L, 114,25 K, 115, KX(8)+wReactor*cos(180), KY(8)+wReactor*sin(180)
L, 115,8 LPTN, 95,17 LPTN, 7,101 LDELE, 102,103/com,**************
/com, Creating Areas and Meshing/tom, *************
allsel,all,all MSHKEY,1 ! MAPPED MESHING AL, 1,2,3,4 MAT,4 ! Pipe LESIZE, 1 ,,,8 LESIZE,3 ,,,8 LESIZE,2,,,20 LESIZE,4,,,20 AMESH, 1 MAT,2 ! Safe End AL, 3, 5, 100, 99 LESIZE,3,,,8 LESIZE,100,,,8 LESIZE,5,,,20 LESIZE,99,,,20 AMESH, 2 LCOMB, 20,6,0 LCOMB, 6,21,0 AL, 100, 6, 17, 104 LESIZE,100,,, 8 LESIZE, 17,,, 8 LESIZE,6,,,10 LESIZE, 104,,, 10 AMESH, 3 File No.: VY-16Q-308 Page A1O of A17 Revision:
0 F0306-OIRO Structural integrity Associates, Inc.I AL, 17, 97, 98, 95 LESIZE, 17,,,8 i LESIZE,98,,,8 LESIZE,97,,, 10 LESIZE,95,,, 10 AMESH, 4 LDELE, 94 LSTR, 7, 30 LCOMB, 26,16,0 LCOMB, 16,25,0 i AL, 98, 96, 7, 16 LESIZE,98,,,8 LESIZE,7,,, 8 LESIZE,96,,, 8 LESIZE, 16,,,8 AMESH, 5 LCOMB, 18,22 AL, 7, 18, 92, 93 LESIZE,7,,,8 LESIZE,92,,,8 I LESIZE, 18,,, 10 LESIZE,93,,, 10 AMESH, 6 AL, 92, 89, 23, 15 LESIZE,92,,,8 I LESIZE,23,,,8 LESIZE,89,,, 8 LESIZE,15
,,, 8 AMESH, 7 AL, 15, 24, 88, 90 i LESIZE, 15 ,,,8 LESIZE,24,,, 8 LESIZE,88
,,,8 LESIZE,90,,, 8 AMESH, 8 AL, 89, 19, 28, 11 LESIZE,89,,, 8 LESIZE, 19,,, 8 LESIZE,28
,,,8 File No.: VY-16Q-308 PageAll ofAl7 i Revision:
0 F0306-O I RO Structural integrity Associates, Inc.LESIZE,1 1,,,8 AMESH, 9 AL, 88, 12, 13, 14 LESIZE,88,,,8 LESIZE, 13 ,,,8 LESIZE, 12, ,,28,5,.,,,1 LESIZE, 14, ,,28,0.2 .... I AMESH, 10 K, 118, KX(80)+wReactor*cos(180), KY(80)+wReactor*sin(180)
L, 118,80 LPTN, 10,20,8 LDELE, 101 AL, 28, 21, 94, 26 LESIZE,28,,,8 LESIZE,94,,,8 LESIZE,21
,,,6 LESIZE,26,,,6 AMESH, 11.LDELE, 9 LSTR, 42,. 11 LSTR, 42, 10 LESIZE, 8, ,2 ..... , LESIZE,9,, ,6 ..... I LESIZE,22,, ,20,0.2 .... I LESIZE,25, ,,.20,0.2
.... 1 AL, 94, 22, 9, 8, 25 AMAP, 12,11,10,80,21 LCOMB, 37, 31 LCOMB, 27, 36 AL, 9, 27, 35, 31 LESIZE,35,,,6 LESIZE,27,,, 4 LESIZE,31,,,4 AMESH, 13 MAT,4 ! Clad LCOMB, 68, 39 File No.: VY-16Q-308 Page A12 of A17 Revision:
0 F0306-01 RO Structural Integrity Associates, Inc.LCOMB, 29,87 i AL, 8, 31, 86, 29 LESIZE,8,,,2 LESIZE,86,,,2 LESIZE,31
,,,4 LESIZE,29,,,4 AMESH, 14 AL, 35, 43, 39, 76 LESIZE,35
,,,6 LESIZE,39,,,6 LESIZE,43
,,,4 LESIZE,76,,,4 AMESH, 15 AL, 86, 76, 66, 91 LESIZE,86,,,2 LESIZE,66
,,, 2 LESIZE,76,,,4 LESIZE,91
,,,4 AMESH, 16 MAT,1 Nozzle LCOMB, 41, 77, LCOMB, 41, 74, LCOMB, 41, 47, LDELE, 41 LDELE, 47 LESIZE,45, ,, 19 ..... 1 LESIZE,30, ,, I ..... 1 LESIZE,10
,,20l LESIZE,85
,,, 6 AL, 39, 10, 85, 45, 30 AMAP, 17,101,98,36,99 MAT,4 ! Clad LESIZE, 79,,, 2 LESIZE,84,, , 20 AL, 66, 30, 45, 79, 84 AMAP, 18,100,101,99,109 MAT,1 ! Nozzle LCOMB, 38, 81 LESIZE, 38,, 14 File No.: VY-16Q-308 Page A13 ofA17 Revision:
0 F0306-01 RO Structural Integrity Associates, Inc.LESIZE, 83,,,6 LESIZE, 51,,,14 AL, 85, 38, 83, 51 AMESH, 19 MAT,4 ! Clad LESIZE, 80,,,2 LESIZE, 65,,, 14 AL, 79, 51, 80, 65 AMESH, 20 MAT, i ! Nozzle LCOMB, 82, 50 LESIZE, 50.,.20 LESIZE, 62,,,6 LESIZE, 60.,.20 AL, 83, 50, 62, 60 AMESH, 21 MAT,4 ! Clad LESIZE, 64.,,2 LESIZE, 63,,,20 AL, 80, 60, 64, 63 AMESH, 22 MATJ1 Nozzle LCOMB, 49, 71 LESIZE, 49,,, 20 LESIZE, 69.,,6 LESIZE, 61,,,20 AL, 62,49,69,61 AMESH, 23 MAT,4 ! Clad LESIZE, 40,,, 2 LESIZE, 59 ,,,20 AL, 64, 61, 40, 59 AMESH, 24 MAT, I ! Nozzle LESIZE, 75..,6 LESIZE, 70..,6 LESIZE, 34,,, 6 AL, 69, 75, 70, 34 AMESH, 25 File No.: VY-16Q-308 Page A14 of A17 Revision:
0 F0306-0 I RO Structural Integrity Associates, Inc.MAT,4 ! Clad U LESIZE, 33.,,2 LESIZE, 32,,,6 AL, 40, 34, 33, 32 AMESH, 26 MAT, 1 ! Nozzle LCOMB, 53, 72 LESIZE, 53,,,8 LESIZE, 58,,,6 LESIZE, 52,,,8 AL, 70, 53, 58, 52 AMESH, 27 MAT,4 ! Clad 3 LESIZE, 57,,,2 LESIZE, 54,,,8 AL, 33, 52, 57, 54 AMESH, 28 MAT,3 ! Vessel I LESIZE, 57,,,2 LESIZE, 54,,,8 LESIZE, 48,,, 100,0.2 .... I LESIZE, 55,,, 100,0.2 .... 1 LESIZE, 56,,, 100,0.2 .... 1 AL, 48, 44, 56, 58 AMESH, 29 MAT,4 ! Clad*LESIZE, 42,,, 2 AL, 57, 56, 42, 55 AMESH, 30 I MAT, 1 ! Nozzle ACLEAR, 17 ADELE, 17 LOVLAP, 10, 46 NUMMRG,KP
.... LOW LCOMB,37,41,0 AL, 20, 37, 85, 45, 30, 39 AMAP,17,101,98,36,99 File No.: VY-16Q-308 Page A15 of Al7 I.Revision:
0 F0306-0 1 RO I VStructural Integrity Associates, Inc.MAT,2 ! Safe End LCOMB, 36,78 LESIZE, 67,,,6 LESIZE, 36,,,6, 0.2,,, 1 AL, 67, 73,36,20,43,27,22 AMAP,3 1,23,82,81,80
/COM **********************
/COM, HTC point of Region 3 ACLEAR, 4 ADELE, 4 LDELE, 95 LDELE, 97 K, 120, KX(18), KY(18) -3/8 K, 121, KX(25), KY(120)L, 25, 121 L, 121,,113 L, 117, 120 L, 120, 33 L, 120, 121 MAT,2 ! Safe End AL, 17, 10, 68,46 LESIZE,10,,, 12 LESIZE,68,,,8 LESIZE,46,,, 12 AMESH, 4 AL, 68, 41, 98, 47 LESIZE,41
,,, 4 LESIZE,98,,,8 LESIZE,47,,,4 AMESH, 32****,***********************
/COM, HTC point of Region 7 MAT,4 ! Clad ACLEAR, 18 ADELE, 18 K, 122, KX( 14)+wReactor, KY(14)L, 14,122 LSBL, 84, 71 File No.: VY-16Q-308 Page A16 of A17 Revision:
0 F0306-01 RO Structural Integrity Associates, Inc. U LESIZE, 72,,,10 i LESIZE, 74,,, 10 AL, 66, 30,45,79,72,74 AMAP,18, 100, 10 1,99,109/COM, HTC point of Region 3 MAT,2 ! Safe End ACLEAR, 2 ADELE, 2 K, 123, KX(120), KY(120)-3 K, 124, KX(4), KY(4)+/-1+1/16 LDELE, 99 L,4, 124 L, 124, 123 L, 123, 116 3 AL, 3, 5, 100, 78, 77, 71 AMAP,2,116,8,3,4
/*I/COM, Define DOFconstraints on lines*** ** *** ** **DL,42, ,SYMM DL,44, ,SYMM FLST,4,9,1,ORDE,2 FITEM,4,1 FITEM,4,-9 I CP, 1 ,UY,P51X I I I I File No.: VY-16Q-308 Page A17 of Al7 Revision:
0 F0306-01 RO I
-Structural Integrity Associates, Inc. File No.: VY-16Q-309 NEC-JH_12 CALCULATION PACKAGE Project No.: VY-16 Q PROJECT NAME: Environmental Fatigue Analysis of VYNPS CONTRACT NO.: 10150394 CLIENT: PLANT: En~terg~y Nuclear Operations, Inc. Vermont Yankee Nuclear Power Station CALCULATION TITLE: Core Spray Nozzle Green's Functions Project Manager Preparer(s)
&Document Affected Revision Description Approval Checker(s)
Revision Pages Signature
& Date Signatures
&Date 0 132, Initial Issue Terry J. Herrmann Roland Horvath Appendix:
7/20/2007 07/19/2007 John F. Staples 07/19/2007 Page 1 of 32 F0306-OI RO Structural Integrity Associates, Inc.Table of Contents 1.0 OBJECTIVE
....................
......................................................................
4 2.0 CORE SPRAY NOZZLE MODEL DESCRIPTION.................................................
4 3.3.0 APPLIED LOADS........................................................................................
7 3.1 Pressure Load ....................
...................................................................
7 3.2 Thermal Load ..................................................................................
11..I 3.2.1 Boundary Fluid Temperatures.................................................................
11 3.2.2 Heat Transfer Coefficients
............................
....................
11 4.0 THERMAL AND PRESSURE LOAD RESULTS .................................................
25
 
==5.0 REFERENCES==
 
.........................................................................................
32 APPENDIX A FINITE ELEMENT ANALYSIS FILES ............................................
Al List of Tables Table 1: Material Properties
@ 300'F .......................................................................
5 Table 2: Heat Transfer Coefficients.................e........................................................
13 Table 3: Heat Transfer Coefficients for Region 1 .........................................................
14 -Table 4: First Partial Heat Transfer Coefficients for Region 3 ..........................................
15 Table 5: Second Partial Heat Transfer Coefficients for Region 3 .......................................
16 I Table 6: First Partial Heat Transfer Coefficients for Region 5...........................................
17 Table 7: Second Partial Heat.Transfer Coefficients for Region 5 ...........
............................
18 Table 8: First Partial Heat Transfer Coefficients for Region 7 ..........................................
19 Table 9: Second Partial Heat Transfer Coefficients for Region 7.......................................
20 Table 10: Third Partial Heat Transfer Coefficients for Region 7 .............................
21 K Table 11: First Partial Heat Transfer Coefficients for Region 9..........................................
22 Table 12: Second Partial Heat Transfer Coefficients for Region 9......................................
23 Table 13: Resultant Heat Transfer Coefficients for the Regions.........................................
24 Table 14: Pressure Results (1,000 psi) ...................................................................
30.3 File No.: VY-16Q-309 Page 2of 32 3 Revision:
0 F0306-OIRO V Structural Integrity Associates, Inc.List of Figures Figure 1: ANSYS Finite Element Model ........................
.........................
6 Figure 2: Core Spray Nozzle Internal Pressure Distribution
................................................................
8 Figure 3: Core Spray Nozzle Pressure Cap Load .............
I.........................................
9 Figure 4: Core Spray Nozzle Vessel Wall Boundary Conditions
.............................
10 Figure 5: Nozzle and Vessel Wall Thermal and Heat Transfer Boundaries (not to scale) ........I ...... 12 Figure 6: Safe End Critical Thermal Stress Location, Node 3719 ............................
25 Figure 7: Blend Radius Limiting Pressure Stress Location, Node 2166 .................
...............
26 Figure 8: Safe End Total Stress.History, 100% Flow ....................................................
28 Figure 9: Blend Radius Total Stress History, 100% Flow .............................................................
28 Figure 10: Safe End Total Stress History, 0% Flow .....................
..............
29 Figure 11: Blend Radius Total Stress History, 0% Flow ..............................................................
29 File No.: VY-16Q-309 Revision:
0 Page 3of 32 F0306-01 RO V Structural Integrity Associates, Inc.1.0 OBJECTIVE The objective of this calculation is to compute the pressure stresses, thermal stresses, and the Green's Functions for high (100%) and no (0%) flow thermal loading of the Vermont Yankee Nuclear Power Station Core Spray Nozzle.2.0 CORE SPRAY NOZZLE MODEL DESCRIPTION An axisymmetric finite element model of the core spray nozzle was developed in Reference
[1] using ANSYS [2]. The geometry used in Reference
[1] was utilized in this calculation.
The material properties are taken at an average temperature of 300'F. This average temperature is based on a thermal shock of 500 0 F to 100&deg;F, which will be applied to the FE model for Green's Function development.
Table 1 lists the material properties at.300&deg;F.
The meshed model is shown in Figure 1.I I I I I I U I I I I I I I I I I I I File No.: VY-16Q-309 Revision:
0 Page 4 of 32 F0306-0 I RO V Structural Integrity Associates, Inc.Table 1: Material Properties
@ 300&deg;F ()Coefficient Modulus of of Thermal Thermal Part Elasticity, e+6 Expansion, Conductivity, Thermal Specific Heat, Pois MaeilDiffusivity, Btu/Ib-0 F Ra Description psi e-6, Btu/hr-ft-0 F ft2/hr 1C] (3) INU[EXI in/in/IF [KXXI[ALPXI Safe End SB 166 72Ni-Weld INCONEL 15Cr-8Fe 29.8 7.9 9.6 0.160 0.1157 0.: Overlay 82 N06600 A508 3/4 Ni-Nozzle 'Class 11 /2Mo-1/3 26.7 7.3 23.4 0.401 0.1193 0.Cr-V Mn-SA533 n0.13.Vessel Gade 1/2Mo- 28.0 7.7 23.4 0.401 0.1193 0.Grade B l/2Ni SA240 3/16 Clad TP304 80 x 100 SA312 Con.(2  TP304 18Cr-8Ni 27.0 9.8 9.8 0.160 0.1252 0.Reduction(2 P0 Thermal SA312 Sleeve TP304 Notes: 1. The material properties applied in the analyses are taken from ASMIE Code, Section II, Part D 1998 Edition, with 2000 A, information provided in the Design Input Record (page 13 of VY EC No. 1773, S1 File No. VY-16Q-209).
The use of a 1, for the original design code is acceptable, since later editions typically reflect more accurate material properties than was Material Properties are evaluated at 300'F from the 1998 ASME Code, 2000 Addenda, Section II, Part D, except for density and Poiss(values [3].2. In the FEM, the 80 x 100 Conc. Reduction was modeled as a straight pipe with the material properties of the original des was replaced by a new material (SA403 T316L). These two stainless steels have the same modulus of elasticity and therrr 3. Calculated as [k/(pd)]1/12 3.Fie No.: VY-16Q-309 Revision.
0 Structural Integrity Associates, Inc.Core Spray Nozzle Finite Element Model Figure 1: ANSYS Finite Element Model File No.: VY-16Q-309 Revision:
0 Page 6 of 32 F0306-OI RO I Structural Integrity Associates, Inc.3.0 APPLIED LOADS Both pressure and thermal loads were applied to the finite element model.3.1 Pressure Load A uniform pressure of 1000 psi was applied along the inside surface of the core spray nozzle and the reactor vessel wall (Figure 2). A pressure load of 1000 psi was used because it is easily scaled up or-down to account for different pressures that occur during transients.
In addition, a cap load was applied to the piping at the end of the nozzle. This cap load was calculated as follows: 2 P-D I PCAI' 2 2 Do-D, where: P = Pressure 1,000 psi Di Inside Diameter = 9.834 in D, = Outside Diameter = 10.815 in Therefore, the cap load is 4,774 psi. The calculated value was given a negative sign in order for it to exert tension on the end of the model. The nodes on the end of the safe end are coupled in the axial direction (UY, Figure 4) to ensure mutual displacement of the end of the nozzle due to attached piping.The boundary conditions at the end of the modeled portion of the reactor pressure vessel wall constructed to be "symmetric" (Figure 3).The ANSYS input file VY 16QP.inp generates the core spray nozzle geometry from VYCSNGeom.inp
[1] and performs the internal pressure load case just described.
Figure 2, 3 and 4 show the internal pressure distribution, cap load, and symmetry conditions applied to the vessel end of the model, respectively.
File No.: VY-16Q-309 Revision:
0 Page 7 of 32 F0306-OI RO Structural Integrity Associates, Inc.I I I I I I I I Core Spray Nozzle Finite Element Model Figure 2: Core Spray Nozzle Internal Pressure Distribution File No.: VY-16Q-309 Revision:
0 Page 8 of 3K F0306-01 RC V Structural Integrity Associates, Inc.Core Spray Nozzle Finite Element Model Figure 3: Core Spray Nozzle Pressure Cap Load File No.: VY-16Q-309 Revision:
0 Page 9 of 32 F0306-01 RO Structural Integrity Associates, Inc.Core Spray Nozzle Finite Element Model Figure 4: Core Spray Nozzle Vessel Wall Boundary Conditions File No.: VY-16Q-309 Revision:
0 Page 10 of 32 F0306-OIRO I(SStructural Integrity Associates, Inc.I* 3.2 Thermal Load Thermal loads are applied to the core spray nozzle model. The heat transfer coefficients (HTC) were determined using the methodology in the Excel spreadsheet "Heat Transfer Coefficients.xls", which is included in the project files. The HTCs were determined for various regions of the core spray FEM, (see Figure 5) for two different flow cases. The flow cases are for 100% (3200 gpm [6]) and 0% core spray flow through the nozzle.The 0% flow case simulates a stagnant condition of the core spray nozzle when not in operation (i.e., the entire core spray nozzle is at the same temperature as the reactor pressure vessel due to reflooding).
The HTCs for the no flow case are for free convection (stagnant) at the temperature of the reactor pressure vessel 5007F. The applied boundary .fluid temperature is changed to simulate a thermal shock from 500OF to 100&deg;F to develop the stress response on the core spray nozzle in the stagnant Condition.
The 100% flow case simulates operational condition of the core spray nozzle (i.e., the entire core spray I nozzle experiences 100&deg;F water due to injection).
The HTCs for the high flow case are for forced and free convection depending on the region of the FEM. The applied boundary fluid temperature is changed to simulate a thermal shock from 500'F to 100'F to develop the stress response on the core spray nozzle due to injection.
For both Green's Functions, a 500F -100l F thermal shock was run to determine the stress response.For the 0% flow case, the entire inside surface of the FEM was shocked. For the 100% flow case, only the nozzle flow path was shocked.1 3.2.1 Boundary Fluid Temperatures For the Green's Functions, a 500OF -100&deg;F thermal shock was run to determine the stress response to a degree change in temperature.
The temperature on the exterior of the reactor, nozzle, safe end and the pipe is assumed to be 120 OF (ambient).
3 3.2.2 Heat Transfer Coefficients Figure 5 shows where the heat transfer coefficients were applied to the FEM for the 0% (steady-* state) and 100% core spray flow injection load case. For all the regions, the applied heat transfer U coefficients and the initial temperatures are summarized in Table 2. The heat transfer coefficient for outside the reactor vessel wall is 0.2 BTU/hr-fi 2-OF and the heat transfer coefficient for inside the I reactor vessel wall is 500 BTU/HIr-ft 2-OF, from page I-T7-5 of Reference
[8].Table 3 through Table 12 show the excel spreadsheets to calculate the HTC for regions 1, 3, 5, 7, and 9 respectively.
These tables calculate the HTC for a certain part of the nozzle using the geometry of the bounding piping, the flow rate, and other physical fluid parameters.
These tables calculate the Reynolds, Grashof and Rayleigh numbers in order to determine the HTC for inside surface/annulus forced and natural convection
[4]. For several regions, the resultant HTCs had to be calculated from the partial heat transfer coefficients.
These resultant HTCs are summarized in Table 13. In regions 2, 4, 6, 8, and 10 the HTCs are interpolated because of the complexity of the material profile.* File No.: VY-16Q-309 Page 11 of 32 Revision:
0 F0306-01 RO C Structural integrity Associates, Inc.Region 11 Region 10 Region 7 Region 6 Regi Region 4_Region 12 Region 1 Figure 5: Nozzle and Vessel Wall Thermal and Heat Transfer Boundaries (not to scale) I I I I ge 12 of 32 I F0306 OIRO I File No.: VY-16Q-309 Revision:
0 S Table 2: Heat Transfer Coefficients 0% Flow 100% Flow Regions Initial HTC Initial HTC Temperature
&deg;F Btu/hr-ftZoF Temperature IF Btu/hr-ft2_oF F R1 500 143 500 2693 R3 1 500 39 500 52 50~ p'1aid) 500 iiepitX R5 0 500 47 500 66 R6B1 500 97 500 97 R7A&deg;' 500 38 500 50 R7B '1 500 20 500 23 Kll 5O00 :-hte~r a~ ~ 5O hrpollatcd 5 1__ R9 (_ ) 500 33 500 41___\____ 10________
___A_____
hiipolatd50 RIH 500 500 500 500 R12 120 0.20 .120 0.2 (1) See Table 13 File No.: VY-16Q-309 Revision:
0 Page 13 of 32 F0306-O1 RO C Structural Integrity Associates, Inc.I I I Table 3: Heat Transfer Coefficients for Region 1 Pipe Inside Diameter, D 0 9.834 Flow, % of rated = 100%inches = 0.820 ft 0.250 m 100% rated flow= 3,200 gpm@T= 549 -F Density, p = 48.087 ibmift 3 1.234236214 Mlb/hr Fluid Velocity, V =Characteristic Length, L = 0 =13.517 ft/sec 0.820 ft=12.00 24.00 6.67 13.33 3,200.0 0.250 36.00 20.00 gpm 48.00 26.67 i TUd -T.&#xfd;-, AT = assumed to be 12% of fluid temperature
=NO.e: Th. abo.e -10rri- i. base -n e-"ei-n -1wfh 8.40 4.67 60.00 33.33 72.00 -F 40.00 &deg;C 5 R'Vhest transter at Fluid Temperature, T [7] Units Conversion 70 100 200 300 400 500 600 &deg;F Water Property Factor [4] 21.11 37.78 93.33 148.89 204.44 260.00 315.56 'C k 1.7307 0.5997 0.6300 0.6784 0.6836 0.6611 0.6040 0.5071 W/m-'C... T-.LC u ....... .... .6 ... ...............
3950 ........ 3820 0.34900.2930
... .t'F cp 4.1869 4.185 4.179 4.229 4.313 4.522 4.982 6.322 kJikg-&deg;C.... .~ ~ H~A ... ...............
000 0.998 1.010 .1.030 1.080 1.190 1.510 Bl/bm'.........................
~~~~~~~~~~~
I ......._ ...........................................
.... .. ._0... .....................................-.......
.....................
1..0.........
............
..08 0 .... ...............
1... ......... ..............
I..............
B ........p .16.018 997.1 994.7 962.7 917.8 858.6 784.9 679.2 kg/m 3._(.Density) 62.3 62.1 60.1 57.3 53.6 49.0 42.4 Ibm/ft 3 0 1.8 1.89E-04 3.24E-04 6.66E-04 1.01E-03 1.40E-03 1.98E-03 3.15E-03 m 3 1m 3.C (Volumetric Rate of Expansion) 1.05E-04 1.80E-04 3.70E-04 5.60E-04 7.806-04 1.10E-03 1.75E-03 f 3/fe 3'....... ... (V ~ m eri. a _anE o! .....................................
... ........ 1-5_ -! ..........
1 .R4 ... ...........
..2E -- ............
..... ........ ................
.:_ E O ..............
.. I.. O.E.-. ......... .........
._... 3 ...... ....... ... ..!. ? ... ... ...g 0.3048 9.806 9.806 9.806 9.806 9.806 9.806 9.806 Mrs 2.... ......(G~ravit-ational Constant 32.17 32.17 32.17 32.17 32.17 32.17 32.17 fj 2....... ..... G f v~ati nal.&#xa3; o~ s a n ) .. .................
....... ...... .... .. ....... .. 3 .2= ..........
........ ....3. 1...7.. .......- ----. ....... 2 .... .. ..... ...... 32..17.....................
3.2... ....... ... ... .?. .... 2 .1 ................
........ .3 _ ..1 .. .............
...... f .=... ....1.4881 9.96E-04 .6.82E-04 3.07E-04 1.93E-04 1.38E-04 1.04E-04 8.62E-05 kg/im-s....... ..........
...... .... ..6. 9-0 4.8.0 .......-04 1.0.0 93E 5 7.00 -05 .7605 Imf-s Pr .6.980 4.510 1.910 1.220 0.950 0.859 1.070 --.(Prandtl Number)Calculated Parameter Formula 70 100 200 300 400 500 600 'F Reynold's Number, Re pVD/g 1'0307E+06 1.5019E+06 3.2317E+06 4.8825E+06 6.3843E+06 7.7540E+06 8.1118E+06
--Grashof Number, Gr gPATL/(gJp) 2  1.3522E+08 7.0314E+08 1.3383E+10 6.9351E+10 2.2021E+11 5.7264E+11 1.1964E+12
--Rayleigh Number, Ra GrPr 9.4382E+08 3.1712E+09 2.5562E+10 8.4608E+10 2.0920E+11 4.9189E+11 1.2802E+12 From [4].Inside Surface Forced Convection Heat Transfer Coefficient:
H._, = 0.023Re 5 5 Pr&deg;'k/D 7,765.07 9,25725 13,05072 15,291.12 16,581.64 16,999.27 16,154.74 W/m 2_&deg;C 1,367.53 1,M.33 2,298,41 r-V ? -' .2,920.25 2 1.Z845,07 Btu/hr-ft 2-'F Bt2.63803 3.1458-03 4.434E-03 5 I.15803 5.63E03 577SE-03 5.4882-03 Btulsec-in 2--F From [41: Inside Surface Natural Convection Heat Transfer Coefficient:
Case: Enclosed cylinder .C= -.0 n = (see o [4]H&#xfd;&#xfd;= C(GrPr)'k/L 231.44 329 18 59732 811.84 984.52 1,11382 1,18770 W/m 2_oC 4 520 I73-39 19616 209.17 Btu/ser-fin-'F 7.863E-05
.1 .1 1S.04 .~2.029F-04 2 758E-04 3.34SE-04
-< 3.784E
>.(4.035L,01~
Btu/sec-in 2_,F I I I I I I I I I I i I I I I File No.: VY-16Q-309 Revision:
0 Page 14 of 32 F0306-01 RO VStructural Integrity Associates, Inc.I Table 4: First Partial Heat Transfer Coefficients for Region 3 Pipe Inside Diameter, D = 7."I. I inches 0665 ft= 0.203 m Flow, % of rated -i00>*Fluid Velocity, V = 20.522 ftlsec = 3,200.0 gpm =Characteristic Length, L = D = 0.665 ft = 0.203 m T&#xfd;&#xfd; AT = assumed to be 12% of fluid temperature
= 8.40 12.00 24.00 36.00 48.00 ,Vole: Thoaboe o~d
= 4.67 6.67 13.33 20.00 26.67 100% rated flow = 3,200 gpm@T= 549 -F Density, p =' 48.087 Ibm/ft'1.234236214 Mlb/hr 60.00 33.33 72.00 -F 40.00 &deg;C p. SRPV hlea Value at Fluid Temperature, T [7] Units Conversion 70 100 200 300 400 500 600 -F Water Property Factor [4] 21.11 37.78 93.33 148.89 204.44 260.00 315.56 C k 1.7307 0.5997 0.6300 0.6784 0.6836 0.6611 0.6040 0.5071 W/m-&deg;C n t 0.3465 0. 3640. 3920 0.3950 .3820 0.3490 0.2930 Btuthr-ft-&deg;F C 4.1869 4.185 4.179 4.229 4.313 4.522 4.982 6.322 kJikg-&deg;C (..i!9H 1M00 0.996 -1.010 1.030 1.080 1.190 1.510 Btullbm-&#xfd;F p 16.018 997.1 994.7 962.7 917.8 858.6 784.9 679.2 kg/in (.es .. 62. ............
..2 62 .60. 1 57.3 53.6 49.0 42.4 Ibm/ft 3 1.8 1.89E-04 3.24E-04 6.66E-04 1.01E-03 1.40E-03 1.98E-03 3.15E-03 m3/mloC (Volumetric, Rate of Expansion) 1.05E-04 1 .80E-04 3.70E-04 5.60E-04 7.80E-04 1.1 OE-03 1.75E-03 ft 3 ,f, 3-'F g 03048 9.806 9.806 9.806 9.806 9.806 9.806 9.806 m/s2 (Gravitational Constant) 32.17 32.17 32.17 32.17 32.17 32.17 32.17 ft/s 2 p 1.4881 9.96E-04 6.82E-04 3.07E-04 1.93E-04 1.38E-04 1.04E-04 8.62E-05 kg/m-s....... ........................-
4..58 -.. ........ 206 4 .30- ..30 5 700E 05..........
579 .05 ..... Ibmft-s Pr 6.980 4.510 1.910 1.220 0.950 0.859 1.070 -(Prandtl Number)Calculated Parameter Formula 70 100 200 300 400 500 600 -F Reynold's Number, Re pVO/lp 1.2700E+06 1.8507E+06 3.9821E+06 6.0161E+06 7.8665E+06 9.5543E+06 9.9952E+06 Grashof Number, Gr g)IATL 3/(plp)2  7.2279E+07 3.7586E+08 7.1540E+09 3.7071E+10 1.1771E+11 3.0610E+11 6.3954E+11
-RayleighNumber, Ra GrPr 5.0451E+08 1.6951E+09 1.3664E+10 4.5226E+10 1.1183E+11 2.6294E+11 6.8430E+11
-From [4]: Inside Surface Forced Convection Heat Transfer Coefficient:0.023ReoePr&deg;41Dk 11,307.23 13,480 10 19,004.02 22,266+42 24,145.63 24,753.78 23,524.01 W/m 2-&deg;C 94,14290 Btu/hr-ft.-&deg;F 3..841E-.03 4-580E-03
,6.45GE.03
/~ .564E-03 8.203E-03
.7 .409E-W~ 7,92E-03' 31u/sec-,n 2-F From [4]: Inside Surface Natural Convection Heat Transfer Coefficient:
Case: Enclosed cylinder C 0.5 n = p Hse = C(GrPr)nlkL 243:85 346.81 629.32 85534 1,03727 1.173.50 1,251 33 W/m 2-&deg;C 12.94 ~ ~~~ ~ ~ ~ ~ 610 M8 It0.- 126, 26 7 220,8'3 Btu/hr-f 2-'F n.L8741HOA5 I.-1786E-04 2, 1380-014.
2.906E-G4~.
3.524E-04.
~3.587E-G4 7 '4.251E-04 Btufsec-in 2_.p'Page 15 of 32 File No.: VY-16Q-309 Revision:
0 Page 15 of 32 F0306-O IRO Structural Integrity Associates, Inc.Table 5: Second Partial Heat Transfer Coefficients for Region 3 I I I I I Pipe Inside Diameter, 0 = , inches 0.820 ft 0.250 m Outer Pipe, Inside radius, r. = 4.917 inches 0.410 ft 0.125 m Inner Pipe Outside Diameter, 0 = 2 inches = 0.719 ft 0.219 m Inner Pipe, Outside radius. r = 4.3125 inches = 0.359 ft 0.110 m Fluid Velocity, V = 13.517 ft/sec = gpm Characteristic Length, L = D = 0.820 ft = 0.250 m (Outside)
T, -T,,~, AT = 840 12.00 24.00 36.00 48.00= 4.67 6.67 13.33 20.00 26.67 60.00 .72.00 'F 33.33 40.00 'C Value at Fluid Temperature, T 7] Units Conversion 70 100 200 300 400 500 600 'F Water Property Factor [4] 21.11 37.78 93.33 148.89 204.44 260.00 315.56 &deg;C k 1.7307 0.5997 0.6300 0.6784 0.6836 0.6611 0.6040 0.5071 W/m-'C...... ..............
ml 0 5. ...... 0.3465 0.3640 0.3920 0:3950 0.3820 0.3490. 0.2930 Btu/ir-ftF C. 4.1869 4.185 4.179 4.229 4.313 4.522 4.982 6.322 kJ/kg-'C..... H eat)....9
..00 0 .. .. ... 0 80 .. .. .......1..190 .. ........ .5..... 1. 0 .B tu/lbm -F_ ..p 1.018 997.1 994.7 962.7 917.8 858.6 784.9 679.2 kg/mr (est)62.3 62.1 .60.1 57.3 53.6 49.0 42.4 Ibm/ft 3 1.8 1.89E-04 3.24E-04 6.66E-04 1.01E-03 1.40E-03 .1.98E-03 3,15E-03 m 3/m-.OC (Volumetric Rate of Expansion) 1.05E-04 1.80E-04 3.70E-04 5.60E-04 7;80E-04 1.10E-03 1.75E-03 ft 3 1ft 3-'F...............
.. ..............
..... ..... ... .....................
........ -.- ... ...............
.................
............
.........
.............................................
.... ....... .....................
..... .... ... ... ............ ..... ....... ..9 0.3048 9.806. 9.806 9.806 9.806 9.806 9.806 9.806 m/s 2 (Gravitational Constant) 32.17 32.17 32.17 32.17 32.17 32.17 32.17 ft/s 2 p 1.4881 9.96E-04 6.82E-04 3.07E-04 1.93E-04 1.38E-04 1.04E-04 8.62E-05 kg/m-s.... .... (Pyamic .V......scos....ity)...
..... ..... 6. 9-4 ..E0 .. 2.06... -04&#xfd; 1.3()E-04 9.30E-05 7.OOE-05 5.79E-05 Imf-Pr 6.980 4.510 1.910 1.220 0.950 0.859 1.070 --(Prandtl Number)Calculated Parameter Formula 70 100 200 300 400 500 600 'F Reynold's Number, Re pVD/p 1030724 1501950 3231741 4882481 6384268 7754027 8111787 --Grashof Number, Gr gp3ATL 3/(p/p)2  135217684.2 703144247.6 13383382850 69350803914 2.2021E+11 5.72636E+11 1.19642E+12
--Grashof Number, Gr&#xfd; g93AT(r,-rj) 3/(Pjp)3  3.14E+04 1.63E+05 3.11E+06 1.61E+07 5.11E+07 1.33E+08 2.78E+08 -Rayleigh Number, Ra GrPr 943819435.9 3171180557 25562261244 84607980776 2.092E+11 4.91894E+11 1.28017E+12 Rayleigh Number, Ra Gr 5 Pr 2.19E+05 7.37E+05 5.94E+06 1.97E+07 4.86E+07 1.14E+08 2.97E+08 -From [41: Annulus Natural Convection Heat Transfer Coefficient:
Case: Enclosed cylinder C= 0d n = "0 ('si e .-Agc29 o 15])Hsee C(GrsPr)nlk(r,-)
18278 24468 40000 512.07 593.51 643.36 653 99 Wlm 2-oc ,".3219 4309 70.45 104 53 -1t1330 :11518 Btu/hr-ft 2-'F I I I I I I I I I I I I I I File No.: VY-16Q-309 Revision:
0 Page 16 of 32 F0306-01 RO V Structural Integrity Associates, Inc.I Table 6: First Partial Heat Transfer Coefficients for Region 5 Pipe Inside Diameter, D = s7,C.', inches 0.665 ft 0.203 m Flow, % of rated = 0 Fluid Velocity, V = 20.522 fl/sec = 3,200.0 gpm Characteristic Length, L= = D 0.665 ft = 0.203 m T&#xfd;,w -T==am, AT = assumed to be 12% of fluid temperature
= 8.40 12.00 24.00 36.00 48.00 100% rated flow = 3;200 gpm@T= 549 -F Density, p = 48.087 Ibm/ft 3 1.234236214 Mlblhr 60.00 72.00. -F ,oe.. 7h., b-, .t, .,, Weh = 4.67 6.67 13.33 20.00 26.67 33.33 40.00 &deg;C me RPVh.t nI.rensy=
Value at Fluid Temperature, T M] Units Conversion 70 100 200 300 400 500 600 -F Water Property Factor [4] 21.11 37.78 93.33 148.89 204.44 260.00 315.56 C k 1.7307 0.5997 0.6300 0.6764 0.6636 0.6611 0.6040 0.5071 W/m-&deg;C.. Thermal Conductivity) 0.3465 0.3640 0.3920 0.3950 0.3820 0.3490 0.2930 Btu/hr-ft-&deg;F Cv 4.1869 4.185 4.179 4.229 4.313 4.522 4.982 6.322 kJ/kg-&deg;C ai ~ 1.0. 0082.3~ 0 ~ 4 1.190, 151 Btu/Ibm-'F p 16.018 997.1 994.7 962.7 917.8 858.6 784.9 679.2 kg/m 3 (Density) 62.3 62.1 60.1 57.3 53.6 49.0 42.4 Ibm/ft 3 II 1.8 1.89E-04 3.24E-04 6.66E-04 1.01E-03 1.40E-03 1.98E-03 3.15E-03 m 3 lm 3_-c (Volumetric Rate of Expansion)
: 1. .05E-04 1.80E-04 3.70E-04 5.60E-04 7.80E-04 1.10E-03 1.75t-03 ft 3/ft_-.F g 0.3048 9.806 9.806 9.806 9.806 9.806 9.806 9806 mls 2 (Gravitational Constant) 32.17 32.17 32.17 32.17 32.17 32.17 32.17 ft/s2 1.4881 9.96E-04 6.82E-04 3.07E-04 1.93E-04 1:38E-04 1.04E-04 8.62E-05 kglm-s.......... .DnarncVscosity..
669E04 ..4.58E-04 2.06-E04 1.30E-04 9.30E-05 7.OOE-05 5. .. .Ibmfts Pr 6.980 4.510 1.910 1.220 0.950 0.859 1.070 (Prandtl Number)Calculated Parameter Formula 70 100 200 300 400 500 600 " -&deg;F Reynold's Number, Re pVD/9 1.2700E+06 1.8507E+06 3.9821E+06 6.0161E+06 7.8665E+06 9.5543E+06 9.99526+06
-Grashof Number, Gr g1ATI-3 (pip)2  7.2279E+07 3.7586E+08
.7.1540E+09 3.7071E+10 1.1771E+11
.3.0610E+11 6.3954E+11
-Rayleigh Number, Ra GrPr 5.0451E+08 1.6951E+09 1.3664E+10 4.5226E+10 1.1183E+11 2.6294E+11 6.8430E+11
-From [4]: Inside Surface Forced Convection Heat Transfer Coefficient:
= 0.023Re 8 Pr&deg;'k./D 11,307.23 13,48010 19,00402 22,266.42 24,14563 24,75378 23,52401 W/m 2-oC 1,<991.36 2,737403 3468 4,22.8 , 4,359-48 4,142-90 , Btu/hr-ft 2.-F 3.4E0 .8E0 .5E0 .&#xfd;L0 .0E0 49-3 792-3 Btu/sec-in 2&deg;From [4]: Inside Surface Nlatural Convection Heat Transfer Coefficient: ,Case: Enclosed cylinder 0= 055 n 0.25 (see page 29 "of He C(GrPr)'kJL 24385 346 81 62932 85534 1,037.27 1,17350 1,251.33 Wlm 2 1-C 42.94 : 61.08 1  110,83 10O f , 182.68. ,. 206, 67 : <, 220.38 Btu/hr-f 2-"F 8.284E- 1.17BE.04 2138E4 2.906E 0 1 -24E-04 19M-04 4.25iE-04 Btu/sec-in 2-&deg;F File No.: VY-16Q-309 Revision:
0 Page 17 of 32 F0306-01 RO Structural Integrity Associates, Inc.Table 7: Second Partial Heat Transfer Coefficients for Region 5 I I I i I Title N,= wP , &#xfd;I &#xfd;, nLi-&#xfd; &#xfd;&#xfd;&#xfd;&#xfd;Pipe Inside Diameter D = D inches= 0750 ft 0.229 m Outer Pipe, Inside radius, r. 4.5 inches 0.375 ft 0.114 tm Inner Pipe Outside Diameter, D = .>. A inches 0.719 ft 0.219 m Inner Pipe, Outside radius, ri 4.3125 inches 0.359 ft Fluid Velocity, V =Characteristic Length, L = D =(Outside)
T,, -T,-, AT 8.40 4.67 16.138 0.750 12.00 6.67 0.110 m ftsec -I gpm ft = 0.229 m 24.00 36.00 13.33 20.00 48.00 26.67 60.00 72.00 33.33 40.00 Value at Fluid Temperature, T M7] Units Conversion 70 100 200 300 400 500 600 -F Water Property Factor [4] 21.11 37.78 93.33 148.89 204.44 260.00 315.56 &deg;C k 1.7307 0.5997 0.6300 0.6784 .0.6836 0.6611 0.6040 0.5071 W/m-&deg;C...............
I(m h)e 1-1n- --! .... ... ... .........
............
...... .0 5.............
0.3_6 1Q0 .... .... 0 :3 .. ..... =3 5O. ..... .3 2 .. ............
= .4.9 ..... .............
.o 2 3 ................. r_ &deg;q!x .1. ... ....~ 6 0.364. 0..2 0.90 0..00.9.290 Bulr ci- 4.1869 4.185 4.179 4.229 4.313 4.522 4.982 6.322 kJ/kg-&deg;C.. ... .............
.......... (Sp..2&#xfd; ,ic .Hea&#xfd;t9 ................
.... ........ ... ...........
....................
..... ..... ..........
1 999.0.0 .........................
0.9 ..........
.1 0 .1 q ..................
1..0._ , ..... ...... 1: ....... ...... :1 0 ..............
.= 1 .... ....... ..tuf m .p 16.018 997.1 994.7 962.7 917.8 858.6 784.9 679.2 kg/m 3 (Density) 62.3 62.1 60.1 57.3 53.6 49.0 42.4 Ibm/ft 3.1.8 1,89E-04 3.24E-04 6.66E-04 1.01E-03 1.40E-03 1.98E-03' 3.15E-03 m 3 lm 3-&deg;C (Volumetric Rate of Expansion) 1.056-04 1.80E-04 3.70E-04 5.60E-04 7.80E-04 1.10E-03 1.75E-03 ft 3/tt 3 -F.. .........
....! o _ .e !.... -............
.n .}...........
... ... ........ ..................
....... ... ...... ....... ... O. E. ...........
..................
L 8 0.-.. ........................... .0 _ ...............
-... .... ...................
._ 9 ..... ..... ..... -:.0_. ....................
: l. .E. ........ .... ..........g 0.3048 9.806 9.M06 9.806 9.806 9.806 9.806 9.806 m/s 2 (Gravitational Constant) 32.17 32.17 32.17 32.17 32.17 32.17 32.17 ft/s 2 1 1.4881 9.96E-04 6.82E-04 3.07E-04 1.93E-04 1.38E-04 1.04E-04 8.62E-05 kg/i-s.. ..........-(y iVs 6.696-04 4.586-04.2.006E-04 1.306-04 9.30E-05 7.006-05 5.79E-05 Ib/ts R..........
.4 &#xfd;ninc.V y.co .) .. .............
... ............
.. .. ..... ..............
...........
.: 9 -' ........ ... .............
: .5.......
......I...........
.. 2... 0..... -0.. ...................
.. 1 .E ............
..........
9 =-5-9 .....................
.=g ........ ..........
.....0= ......... .. ..! .....Pr 6.980 4.510 1.910 1.220 0.950 0.859 1.070 --(Prandtl Number)Calculated Parameter Formula 70 100 200 300 400 500 600 -F Reynold's Number, Re pVD/p 1126238 1641130 3531215 5334924 6975877 8472567 8863480 --Grashof Number, Gr goATL 3/(Ipp)2  103650263.4 538990790.5 10258947757 53160421562 1.68801E+11 4.3895E-11 9.17108E+11 Grashof Number, Gri g0AT(r _r)3/(p!p)3  9.37E+02 4.87E+03 9.28E+04 4.81E+05 1.53E+06 3.97E+06 8.29E+06 --Rayleigh Number,.Ra GrPr 723478838.9 2430848465 19594590215 64855714305 1.60361E+11 3.77058E+11 9.81306E+11
--Rayleigh Number, Ra Gr&#xfd;Pr 6.54E+03 2.20E+04 1.77E+05 5.86E+05 1.45E+06 3.41E+06 8.87E+06 --From [4]: Annulus Natural Convection Heat Transfer Coefficient:
Case: Enclosed cylinder C 2 238.7 n1 of [5p titeC(GrsPr)kl(r 0 ri) 291.94 390.80 638 87 817.88 94795 1,027 56, 1,044 55 W/im 2-tc 5 1,. .541 .68.83 112.51 1,G.16950 , 180.97 -18396 Utu/hir-fe,-
F.I I I I I I I I I I I I File No.: VY-16Q-309 Revision:
0 Page 18 of 32 F0306-O1RO I
V Structural Integrity Associates; Inc.Table 8: First Partial Heat Transfer Coefficients for Region 7 Pipe inside Diameter, D = i7j I Flow, % of rated= "100%, Fluid Velocity, V = 20.522 Characteristic Length, L = D = 0.665 TO, -T,,.,um, AT = assumed to be 12% of fluid temperature 8.40 12.00 Woe The aboe r I bed on exeriee h 467 6.67 inches =ftlsec 6f=24.00 13.33 0.665= 0.203 3,200.0 0.203 36.00 20.00 ft m gpm m 48.00 2667 100% rated flow = 3,200 gpm@T 549 &deg;F Density, p = 48.087 Ibm/ft 3 1.234236214 Mlbthr 60.00 33.33 72.00 &deg;F 4000 rC ana~y... .Value at Fluid Temperature, T [M Units Conversion 70 100 200 300 400 500 600 &deg;F Water Property Factor [4] 21.11 37.78 93.33 148.89 204.44 260.00 315.56 &deg;C k 1.7307 0.5997 0.6300 0.6784 0.6836 0.6611 0.6040 0.5071 W/m-&deg;C.0.3465 0.3640 0.3920 0:3950 0.3820 0.3490 0.2930 Btu/hr-ft-*F CP 4.1869 4.185 4.179 4.229 4.313 4.522 4.982 6.322 kJ/kg-&deg;C....... p~ e i.8(L 1.00. 0..998 010 1.00 1N ..080 .190 ..m-'F.*P .16.018 997.1 994.7 962.7 917.8 858.6 784.9 679.2 kg/m 3 (Density)
' 62.3 62.1 60.1 57.3 53.6 .49.0 42.4 Ibm/ft 3 1.8 1.89E-04 3.24E-04 6.66E-04 1.01E-03 1.40E-03
* 1.98E-03 3.15E-03 m 3/m 3-&deg;C.(olumetri RateoExpansion)
....1.05E-_4 1.80E-04 3.70E-04 5.60E-04 7.80E-04 1.10E-03 1.75E-03 ft'/.l-'F g 0.3048 9.806 9.806 9.806 9.806 9.806 9.806 9.806 m/s 2 (Gravitational Constant)
..32.17.32.17.32.17 32.17 32.17 32.17 32.17 ft/S 2 p 1.4881 9.96E-04 6.82E-04 3.07E-04 1.93E-04 1.38E-04 1.04E-04 8.62E-05 kg/m-s...........
-amic Vscosi~y 6.69E-04 4.586-04 206E-04 1.30-04 9.30E-05 700E-05 579E-05 Ibm/ft-s Pr 6.980 4.510 1.910 1.220 0.950 0.859 1.070 -(Prandtl Number)Calculated Parameter Formula 70 100 200 .300 400 500 600 &deg;F Reynolds Number, Re pVD/p 1.2700E+06 1.8507E+06 3.9821E+06 6.0161E+06 7.8665E+06 9.5543E+06 9.9952E+06 Grashof Number, Gr goATL 3/(igp)2  7.2279E+07 3.7586E+08 7.1540E+09 3.7071E+10 1.1771E+11 3.0610E+11 6.3954E+11
--Rayleigh Number, Ra GrPr 5.0451E+08 1.6951E+09 1.3664E+10 4.5226E+10 1.1183E+11 2.6294E+11 6.8430E+11
-From [41: Inside Surface Forced Convection Heat Transfer Coefficient:
H., = 0.023Re"Pr-kJD 11,307.23 13,480.10 1900402 22,266.42 24,145.63 24,753.78 23,524.01 W/m 2.&deg;C 3 71403 .3 T4 3 <8174,242,8
-, ?,q435:8 1" Btulhr-ft 2 3.lE1E03 >4 580E-.03>
6,1566I03.Y 7.4E203. 8, 2603E'13.
F,, -0 7.92ET-43~
3 tu/sec-in 2--F From [4]: Inside Surface Natural Convection Heat Transfer Coefficient.
Case: Enclosed cylinder 0 2 n -f [4])Hfte, C(GrPr)nk/L 243.85 346.81 62932 85534 1,03727 1.173.0 1,251.33 W/m 2-&deg;C 4 7&#xfd;. i6 1'08' ' 11083, e'<8:8- ""; 206.,7 2-1 ' &#xfd;' 2'2 ~2844t 05' >~1 78E-0 2 1386-4 '"1 2 A1 '0 -1.2E0 3 9,-7E -04~i _________i'-*
File No.: VY-16Q-309 Revision:
0 Page 19 of 32 F0306-0I RO Structural Integrity Associates, Inc.Table 9: Second Partial Heat Transfer Coefficients for Region 7 Pipe Inside Diameter, D = 1inches=Outer Pipe, Inside radius, r. = 5.01 inches =Inner Pipe Outside Diameter, D = inches Inner Pipe, Outside radius, r = 4.3125 inches =Fluid Velocity.
V = 13.020 ft/sec =Characteristic Length, L = 0 = 0.835 ft =(Outside)
TT -T, = AT 8.40 12.00 24.00-4.67 6.67 13.33 0.835
* ft 0.255 m 0.418 ft 0.127 .m 0.719 ft 0.219 m 0.359 ft 0.110 m'20&#xfd; gpm 0.255 m 36.00 20.00 48.00 26.67 60.00 72.00 &deg;F 33.33 40.00 C Value at Fluid Temperature, T [ Units Conversion
: 70. 100 200 300 400 500 600 &deg;F WaterProperty Factor [4] 21.11 37.78 93.33 148.89 204,44 260.00 315.56 C k 1.7307 0.5997 0.6300 0.6784 0.6836 0.6611 0.6040 0.5071 W/m-&deg;C Thermal Conductiv)----------------03465 0.3640 0.39 0.3950 0820. 03490 .0 -2930 tu/hr-ft-&deg;F c 4.1869 4.185 .4.179 4.229 4.313 4.522 4.982 6.322 kJ/kg-&deg;C........ .._Sp c~c ~e !_ .. ........ .... ... ........-.
1-1.:000 ..... 099.9 9 8 .1..0 0..........1...030.
........ 01 8 0.0,_119..
..... 1.519_0.......
..t151 ...... tu -m &deg;p 16.018 997.1 994.7 962.7 917.8 858.6 784.9 679.2 kg/m 3 (Density) 62.3 62.1 60.1 57.3 53.6 .. 490 42.4 .bm/ft 3 S1.8 1.89E-04 3.24E-04 6.66E-04 1.01E-03 140E-03 1.98E-03, 3.15E-03 m 3/m 3-C (Volumetric Rate of Expansion) 1.05E-04 1.80E-04 ..70E-04 ......60-04 7.80E-4 .. .1E03 ..75E-03 ft 3/t 3-oF 9 0.3048 9.806 9.806 9.806 9.806 9.806 9.806 9.806 mrs 2 (Gravitational Constant) 32.17 32.17 32.17 32.17 32.17 32.17 32.17 fijs2 p 1.4881 9.96E-04 6.82E-04 3.07E-04 1.93E-04 1.38E-04 , 1.04E-04 8.62E-05 kg/mr-s.... .a.nic. Vs ..6.69E-04 4.58E-04 2.06E-04 1.30E-G4 9.30E-05 7.00E-05 5.79--05 Ibm/ft-s Pr 6.980 4.510 1.910 1.220 0.950 0.859 1.070 (Prandtl Number)Calculated Parameter Formula 70 100 200 300 400 500 600 'F Reynolds Number, Re pVD/p 1011591 1474069 3171750 4791848 6265758 7610090 7961209 -Grashof Number, Gr gpATL 3/(gp)2  143036227.2 743801381.9 14157235436 73360798959 2.32943E+11 6.05747E+11 1.2656E+12
-Grashof Number, Gr 6  g0AT(r 0-rj)3/(i/p)3  4.62E604 2.51E+05 4.78E+06 2.47E607 7.86E+07 2.04E+08 4.27E-08 -Rayleigh Number, Ra GrPr 998392866.2 3354544233 27040319682 89500174730 2.21296E+11 5.20336E+11 1.35419E+12
-Rayleigh Number, Ra Gr 6 Pr 3.37E+05 113E+06 9.12E+06 3.02E+07 7.46E+07 1.76E+08 4.57E+08 -From [4].Annulus Natural Convection Heat Transfer Coefficient:
Case: Enclosed cylinder C = ' n = --'0 C(Gr 6 Pr)'kI(ro-r,)
172.61 231.07 377.74 483.58 560.49 607.56 617.61 W/m 2-oC I I U I I I I I I I I I I I I I I I I File No.: VY-16Q-309 Revision:
0 Page 20 of 32 F0306-01 RO Structural Integrity Associates, Inc.Table 10: Third Partial Heat Transfer Coefficients for Region 7 Pipe Inside Diameter, D =_ inches 0.979 ft= 0.298 m Outer Pipe, Inside radius, r. = 5.875 inches = 0.490 ft 0.149 m Inner Pipe Outside Diameter, D = inches = 0.896 ft= 0.273 rm Inner Pipe, Outside radius, ri =5.375 inchbs = 0.448 ft 0.137 m Fluid Velocity, V = 9.468 ft/sec = " (-.-9 , Pm Characteristic Length, L = D = 0.979 ft = 0.298 m (Outside)
T&#xfd;&#xfd; -Tr, AT 8.40 1200 24.00 36.00 48.00-4.67 6.67 13.33 20.00 26.67 60.00 72.00 &deg;F 33.33 40.00 C Value at Fluid Temperature, T [7] Units Conversion 70 100 200 300 400 500 600 -F Water Property Factor [41 21.11 37.78 93.33 148.89 204.44 260.00 315.56 C k 1.7307 0.5997 0.6300 0.6784 0.6836 0.6611 .0.6040 0.5071 W/m-&deg;C.(.ThermalConduivity) 0.3465 0.340 0.3920 0.3950 0.3820 .- 0.3490 0.2930 Btu/hr-ft-TF C 4,1869 4.185 4.179 4.229 4.313 4.522 4982 6.322 kJlkg-&deg;C............................. (Sefi ). ..........................
: 1. 0.998 1.010 1.030 1.080 1.190 1.510 2 tu/tbm-&deg;F P 16,018 997.1 994.7 962.7 917.8 858.6 784.9 679.2 kg/m 3 (Density) 1 62.3 62.1 60.1 57.3 53.6 .49.0 42.4 Ibm/ftI1.8 1.89E-04 3.24E-04 6.66E-04 1.01E-03 1.40E-03 1.98E-03
* 3.15E-03 m 3/m 3-&deg;C (Volumetric.Rate of Expansion) 1 .05E-04 1 .80E-04 3.70E-04 5.60E-04 7.80E-04 1 .IOE-03 1..75E-03 f...ft 3 g 0.3048 9.806 9.806 9.806 9.806 9.806 9.806 9.806 m/s 2 (Gravitational Constant) 32.17 32.17 32.17 32.17 32.17 7 32.17 ft.s 2 P 1.4881 9.96E-04 6.82E-04 3.07E-04 1.93E.04 1.38E-04 1.04E-04 8.62E-05 kg/m-s (Dinmc Viscosity
--6 69E-04 4.5811-04 2.06E-04 1.30E-G4 9.30E-05 7.OOE-05 5.79E-05 Ibm/ft-s Pr 6.980 4.510 1.910 1.220 0.950 0.859 1.070 -FPrandtl Number)Calculated Parameter Formula 70 100 .200 300 400 500 600 &deg;F Reynold's Number, Re pVD/p 862650 1257036 2704761 4086325 5343225 6489626 6789048 -Grashof Number, Gr gOATL 3/(pJp)2  230651605.4 1199409312 22829105215 1.18297E+11 3.75631E+11 9.76791E+11 2.04083E+12 Grashof Number, Grq gPAT(ro-rj) 3/)(pp)3  1.78E+04 9.24E+04 1.76E+06 9.12E+06 2.89E+07 7.53E+07 1.57E+08 Rayleigh Number, Ra GrPr 1609948206 5409335995 43603590961 1.44323E+11 3.56849E+11 8.39063E+11 2.18369E+12
-Rayleigh Number, Ra GrPr 1.24E+05 4.17E+05 3.36E+06 1.11E+07 2.75E+07 6.47E+07 1.68E-08 -From [4]: Annulus Natural Convection Heat Transfer Coefficient:
Case: Enclosed cylinder C = 'o n 020 9&#xfd;1 of -51)H+re C(GriPr)nk/(r 0-ri) 197.20 26398 431 55 552.46 640.32 694.10 70557 Wim 2-&deg;c: '. 34:73 4649 7600w j112.77 .11 7 :7,: A1 A .12 124.26 B t/hF-f1 2_-F File No.: VY-16Q-309 Page 21 of 32 Revision:
0 F0306-01 RO V Structural Integrity Associates, Inc.-I I I Table 11: First Partial Heat Transfer Coefficients for Region 9 Pipe Inside Diameter, D = ., inches =0.665 ft 0.203 m 100% rated flow = 3,200 gpm@ @T= 549 TF Density, p = 48.087 Ibm/ft 3 Flow, % of rated- I ." Fluid Velocity, V = 20.522 Characteristic Length, L = D = 0.665 Tfl&#xfd; -Ta,_, AT = assumed to be 12% of fluid temperature
= 8.40 12.00 Note The ebove -fVno3n is basedon W With 467 667 fl/sec =ft=24.00 13 33 3,200.0 gpm =0.203 m 36.00 48.00 2000 28 67 1.234236214 Mlb/hr I 60.00 33.33 72.00 TF 40.00 &deg;G pa y- Value at Fluid Temperature, T M Units Conversion 70 100 200 300 400 500 600 'F Water Property Factor [4M 21.11 37.78 93.33 148.89 204.44 260.00 315.56 TC k , 1.7307 0.5997 0.6300 0.6784 0.6836 0.6611 0.6040 0.5071 W/m-'C........... (Thea Conductivity 03465 0.3640 03920 0.3950 3820 .3490 0.2930 8tu/hr-ft-&deg;F CP 4.1869 4.185 4.179 4.229 4.313 4.522 4.982 6.322 kJ/kg-&deg;C.(SeificHeat
..1.000 0.998 1.010 1.030 1.080 1.190 1.510 Btu/lbm-'F p 16.018 997.1 994.7 962.7 917.8 858.6 784.9 679.2 kg/m3 (Density) 62.3 62.1 60.1. ,57.3 53.6 49.0 42.4 Ibm/ft 3 p 1.8 1.89E-04 3.24E-O4 .66E-04 1.01E-03 1.40E-03 1.98E-03 3.15E-03 m 3/m 3-'C (Volumetric Rate of Expansion)
I.OSE-04 1.80E-04 3.70E-04 5.60E-04 7.80E-04 1.10E-03 .1.75E-03 ftlift 5-'F 9 0.3048 9.806 9.8068 06 9.8 06 9.806 9.806 9.806 m/s 2 (Gravitational Constant) 32.17 32.17 32.17 32.17 32.17 32.17 32.17 ft/s 2 1.4881 9.96E-04 6.82E-04 3.07E-O4 1.93E-04 1.388-04 1.04E-04 8.628-05 kg/n-s.. .................(D .n..a~m .] .V i~s.cos .........
...... ..........................
....... .............
..-... .....................
.................
_.O..................
..0.---0......
.........
0..-8E-0............._7_.0 E 951........
....30E. _5..T O5. ...........
05 mIb m s ....Pr 6.980 4.510 1.910 1.220 0.950 0,859 M1.070-(Prandtl Number)Calculated Parameter Formula 70 100 200 .300 400 500 600 'F Reynold's Number, Re pVD/I 1.2700E+06 1.8507E+06 3.9821E+06 6.0161E+06 7.8665E+06 9.5543E+06 9.9952E+06
-Grashof Number, Gr gRIATL 3/(Pip)2  7.2279E+07 3.7586E+08 7.1540E+09 3.7071E+10 1.1771E+11 3.0610E+11 6.3954E+11
--Rayleigh Number, Ra GrPr 5.0451E+08 1-6951E+09 1.3664E+10 4.5226E+10 1.1183E+11 2.6294E+11 6.8430E+11
-From [4j.Inside Surface Forced Convection Heat Transfer Coefficient:
H._= 0.023Re 0 8 p 0 r 4 kD 11,307.23 13,480.10 19,00402 22,266.42 24,145.63 24,753.78 23,524.01 W/m 2-.C B1t99r3t 2,37403 ,3 8 252-38 4,359.48 4,142900 61 r-ft 2-'F'3,841E-03~
~48580EO3.
6.4-56E-03 7.564E-03
.8.203E03~
28.409E-03K "7.92-03 Btu/sec-in 2-'F From [4J.: Inside Surface Natural Convection Heat Transfer Coefficient:
Case: Enclosed cylinder C 5 K<.5 G ~. n= ~ ,25 (se- pae9),39M 41 H 1 ftee C(GrPr)'knL 24385 346.81 62932 85534 1,03727 1,17350 1,251 33 W/m 2-&deg;C 42.94 6108 1103 I '- 182.68 20GA7 220.38 Btu/hr-ft 2-&deg;F 8,284E-05 1,178E-04'
>2l381E04 2 ZS0,1 3 524E04' -87E.O4 4.261k+ Btu/sec-in-&deg;F I I I I I I I I U I I I I I I File No.: VY-16Q-309 Revision:
0 Page 22 of 32 F0306-01 RO V Structural Integrity Associates, Inc.Table 12: Second Partial Heat Transfer Coefficients for Region 9 Pipe Inside Diameter, D = 1 1 inches = 0.979 ft 0.298 m Outer Pipe, Inside radius, r. = 5.875 inches = 0.490 ft 0.149 m Inner Pipe Outside Diameter, D = inches 0.719 ft 0.219 m Inner Pipe, Outside radius, r = 4.3125 inches = 0.359 ft 0.110 m Fluid Velocity, V = 9.468 ftlsec = )'igpm Characteristic Length, L = 0 = 0.979 ft = 0.298 m (Outside) -Tj,_ AT = 8.40 12.00 24.00 36.00 4.67 .6.67 13.33 20.00 48.00 26.67 60.00 72.00 &deg;F 33.33 40.00 C Value at Fluid Temperature, T [7] Units Conversion 70 100 200 300 400 500 600 &deg;F Water Property Factor [41 21.11 37.78 93.33 148.89 204.44 260.00 315.56 C k 1.7307 0.5997 0.6300 &.6784 0.6836 0.6611 0.6040 0.5071 W/m-&deg;C..Theral.Conducivity) 0.3465 0.3640 0.3920 0.3950 0.3820 .0.3490 0.2930 Btu/hr-ft-&deg;F Cp 4.1869 4.185 4.179 4.229 4.313 4.522 4.982 6.322 kJ/kg-&deg;C-.. .1.000 0.998 1.010 1.030 1.080 1.190 1.510 Btu/Ibm-&deg;F p 16.018 997.1 994.7 962.7 917.8 858.6 784.9 679.2 kg/m 3 62.3 62.1 60.1 57.3 53.6 49.0 42.4 Ibm./ft 3 p .1.8 1.89E-04 3.24E-04 6.66E-04 1.01E-03 1.40E-03 .1.98E-03 3.15E-03 m'/m 3-.C (Volumetric Rate of Expansion) 1.05E-04 1.80E-04 3.70E-04 5.60E-04 7.80E-04 1.10E-03 1 1.75E-03 ft 3/ft 3--F.0.3048 9.806 9.806 9.806 9.806 9.806 9.806 9.806 iMns 2.. avitat ional Constant)
.32.17 32.17 .32.17 32.17 32.17 32.17 32.17 ft/s.p 1.4881 9.96E-04 6.82E-04 .3.07E-04 1.93E-04 1.38E-04 1.04E-04 8.62E-05 kg/m-s is .9.......0......4 4.58E-04 2.06E-04 1.30E-04 9.30E-05 7.OOE-05 5.79E-05 Ibmt-s Pr 6.980 4.510 1.910 1.220 0.950 0.859 1.070 --(Prandtl Number)Calculated Parameter Formula 70 100 200 300 400 500 600 -F Reynolds Number, Re PVD/1p 862650 1257036 2704761 4086325 5343225 6489626 6789048 ---Grashof Number, Gr g0ATL 3/(Pilp)2  230651605.4 1199409312 22829105215 1.182976211 3.75631E+11 9.76791E+11 2.04083E+12
--Grashof Number, Gr 5  gDAT(r 0-ri)3/(p/p)3  5.42E+05 2.82E+06.
5.37E+07 2.78E+08 8.83E+08 2.30E+09 4.80E+09 ---Rayleigh Number. Ra GrPr 1609948206 5409335995 43603590961 1.44323E+11 3.56849E+11 8.39063E+11 2.18369E+12
---Rayleigh Number, Ra GrsPr 3.79E+06
* 1.27E+07 1.03E+08 3.39E+08 8.39E+08 1.97E+09 5.13E+09 ---From [4]: Annulus Natural Convection Heat Transfer Coefficient:
Case Enclosed cylinder C = n =H- C(Gr&#xfd;Pr)'kJ(ro-r) 125.02 167.35 273.58 350.24 405.94 440.03 447.30 WIm 2-C'o &#xfd;-. 2 ..41..1 i A 7 7 --' .1. 1, 77 File No.: VY-16Q-309 Revision:
0 Page 23 of 32 F0306-01 RO V Structural Integrity Associates, Inc.Although the thermal sleeve was excluded from the analysis, its effect had to be included in the finite element model. For several thermal regions, the resultant HTCs had to be calculated from the partial heat transfer coefficients (HTCj in Table 13). These are generated by "Heat Transfer Coefficients.xls".
I HTCRes RTC+HTCJ TC f) l 1+ 1T -Till )TCJJJ)I I I I I i I Where: HTCRes HTCi Ti TCi= Resultant HTC= HTC of i t" material= Thickness of ith material= Thermal Conductivity of i" material The reference for this equation is [4].I Table 13: Resultant Heat Transfer Coefficients for the Regions 100% Flow Regions S R2 Material i HTC I Thenl-I Conductivity, TicsTCII Bnh~rt'F Thickness Iftli Btu/hr-ft-OF 3,921.42 9.8. .. 0.0268 9018 3,921.42..........
....002681 3,9.1 114-29..l-10_,2_6_-__
-.1 144.04.Material Conductivity, Btu/hr. Thickness Ift]t,- ...I-ITC111 I I.3j,921.42 3,921.42 3,921.42 500 0.2 i { ."{ 97.30 L 00268 85.17 9.8 00.268 8.5.17 98 00304 97.30 9.8 0.0268 i 61.68 4-iT Regions 14TC I 142.98 150.64 150.64 150.64 150.641-506 0.2 0% Flow M STheres ConduHvit.
i fITC! ThH,; -liTCIIl [Cs n T Co utiy' Thickness .f' Conductivity, Btu/fidr-Thickness
[ftl: B (u/r-ft-or 98 0.0268 4.4'61_- ... ....... ....I .. ....2 ............
..... ... ..... -..... .-2 ...... * ...... ....... ........ ... ............~ ~ ~ ~ .. ..........................................................
o -30== = = = = = = = = == === = = = ==== = ==9.8 0.0268 85.17 9...............
00268 8517 98 0 .0304 9730 9.8 .0 .0268 .61. ......I I I I I I I File No.: VY-16Q-309 Revision:
0 Page 24 of 32 F0306-O I RO 1Structural integrity Associates, Inc.1 4.0 THERMAL AND PRESSURE LOAD RESULTS The two flow dependent thermal load cases outlined in previous section were run on the core spray FEM.For ANSYS, the thermal transient input files "VY_16Q_T 100.inp," "VY_16QT0.inp," for 100% and 0% flow, respectively.
The stress input filenames are "VY_ 6QST100.inp"and "VYI6QST0.inp," respectively.
The limiting safe end location was chosen based on the highest thermal stress intensity at 100% flow.Node 3719 on the inside surface of the core spray nozzle was selected for the safe end analysis and shown in Figure 6.NODAL SOLUTION STEP=26 SUB =1 TIME=2.5 SINT (AVG)DMX =.816948 SMN =97.958 SMX =75874 AC AN'APR 27 2007 16:10:09-Node 3737 NODAL SOLUTION STEP=26 SUB =1 TIME=2.5 SINT (AVG)DMX =.816948 SMN =97.958 SMX =75874 Node 3719 AN7 APR 27 2007 16:10:09-Node 3737 i15 67454 59035 75874.Node 3719 -rr x 97.958 16937 33776 50615 67454 8517 25357 42196 59035 75874 Core Spray Nozzle Finite Element Model 8517 2535" Figure 6: Safe End Critical Thermal Stress Location, Node 3719 File No.: VY-16Q-309 Revision:
0 Page 25 of 32 F0306-01R0 Structural Integrity Associates, Inc.The. limiting blend radius location was chosen based upon the highest pressure stress intensity.
Node 2166 on the inside surface of the blend radius was therefore selected for the nozzle forging analysis and shown in Figure 7. The highest thermal stress and pressure stress occur very close to the same location in the nozzle forging region. Therefore, this location is a reasonable choice for the limiting location.I I I I I I i I I I U U I I I i II Figure 7: Blend Radius Limiting Pressure Stress Location, Node 2166 File No.: VY-16Q-309 Revision:
0 Page 26 of 32 F0306-O I RO I I IV Structural Integrity Associates, Inc.The stress intensity time history forthe critical safe end and blend radius paths were extracted using the ANSYS post-processing file "extract1OO.inp" for 100% flow. This produced the two files,"SE_ F100.out" and "BRF 100.out," which contain the thermal stress history. The membrane plus bending stresses and total stresses for the'Green's Functions were extracted from these files to produce the four files "SE_F100.cln, BR_FIOO.cln" and "SE_FLOGINSIDE.RED, BR_FlO_ INSIDE.RED." The stress intensity time history for the critical safe end and blend radius paths were extracted using the ANSYS post-processing file "extractO.inp" for 0% flow. This produced the two files, "SE_FO.out" and"BR FO.out," which contain the thermal stress history. The membrane plus bending stresses and total stresses for the Green's Functions were extracted from these files to produce the four files "SEFO.cln, BRFO.cln" and "SEFOINSIDE.RED, BR_FO_ INSIDE.RED." As the models were run with a 400'F step change in temperature, and the Green's Functions are for a I&deg;F.step change in temperature,.
all data values were divided by 400. The governing Green's Functions for the core spray nozzle during 100% flow and 0% flow are shown in Figure 8 through Figure 11. The data for the Green's Functions is included in the files: 0% Flow Rate: SE FlowO T Green.xls SE Flow0 M+B-Green.xls BLEND FlowO M+B Green.xls BLENDFlowOTGreen.xls 100 Flow Rate: SE FlowlO0 T Green.xls SE FlowlO_ M+B-Green.xls BLEND FlowlO0 M+B Green.xls BLENDFlowlO0_TGreen.xls File No.: VY-16Q-309 Revision:
0 Page 27 of 32 F0306-OI RO Structural Integrity Associates, Inc.80000 40000 0 200 400 600 800 Time (see)Figure 8: Safe End Total Stress History, 100% Flow 1000 30000 15000 V)0 1000 2000 3000 4000 5000 6000 7000 Time (sec)Figure 9: Blend Radius Total Stress History, 100% Flow 8000 File No.: VY-16Q-309 Revision:
0 Page 28 of 32 F0306-OI RO VStructural Integrity Associates, Inc.30000 15000 0 200 400 600 800 Time (sec)Figure 10: Safe End Total Stress History, 0% Flow 1000 25000 20000 15000 U)10000 5000 0 1000 2000 3000 4000 Time (sec)5000 6000 7000 8000 Figure 11: Blend Radius Total Stress History, 0% Flow File No.: VY-16Q-309 Revision:
0 Page 29 of 32 F0306-01 RO Structural Integrity Associates, Inc.The pressure stress intensities for the safe end and blend radius paths were extracted using the ANSYS post-processing file "extractP.inp." This produced two files, SEP.OUT for the safe end and BRP.OUT for the blend radius.Results of the internal pressure load case for Node 2166 (blend radius) is a total stress intensity of 35,860 psi and for Node 3719 (safe end), a total stress intensity of 12,030 psi. The membrane plus bending stress intensity at Node 2166 and Node 3719 are 34970 psi and 12,020 psi, respectively.
Table 14 shows the final pressure results for the safe end and blend radius.Table 14: Pressure Results (1,000 psi)Membrane plus Total Stress Location Bending Stress Intensity Intensity (psi)(psi)Safe End 12,020 12,030 Blend Radius 34,970 35,860 I I I I I I I I I I I I I Results were also extracted from the vessel portion of the model to verify the accuracy of the results obtained from the ANSYS model, and to check the results due to the use of the 2.0 multiplier on the vessel radius. These results are contained in the file VESSEL P.OUT. The radius of the finite element model (FEM) was multiplied by a factor of 2.0 [1] to account for the fact that the vessel portion of the 2D axisymmetric model is a sphere, but the true geometry is the intersection of two cylinders.
The equation for the membrane hoop stress in a sphere is: r:( (press-ure ) x (radius )2 x thickness j Considering a vessel base metal radius, R, of 105.906 inches increased by a factor of 2.0, a vessel base metal thickness, t, of 5.4375 inches, and an applied pressure, P, of 1,000 psi, the calculated stress for a sphere is PR/(2t) = 19,477 psi. This compares very well with the remote vessel wall membrane hoop stress from the ANSYS result file, VESSEL_P.OUT, of 18,530 psi. Thus,.considering the peak total pressure stress of 35,860 psi reported above, the stress concentrating effect of the nozzle corner is 35,860/19,477
= 1.84. In other words, the peak nozzle corner stress is 1.84 times higher than nominal vessel wall stress for the 2D axisymmetric model.I I I I File No.: VY-16Q-309 Revision:
0 Page 30 of 32 F0306-01 RO I Structural Integrity Associates, Inc.* The equation for the membrane hoop stress in a cylinder is: 07 (-(pressure) x (radius))S thickness D Based on the previous dimensions, the calculated stress for a cylinder without the 2.0 factor is 19,477 psi. Increasing this by a factor of 1.84 yields an expected peak nozzle corner stress of 35,838 psi, which would be expected from a cylindrical geometry that is representative of the nozzle configuration.
Therefore, the result from the ANSYS file for the peak nozzle comer stress (35,860 psi) is close to the peak nozzle corner stress for a cylindrical geometry because of the use of the 2.0 multiplier.
This is consistent with SI's experience where a factor of two increase in radius is typical* for representing the three-dimensional (3D) effect in a 2D axisymmetric model.*File No.: VY-16Q-309 Revision:
0 Page 31 of 32 F0306-01 RO V Structural Integrity Associates, Inc. .I
 
==5.0 REFERENCES==
 
I 1. SI Calculation No. VY- 16Q-308, Revision 0, "Core Spray Nozzle Finite Element Model".I 2. ANSYS, Release 8.1A1 (w/Service Pack 1), ANSYS, Inc., June 2004.I 3. American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section II, Part D, 1998 Edition, 2000 Addenda.4. J. P. Holman, "Heat Transfer," 4th Edition, McGraw-Hill, 1976.5. J. P. Holman, "Heat Transfer," 5th Edition, 1981.6. Entergy Design Input Record (DIR) EC No. 1773, Revision 0, "Environmental Fatigue Analysis for Vermont Yankee Nuclear Power Station," 7/3/07, SI File No. VY-16Q-209.
I 7. N. P. Cheremisinoff, "Heat Transfer Pocket Handbook," Gulf Publishing Co., 1984.8. CB&I RPV Stress Report, Section T7, "Thermal Analysis of Core Spray Nozzle, Vermont Yankee Reactor Vessel, CB&I Contract 9-6201, SI File No. VY-16Q-206.
I I I I I File No.: VY-16Q-309 Page 32 of 32 I Revision:
0 F0306-0I RO I VStructural Integrity Associates, Inc.APPENDIX A FINITE ELEMENT ANALYSIS FILES ,File No.: VY-16Q-309 Revision:
0 Page Al of A3 F0306-OIRO Structural Integrity Associates, Inc.ANSYS Input Files File Name Description vy csn geom.inp ANSYS input file includes the geometry and material properties Heat Transfer Coefficients.xls Excel file to calculateHeat Transfer coefficients VY 16Q P.inp ANSYS input file for the pressure stress analysis VY 16Q T100.inp ANSYS input file for the thermal analysis, 100% flow rate VY 16Q_TO.inp ANSYS input file for the thermal analysis, 0% flow rate VY 16Q ST100.inp ANSYS input file for the thermal stress analysis, 100% flow rate VY 16QSTO.inp ANSYS input file for the thermal stress.analysis, 0% flow rate extractl0O.inp ANSYS input file to extract the limiting paths, 1.00% flow rate extract0.inp ANSYS input file to extract the limiting paths, 100% flow rate extractP.inp ANSYS input file to extract the limiting paths extractVessel.inp ANSYS input file to extract the membrane stress in the vessel wall I I i I I I I I I I I File No.: VY-16Q-309 Revision:
0 Page A2 of A3 F0306-01 RO I V Structural Integrity Associates, Inc.ANSYS Output Files File Name Description BR_F 100.out ANSYS output file, Results of running: extract100.inp, Blend Radius 100% Flow SE_F100.out ANSYS output file, Results of running: extract100.inp, Safe End 100% Flow BRF 00.cln Reduced ANSYS output file, contains the stress values in time, Blend Radius 100% Flow SE_Fl00.cln Reduced ANSYS output file, contains the stress values in time, Safe End 100% Flow BR-FI100 INSIDE.RED Reduced ANSYS output file, contains detailed stress values in time, Blend Radius 100% Flow SE-F100lINSIDE.RED Reduced ANSYS output file, contains detailed stress values in time, Safe End 100% Flow BR_FO.out ANSYS output file, Results of running: extract0.inp, Blend Radius 0% Flow SE_FO.out ANSYS output file, Results of running: extractO.inp,_Safe End 0% Flow BRFl00.cln Reduced ANSYS output file, contains the stress values in time, Blend Radius 0% Flow SE_F100.cln Reduced ANSYS output file, contains the stress values in time, Safe End 0% Flow BRF0_ INSIDE.RED Reduced ANSYS output file, contains detailed stress values in time, Blend Radius 0% Flow SEFOINSIDE.RED Reduced ANSYS output file, contains detailed stress values in time, Safe End 0% Flow File No.: VY-16Q-309 Revision:
0 Page A3 of A3 F0306-01 RO FS't-ructural Integrity Associates, Inc. File No.: VY- 16Q-310 CALCULATION PACKAGE Project No.: VY-16Q PROJECT NAME: Environmental Fatigue Analysis of VYNPS CONTRACT NO.: 10150394 CLIENT: PLANT: Entergy Nuclear Operations, Inc. Vermont Yankee Nuclear Power Station CALCULATION TITLE: Fatigue Analysis of Core Spray Nozzle Document Affected Project Manager Preparer(s)
&Revision Pages Revision Description Approval Checker(s)
Signature
& Date Signatures
& Date 0 1-27 Initial issue Terry J. Herrmann Roland Horvath/Appendix:
Minghao Qin A1-A2 07/26/2007 07/26/2007 07/26/2007 Carl Limpus 07/26/2007 Page 1 of 27 F0306-OIRO Structural Integrity Associates, Inc. H!Table of Contents 1 .0 O B J E C T I V E ..................................
....... ...... .....................................................
....2... ..................... 4 2.0 METHODOLOGY....................................................................................
4 3.0 A N A L Y SIS ..............................................................................................................................
7 3.1 Transient Definitions (for program STRESS.EXE) 7 3.2 Peak and Valley Points of the Stress History (for program P-V.EXE) 7 3.3 Pressure Load 8 3.4 Attached Piping Loads 8 3.5 Fatigue Analysis (for program FATIGUE.EXE) 11 4.0 Fatigue Usage Results ................................................
11 5.0 Environm ental Fatigue Analysis .....................................................................................
12 6.0 R eferences
.............................................................
..................................................................
13 APPENDIX A INPUT AND OUTPUT FILES ......................................................................
Al.I List of Tables Table .1: Blend Radius Transients
........................
.............................
14 Table 2: Safe End Transients
....................................................
15 Table 3: Maximum Piping StressIntensity Calculations for Blend Radius ..................................
16 Table 4: Maximum Piping Stress Intensity Calculations for Safe End ..... ......................
17 I Table 5: Blend Radius Stress Summ ary ...............
I ............................
................................
18 Table 6: Safe End Stress Sum m ary .............
I ......................................................................................
19 3 Table 7: Fatigue Results for Blend Radius (60 Years) ...............................
20 Table 8: Fatigue Results for Safe End (60 Years) ......................................................................
21 Table 9: Fatigue Results for Stainless Steel Piping (60 Years) .........................................................
22 I I I File No.: VY-16Q-310 Page 2 of 27 I Revision:
0 F0306-01 RO I U Structural integrity Associates, Inc.List of Figures Figure 1: Figure 2: Figure 3: Figure 4: Figure 5: Figure 6: Figure 7: Figure 8: Figure 9: Transient 03: Start Up..................................................................................
23 Transient 11: Loss of Feedwater Pumps, Isolation Valves Close ................................
23 Transient 14: Single Relief of Safety Valve Blow Down .............................................
24 Transient 21-23: Shut Down Vessel Flooding ..............................................................
24 Transient 30: Emergency Shut Down 100% Flow (Safe End) ........................
.................
25 Transient 30: Emergency Shut Down 100% Flow (Blend Radius) .......................
25 External Forces and Moments on the Core Spray Nozzle .........................................
26 Typical Green's Functions for Thermal Transient Stress ..........................
26 Typical Stress Response Using Green's Functions
........................................................
27 File No.: VY-16Q-310 Revision:
0 Page 3 of 27 F0306-01 RO Structural Integrity Associates, Inc. i 1.0 OBJECTIVE The purpose of this calculation is to perform a revised fatigue analysis for the core spray nozzle. Two locations will be analyzed for fatigue acceptance:
the blend radius (SA508 Class II) and the safe end (SB 166 N06600). Both locations are chosen based on the highest overall stress of the analysis performed in Reference
[1]. A revised fatigue usage will be determined for both locations, the nozzle forging and safe end, respectively.
In the end, the environmental fatigue usage factors will be determined for the limiting locations.
 
==2.0 METHODOLOGY==
In order to provide an overall approach and strategy for evaluating the core spray nozzle, the Green's Function methodology and associated ASME Code stress and fatigue analyses are described in this I section.Revised stress and fatigue analyses are being performed for the core spray nozzle using ASME I Code, Section III methodology.
These analyses are being performed to address license renewal requirements to evaluate environmental fatigue for this component in response to Generic Aging Lessons Learned (GALL), Report [12] requirements.
The revised analysis is being performed to I refine the fatigue usage so that an environmental fatigue factor can be determined for subsequent license renewal efforts. i Two sets of rules are available under ASME Code, Section III,. Class 1 [8]. Subparagraph NB-3600 of Section III provides simplified rules for analysis of piping components, and NB-3,200 allows for more detailed analysis of vessel components.
The NB-3600 piping equations combine by absolute I sum the stresses due to pressure, moments and through wall thermal gradient effects, regardless of where within the pipe cross-section the maximum value of the components of stress are located. By considering stress signs, affected surface (inside or outside) and azimuthal position, the stress ranges I may be significantly reduced. In addition, NB-3600 assigns stress indices by which the stresses are multiplied to conservatively incorporate the effects of geometric discontinuities.
In NB-3200, stress indices are not required, as the stresses are calculated by finite element analysis and consider applicable stress concentration factors. In addition, NB-3200 methodology accounts for the different locations within a component where stresses due to thermal, pressure Or other mechanical loading are a maximum. This generally results in a net reduction of the stress ranges and consequently, in the calculated fatigue usage. Article 4 [14] methodology was originally used to evaluate the core spray nozzle. NB-3200 methodology, which is the modem day equivalent to Article 4, is used in this analysis to be consistent with the Section III design bases for this component, as well as toallow a more detailed analysis of this component.
In addition, several of the conservatisms originally used in the original core spray nozzle evaluation (such as grouping of transients) are removed in the current evaluation so as to achieve a more refined CUF.For the core spray nozzle evaluated as a part of this work, stress histories will be computed by a time integration of the product of a pre-determined Green's Function and the transient data. This Green's Function integration scheme is similar in concept to the well-known Duhame! theory used in File No.: VY-16Q-310 Page 4 of 27 i Revision:
0 F0306-OIRO I
H S9trluctlraI -integrity Associates, Inc.1structural dynamics.
A detailed derivation of this approach and examples ofisapplication to specific plant locations is contained in Reference
[11]. A general outline is provided in this section.The steps involved in the evaluation are as follows: SDevelop finite element model*Develop heat transfer coefficients and boundary conditions for the finite element model:Develop Green's Functions I Develop thermal transient definitions
*Perform stress analysis to determine stresses for all thermal transients I .* Perform fatigue analysis A Green's Function is derived by using finite-element methods to determine the transient stress response of the component to a step change in loading (usually a thermal shock). The critical*location in the component is identified b ased on the maximum stress, and the thermal stress response over time is extracted for this location.
This response to the input thermal step is the "Green's Function." Figure 8-s~hows a typical set of two Green's Functions, each for a different set of heat transfer coefficients (representing different flow rate conditions).
To compute the thermal stress response for an arbitrary transient, the loading parameter (usually I local fluid temperature) is deconstructed into a series of step-loadings.
By using the Green's Function, the response to each step can be quickly determined.
By the. principle of superposition, these can be added (algebraically) to determine the response to. the original load history. The result is demonstrated in Figure 9. The input transient temperature history contains five step-changes of varying size, as shown in the upper plot in Figure 9. These five step changes produce the five successive stress responses in the lower plot shown in F'igure 9. By adding all five response curves,*the real-time stress response for the input thermal transient is computed.The Green's Functi on-methodology produces identical results compared to running the input transient through the finite element model. The advantage of using Green's Functions is that many individual transients can be run with a significant reduction of effort compared to running all transients through the finite element model. The trade-off in this process is that the Green's Functions are based on constant*material properties and heat transfer coefficients.
Therefore, these parameters are chosen to bound all.transients that constitute the majority of fatigue usage, i.e., the heat transfer coefficients at 300'F bound the cold water injection transient.
In addition, the 'instantaneous value for the coefficient of thermal expansion is used instead of the mean value for the coefficient of thermal expansion.
This conservatism is more than offset by the benefit of not having to analyze every transient, which was done in the VY core spray nozzle evaluation.
Once the stress history is obtained for all transients using the Green's Function approach, the remainder of the fatigue analysis is carried out using traditional methodologies in accordance with ASME Code, Section III requirements.
I Fatigue calculations are performed in accordance with ASME Code, Section 111, Subsection NB-.3200 methodology.
Fatigue analysis is performed for the two limiting locations (one in the safe end I*File No.: VY-16Q-310 .Page 5of 27 Revision:
0 F0306-01 RO Structural integrity Associates, Inc. H and one in the nozzle forging, representing the two materials of the nozzle assembly) using the Green's Functions developed for these two locations and 60-year projected cycle counts.Three Structural Integrity utility programs will be used to perform the fatigue analysis.
The first two calculate stresses in response to transients.
The transients analyzed are those described in the thermal cycle diagrams [2] for the core spray nozzle. These transients are shown in Figure 1- Figure 6. The temperatures and pressures for these transients have been modified to account for power uprate [3]. The power uprate pressures and temperatures were used for this analysis.
The last program calculates fatigue based on the stress output. The three programs are STRESS.EXE, P-V.EXE, and FATIGUE.EXE.
The first program, STRESS.EXE, calculates a stress history in response to a thermal transient using a Green's Function.
The second program, P-V.EXE, reduces the stress history to peaks and valleys, as required by ASME Code fatigue evaluation methods. The third program, FAT[GUE.EXE, calculates fatigue from the reduced peak and valley history using ASME Code, Section III range-pair methodology.
All three programs are explained in detail and have been independently verified for generic use in the Reference
[4] calculation.
In order to perform the fatigue analysis, Green's Functions are developed using the finite element model. Then, input files with the necessary data are prepared and the three utility computer I programs are run. The first program (STRESS.EXE) requiresthe following three input files:* Input file "GREEN.DAT":
This file contains the Green's Function for the location being I evaluated.
For each flow condition, two Green's Functions are determined:
a membrane plus bending stress intensity Green's Function and a total stress intensity Green's Function.
This allows computation of total stress, as well as membrane plus bending stress, which is necessary I to compute K, per ASME Code, Section III requirements.
0 Input file "GREEN.CFG":
This file is a configuration file containing parameters that define the Green's Function (i.e., number of points, temperature drop analyzed, etc.).* Input file "TRANSNTJNP":
This file contains the input transient definition for all thermal transients to be analyzed for the location being evaluated.
Pressure and piping stress intensities are also included for each transient case, based on pressure stress results from finite element analysis and attached piping load calculations.
The second program (P-V.EXE) simply extracts only the maxima and minima stress (i.e., the peaks and valleys) from the stress histories generated by program STRESS.EXE.
.The third program (FATIGUE.EXE) performs the ASME Code peak event-pairing required to calculate a fatigue usage value. The input data consists of the output peak and valley history from program P-V.EXE, and a configuration input file that provides ASME Code configuration data relevant to the fatigue analysis (i.e., K, parameters, Sm, Young's modulus, etc.). The output is the final fatigue calculation for the location being evaluated.
.The Green's Function methodology described above uses standard industry stress and fatigue analysis practices, and is the same as the methodology used in typical stress reports. Special approval for the use of this methodology is therefore not required.File No.: VY-16Q-310 Page 6 of 27 I Revision:
0 F0306-OIRO i
UStructural Integrity Associates, Inc.3.0 ANALYSIS The transients analyzed for the core spray nozzle were developed based on the definitions in the original RPV Design Specification
[10], as modified for EPU [3], as well as more recent definitions based on BWR operating experience
[2] for BWR. The final transients evaluated in the stress and fatigue analyses are shown in Figure 1 thru Figure 6.The fatigue analysis involves the preparing of input files for, and running of three programs [4]. The programs STRESS.EXE and P-V.EXE are run together through the use of a batch file. The program FATIGUE.EXE is run after processing the output from.PV.EXE.
The steps associated with this process are described in the following sub-sections.
 
===3.1 Transient===
 
Definitions (for program STRESS.EXE)
The program STRESS.EXE requires the following three input files for analyzing an individual transient:
Green.dat.
There are 8 stress history functions obtained from References
[1]. They represent the membrane plus bending and total stress intensities at the blend radius and safe end locations.
Both of the blend radius and the safe end have two stress history functions for flow condition of 0% and 100%.* Green.cfg is configured as described in Reference
[4].I
* Transnt.inp.
These files are created to represent the selected transients obtained from the thermal cycle diagrams [2] and redefinedby power uprate [3]. Table 1 and Table 2 contain the loading defined for each transient.
Based upon the thermal cycle diagram for the RPV and the core spray nozzle, the transients are split into the following groups based upon flow rate: o Transients 02, 03, 11, 14, 21-23 and 24 are run at 0% flow.o Transient 30 runs at 100% flow rate per [3]. The transient of emergency shutdown is numbered as 30.The remaining transients are not included in this analysis, as temperature changes from them are considered negligible to have impact on the results.3.2 Peak and Valley Points of the Stress History (for program P-V.EXE)The program P-V.exe is then run to extract the peaks and valleys from the STRESS.OUT file produced by the STRESS.EXE program. The only input required for this program is STRESS.OUT and it outputs all the peaks and valleys to P-V.OUT. Columns 2 through 5 of Table 5 (for the blend radius) and Table 6 (for the safe end) show the final peak and valley output. The pressure for column six is then filled in using the thermal cycle diagrams.
Pressure and piping loads have to be added to the peak and valley points to calculate the final stress values used for fatigue analysis.FileNo.: VY-16Q-310 Page 7 of 27 Revision:
0 F0306-01 RO V Structural Integrity Associates, Inc.3.3 Pressure Load The pressure stress associated with a 1000 psi internal pressure was determined in Reference
[1].These values are as follows: Membrane plus Total Stress Location Bending Stress Intensity Intensity (psi)(psi)Safe End 12,020 12,030 Blend Radius 34,970 35,860 These pressure stress values for each location were linearly scaled according to the pressure of the transient.
The actual pressure for column 6 of Table 5 and Table 6 is obtained from Reference
[2] and shown in Tables 1 and 2. The scaled pressure stress values are shown in columns 7 and 8 of Table 5 (for the blend radius) and Table 6 (for the safe end).The pressure stress is combined with the peak and valley points to calculate the final stress values used for fatigue analysis.3.4 Attached Piping Loads Additionally, the piping stress intensity (stress caused by the attached piping) was determined.
These piping forces and moments are determined as shown in Figure 7.The following formulas are used to determine the maximum stress intensity in. the nozzle at the two locations of interest.
From engineering statics, the piping loads at the end of the model can be translated to the first cut (blend radius) and second cut (safe end) locations using the following equations:
I I I ,I I I I I I I I I I I I ,I I I I For Cut I: (Mx)1 = M. -FYLI (MY), = My + F&#xfd;,Lj For Cut 11: (M*)2=MX -FL (My)2 = My + FxL2 File No.: VY-16Q-310 Revision:
0 Page 8 of 27 F0306-01 RO U Structural Integrity Associates, Inc.I The total bending moment and shear loads are obtained using the equations below: ForCut1:MI, = x/(MJ), + (MY),, For CutI: 1 I FY= V(Fx)2 2 + (F&#xfd;)2 2 The distributed loads for a thin-walled cylinder are obtained using the equations below: N 7 rR N[2 RN]I IM N- F +-q rRN 2RN To determine the primary stresses, PM, due to internal pressure and piping loads, the following* equations are used.For Cut I, using thin-walled equations:
PaIV Nz 2tN tN I (PM)o = Pa-NtN (PM) R -P qN TM.SI 4(P 2 Ior S 2 =\(jPm)z -(M)R + -i(ZM)Z 6 2 3 Where: L, = The length from the end of the nozzle where the piping loads are applied to the location of interest in the blend radius.I FileNo.: VY-16Q-310 Page 9 of 27 Revision:
0 F0306-01 RO V Structural Integrity Associates, Inc.L2 The length from the end of the nozzle where the piping loads are applied to the locationI of interest in the safe end.Mxy, = The maximum bending moment in the xy plane.Fyx = The maximum shear force in the xy plane..NZ = The normal force per inch of circumference applied to the end of the nozzle in the z direction.
qN = The shear force per inch of circumference applied to the nozzle.RN = The mid-wall nozzle radius.Because pressure was not considered in this analysis, the equations used for Cut I are valid for Cut II.In addition, the equations.
can be simplified as follows: NZ (PM, =-tN (PM) =0 I (PM)R =0 T-M =-q=2(r. )&#xfd;oi or OF(S1m4x= 2 ; +(rM).&deg;Per Reference
[5], the core spray nozzle piping loads are as follows: F,, = 2,500 lbs M, 22,000 ft-lb = 264,000 in-lb Fy 4,600 lbs My = 7,100 ft-lb = 85,200 in-lb I F, = 1,700 lbs M= 8,800 ft-lb = 150,600 in-lb The location of.the nozzle piping loads is assumed to be at the end of the connection of the safe end I and the attached pipe. Therefore, the LI is equal to 30.817 inches and the L2 is equal to 0.303 inches. The, calculations for the blend radius and safe end are shown in Table 3 and Table 4. The first cut location is the middle of Green's Function cross section for the blend radius (Node 2181)per [1], and the second cutis from Node 3719 (inside) to Node 3737 (outside).
The maximum stress intensities, due to piping loads are 322.52 psi at the blend radius and 6949.94 psi at the safe end, respectively.
The piping load sign is set as the same as the thermal stress sign.These piping stress values are scaled assuming no stress occurs at an ambient temperature of 70'F and the full values are reached at reactor design temperature, 575TF [2]. The scaled piping stress values are shown in columns 9 and 1.0 of Table 5 and Table 6. Columns 11 and 12 of Table 5 and Table 6 show the summation of all stresses for each thermal peak and valley stress point.File No.: VY-16Q-310 Page 10 of 27 Revision:
0 F0306-OIRO V Structural Integrity Associates, Inc.3.5 Fatigue Analysis (for program FATIGUE.EXE)
The number of cycles projected for the 60-year operating life. is used for each transient, as obtained from Reference
[2]. Column 13 in Table 5 and Table 6 shows the number of cycles associated with each transient.
The program FATIGUE.EXE performs the "ASME Code style" peak event pairing required to calculate a fatigue usage value. The input data for FATIGUE.CFG is as follows: Blend Radius Safe End Piping (SA508 Class II) (N06600) (Stainless Steel)Parameters m and n for 2.0 & 0.2 Computing K, (low alloy steel) [81 Design Stress Intensity 26,700 psi [6] @ 23,300 psi [6] @ 17,000 psi [6] @Values, Sm 600&deg;F 600OF 600&deg;F Erastic Modulus from Applicable Fatigue Curve 30.0x10 6 psi [8] 28.3x10 6 psi [8] 28.3x10 6 psi [81 Elastic Modulus Used in Finite Element Model (300TF) 26.7x10 6 psi [1] 29.8x10 6 psi [1] 27.0x10 6 psi [1]The Geometric Stress Th e m ti tes1.0 4.0 See Note 1.8 [14]Concentration Factor K1 Note: Conservative bounding value per ASME Code, Section NB-3600 to cover thread and weld regions.The results of the fatigue analyses are presented in Table 7 through Table 9 for the blend radius, safe end and stainless steel piping for 60 years, respectively.
The Core Spray piping adjacent to the safe end was also analyzed because of its proximity to the maximum safe end thermal stress location.
For this fatigue analysis, the stress results of the safe end were used with stainless steel material properties and a value of 1.8 was selected for Kt at the weld location, based on the maximum value given in ASME Code, Section III, table NB-3681(a)-1
[8].The results described are contained in EXCEL files BRresults.xls and SEresults.xls, which are contained in the computer files.4.0 FATIGUE USAGE RESULTS The blend radius Cumulative Usage Factor (CUF) from system cycling is 0.0043 for 60 years. The safe end CUF is 0.0184 and the CUF of stainless steel piping is 0.0005 for 60 years.File No.: VY-16Q-310 Revision:
0 Page 11 of 27 F0306-0IRO V Structural Integrity Associates, Inc.5.0 ENVIRONMENTAL FATIGUE ANALYSIS Per Reference
[7], the dissolved Oxygen (DO) calculation shows the overall HWC availability is 47%.It means the pre-HWC is 53%.The fatigue calculation will be re-performed for the nozzle base material, since cladding is structurally neglected in modem-day fatigue analyses, per ASME Code, Section III, NB-3122.3
[8]. This is also consistent with Sections 5.7.1 and 5.7.4 of NUREG/CR-6260
[9]. Therefore, the cladding will be neglected and EAF assessment of the nozzle base material is performed.
For the blend radius location, the environmental fatigue factors for pre-HWC and post-HWC are 11.14 and 8.82 from Table 4 of Reference
[7]. It results in an EAF adjusted CUF of (11.14 x 53% +8.82 x 47%) x 0.0043 = 0.0432 for 60 years, which is acceptable (i.e., less than the allowable value of 1.0). The overall environmental multiplier is 10.05.For the safe end location, the environmental fatigue factors for post-HWC and pre-HWC are all 1.49 from Reference
[13]. It results in an EAF adjusted CUF of 1.49 x 0.0184 = 0.0274 for 60 years, which is acceptable (i.e., less than the allowable value of 1.0). The overall environmental multiplier is 1.49.For the stainless steel piping, the environmental fatigue factors for post-HWC and pre-HWC are all 8.36 from Table 4 of Reference
[7]. It results in an EAF adjusted CUF of 8.36 x 0.0005 = 0.00418 for 60 years, which is acceptable (i.e., less than the allowable value of 1.0). The overall environmental multiplier is 8.36.I I i I I I I I I I A Fatigue Environmental Multiplier of 1.49 for Ni-Cr-Fe was applied to the safe end fatigue usage I and 8.36 for stainless steel to the piping. This results in the safe end being the limiting location for fatigue.U I I I I I I File No.: VY-16Q-310 Revision:
0 Page 12 of 27 F0306-OI RO Structural Integrity Associates, Inc.
 
==6.0 REFERENCES==
 
I SI Calculation No. VY-16Q-309, Revision 0, "Core Spray Nozzle Green's Functions." 2 "Reactor Thermal Cycles for 60 Years of Operation," Attachment I of Entergy Design' Input Record (DIR), Revision 1, EC No. 1773, Revision 0, "Environmental Fatigue Analysis for Vermont Yankee Nuclear Power Station," 7/26/07, SI File No. VY-16Q-209.
3 GE Certified Design Specification No. 26A6019, Revision 1, "Reactor Vessel -Extended Power Uprate," August 29, 2003, SI File No. VY-05Q-236.
4 Structural Integrity Associates Calculation (Generic)
No. SW-SPVF-01Q-301, Revision 0,"STRESS.EXE, P-V.EXE, and FATIGUE.EXE Software Verification." S 5 VY Drawing 5920-0024, Revision 11, Sht. No. 7, "Reactor Vessel," (GE Drawing No.919D294), SI File No. VY-05Q-241.
6 American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section II, Part D, 1998 Edition, 2000 Addenda.7 SI Calculation No. VY- 16Q-3 03, Revision 0, '"'Environmental Fatigue Evaluation of Reactor Recirculation Inlet Nozzle and Vessel Shell Bottom Head." 8 American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section III Subsection NB, 1998 Edition, 2000 Addenda.9 NUREG/CR-6260 (INEL-95/0045), "Application of NUREG/CR-5999 Interim Fatigue Curves to Selected Nuclear Power Plant Components," March 1995.10 GE Design Specification No. 21A1 115, Revision 4, "Vermont Yankee Reactor Pressure Vessel," October 21, 1969, SI File No. VY-05Q-210.
11 Kuo, A. Y., Tang, S. S., and Riccardella, P. C., "An On-Line Fatigue Monitoring System for Power Plants, Part I -Direct Calculation of Transient Peak Stress Through Transfer Matrices and Green's Functions," ASME PVP Conference, Chicago, 1986.12 NUREG-1801, Revision 1, "Generic Aging Lessons Learned (GALL) Report," U. S. Nuclear Regulatory Commission, September 2005.13 EPRI Report No. TR-105759, "An Environmental Factor Approach to Account for Reactor Water Effects in Light Water Reactor Pressure Vessel and Piping Fatigue Evaluations," December 1995.14 American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section III, Subsection A, Article4, 1965 Edition with Winter 1966 Addenda.File No." VY-16Q-310 Page 13 of 27 Revision:
0 F0306-01 RO Structural Integrity Associates, Inc.Table 1: Blend Radius Transients 1,2,3 Transient Time Temp Time Step Pressure Flow Rate Number { (GPM)2. Design HYD Test -- 100 -- 0 1100 120 Cycles 50 3. Startup 0 100 0 0 300 Cycles 16164 549 16164 1010 (0%)24164 549 8000 1010 11. Loss of Feedwater 0 526 1010 0 Pumps 3 526 3 1190 (0%)10 Cycles 13 526 10 1135 233 300 220 1135 2213 500 1980 1135 2393 300 180 885 6893 500 4500 1135 7313 300 420 675 7613 300 300 675 11213 400 3600 240 16577 549 5364 1010 16637 549 60 1010 16638 542 1 1010 16698 542 60 1010 16699 526 1 1010 24699 .526 8000 1010 14. SRV Blowdown 0 526 1010 0 I Cycle 600 375 600 400 (0%)11580 70 10980 50 19580 70 8000 50 21-23. Shutdown 0 549 1010 0 300 Cycles 6264 375 .6264 50 (0%)6864 330 600 50 16224 100 9360 50 24224 100 8000 50 24. Hydrostatic Test -- 100 -- 50 1 Cycle 1563 50 30. Emergency Shut Down 0 549 1010 3200 I Cycle 10 406 10 250 (100%)11 70 1 250 8011 70 8000 0 -j 1. Instant temperature change is I sec.2. This is due to the length of the Green's Function; The transients are plotted using an 8000 second steady state increment.
: 3. The number of cycles for 60 years is from Reference
[2].I I I I I I I I I I I I I I I I I I I Note: File No.: VY-16Q-310 Revision:
0 Page 14 of 27 F0306-OIRO U Structural Integrity Associates, Inc.I-Table 2: Safe End Transients",2,'
3 Transient Time Temp Time Step Pressure Number (s) f F) Ls) sfs&sect;q)2. Design HYD Test 100 -- 0 120 Cycles 1100 50 3. Startup 0 100 0 300 Cycles 16164 549 16164 1010 17164 549 1000 1010 11. Loss of Feedwater Pumps 10 Cycles 0 3 13 233 2213 2393 6893 7313 7613 11213 16577 16637 16638 16698 16699 17699 526 526 526 300 500 300 500 300 300 400 549 549 542 542 526 526 3 10 220 1980 180 4500 420 300 3600 5364 60 1 60 1 1000 1010 1190 1135 1135 1135 885 1135 675 675 240 1010 1010 1010 1010 1010 1010.14. SRV Blowdown 0 526 1010 0 1 Cycle 600 375 600 400 (0%)11580 70 10980 50 12580 70 1000 50 21-23. Shutdown 0 549 1010 0 300 Cycles 6264 375 6264 50 (0%)6864 330 600 50 16224 100 9360 50 17224 100 1000 50 12. Hydrostatic Test --- 100 50 1 cycle 1563 50 30. Emergency Shut Down 0 549 1010 3200 1 Cycle 10 406 10 250 (100%)11 70 1 250 1011 70 1000 0 Note: I. Instant temperature change is 1 sec.2. The transients are plotted using a 1000 second steady state increment.
the Green's Function for the safe end.3. The number of cycles for 60 years is from Reference
[2].The difference is due to the length of File No.: VY-16Q-310 Revision:
0 Page 15 of 27 F0306-OIRO Structural Integrity Associates, Inc.Table 3: Maximum Piping Stress Intensity Calculations for Blend Radius Blend Radius External Pipinq Loads Fz=Mx=my=Mz-OD=ID=RN --kips kips Kips in-kips in-kips in-kips in in in I I I I I I I I I I I 7.65 L = ________in tN = 3.56 in (Mx)2 22.24 in-kips (MY)2 162.24 in-kips MxV = 203.14 in-kips FxY = 5.24 kips Nz= 1.14 kips/in N -0.07 kips/in Primary Membrane Stress Intensity PMz 0.32 ksi= -0.02 ksi SImax 0.32 ksi Si[max 322.52 1 psi.Note: The locations for Cut I and Cut 1I were defined in Reference
[1] for safe end and blend radius paths, respectively.
I I I I I I File No.: VY-16Q-310 Revision:
0 Page 16 of 27 F0306-O1RO V Structural Integrity Associates, Inc.Table 4: Maximum Piping Stress Intensity Calculations for Safe End Safe End External Piping Loads Parameters Fx = F 0 , kips Fz = kips Fz &#xfd; ' 1.70 kips M24= in-kips M 8a5 20. in-kips MZa 105160 in-kips OD= 0149 in ID= 262.60 in MRN= 5.16 in L = 0.30 in tN =0.49 in NO1 262.60 in-kips (y,= 85.96 in-kips MX 276.31 in-kips Fxy 5.24 kips Nz= 3.35 kips/in qN= -0.31 kips/in Primary Membrane Stress Intensity PMz 6.84 ksi: -0.63 ksi Slmax 6.95 ksi Simax 6949.94 psi Note: The locations for Cut I and Cut II were defined in Reference
[1]paths, respectively.
for safe end and blend radius File No.: VY-16Q-310 Revision:
0 Page 17 of 27 F0306-01RO Structural Integrity Associates, Inc. I Table 5: Blend Radius Stress Summary I 1 2 3 4 5 6 7 8 9 10 11 12 13 Total M+B Total M+B Total Total Number Total M+B1 Pressure Pressure Piping Piping Total M+B of Transient Time. Stress Stress Temperature Pressure Stress Stress Stress Stress Stress Stress Cycles Number Is) (psi) (psi) F (psiq) J(psi (psi). (psi) (psi) (psi) (psi) (60 years 2: ___________
100 ___ 0 ____0 ____0 ___ 19 19 19 ___ 19 120____100 1100 39446 38467 ____19 19 39465 __ 38486 120___100 50 1793 1749 _ _ 19 19. 1812 ___1768 120 3 ___0 23700 12600 _ _ 100 _ _ 0 ___0 0 ___19 19 23719 ___12619 300 24164 2100 _3180 ___ 549 1010 36219 35320 306 306 38625 ___38806 300 1 ___0 3209 _3644 ___ 526 1010 36219 35320 291 291 39719 ___39255 ____10 3 3209 _36,44----__
526 1190 42673 41614 291 291 46174 ___45550 __ _10____ 526 10458 5374 ____330 1135 40701 3969.1 166 166 _ 51325 ___45231 _ _ 10 2222 5488 -1664 ___ 490 1122: 40235 39236 -268 268 _ 45991 -41168 ____10.2860 11776, 7444 ___ 321 911 32668 31858 ___160 160, 44605 ___39462 ____10 6903 5435 3621 ___ 495 1124 40307 39306 ___272 272 _ 46013 ___43199 ____10 8012 12577 6791 ___ 390 ___627 22484 21926 ___204 204 _ 35265 ___28921 TO__ 1 16640 2772 4370 ___ 542 1010 36219 35320 ___301 301 _ 39292 ___39991 ____10 S1699.1 3389 4115 ___ 526 1010 36219 35320 ___291 291 _ 39899 ___39726 ____10 24699 3209 364,4 ____526 1010 36219 35320 ___291 291 _ 39719 39255 _ _ 10 14 0 3209 3644 ___ 526 1010 36219 35320.__ 291 291 39719.___
39255 1___19580 25122. 13197 _ __ 70 ____50 1793 ___1749 _ _ 0 __ 0 26915 149461 21-23 0 2103 3161 549[ 1010 36219 35320 306 306 38628 38787 300____ 24224 23680 12568 -100 _ __50. :1793 1749 _ __19 19 25492 14336 300 24 ____ ___ ___100 ____50 1793 1749 ____19 19 1812 ____1768 1_____100 1563 56049 54658 ____19 19 56068 54677 1 100 ____50 1793 1749 19 19 1812 1768 1 300 2040 2950 549 1010, 362191 35320 3061 3061 38565 385761 11____ 8011, 25700, 149001 701 of__ : 0 0 ___ 0 ____ 01 257001 149001 11 I I I I I I NOTES: Column 1: Transient number identification.
Column 2: Time during transient where a maxima or minima stress intensity occurs from P-V.OUT output file.Column 3: Maxima or minima total stress intensity from P-V.OUT output file.Column 4: Maxima or minima membrane plus bending stress intensity from P-V.OUT output file.Column 5: Temperature per total stress intensity.
Column 6: Pressure per Table 1.Columnn 7: Total pressure stress intensity from the quantity (Column 6 x 35,860)/1000
[1].Column 8: Membrane plus bending pressure stress intensity from the quantity (Column 6 x 34,970)/1000
[1].Columni 9: Total external stress from calculation in Table 3, 322.52 x (Column 5 -70&deg;F)/(575&deg;F
-70'F).Column 10: Same as Column 9, but for M+B stress.Column 11: Sum of total stresses (Columns 3, 7, and 9).Column 12: Sum of membrane plus bending stresses (Columns 4, 8, and 10).Column 13: Number of cycles for the transient (60 years).I I I I I I I I I I I File No.: VY-16Q-310 Revision:
0 Page 18 of 27 F0306-01 RO V Structural Integrity Associates, Inc.Table 6: Safe End Stress Summary 1 2 3 4 5 6 7 8 9 10 11 12 .13 Total M+B " Total M+B Total Total Number Total M+B. Pressure Pressure Piping Piping Total M+B of Transient Time Stress Stress Temperature Pressure Stress Stress Stress Stress Stress Stress Cycles Number (s) (psi) (psi) F (psig) (psi) (psi) (psi) (psi) (psi) (psi) (60 years)2 ___100 0 0 ____0 413 __ 413 413 413 __ 120_____ ___________100, 1100 13233 13222. 413 ___413. 13646 13635 ___120______100 50 602 601 ___413 __ 413 __ 1014 1014 __ 120 3 0 661 759 100 0 0 0 413 413 1074 1172 300 17164 9240 10700 549 1010 12150 12140 6592 6592 _ 27982 29432 300 11 0 8802 10236 526 1010 12150 12140 __ 6276 _;_, 6276 ____ 27228 28652 ___:_ 10 3 8 6802 10236 526 1190 14316 14304 6276 _. : 6276 ___ 29393 30815 _ 10 13 8802 10236 526 1135 13654 13643 l .3 6276 .6276 ___ 28732 ____ 30154 _ : .10 1_______ 164 11645 11598 408 1135 13654 13643 ___ 4657 4657 ___ 29956 _ 29898 _ 10 672 4808 5791 344 1135 13654 136&#xfd;43 __ 3775 3775 ___ 22237 :____ 23209 , 10_.__.________
2374 11140 10841 361 912 10971 10962 ___ 4005 4005 ___ 26116 _;:-_:25808
__;= 10;-2955 4722 5577 325 916 11019 1.1010 3509 3509 __;19250 ____ 20096 ____ 10 7054 9518 10162 _._.__ 441 959 11537 ___ 5100 __ 5100 __ 26155 __.: 26789 .___::10 7930 4491 5276 ______: 309 637 7663 7657 __ 3287 3287 15441 16219 .10 1 16709 9960 11,116 : _____ 526 1010 12150 12140 ___ 6276 6276 _:_28386 __ 29532 __;;_- 10 17699 8802, 10236 _ _ 526 1010 12150 12140 __ 6276 : 6276 _ 27228 _ 28652 ___-__ 10 14 0 8802 10236 526 1010 12150 12140 6276 6276 27228 28652 1 152 9499 10570 497 855 10286 10277 5880 5880 25664 26727 1 12580 91 95
* 70 50 602 601 0 0 693 696 1 21.23 .0 223 9242 0 .5 0 299549 1010 12150 12140 6592 6592 27984 18732 300 17224 ;664 ,.:; 0 _____ 100 50 s 602 601 ____.413 413 187 _,6781 1014 300 24 100 50 602 601 413 413 1014 1014 1 1 100 1563 18803 18787 413 413 19216 19200 1 100 50 602 601 413 413 1014 1014 1 30 0 9280 108001 549 1010 121501 12140' 6592 6592 28022 29532 ____.,1:13 85600 44694 162 250 3002 30001 1260 1260 89862 48953 ______ 1____ 1011 -1? -101 70 0 01 0___' _ 0 ____0 10 ____1 NOTES: Column 1: Transient number identification.
Column 2: Time during transient where amaxima or minima stress intensity occurs from PrV.OUT output file.Column 3: Maxima or minima total stress intensity from P-V.OUT output file.Column 4: Maxima or minima membrane plus bending stress intensity from P-V.OUT output file.Column 5: Temperature per total stress intensity.
Column 6: Pressure per Table 2.Column 7: Total pressure stress intensity from the quantity (Column 6 x 12,030)/1000.
Column 8: Membrane plus bending pressure stress intensity from the quantity (Column 6 x 12,020)/1000.
Column 9: Total external stress from calculation in Table 4,-6949.94 x (Column 5-70'F)/(575&deg;F
-70'F).Column 10: Same as Column 9, but for M+B stress.Column 11: Sum of total stresses (Columns 3, 7, and 9).Column 12: Sum of membrane plus bending stresses (Columns 4, 8, and 10).Column 13: Number of,cycles for the transient (60 years).File No.: VY-16Q-310 Revision:
0 Page 19 of 27 F0306-0I RO Structural Integrity Associates, Inc.Table 7: Fatigue Results for Blend Radius (60 Years)LOCATION = LOCATION NO. 2 -- BLEND RADIUS FATIGUE CURVE = 1 (1 = CARBON/LOW ALLOY, 2 = STAINLESS STEEL)m= 2.0 n .2 Sm = 26700. psi Ecurve = 3.000E+07 psi Eanalysis
= 2.670E+07 psi Kt = 1.00 MAX MIN RANGE 56068.51325.46174.46013..45991.44605.39899.39719.39719.39719.39465.39465.39292.38628.38628.38628.38628.38625.38625.38565.35265..26915.25700.19.19.19.19.19.19.19.19.19.19.19.1812.1812.1812.1812.1812.23719.23719.25492.25492.25492.25492.25492.56049.51306.46155.45994.45972.44586.39880.39700.39700.39700.39446.37653.37480.36816.36816.36816.14909.14906.13133.13073.9773.1423.208.MEM+BEND Ke 54658. 1.000 45212. 1.000 45531. 1.000 43180. 1.000 41149. 1.000 39443. 1.000 39707. 1.000 39236. 1.000 39236. 1.000 39236. 1.000 38467. 1.000 36718. 1.000 38223. 1.000 37019. 1.000 37019. 1.000 37019. 1.000 26168. 1.000 26187. 1.000 24470. 1.000 24240. 1.000 14585. 1.000 610. 1.000 564. 1.000 Salt Napplied Nallowed 31488. 1.OOOE+00 1.896E+04 28824. 1.OOOE01 2.501E+04 25930. 1.OOOE+01 3.460E+04 25839. 1.OOOE+01 3.498E+04 25827. 1.OOOE+01 3.503E+04 25048. 1.00E++/-01 3.848E+04 22404. 1.OOOE+01 5.695E+04 22303. 1.000E+01 5.824E+04:22303. 1.OOOE+01 5.824E+04 22303. 1.OOOE+00 5.824E+04 22161. 3;800E+01.6.012E+04 21153. 8.200E+01 7.572E+04 21056. 1.OOOE+01 7.747E+04 20683. 2.800E+01 8.466E+04 20683. 1.OOOE+00 8.466E+04 20683. 1.OOOE+00 8.466E+04 8376. 2.700E+02 5.366E+07 8374. 3.OOOE+01 5.375E+07 7378. 2.700E+02 3.042E+08 7344. 1*000E+00 3.374E+08 5490. 1.OOOE+01 1.OOOE+20 799. i.OOOE+00 1.OOOE+20 117. 1.OOE+00 1.000E+20 U.0001.0004.0003.0003.0003.0003.0002.0002.0002.0000.0006.0011.0001.0003.0000.0000.0000.0000.0000.0000.0000.0000.0000.0043 TOTAL USAGE FACTOR I I I I I I I I I I I I I I I I I I I File No.: VY-16Q-310 Revision:
0 Page 20 of 27 F0306-01 RO I Structural Integrity Associates, Inc.I Table 8: Fatigue Results for Safe End (60 Years)LOCATION = LOCATION NO. 1 -- SAFE END FATIGUE CURVE = 2 (1 = CARBON/LOW ALLOY, 2 = STAINLESS STEEL)m =1.7 n= .3 Sm 23300. psi Ecurve 2.830E+07 psi Eanalysis 2.980E+07 psi Kt 4.00 MAX 89862.29956.29393.28732.28386.28022.27984.27984.27984.27984.27984.27984.27982.27982.27228.27228.27228.26155.26116.25664.22237.19250.19216.15441.13646.MIN-12.413.413.413.413.413.413.693.1014.1014.1014.1074.1074.1678.1678.1678.1678.1678.1678.1678.1678.1678.1678.1678.1678.RANGE 89874.29543.28980.28319.27973.27609.27571.27291.26970.26970.26970.26910.26908.26304.25550.25550.25550.24477.24438.23986.20559.17572.17538.13763.11968.MEM+BEND Ke Salt Napplied Nallowed 48963.29485.30402.29741.29119.29119.18319.18036.17718.17718.17718.17560.28260.28418.27638.27638.27638.25775.24794.25713.22195.19082.18186.15205.12621.1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 112423.56029.57068.55813.54762.54590.39187.38651.38045.38045.38045.37792.53033.52971.51502.51502.51502.48339.46923.48017.41379.35526.34234.28195.23661.1. OOOE+00 1.00OE+OI 1.OOOE+01 1.OOOE+01 1.OOOE+01 1. OOOE+00 7. 900E+01 1. OOOE+00 1. 200E+02 1. OOOE+00 1. ooE+00 9. 800E+01 2.020E+02 9. 800E+01 1. OOOE+OI 1. OOOE+01 1. OOOE+00 1 OOOE+01 1.OOOE+01 1. OOOE+00 1.OOOE+01 1.OOOE+01 1. OOOE+00 1. OOOE+01 1. 200E+02 1. 213E+03 1. 910E+04 1. 746E+04 1. 946E+04 2. 140E+04 2. 174E+04 1.244E+05 1.341E+05 1.460E+05 1.460E+05 1.460E+05 1. 514E+05 2. 517E+04 2. 532E+04 2. 919E+04 2. 919E+04 2. 919E+04 4.021E+04 4. 673E+04 4. 159E+04 9. 257E+04 2. 135E+05 2. 691E+05 1-001E+06 1.772E+06 U.0008.0005.0006.0005.0005.0000.0006.0000.0008.0000.0000.0006.0080.0039.0003.0003.0000.0002.0002.0000.0001.0000.0000.0000.0001.0184 TOTAL USAGE FACTOR File No.: VY-16Q-310 Revision:
0 Page 21 of 27 F0306-01 RO V Structural Integrity Associates, Inc.Table 9: Fatigue Results for Stainless Steel Piping (60 Years)LOCATION = LOCATION NO. 1 -- SS Piping FATIGUE CURVE = 2 (1 = CARBON/LOW ALLOY, 2 = STAINLESS STEEL)m= 1.7 n= .3 Sm = 17000. psi Ecurve = 2.830E+07 psi Eanalysis
= 2.700E+07 psi Kt =,1.80 MAX 89862.29956.29393.28732.28386.28022.27984.27984.27984.27984.27984.27984.27982.27982.27228.27228.27228.26155.26116.25664.22237.19250.19216.15441.13646.MIN-12.413.413.413.413.413.413.693.1014.1014.1014.1074.1074.1678.1678.1678.1678.1678.1678.1678.1678.1678.1678.1678.1678.RANGE MEM+BEND Ke Salt Napplied Nallowed 89874.29543.28980.28319.27973.27609.27571.27291.26970.26970.26970.26910.26908.26304.25550.25550.25550.24477.24438.23986.20559.17572.17538.13763.11968.48963.29485.30402.29741.29119.29119.18319.18036.17718.17718.17718.17560.28260.28418.27638.27638.27638.25775.24794.25713.22195.19082.18186.15205.12621.1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 67629.27845.27934.27310.26868.26678.22130.21864.21563.21563.21563.21465.25950.25700.24978.24978.24978.23634.23202.23351.20080.17209.16816.13588.11564.1.O00E+00 1.000E+01 1.000E+01 1.OOOE+01 1.OOOE+01 1.OOOE+00 7. 900E+01 1.000E+00 1.200E+02 1. OOOE+00 1. 000E+00 9. 800E+01 2.020E+02 9.800E+01 1.000E+01 1.000E+01 1.OOOE+00 1.000E+01 1.000E+01 1.00E+00 1.OOOE+01 1.000E+01 I .O00E+00 1.OOOE+01 1.200E+02 8.006E+03 1. 042E+06 1.031E+06 1.11OE+06 1.171E+06 1. 198E+06 2. 272E+06 2. 392E+06 2. 539E+06 2. 539E+06 2.539E+06 2. 588E+06 1.311E+06 1.354E+06 1.485E+06 1. 485E+06 1.485E+06 1.779E+06 1.889E+06 1.850E+06 3.442E+06 7.481E+06 8.600E+06 1.000E+20 1.000E+20 U.00001.0000.0000.0000.0000.0000.0000.0000.0000.0000..0000.0000.0002.0001.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0005 I I I I I I I I I I I I I I I U I I I TOTAL USAGE FACTOR File No.: VY-16Q-3 10 Revision:
0 Page 22 of 27 F0306-01 RO Structural Integrity Associates, Inc.-Temp (F) --Pressure (psig)600* 1100 1050~1000 950 500 900 850 800 750 4'00 -700&.0, -- .650 6500 30 .e-6 500 Q..00 5050-I- 400 200 3 050 300-250.0e -200 1150 1 00-50-0 0- --50 0 1000 2000 3000 4000 5000 6000 7000 8000 9000 10000 11000 12000 13000 14000 15000 16000 17000 Time (seconds)Figure 1: Transient 03: Start Up I- Temp (F) --Pressure (psig)I 600 -1280 1240 1200 1160 1120 500 1080 1040 400-960 0 920~880 400 840/ 800 S5 760/57200-680 200/ 6440" 600 E 60." 520 480 200 440 2400 360 320 280 240 100 200 160 120 80 40 0 0 0 1000 2000 3000 4000 5000 6000 7000 8000 9000 10000 11000 12000 13000 14000 15000 16000 17000 Time (seconds)Figure 2: Transient 11: Loss of Feedwater Pumps, Isolation Valves Close.File No.: V.Y-16Q-310 Page 23 of 27 Revision:
0 F0306-O1RO V Structural Integrity Associates, Inc.I-Temp (-F) --Pressure (psig)600 500 E i-*.1100-1050 1000-950.-900-850-800-750-700-650-600-550-500-450 400-350-300-250-200-150-100-50 sa 200 "-100 0 1000 2000 .3000 4000 5000 6000 7000 8000 9000 10000 11000 12000 13000 14000 15000 16000 17000 Time (seconds)I I I I I I I I I I I I I I I Figure 3: Transient 14: Single Relief of Safety Valve Blow Down I-Temp (&deg;F) --Pressure (psig)}600 -500-400 300 200 100 1100 1000 900 800 700-600-500-a 400 300-200.100 0 0 1000 2000 3000 4000 5000 6000 7000 8000 9000 10000 11000 12000 13000 14000 15000 16000 17000 Time (seconds).
Figure 4: Transient 21-23: Shut Down Vessel Flooding K File No.: VY-16Q-310 Revision:
0 Page 24 of 27 I I F0306-OI RO V Structural Integrity Associates, Inc.600-Temp (&deg;F) --Pressure (psig)]400 300 I-200 100 1100 1000 900 800 700 600 500 400 300 200 100 0 500 a,-0 100 200 300 400 Time (seconds)Figure 5: Transient 30: Emergency Shut Down 100% Flow (Safe End)I- Temp (*F) --Pressure (psig) I 600 500-400 300 200 100 1100 1000 900 800 700 600 500 400 300 200 100-0 5000 0.0 1000 2000 3000 4000 Time (seconds)Figure 6: Transient 30: Emergency Shut Down 100% Flow (Blend Radius)File No.: VY-16Q-310 Revision:
0 Page 25 of 27 F0306-OI RO CStructural Integrity Associates, Inc.Figure 7: External Forces and Moments on the Core Spray Nozzle 0)V, 0 200 400 600 800 Time (sec) 92825r0 Figure 8: Typical Green's Functions for Thermal Transient Stress Note: A typical set of two Green's Functions is shown, each for a different set of heat transfer coefficients (representing different flow rate conditions).
File No.: VY-16Q-310 Revision:
0 Page 26 of 27 F0306-O1RO Structural Integrity Associates, Inc.I CA 30O~I *..200".50 ... -t ip-25 sup~-is SliP k 1671 0 200 400, 560 8M 1000 t200 1400 160 1800 2I00 Time sme 10 0 zw2 400 600 600 1000 1200 1400 IM 1M0200 Figure 9: Typical Stress Response Using Green's Functions File No.: VY-16Q-310 Revision:
0 Page 27 of 27 F0306-01 RO V Structural Integrity Associates, Inc.APPENDIX A INPUT AND OUTPUT FILES File No.: VY-16Q-310 Revision:
0 Page Al of A2 F0306-OIRO IStructural Integrity Associates, Inc.Input Files File Name Description TRANSNT 03.INP Text file describing transient 03 for STRESS.EXE TRANSNT I 1.INP Text file describing transient 11 for STRESS.EXE TRANSNT 14.INP Text file describing transient 14 for STRESS.EXE TRANSNT 21 22 23.INP Text file describing transients 21-23 forSTRESS.EXE TRANSNT 30.INP Text file describing transient 30 for STRESS.EXE Output Files File Name Description P-V_03.OUT Output text file of STRESS.EXE and P-V.EXE, Stress peaks and valleys of transient 03 P-VI 1.OUT Output text file of STRESS.EXE and P-V.EXE, Stress peaks and valleys of transient 11 P-V_14.OUT Output text file of STRESS.EXE and P-V.EXE, Stress peaks and valleys of transient 14 P-V_21_22_23.OUT Output text file of STRESS.EXE and P-V.EXE, Stress peaks and valleys of transients 21-23 P-V_30.OUT Output text file of STRESS.EXE and P-V.EXE, Stress peaks and valleys of transient 30 File No.: VY-16Q-310 Revision:
0 Page A2 of A2 F0306-01 RO II JSt cuaI~tg~ ,ooe,- --File No.: VY-16Q-3 11 StrucuralIntegrity Ass oci ate si Inc.NECH-IH14 CALCULATION PACKAGE Project No.: VY-16Q PROJECT NAME: Environmental Fatigue Analysis of VYNPS CONTRACT NO.: 10150394 CLIENT: PLANT: Entergy Nuclear Operations, Inc. Vermont Yankee Nuclear Power Station CALCULATION TITLE: Feedwater Class I Piping Fatigue Analysis Document Affected Project Manager Preparer(s)
&Revision Pages Revision Description Approval Checker(s)
Signature
& Date Signatures
& Date Keith R. Evon 0 1-17, Initial Issue Terry J. Herrmann 7/16/2007 7/16/2007 Al -A38, 7/20/2007 In Computer Files Ryan V. Perry 7/16/2007 Li Pagel of 17 F0306-O,1RO V Structural Integrity Associates, Inc.Table of Contents 1.0 O B JE C T IV E ... ....*. .......................................................................................................................
3 2.0 M ETH O D O LO G Y ..................................
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3 3.0 ASSUMPTIONS/DESIGN INPUT ..................................................
11 4.0 A N A L Y SIS... .......................................................................
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14 5.0 RESU LTS O F A N A LY SIS .......................................................................................................
16 6.0 R E FE R E N C E S ............................................................................................................................
17 APPENDIX A PIPESTRESS INPUT FILE ("FWHPCI.FRE").........
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Al APPENDIX B PIPESTRESS OUTPUT FILE ("FWFHPCI.PRF")
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B I List of Tables Table 1: Thermal Cycle Definitions for Feedwater Line ...............................................................
4 Table 2: Material Properties for Feedwater System Class 1 Piping [2 App. E, 5] .........................
12 Table 3: Feedwater/HPCI Piping Size linformation
[2] ...............................
13 Table 4: Thermal Cycle Load Cases ...................................
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15 I ,I I I I I I I I I List of Figures Figure 1: Feedwater/HPCI Piping from Anchor HD-36 to RPV Nozzles N-4A and N-4B .......10 I I I I I File No.: VY-16Q-311 Revision:
0 Page 2 of 17 F0306-01RO I
* ~Structural Integrity Associates, Inc.1.0 OBJECTIVE The purpose of this calculation is to perform an ASME Section III, NB-3600 fatigue calculation (Including environmental fatigue) of the Vermont Yankee (VY) Class I feedwater piping located I inside the drywell (originally analyzed to B3 1.1 requirements).
This section of piping was originally identified in the Recommendation Report [6] for installing a fatigue monitoring system at VY.* The fatigue calculation performed herein is not a certified ASME Code NB-3600 stress and fatigue analysis.
Rather, it is an evaluation for the purposes of establishing fatigue usage to accommodate fatigue monitoring of the, subject B3 1.1 piping. Although the PIPESTRESS program implements all ASME Code NB-3600 equations, only the fatigue usage results are utilized.
All stress limit checks, although calculated by the program, are ignored since satisfactory stress limit checks were performed as a part of the already existing governing B3 1.1 stress analyses for all piping systems.I 2.0 METHODOLOGY The Class 1 Loop A feedwater piping system line extending from anchor HD-36 to r eactor pressure I .vessel (RPV) nozzles N-4A and N-4B was evaluated.
This includes a portion of the HPCI line to support HIPCI-HD35A
[7], so that the appropriate stiffness affects. of this line on the feedwater piping are included.
This evaluation is also considered valid forthe Loop B lineextending from anchor HD-I39 to RPV nozzles N-4C and N-4D for the following reasons: 1. The Class 1 sections of Loop A and Loop B are mirror images of each other. This evaluation includes piping beyond the Class I boundary check valve so that its influence on the Class 1 piping is taken into account. The final fatigue analysis will only consider points on the Class 1 portion of the piping.* 2. A 14" HPCI line tees into Loop A and a 4" RCIC line tees into Loop B. The HPCI line is more than three times the size of the RCIC line and will therefore have a greater influence on the feedwater piping.3. The transients defined in this calculation are the bounding set for the two loops.The operating conditioris for the Class 1 portion of the feedwater line were defined based on References
[11 and 12]. The resulting piping transient definitions are specified in Table 1. For each thermal cycle, the operating temperatures for Regions I through V define the conditions to be applied to the model.Region boundaries are defined at branches, transitions, or locations where temperature and flow conditions change. These boundary locations are also shown in Figure 1. A listing of the PIPESTRESS input file "FVWPCI.FRE" is given in Appendix A and is also included in the project computer files.File No.: VY-16Q-311 Page 3 of 17 Revision:
0 F0306-01RO Structural Integrity Associates, Inc.I I Table 1: Thermal Cycle Definitions for Feedwater Line Thermal Conditions (2) Pressure Conditions No.Transient Description (1) Piping 0per. Temp. T, Ta-t Time Rate T.- 0o-4 Pinit Pfinal of Cycle Region (3) .(IF) (0 F) (IF) (sec.) (*F/hr) ("89 (%) Ratio (gpm)(4) (psig) (psig) Cycles (1)1 100 70 .100 1800 60 85 0 1 200.0 0.0 1100 Ia 100 70 100 1800 60 85 0 1 150.0 0.0 1100 llb 100 70 100 1800 60 85 0 1 150.0 0.0 " 1100 Design Hydrotest (teak 11 100 70 100 1800 60 85 0 1 150.0 0.0 50 .Mi 100 .70 100 1800 60 85 0 1 200.0. 0.0 1100 120 Test)(N)IV 100 70 100 1800 60 85. 0 1/2 100.0 0.0 1100.Iva 100 70 100 1800 60. 85' 0 1/2 100.0 0.0 1100 IVb 100, 70 100 1800 60 .85 0 1/2 100.0 0.0 1100 V 100 70 100 1800 60 85 0 1/2 100.0 0.0 1100 1 100 100 100 0 0 100 0 1 200.0 1100.0 50 la 100 100 100 0 0 100 0 1 150.0 1100.0 50 lIa 100 100 100 0 0 100 0 1 150.0 1100.0 50 Design Hydrotest (eak II 100 100 100 0 0 100 0 1 150.0 50.0 50 2m IGe 100 100 0 0 100 0 1 200.0 1100.0 50 120 Test)(-) IV .100 100 100 0 0 100 0 1/2 100.0 1100.0 50 IVa 100 100 100 0 '0 100 0 1/2 100,0 1100.0 50 IVb 100 100 100 0 0 100 0 1/2 100.0 1100.0 50 V 100 100 100 0 0 100- 0 1/2 100.0 1100.0 50 1 150 100 150 16164 H1A. 125 0 1 200.0 50.0 1010 Ila 150 100 150 16164 11.1 .125 0 1 150.0 50.0 1010 1lo 125 100 125 16164 5.6 113 0 1 150.0 50.0 1010 I1 100 .100 100 16164 0.0 100 0 1 150.0 50.0 50 3 Startup (1) I 150 100 150 16164 11.1 125 0 1 200.0 50.0 1010 300 IV 150 100 150 16164 11.1 125 0 1/2 100.0 50.0 1010 Iva 283 100 283 16164 40.8 192 0 1/2 100.0 50.0 1010 IVb 416 100 416 16164 70.4 258 0 1/2 100.0 50.0 1010 V 549 100 549 16164 100 325 0 1/2 100.0 50.0 1010 1 100 150 100 0 STEP 125 15 1 1377.0 1010.0 1010 Turbine Roll & Increase to ha 100 ]SO 100 0 STEP 125 0 1 150.0 1010.0 1010 Rated Power (-) Rfb 100 125 100 0 STEP 113 0 1 150.0 1010.0 1010 (Includes 10 SCRAM, Loss I. 100 100 100 0 STEP 100 0 1 150.0 50.0 50 4 of Feed-ater Pumps and In 100 ISO 100 0 STEP 125 15 I 1377.0 1010.0 1010 610 IV 100 150 100 0 STEP 125. 15 1/2 .688.5 1010.0 1010 300HotStandby
-' Iva 100 283 100 0 STEP 192 15 1/2 688.5 1010.0 1010 FeedsuaterCycling)
.100. 416 100 0 STEP 258 15 1/2 688.5,. 1010.0 1010 V 100 1 549 100 0 STEP 325 15 1/2 688.5 1010.0 1010, I 260 100 260 0 .S~TEP 100 IS 1 1377.0 1010.0 1010 Turbine Roll & Increase to H 260 100 260 0 STEP 180 0 1 150.0 1010.0 1010 Rated Power2(+)
Rb .180 100 180 0 STEP 140 0 1 150.0 1010.0 1010 ofeesalrcms I1820 100 260 0 STEP 180 01 1377.0 1010.0 1010 9 (Includes 10 SCRAS4. Loss 11 100 100 100 0 STEP 100 0 1 150.0 50.0 50 5 of Feedwater Pumps, I 111 260 100 260 0 STEP ]so 15 1 1377.0 1010.0 1010 599 Reactor Overpressure, 228 IV 260 100 260 0 STEP 180 15 1/2 688.5 1010.0 1010 Other SCRAMS and 60 WVa 260 100 260 0 STEP 180 15 1/2 688.5 1010.0 1010 Turbine Gnerator Trip) IVb 260 100 260 0 STEP 180 15 1/2 6885 1010.0 1010 V 260 100 260 0 STEP 180. 15 1/2 688.5 1010.0 1010 Turbine Roll & Increase to 392 260 392 1800 264 326 100 1 9180.0 1010.0 1010 te RolI&#xfd;o 3 392 260 392 1800 264 326 0 1 150.0 1010.0 1010 IntedePswSerA3(+)
b1 246 180 246 1800 132 213 0 1 150.0 1010.0 1010 (6ncludes 10 SCRAM, tess H 100 100 100 1800 0 100 0 1 .150.0 50.0 50 6 fpeesdt-ater Pumps, 1 1In 392 260 392 1800 264 326 100 1 9180.0 1010.0 1010 599 Reactor Overpressure, 228 " V. 392 260 392 1800 264 326 100 1/2 4590.0 1010.0 1010 I Other SCRAMS and 60 IVa 392 260 392 1800 264 326 100 1/2 4590.0 1010.0 1010 Turbine Gunerator Trip) fVI, 392 260 392 1800 264 326 100 1/2 4590.0 1010.0 1010 V 392 260 392 1800 264 326 100 1/2 4590.0 1010.0 1010 1 310 392 310 900 -328 351 75 1 6885.0 1010.0 1010 11. 310 392 310 900 -328 351 0 1 150.0 1010.0 1010 Rlb 205 246 205 900 -164 226 0 1 150.0 1010.0 1010 Daily Reduction to 75% 10 100. 100 100 .900 0 100 0 1 150.0 50.0 50 7 PoIern1 310 392 310 900 -328 351 75 1 6885.0 1010.0 1010 10000 IV 310 392 3)0 900 -328 351 75 1/2 3442.5 1010.0 1010 NVa 310 392 310 900 -328 351 75 1/2 3442.5 1010.0 1010 IVb 310 392 310 900 -328 .351 75 1/2 3442.5 1010.0 1010 V 310 392 310 900 -328 351 75 1/2 3442.5 1010.0 1010 V 392 310 392 900 328 351 75 1 68853 0 1010.0 1010 Ila 392 310 392 900 328 351 0 I 150.0 1010.0 1010 Rlb 246 205 246 900 164 226 0. 1 150.0 1010.0 1010 Daily Reduction to 75% I1 100 100 100 900 0 100 0 1 150.0 50.0 .50 8 Po(+) 1 392 310 392 900 328 351 75 1 6885.0 1010.0 1010 10000 IV 392 310 392 900 328 351 75 1/2 3442.5 1010.0 1010 Wva 392 310 392 900 328 351 75 1/2 3442.5 1010.0 1010 lVb 392 310 392 900 328 351 75 1/2 3442.5 1010.0 1010 V 392 310 392 900 328 351 75 1/2 3442.5. 1010.0 1010 1 280 392 280 1800 -224 336 50 1 4590.0 1610.0 1010 Ila 280 392 280 1800 -224 336 0 1 150.0 1010.0 1010 11o 190 246 190 1800 -112 218 0 1 150.0 1010.0 1010 Weekly Reduction tno 500/ 11 100 100 100 1800 0 100 0 1 150.0 50.0 50 P9scer 111 280 392 .280 1800 -224 336 50 1 45900 1010.0 1010 2000 IV 280 392 280 1800 -224 336 50 1/2 2295.0 1010.0 1010 Wva 280 392 280 1800 -224 336 50 1/2 2295.0 1010.0 1010_ _ 280__ __9_ 2_ 0 1_00 -22 336 _ 0 112 225. 1010.0I lVb 280 392 280 1800 -224 336 1 50 1/2 2295.0 1010.0 1010 V " 280 392 280 1800 -224 336 50 1/2 2295.0 1010.0 1010 For notes, see last page of table.File No.: VY-16Q-311 Revision:
0 Page 4 of 17 f F0306-O1R0 I
*. jiStructural Integrity Associates, Inc.I I I I I I I Table 1: Thermal Cycle Definitions for Feedwater Line (continued)
Thermal Conditions (2) Pressure Conditions No.Transient Description (1) Pipin Ope. Temp. T TL. Time Rate T.,. Flo. Pint Pfinal of Cycle Region (3) (&deg;F) ('F) (*F) (see-) ('F/br) (F) (%) Ratio (gpm)(4). (psi-) (psig) Cycles (I)1 392 280 392 1800 224 336 50 1 4590.0 1010.0 1010-la 392 280 392 1800 224 336 0 1 150.0 1010.0 1010 fIb 246 190 246 1800 112 218 0 I 150.0 1010.0 1010 28 l "t0 l0 392 1800 22 336 50 ] 4590.0 100.0 500 t0 Weekly Reduction to 50% 11 100 100 100 1800 0 100 0 1 150.0 50.0 so0 2000 Power(+) IV 392 280 392 1800 224 336 50 1/2 2295.0 1010.0 1010 IVa 392 280 392 1800 224 336 50 1/2 2295.0 1010.0 1010 lVb 392 280 392 1800 224 336 50 1/2 2295.0 1010.0 1010 V 392 280 392 1800 224 336 50 1/2 2295.0 1010.0 1010 1 1 265 392 265 1800 -254 329 50 I 4590.0 1010.0 1010 Loss of Feedsater Heater, 1M, 265 392 265 .1800 -254 329 0 1 150.0 1010.0 1010 Turbine Trip I (-) 9ib 182.5 246 182.5 1800 -127 214 0 1 150.0 10100 1010 (Includes 10 Loss of .] JO0 100 1O0 )800 0 100 0 1 150.0 50.0 50 11 Feedsster Hester Turbine 10 265 392 265 1800 -254 329 .50 1 4590.0 1010.0 1010 310 T IV 265 392 265 1800 .254 329 50 1/2 2295.0 1010.0 1010 Trip. ad 300 Redctio Va 265 392 265 1800 .254 329 50 1/2 2295.0 1010.0 1010 0J Power) IVb 265 392 265 1800 -254 329 50 112 2295.0 1010.0 1010 V 265 .392 265 1800 -254. 329 50 1/2 2295.0 1010.0 1010 1 90 265 90 360 -1750 .178 15 1 1377.0 1010.0 1010 lHa 90 265 90 360 -1750 178 0 1 150.0 1010.0 1010 Ill 95 182.5 95 360 -875 139 0 I 150.0 1010.0 1010.oss of Feedwater Heater, 0I 10 100 100 360 0. 100 0 1 150.0 50. 50 12 111 90 265 90 360 -1750 .178 15 1 1377.0 1010.0 1010 10 Turbine Trip 2(-) IV 90 265 90 360 -1750 178 15 1/2 688.5 1010.0 1010 IVa 90 265 90 360 -1750 178 15 1/2 688.5 1010.0 1010 1Vb 90 265 90 360 -1750 178 15 1/2 688.5 1010.0 1010 V 90 265 90 360 -1750 178 15 1/2 688.5 1010.0 1010 1 1 265 90 265 900 700 178 15 1- 1377.0 1010.0 1010 Ila 265 90 265 900 700 178 0 I 150.0 1010.0 1010 Ill 182.5 95 182.5 900 350 139 0 I 150.0 I010.0 1010 L II 100 100 1QO 900 0 100 0 1 150.0 50.0 50 13 LoTurofFedw treHipe3 111 265 90 265 900 700 178 15 1 1377.0 1010.0 1010 10 TurbineTrip3(+}
IV 265 90 265 900 700 178 15 1/2 68U.5 1010.0 1010 Iva 265 90 265 900 700 178 15 1/2 688.5 1010.0 1010 IVb 265 90 265 900 700 178 15 1/2 688.5 1010.0 1010 V 265 90 265 900 .700 178 15 1/2 688.5 1010.0 1010 I. 392 265 392 1800 254 329 50 1 4590.0 1010.0 1010 IIa 392 265 392 1800 254 329 0 1 150.0 1010.0 1010 fib 246 182.5 246 .1800 127 214 0 1 150.0 1010.0 1010 Loss ofFeed-ater Heater, 0 100 100 100 1800 0 100 0 1 150.0 50.0 50 14 Turbine Trip 4 111 392 265 392 1800 254 329 50 1 4590.0 1010.0 1010 10 IV 392 265 392 1800 254 329 50 1/2 2295.0 1010.0 1010 Iva 392 265 392 1800 254 329 50 1/2 2295.0 1010.0 1010 IVb 392 265 392 1800 254 329 50 1/2 2295.0 1010.0 1010 V 392 265 392 1800 254 329 50 1 1/2 2295,0 10100 1010 1 1 265 392 265 90 -5080 329 100 1 9180.0 1010.0 1010 fla 265 392 .265 90 -5080 329 0 1 150.0 1010.0 1010 fib 182.5 246 182.5 90 -2540 214 0 1 150.0 1010.0 1010 Loss of Feedster Heater, 1 100 100 rOO 90 0 100 0 1 150.0 50.0 50 I5 FW ISeer Bypass 111 265 392 265 90 -5080 329 100 1 9180.0 1010.0 1010 70 W yIV 265 392 265 90 -5080 329 100 1/2 4590.0 1010.0 1010 IVa 265 392 265 90 -5080 329 100 1/2 4590.0 1010.0 1010 MVb 265 392 265 90 -5080 329 100 1/2 4590.0 1010.0 1010 265 392 265 90 -5080 329 100 1/2 "4590.0 1010.0 1010 1 I 392 265 392 180 2540 329 100 1 9180.0 1010.0 l0lo Ila 392 265 392 180 2540 329 0 1 150.0 1010.0 1010 fib 246 182.5 246 180 1270 214 0 1 150.0 1010.0 1010 Loss oflFeedwter Heater, 11 100 100 100 180 0 100 0 1 130.0 50.0 so 16 1Heter + 11 392 265 392 180 2540 329 100 1 9180.0 1010.0 1010 70 IV 392 265 392 180 2540 329 100 1/2 4590.0 1010.0 1010 IVa 392 265 392 180 2540 329 100 1/2 4590.0 1010.0 1010 Va 392 265 392 ]80 2540 329 100 1/2 .4590.0 1010.0 1010!Vb 392 265 392 180 2540 329 100 1/2 4590.0 1010.0 1010*V 392 265 1 392 180 1 2540 329 1 001 112 4590.0 1010.0 1010 1 1 275 392 275 60 -7020 334 110 1 10098.0 1010.0 1010 SCRAM, T.G,.Trip, Reactor Ila 275 392 275 60 -7020 334 0 1 150.0 1010.0 1010 Overpressure.
and All Other lIb 187.5 246 187.5 60 -3510 217 0 1 150.0 1010.0 1010 Scrams I (-) 0 100 JOG 100 60 0 100 0 1 150.0 50.0 50 17 (Includes I Reactor 10 275 392 275 60 -7020 334 110 1 10098.0 1010.0 1010 289 Overpressure, 228 Other IV 275 392 275 60 -7020 334 110 112
* 5049.0 1010.0 1010 SCRAMS and 60 Turbine WVa 275 392 275 60 -7020 334 I10 1/2 5049.0 1010.0 1010 Generator Trip) l/b 275 392 275 60 -7020 334 110 1/2 5049.0 1010.0 1010 V 275 .392 275 60 -7020 334 110 1/2 5049.0 1010.O 1010 S 100 " 275 100 900 -700 188
* 3 1 275.4 10100 .1010 SCRAM. T.G. Trip. Reaco .100 275 100 900 -700 188 0 I 150.0 1010.0 1010 Overpressure, a-d All Otb 11b 100 187.5 100 900 -350 14,4 0 I 150.0 1010.0 1010 Scrams 2 (- 1 100 100 100 900 0 100 0 I 150.0 50.0 50 18 (Includes I Reactor 01 100 275 100 900 -700 188 3 1 275 4 1010.0 1010 289 Overpressure, 228 Other IV 100 275 100 900 -700 188 3 1/2 137.7 1010.0 1010 SCRAMS and 60 Turbine /Va 100 275 100 900 -700 188 3 1/2 137,7 1010.0 1010 Generator Trip) "Io 100 275 100 900 -700 88 3 112 137.7 1010.0 1010 V )OO 275 100 900 -700 188 3 /2 1377 1010.0 1010 I U For notes, see last page of table.File No.: VY-16Q-311 I Revision:
0 Page 5 of 17 F0306-01 RO VStructural Integrity Associates, Inc.Table 1: Thermal Cycle Definitions for Feedwater Line (continued)
' Thermal Conditions (2) iPressure Conditions No.Transient Description(1)
Piping Oper.Temp.
T, T&#xfd;, Time Rate T_, Fs Plait Pfinal.. of Cycle Region (3) y (F) (,F) (0 F) .(se) (rF/hr) (IF) ( Ra., (gpm)(4) (psig) (psig) Cyces ()1 265 265 265 0 STEP 265 0 1 200.0 1010.0 1010 1a 265 265 265 0 STEP .265 0 1 150.0 1010.0 1010 0b 182.5 182.5 [82.5 0 SuEP 183 0 1 150.0 1010.0 1010* 100 100 100 0 STEP 100 0 1 150.0 50.0 50 19 Hot Standby1(+)
.aI 265 265 265 0 STEP 265 0 1 2000 1010.0 1010 300 IV 265 265 265 .0 STEP 265 0 1/21 100.0 1010.0 1010 Iva 323 265 323 0 STEP 294 0 1/2 100.0 1010.0 1010 1Vb 382 265 382 0 STEP 324 0 1/2 100.0 1010.0 1010 V 440 265 440 0 STEP 353 0 1/2 100.0 1010.0 1010 I 265 265 265 0 0 265 0 1 200.0 1010.0 1010 Ila 265 265 265 0 0 265 0 I 150.0 1010.0 1010 Ilb 182.5 182.5 182.5 0 0 183 0 1 150.0 -1010.0 1010 U 100 100 100 0 0 100 0 1 150.0 50.0 50 20 Hot Standby 2 (+) Mi I 265 265 265 0 0 265 0 1 200.0 1010.0 1010 300 IV 265 265 265 0 0 .265 0 1/2 100.0 .10100 1010 WVa 360 323 360 3924 34 342 0 1/2 100.0 1010.0 1010 IVb 454 302 454 3924 66 418 0 1/2 100.0 1010.0 1010 V .549 440 549 3924 1 100 495 0 1/2 100.0 1010.0 1010 1 150 265 150 4140 -100 208 0 1 200,0 1010.0 1010 Ha ]so 265 150 4140 -100 208 0 1 150.0 1010.0 1010/O 125 182.5 125 4140 154 .1 150.0 1010.0 1010 1 100 100 100 0 0 100 0 1 150.0 .50.0 50 21 Hot Standby 3(-) 11 150 265 .150 4140 -100. 208 0 1 200.0 1010.0 1010 300 IV 150 265 150 4140 -100 208 0 1/2 100.0 .1010.0 1010 IVa 283 360 203 4140 .-67 322 0 1/2 100.0 1010.0 1010 IVb 416. 454 416 4140 -33 435 0 1/2- 100.0 1010.0 1010 V 549 549 549 0 0 549 0 .12 100.0 1010.0 1010 1 150 150 150 0 0 150 0 1 200.0 1010.0 170"fa 150 150 150 0 , 0 ISO 0 I 150.0 1010.0 170 Ob. 125 125 125 0 0 .125 0 1 150.0 1010.0 170 O 100 lo30 l00 0 0 100 0 1 150.0 50.0. 50 22 Shutdown I (M) 0 150 .150 150 0 0 150 0 1 200.0 1010.0 170 300 IV ISO 150 150 0 .0 [so 0 1/2 100.0 1010.0 170 IVa 225 283 225 6264 -33 254 0 1/2 100.0 1010.0 170 ,Vb 300 416 300 6264 .-67 358- 0 1/2 100.0 1010.0 170 V 375 549 375 6264 -100 462 0 1/2 100.0 1010.0 170 S ISO ISO ISO 0 0 150 0 1 .200.0 170.0 88"la I50 ISO 150 0 0 150 0 I 150.0 170.0 88 111 125 125 125 0 0 125 0 1 150.0 170.0 88 II 100 100 100 0. 0 100 0 1 150.0 50.0 50 23 Shutdown2(-)
201 150 150 150 0 0 150 0 1 200.0 170.0 88 300 IV 150 150 .150 0 0 150 0 112 100.0 170.0 88 IVa 210 225 .210 600 -90 218 0 1/2 100.0 170.0 08 IVb 270 300 270 600 -100 285 0 1/2 100.0 170.0 88 V 330 375 330 600 -270 353 0 1/2 100.0 170.0 08 1 100 .150* 100 8280 -22 125 0 1 200.0 88.0 50 Ila 100 150 100 8280 * -22 125 0 I 150.0 88.0 50 Oh 100 125 100 8280 .-11 113 0 1 150.0 88.0 50 1* 100 100 100 8200 0 100 0 1 150.0 50.0 50 24 Shutdown 3 (-) 13 100 150 100 8280 -22 125 0 I 200.0 80.0 50 300 IV l O0 150 100 8280 -22 125 0 1/2 100.0 80.0 50 Iva 100 210 100 8280 -40 155 0 1/2 100.0 88.0 50 1Vb 100 270 100 8280 -74 185 0 1/2 100.0 08.0 50 V 100 330 100 8280 -100 215 0 1/2 100.0 88.0 50 1 392 392 392 12 0 392 0 1 2000 1010.0 1190 Ila 392 392 392 12 0 392 0 1 150.0 1010.0 1190 OIh 246 246 246 12 0 246 0 1 150.0 1010.0 1190 SCRAM, Loss ofFeedwate 01 100 100. 100 12 0 100 0 1 150.0 50.0 50 25 M 392 392 392 12 0 392 0 1 200.0 1010.0 1190 10 Pumps1(+)
IV 392 392 392 12 0 392 0 1/2 100.0 1010.0 1190 Iva 450 392 450 12 17400 421 0 1/2 100.0 1010.0 1190 IVb 507 392 507 .12 34500 450 0 1/2 100.0 1010.0 1190 V 565 392 " 565 12 51900 1 479 0 1/2 100.0 1010.0 1190 I I I 3 I I I I U I I I I 26 SCRAM, Loss of Feedwater Pumps 2 (-)(First HPCI)i IDa l13 IV Iva IVb V so 50 50 50 50.50 50 50 50 392 392 246 100 392 392 450 507 50 50 50 50 50 50 50 50 0.0 0 0 0 0 0 0 0 STEP STEP STEP STEP STEP STEP STEP STEP STEP 221 221 148 75 221 221 250 279 308 40 40 40 40 40 40 40.40 40.1 12 1/2 1/2 1/2 3672.0 3672.0 3672.0 3672.0 3672.0 1836.0 1836.0 1836.0 1836.0 1190.0 1190.0 1190.0 50.0 1190.0 1190.0 1190.0 1190.0 1190.0 1135 1135 1135 1135 1135 1135 1135 1135 1135 10 565 1 50 I I I T 150 50 )so 1300 261 ) 100 1 200.0 1135.0 1135 Ia 150 50 150 1380 261 100 0 1 150.0 1135.0 1135 111, 125 50 125 1380 196 88 0 1 150.0 1135.0 1135 27 SCRAM, Loss of Feedwater 0f 100 50 t00 1380 130 75 0 1 150.0 11350 50 Pumps 3 (4) M0 150 50 150 1380 261 100 0 1 200.0 1135.0 1135 1l Iv 150 50 247 1380 261 149 0 1/2 100.0 1135.0 1135 IVa 247 50 247 1380 514 149 0 1/2 100.0 1135.0 1135"Vb 343 50 343 1380 764 197 0 1/2 100.0 1135.0 1135 V 440 50 440 1 1380 1017 245 10 1/2 100.0 11350 1 1135 1 For notes,. see last page of table.File No.: VY-16Q-3 11 Revision:
0 Page 6 of 17 I F0306-01RO I
S3Structural IntegrityAssociates, Inc.Table 1: Thermal Cycle Definitions for Feedwater Line (continued)
Thermal Conditions (2) .. Pressure Conditions No.Transient Description (1) Piping Oper. Temp* T-* Tr Time Rate T .low P.nit Pfsal of Cyde Region (3) ('F) (IF) (*F) (sei.) (aF/hr) (*F) (%) Ratio (gpm)(4) (psig) (psig) Cydes (1)150 150 150 0 STEP 150 0. I 200.0 1135.0 1135 1a .50 150 150 0 STEP 150 0 1 150.0 1135.0 1135 Ilb 125 125 125 0 STEP 125 0 1 150.0 1135.0 1135 28 SCRAM Loss of Feedsata II 100 .100 100 0 STEP 100 0 1 150.0 50.0 50 2 Mi 150 150 150 0 STEP 150 0 1 200.0 1135.0 1135 30 Pumps4(+)
V 150 150 150 0 STEP 150 0 1/2 100.0 1135.0 1135 Iva 288 247 288 0 STEP 268 0 1/2 100.0 1135.0 1135 lVb 427 343 427 0 STEP 385 0 1/2 100.0 1135.0 1135 V 565 440 565 0 STEP 503 0 1/2 100.0 1 135.0 1135 1 50 150 50 0 STEP 100 30 1 2754.0 1135.0 885 Ua 50 150 50 .0 .STEP 100 30 1 2754.0 1135.0 885 1lb 50 125 50 0 STEP 88 30 1 2754.0 1135.0 885 SCRAM, Loss of Feed-atet 1U 50 100 50 0 STEP 75 30 1 2754.0 1135.0 885 29 Pumps 5 (-) 11I 50 150 50 0 STEP 100 30 1 2754.0 1135.0 885 10 (Second HPCI) N o 50 150 50 0 STEP 100 30 1/2 1377.0 1135.0 885 IVN 50 288 50 0 STEP 169 30 1/2 1377.0 1135.0 885 IVb 50 427 50 0 STEP 239. 30 1/2 1377.0. 1135.0 885 V 50 565 50 0 .STEP 308 30 1/2 1377.0 1135.0 885 I 150 50 150 3060 118 .100 0 1 200.0 885.0 1060 Ha 150 50 150 3060 1f8 100 0 1 150.0 885.0 1060 11, 125 50 125 3060 80 88 0 1 150.0 885.0 1060 SCRA Loss of Feed0at 1 00 50 100 3060 59 75 0 1 150.0 885.0 50 30 Pup 6 150 50 150 3060 118 100 0 1 200.0 885.0 1060 l0 Pumps 6 (+) .V 150 50 ISO 3060 118 100 0 1/2 109.0 885.0 1060 Iva 247 .50 247 3060 232 149 0 1/2 100.0 885.0 1060[Vb 343 50 343 3060 345 197 0 1/2 100.0 885.0 1060 V 440 50 440 3060. 459 245 0 1/2 100.0 .885.0 1060 1 150 150 150 0 STEP 150 0 t 200.0 1060.0 1135 IHa 150 ISO 150 0 STEP 150 0 1 150.0 1060.0 1135 lib 125 125 125 0 STEP 125 0 1 150.0 1060.0 1135 SCRAM, Loss of Feedstbe&#xfd;r 1 100 100 100 0 STEP 100 0 1 150.0 50.0 50 Pumps 7 (+) 1 150 150 I50 0 STEP 150 0 1 200.0 1069.0 1135 N 150 150 150 I 0 STEP 150 0 1/2 100.0 1060.0 1135 OVa 283 247 .283 0 STEP 265 0 112 100.0 1060.0 1135 17b 416 343 416 0 STEP 380 0 1/2 100.0 1060.0 1135 V 549 440 549 0 STEP 495 0 1/2 100.0 1060.0 1135 1 50 3S0 50 0 STEP 100 17 I 1 560.6 1135.0 675 Ha 50 150 50 0 STEP 100 17I .1560.6 1135.0 675 lib 50 125 50 0 STEP 88 17 1 1560.6 1135.0 675 SCRAM, Loss of Feedwater 11 50 100 50 0 STEP 75 17 1 1560W6 50.0 675 32 Pumps8(-)+
M 50 IS0 50 0 STEP 100 17 1 1560.6 1135.0 675 10 (Third HIPC) IV 50 ISO 50 0 STEP 100 17 1/2 780.3 1135.0 675 Iva 50 283 50 0 STEP 167 17 1/2 700.3 1135.0 675/Vb 50 4Z6 50 .0 STEP 233 17 112 780.3 1135.0 675 V 50 549 " 50 0 STEP 300 17 1/2 780.3 1135.0 675" 150 50 150 300 1200 100 0 1 200.0 675.0 675 Ila 150 50 150 300 1200 100 0 1 150.0 675.0 675 111b 125 50 125 300 900 88 0 1 150.0 675.0 675 SCRAM, Loss of Ffedstez1 13 100 50 100 300 600 75 0 1 150.0 675.0 50 33 3pM 150 50 150 300 1200 100 0 1 , 200.0 6750. 675 10 Pumps 9 (+) N 150 50 150 300 1200 100 0 1/2 100.0 675.0 675 Iva 200 50 200 300 1800 125 0 1/2 100.0 675.0 675 IVb 250 50 250 300 2400. 150 0 112 100.0
* 675.0. 675 V 300 50 300 300 3000 175 0 1/2 100.0 675.0 675 I 150 150 150 8964 0 150 0 1 200.0 240.0 1010 Ha 150 1 350 150 8964 0 150 0 1 150.0 240.0 1010 11b 125 125 125 8964 0 125 0 1 150.0 240.0 1010 , 11 100 300 100 8964 0 100 0 1 150.0 50.0 50 34 SCRAmLossofFeclwater 1 1 150 150 150 8964 0 150 0 1 200.0 240.0 1010 10 Pumps 10 (+)V 150 J50 150 8964 0 150 0 112 100.0 240.0 1010 NVa 283 200 283 8964 33 242 0 1/2 100.0 240.0 1010/Vb 416 250 416 8964 67 333 0 1/2 100.0 240.0 1010 V 549 300 549 8964 100 425 0 1/2 100.0 240.0 1010 I 275 392 275 60 -7020 334 110 1 10098.0 1010.0 885 ffa 275 392 275 60 -7020 334 0 1 150.0 3010.0 885 fib 187.5 246 137.5 60 -3510 217 0 1 150.0 1010.0 885 35 SCRAM, SRV Blosdov 1 100 100 100 60 0 100 0 1 150.0 50.0 50 3w 0B 275 392 275 60 -7020 334 110 1 10098.0 1010.0 885 1 NV 275 392 275 60 -7020 334 110 1/2 5049.0 1010.0 885 IVa * .275 392 275 60 -7020 334 110 1/2 5049.0 1010.0 885 Alb 275 392 275 60 -7020 334 110 1/2 5049.0 1010.0 885 V 275 392 275 60 -7020 .334" 110 1/2 5049.0 1010.0 885 1 100 275 100 900 -700 188 3 1 275.4 885.0 50 Ha 100 275 300 900 -700 188 0 1 150.0 885.0 50 3lb 100 397.5 100 900 -350 144 0 1 150.0 885.0 50 SCRAK, SRV Blowdosn 2 II 100 100 100 900 0 100 0 1 150.0 50.0 50 36 L c00 275 100 900 -700 188 .3 [ 275.4 805.0 50 1 V 300 275 100 900 -700 188 3 1/2 137.7 885.0 50 IVa 100 275 100 900 -700 188 3 1/2 137.7 885.0 50 17b 300 275 300 900 -700 138 *3 1/2 137.7 885.0 50 V 100 275 100 900 -700 .188 3 1/2 137.7 885.0 50 U For notes, see last page of table.FiRe No.: VY-16Q-311 m Revision:
0 Page 7 of 17 F0306-O1 RO Structural Integrity Associates, Inc.I Table 1: Thermal Cycle Definitions for Feedwater Line (continued~
._Thermal Conditions (2) Pressure Conditions No.Transient Description (1) Piping Ope0 .Temp. T&#xfd; T&#xfd;,. Time Rate T,, Fo0 Pinit Pfinal of Cycle Region (3) (0 F) (*F) (*F) (sec.). (5 F/hr) (5 F) (%) Ratio (gpmXl4) (psig) (psig) Cycles (1)1 100 100 100 0 0 "100 0 1 200.0 50,0 1563 M 100 1e00 10 P 0 100 0 1 150.0 50.0 1563 lib 100 100 100 0 0 100 0 I 150.0 ,50.0 1563 H 100 100 100 0 0 100 0 1 150.0 50.0 50 37 Hydrostatic Test (+) OIG 100 .100 100 0 0 100 0 1 200.0 50.0 1563 1 IV 1.00 100 100 0 0 100 0 1/2 100.0 50.0 1563 Iva 100 LO 100 0 0.0 100 0 1/2 100.0 50.0 1563 IVb 100 100 100 0 0.0 100 0 1/2 100.0 50.0 1563 V 100 100 100 0 0 100 0 1/2 1 100.0 50.0 1563 I 100 I00 100 0 0 100 0 1 200.0 1563.0 50 Ila 100 100 100 0 0 100 0 1 150.0 1563.0 50 Jib 100 10o 100. 0 .0 -100 0 1 150.0 1563.0 50 U 100 100 100 0 0 100 0 1 150.0 50.0 50 38 .Hydrostatic Test(-) m 100 100 100 0 0 100 0 1 200.0 1563.0 50 1 IV 100 100 100 0 0 100 0 1/2 100.0 1563.0 50 Wa 100 100 100 0 0.0 100 0 1/2 100.0 1563.0 .50 lVb 100 .100 100 0 0.0 100 0 1/2 100.0 1.563.0 50 V 100 100 100 0 0 100 0 1/2 100.0 1563.0 50 1 392 392 392 60 0 392 110 1 10098.0 1010.0 1375 SCRAM, T.G. Trip, Reacto Ila 392 392 392 60 0 392 0 I 150.0 1010.0 1375 Overpressure, and All Other Ib 246 246 246 60 0 246 0 1 150.0 1010.0 1375 Scrams l (-) R 10O 100 I0O 60 0 100 0 I 150.0 50.0 -50 39 (Includes I Reactor M 392 392 392 60 0 392 .1iO 1 10098.0 1010.0 1375 289 Overpressure, 228 Other IV 392 " 392 392 60 0 392 110 1/2 5049.0 1010.0 1375 SCRAMS and 60 Turbine IVa 392 392 392 60 0 392 110 1/2 5049.0 1010.0 1375 Generator Trip) IVb 392 392 392 60 0 392 110 1/2 5049.0 1010.0 1375 V 392 392 392 60 0 392 110 1/2 5049.0 1010.0 1375 1 392 392 392 900 0 392 3 I 275.4 1375.0 940 SCRAM, T.G. Trip, Reacto Ila 392 392 .392 900 0 392 0 1 150.0 1375.0 940 Overpressure, and All Other 11b 246
* 246 246 900 0 246 0 1 150.0 1375.0 940 Scracs 2 (-)
* 10 100. 100 100 900 0 100 0 1 150.0 50.0 50 40 (Includes I Reactor 13 392 392 392 900 0 392 3 1 275.4 1375.0 940 289 Overpressure, 228 Other IV 392 392 392 900 0 392 3 1/2 137,7 1375.0 940 SCRAMS and 60 Turbine IVa 392 392 392 900 0 392 3 1/2 137.7 1375.0 .940 GeneratorTrip)
IVb 392 392 392 900 0 392 .3 1/2 137,7 1375.0 940 V 392 392 392 900 0 392 3 1/2 .137.7 1375.0 940 S 392 392 392 900 0 392 3 I 275.4 940.0 1010 SCRAM, T.G. Trip, Reacto a 392 392 392 900 0 392 0 1 150.0 940.0 1010.Overpressure, and All Other UIb 246 246 246 900 0 246 0 1 150.0 940.0 1010 Scrams 3 (-) 11 100 100 .100 900 0 100 0 1 150.0 50.0 50 41 .(Includes I Reactor 11M 392 392 392 900 .0 392 3 1 275.4 940.0 1010 289 Overpressure, 228 Other IV 392
* 392 392 900 0 392 3 1/2 137.7 940.0 1010 SCRAMS and 60 Turbine Iva 392 392 392 900 0 392 3 1/2 137.7 940.0 1010 Generator Trip) IVb 392 392, 392 900 0 392 3 1/2 137.7 940.0 1010.V 392 392 392 900 0 392 .3 1/2 ,137.7 940.0 1010 125 100 125 60 1500 113 0 I 200.0 *1010.0 1010 Ua 125 100 125 60 .1500 113 0" 1 150.0 1010.0. 1010 lU
* 112.5 100 112.5 60 *750 106 0 1 150.0 "1010.0 1010 Hot Standby, Feedwat1r 100 100 100 60 0 100 0 1 150.0 50.0 50 42 CIyi 125 1 .100 125 60 1500 113 0 1 200.0 1010.0 1010 300 Cycling 1(+) IV 125 100 125 60. 1500 113 0 1/2 100.0 1010.0 1010 1Va ISO 100 180 60 4800 140 10 1/2 100.0 1010.0 1010 1/Vb 235 100 235 60 8100 168 0 1/2 100.0 1010.0 1010-V 290 100 290 60 11400 195 .0 1/2 100.0 1010.0 1010 I 150 125 150 210 429 138 0 1 200.0 1010.0 1010 lUa 150 125 150 210 429 138 0 1 150.0 1010.0 1010 Slb 125 112.5 125 210 214 119 0 1 150.0 1010.0 1010 1-tot S b eed-tcr 11 100 100 100 210 0 100 0 1 150.0 50.0 50 Cycli, e2 ae HI 150 125 150 210 429 138 0 1 200.0 1010.0 1010 300 1IV 150 125 150 210 429 138 0 1/2 100.0 1010.0 1010 Wva 283 180 283 210 1766 232 10 1/2 100.0 1010.0 1010/Vb 416 235 416 210 3103 326 0 1/2 100.0 1010.0 1010 V 549 " 4 290 549 210 4440 420 0 1/2 100.0 1010.0 1010 I I I I For notes, see next page.I I Page 8 of 17 1 File No.: VY- 16Q-31 1 Revision:
0 F0306-0IRO I
CStructural Integrity Associates, Inc.Table 1: Thermal Cycle Definitions for Feedwater Line (concluded)
Notes: 1. From Reference
[13].2. Normal operating conditions are 1,010 psig, 549'F (steam dome), 392&deg;F (feedwater), and 4590 gpm (feedwater nozzle) [14].3. See Figure 1.4. For the transients where flow is stopped, the natural convection heat transfer coefficient was used. The same approximate value was used within each region. These values are:* 200 gpm for Regions I and III.* 150 gpm for Regions II, Ila, and llb.100 gpm for Regions IV and V.File No.: VY-16Q-3 11 Revision:
0 Page 9 of 17 F0306-O1RO
* Structural integrityAssociates, inc.4o20/20oo9:00:42 AM " 20 '' '0 o -0 20 33 40 50 8 HU1A' V 125* ,2 17Q. *14, 42 .[ qf .I I01 S.4,, , ReO.V Nod ..5T 2,.NO< -S 1Q to 31.7)(,es' 5 .1 Q) 1'42V 43. to* 547)~ (deo34$ t~54?)S0 fr) V1~4Ti3W Figure 1: Feedwater/LIPCI Piping from Anchor HD-36 to RPV Nozzles N-4A anI File No.: VY-16Q-311 Revision:
0 I I i I I I Structural Integrity Associates, Inc.*3.0 ASSUMPTIONS/DESIGN INPUT In order to take advantage of improvements in the ASME Code that result in a lower calculated fatigue usage, this evaluation is done to the ASME Boiler and Pressure Vessel Code, Section III, 1998 Edition with 2000 Addenda [9]. The 1998 Edition of Section III (with 2000 Addenda) has been accepted by the US NRC for use in design analyses.
Although there are a few restrictions on the application of this Edition, they involve the use' of optional increased allowables that are not being used in this calculation.
A piping model was created using PIPESTRESS
[1]. The calculation
[2] that had previously analyzed the subject Class 1 feedwater piping contains the ADLPIPE input file used to create the PIPESTRESS.
input file for this- evaluation.
Valve'dimensions and properties were also obtained from the ADLPIPE input file.The piping model is composed of one carbon steel grade (maximum carbon content of 0.30 %) [2].Temperature dependent material properties were used with values obtained from Reference
[5]. Table 2 summarizes these values. The resulting PIPESTRESS model (including boundary conditions) is shown in Figure 1. The drawings for both feedwater loops [3, 4] and the HPCI line [7] were also consulted to aid in building the PIPESTRESS model.Assumptions:
: 1) The weight of insulation is included in the analysis and PIPESTRESS calculates the heat transfer effects of insulation.
: 2) Node 545 is the end of the as-modeled HPCI piping system. This is, appropriate because of the distance from the HPCI/Feedwater tee, six pipe supports in the segment and multiple pipe direction changes.The feedwater and HPCI line sizes are specified in the previous calculation
[2] and are shown in Table 3.File No.: VY-16Q-311 Revision:
0 Page 11 of 17 F0306-OI RO Structural Integrity Associates, Inc.Table 2: Material Properties for Feedwater System Class 1 Piping [2 App. E, 5]* SA 106 B and SA-234 WPB (Carbon Silicon Steel, C-Si) " Coefficient Mean Design of Linear Coefficient of Yield Stress Young's Thermal Thermal Thermal Thermal Stress Intensity Temperature Modulus Expansion Expansion(1)
Conductivity(')
Diffusivity(1)
S y Smn ("F) (xl 06 psi) (in/100 ft) (10-6/in/in/F) (btu/hr/ft/&deg;F) (ft 2/hr) (ks i) (ksi)50 29.6 0(2) -. 35.0 20:0 70 29.5. 0 6.4 27.5 0.529 35.0 20.0 100 29.3 0.2 27.6 0.512 .35.0 20.0 150 27.6 0.496 200 28.8 1.0 27.6 0.486 32.1 20.0 250 27.4 0.467 300 28.3 1.9 27.2 0.453 31.0 20.0 350 27.0 0.440 400 27.7 2.8 26.7 0.428 29.9 20.0 450 26.3 0.413 500 27.3 3.7 25.9 .398 28.5 18.9 550 25.5 0U387 600 26.7 4.7 25.0 0.374 26.8 17.3 Notes: I. These properties are used for the transient analysis only.2. Assumed equivalent to the value at 707F.The material properties applied in the analyses are taken. from ASME Section II Part D 1998 Edition with 2000 Addenda. This is consistent with information provided in the Design Input Record (page 13 of VY EC No.1773, SI File No. VY-16Q-209).
The use of a later'code edition than that used for the original design code is acceptable since later editions typically reflect more accurate material properties than was published in prior Code editions.I I I I I I I I I I I I I I I I I FileNo.: VY-16Q-311 Revision:
0 Page 12 of 17 F0306-01RO I .jStructural Integrity Associates, Inc.Table 3: Feedwater/HPCI Piping Size Information
[21 16" FW 16" FW 10"2 14" Downstream Upstream FW HPCI of V2-29A of V2-29A Pipe Schedule 80 120 120 120 Fittings Schedule 120 --- 120 Piping O.D. (in.) 16.0 16.0 10.75 14.0 Piping Nom.Pipin .0.843 1.218 0.843 1.093 Wall (in.)Fitting Nom. 1.218 0.843 Wall. (in.)Pipe Weight' 136.46 192.3 89.20 150.7 (lb/fl)Insulation Weight (lb/ft) 14.64 11.98 Note: 1. Weight of contents automatically added by the PIPESTRESS Program.2. Insulation weight assumed to be consistent with thickness.
(2 inches) and composition of insulation on the 16" FW upstream of V2-29A.File No.: VY- 16Q-311 Revision:
0*Page 13 of 17 F0306-O1RO Structural Integrity Associates, Inc.4.0 ANALYSIS Through-wall thermal gradient terms were calculated by the PIPESTRESS program for all of the transients.
Table 1 defines each thermal cycle definition (i.e:, transient load case) and the region of the modeled piping those conditions are applicable.
The forces and moments due to differential thermal expansion need to be included in the fatigue evaluation.
The differential thermal expansion cases as analyzed by the piping program, PIPESTRESS, correspond to the end temperature and pressure of the transient.
Table 4 lists the thermal expansion cases.The material properties were obtained from the ASME Code Section II, 1998 Edition, Part D, with 2000 Addenda [5]. E and are taken at 70'F, and k, p, and cp are taken at the average temperature I over the range of the individual transients.
The internal heat transfer coefficient h for the transients with flow occurring in the pipe is calculated I based on the following relation for forced convection
[8]: I h = 0.023 Re 8 Pr 4 k/D Where Re Reynolds number I Pr Prandtl number The heat transfer coefficients were calculated by PIPESTRESS using the above relation.
The flow rates described for each transient in Table 1 were used. For the transients where flow is stopped, the natural convection heat transfer coefficient was used. The formula for h is [8]: 3 h'= 0.55 (Gr Pr)0 2 5 k/L 3 Where Gr = Grashof Number L = pipe diameter PIPESTRESS:
only has the forced convection heat transfer formula built in, so an equivalent flow rate was determined that would give the same heat transfer coefficient as the free convection coefficient.
As discussed in the next section, the PIPESTRESS input, file "FWHPCI.FRE" will be run and analyzed to Section III, Subsection NB-3600 of ASME 1998 Edition [9] in order to evaluate acceptable fatigue usage values for the Class 1 feedwater loop A system. The code option available in PIPESTRESS is the 1998 edition without addenda. This is acceptable as the 1999 and 2000 addenda to the 1998 code did not change the fatigue analysis method which PIPESTRESS uses. 3 A Listing of the PIPESTRESS input is included as Appendix A.-File No.: VY-16Q-311 Page 14 of 17 Revision:
0 F0306-0RO I
I Structural Integrity Associates, Inc.Table 4: Thermal Cycle Load Cases Load Transients Region I Region Ila Region Ilb Region U Region I. Region IV Region WVa Region IVb Region V Vessel Set Represented Temp. (IF) Temp. (IF) Temp. (IF) Temp. (IF) Temp. (IF) Temp. (IF) Temp. (IF) Temp. (IF) Temp. (oF) Temp. (IF)1 1 100 100 100 100 .100 100 100 100 100 100.2 .2,24.36.38 100 100 100 100 100 100 100 100 100 100 Region UI Pressure (psig)50 50 50 All other.Regions Pressure (psig)1100 50 1010 3 3,21,34,43 150 150 125 100 150 150 283 416 I 549 .549 1 4 1 5 1 260 1 2601 1801 1001 260 260 260 1 260 1 260 5491] [ 50 1010 5 16.8-10.14 161 392 392 246 100 392 392 392 1 392 1 392 1 549 I I 6 7 310 310 205 100. 310 310 310 310. 310 549 7_ 9 280 280 190 100 280 280 280 280 280 549.8 11, 13, 15 265" 265 182.5 100 265 265 265 265 265 549 9 12 90 90 95 100 90 90 90 90 90 549 10 20 265 265 182.5 100 265 265 360 454 549 549 11 22 150 150 125 100 150 150 225 300 375 375 12 23 150 150 125 100 150 150 210 270 330 .330 13 25 392 392 246 100 392 392 450 507 565 565 14 26 50 50 50 50 50 50 50 50 50 565 15 27 150 .150 125 100 150 150 247 343 440 565 16 28 150 150 125 100 150 150 288 427 565 565, 17 30 150 .150 125 100 i 150 150 247 343 440 555 is .31 150 150 125 100 150 150 283 416 549 565 19 32 50 50 50 50 50 50 50 " 50 .50 502 20 33 150I ISO 125 100 150 150 200 250 300 502 21 35 275 275 187.5 100 275 275 275 275 275 549 22 37 100 100 100 100 0 00 100 100 100" 100 100 23 39 392 392 246 100 392 392 392 392 392 600 24 40 392 392 246 100 392 392 392 392 392 539 25 41 392 392 246 100 392 392 392 392 392 549 26 17 275 275 .. 187.5 100 275 275 275 275 .275 539 27 19 265 265 182.5 100 265 265 323 382 440 549 28 4 100 100 100 100 100 100 100 100 100 549 29 18 100 100 100 100 100 100 100 100 100 539 30 42 .125 125 112.5 100 125 125 180 235 290 549 31 29. 50 50 50 50 50 50 50 50 50 532 50 50 50, 50 50 50 50.50 1135 so 50.50 50 5 50 50 50 50 50 50 50 50 50 50.50 885 1010 1010 1010.1010 1010*1010 170 88 1190 1135 1135 1135 1060 1135 675 675 885 1563 1375 940 1010 1010 1010 1010 1010 1010 885 File No.: VY-16Q-311 Revision:
0 Page 15 of 17 F0306-OIRO Structural Integrity Associates, Inc.I I I 5.0 RESULTS OF ANALYSIS Since the piping at VY was designed in accordance with USAS B3 1.1 methodology, fatigue analysis does not exist for the piping. Therefore, fatigue calculations are being developed for selected locations in the Class 1 piping systems at VY. This will result in detailed, Class 1 fatigue calculations for each selected location.
Piping models and transient definitions have been developed for the Class I portion of the feedwater system, as documented in the previous sections of this calculation.
The limiting total fatigue usage for the analyzed feedwater/HPCI piping system occurs at Node 155 on the riser to the feedwater nozzle. The total usage at this location is U =0.1661 (per the PIPESTRESS report FWHPCI.PRF) which passes Class 1 fatigue evaluation.
The second highest total fatigue usage for the analyzed feedwater/HPCI piping system occurs at Node 175, the 16" to 10" reducer on the feedwater piping. The total usage at this location is U = 0.1.114 (per the PIPESTRESS report FWHPCI.PRF) which passes Class 1 fatigue evaluation.
The environmental fatigue multiplier to use from Reference
[10] is 1.74. The total usage including environmental effects is therefore 0.289.Appendix B contains the fatigue usage summary for node 155.I I I I I U I I I I I!I I I I I FileNo.: VY-16Q-311 Revision:
0.Page 16 of 17 F0306-O1 RO Structural Integrity Associates, Inc.I
 
==6.0 REFERENCES==
 
I. PIPESTRESS, Version 3.5.1+0.26, DST Computer Services S.A., QA-1670-301, June, 2004.2. HPCI/FW Piping Stress Information.
ADLPIPE listing for FDW & HPCI piping from Calculation No. VYC-551, Rev. 2, Appendix A, SI File No. VY-05Q-229.
: 3. Vermont Yankee Nuclear Power Corp. Drawing No. VYI-FDW-Part 5, Rev. 1, "Piping Isometric Feedwater:
Drywell-Main Steam Tunnel (FDW) Part 5," SI File No. VY-05Q-22
 
===1.4. Vermont===
Yankee Nuclear Power Corp. Drawing No. VYI-FDW-Part 5A, Rev. 1, "Piping Isometric Feedwater:
Main Steam Tunnel and. Drywell FDW-Part 5A," SI File No. VY-05Q-221.
5; American Society of Mechanical Engineers Boiler & Pressure Vessel Code, Section II, Materials, Part D, "Properties (Customary)," 1998 Edition including the 2000 Addenda.6. Structural Integrity Associates Report No. SIR-0 1-130, Revision 0, 'System Review and Recommendations for a Transient and Fatigue Monitoring System at the Vermont Yankee Nuclear Power Station," February 2002, SI File No. VY-05Q-401.
: 7. Vermont Yankee Nuclear Power Corp. Drawing No. VYI-HPCI-Part 5, Rev. 0, "Piping Isometric Drawing High Pressure Coolant Injection Main Steam Tunnel-Torus Area (HPCI) Part 5," SI File No. VY-05Q-223.
: 8. Holman, J.P., Heat Transfer, Fifth Edition, McGraw-Hill, 1981.9. American Society of Mechanical Engineers Boiler & Pressure Vessel Code, Section il1, Rules for Construction of Nuclear Facility Components, 1998 Edition including the 2000 Addenda.10. Structural Integrity Associates Calculation No. VY-16Q-303, Revision 0, "Environmental Fatigue Evaluation of Reactor Recirculation Inlet Nozzle and Vessel Shell/Bottom Head." 11. "Reactor Thermal Cycles," Attachment 1, page 2, of Entergy Design Input Record (DIR) EC No.1773, Revision 0, "Environmental Fatigue Analysis for Vermont Yankee Nuclear Power Station," 7/3/07, SI File No. VY-16Q-209.
: 12. "Nozzle Thermal Cycles (Feedwater)," Attachment 1, page 3, of Entergy Design Input Record (DIR)EC No. 1773, Revision 0, "Environmental Fatigue Analysis for Vermont Yankee Nuclear Power Station," 7/3/07, SI File No. VY-16Q-209.
: 13. "Reactor Thermal Cycles for 60 Years of Operation," Attachment 1 of Entergy Design Input Record (DIR) EC No. 1773, Revision 0, "Environmental Fatigue Analysis for Vermont Yankee Nuclear Power Station," 7/3/07, SI File No. VY-16Q-209.
: 14. GE Certified Design Specification No. 26A6019, Revision 1, "REACTOR VESSEL -EXTENDED POWER UPRATE," August 29, 2003, SI File No. VY-05Q-236.
File No.: VY-16Q-311 Page 17 of 17 Revision:
0 F0306-01RO Structural Integrity Associates, Inc.I I I I APPENDIX A PIPESTRESS INPUT FILE ("FWHPCi.FRE")(Pages A1 -A38).File No.: VY-16Q-311 Revision:
0 Page Al of A38 F0306-OIRO I Structural Integrity Associates, Inc.IDEN JB=2 *Job number (1 to 99 CD=I *1=ASME Section III vA=0 *0=Calculate GR=-Y *Direction of gravit.IU=1 *Input units OU=I *Output units CH=$ *Delimiter character AB=T *FREE errors =abort PL=-$Vermont Yankee$EN=$KRE$TI.TL BL=3 *Modelinq option: 99)y 2=Verify O=SIU O=SIU 1=USA I=USA* 3.=uniform mass for static analysis* lumped mass for dynamic analysis* rotational inertia ignored GL=" *Report forces/moment 0=Global SU=l *Support summary. 0=No CV=15 *Code version -See Manual HS=l *Highest 20 stress ratios for each case MD=l *Hot modulus TI=$Vermont Yankee Feedwater Piping$$SI Fatigue Analysis$FREQ RF=1 RP=8 FR=33 MP=20 MX=70 TI=$SEISMIC$
1=jocal 1=Yes 2=G et L THERMAL CYCLE LOAD CASES****LCAS LCAS LCAS LCAS LCAS LCAS LCAS LCAS LCAS LCAS.LCAS LCAS LCAS LCAS LCAS LCAS LCAS LCAS LCAS LCAS LCAS LCAS LCAS LCAS LCAS LCAS LCAS LCAS LCAS LCAS RF=0 RF=0 RF=0 RF=0 RF=0 RF= 0 RF=0 RF=0 RF= 0 RF=0 RF=O, RF=0 RF= 0 RF=0 RF=0 RF=O0 RF&#xfd;0 RF=0 RF-=0 RF=O0 RF=0 RF=0 RF=0 RF=0 RF=0 RF=0 RF~=0 RF=0 RF'= 0 CA=1 CA=2 CA=3 CA=4 CA=5 CA=6 CA=7 CA=8 CA=9 CA=f0 CA=11 CA=13 CA=I34 CA=f4.CA=15 CA=16 CA=I7 CA=18 CA=19 CA=2 0 CA=21 CA=22 CA=2 3 CA=2 4 CA=25 CA=2 6 CA=27 CA=28 CA=29 CA=30 TY=0 TY&#xfd;0 TY&#xfd;=0 TY&#xfd;=0 TY&#xfd;0 TY=0 TY=&#xfd;0 TY&#xfd;0 TY=&#xfd;0 TY=z0 TY=0 TY=0 TY~=0 TY=0 TY=0 TY=0 TY=0 TY=0 TY~=0 TY=0 TY'=0 TY=0 TY=0 TY=0 TY~=0 TY=0 TY-.0 TY=O0 ,.i c TI.=$LC-l$
TI=$LC-2$TI=$,LC-3$
TI=$LC-4$TI=~$LC-5$
TI=$LC-6$TI=~$LC-7$
TI=$LC-8S.
TIr=$LC-9$
TI=$LC-10$
TI&#xfd;$LC-11$
TI=$LC-.12$
TI=~$LC-13$
TI=$LC-14$
TI=$LC-15$
TI=~$LC-16$
TI=~$LC-17$
TI=$LC-18$
TI=$LC-19$
TIL=$LC-20$
TI=$LC-21$
TI=$ LC-22$TI=$LC-23$
TI=.$LC-24$
TI$ LC -25$TI=&#xfd;$LC-26$
TI=~$LC-27$
TI=&#xfd;$LC-28$
TI='$LC-29$
TI=~$LC730$
*TC-1*TC-2,24,36,38
*TC-3,21,34,43
*TC-5*TC-6, 8,10,14,16
*TC-7*TC-9*TC-11,13,15
*TC-12*TC-20*TC-22*TC-23*TC-25*TC-26, 29*TC-27*TC-28*TC-30*TC-31*TC-32*TC-33*TC-35*TC-37*TC-39*TC-40*TC-41*TC-17*TC-19*TC-4*TC-18*TC-42 File No.: VY-16Q-311 Revision:
0 Page A2 of A38 F0306-0I RO VStructural Integrity Associates, Inc.LCAS RF=0 CA=31 TY=0 TI=$LC-31 LCAS RF=6.CA=32.TY=6 TI==$SAM$** WEIGHT CASES************ **** **** *.****TC-29 I I I I I I LCAS CA=101 LCAS CA=102 RF=1 TY=3 TI=$OPERATING WEIGHT$RF=2 TY=4 TI=$HYDROTEST WEIGHT$THERMAL TRANSIENT CASES****TCAS*TCAS TCAS TCAS TCAS TCAS TCAS TCAS TCAS TCAS TCAS TCAS TCAS TCAS TCAS TCAS TCAS.TCAS TCAS TCAS TCAS TCAS TCAS TCAS TCAS TCAS TCAS TCAS TCAS TCAS TCAS TCAS TCAS TCAS TCAS TCAS TCAS TCAS TCAS TCAS TCAS TCAS TCAS CA=201 CA=202 CA=203 CA=2 04 CA=2 05 CA=206 CA=207 CA=208 CA=209 CA=210 CA=211 CA=212 CA=213 CA=214 CA=215 CA=216 CA=217 CA=218 CA=219 CA=2 20 CA=221 CA=222 CA=2 23 CA=224 CA=225 CA=226 CA=227 CA=228 CA=229.CA=230 CA=231 CA=232 CA=233 CA=234 CA=235 CA:236 CA=237 CA=2 3.8 CA=239 CA=240 CA=241 CA=242 2 CA=243 I RP=I RP=I RP=I RP=I RP=I RP=I RP=I RP=I RP=1 RP=1 RP=1 RP=1 RP=1 RP=I RP=1 RP=1 RP=1 RP=1 RP=1 RP=1 RP=1 RP=1 RP=1 RP=1 RP=1 RP=1 RP=1 RP=1 RP=1 RP= 1 RP=1 RP=1 RP=1 RP=1 RP=1 RP=1 RP=1 RP=1 RP=1 RP=I RP=I RP=I RP=I 1TI=$Design Hydrotest
+$1TI=$Design Hydrotest
-$1TI=$Startup
+$-TI=$TRoll
& Inc. PWR1 -$TI=$TRoll
& Inc. PWR2 +$TI=$TRoII
& Inc. PWR3 +$* TI=$DlyReduction to 75%TI=$DlyReduction to 75%* TI=$WklyReduct to 50% -$* TI=$WklyReduct to 50% +$* TI=$LOFWH+TT
.1 $TI=$LOFWH+TT 2 -$TI=$LQFWH+TT 3 +$TI=$LOFWH+TT 4 +$TI=$LOFWH+PFWHTR Byp -$TI=$LOFWH+PFWHTR Byp +$TI=$SCRAM+TT+AllOtrScm
-: TI=$SCRAM+TT+AIlOtrScm
-!TI=$HotStandby 1 +$TI=$HotStandby 2 +$TI=$HotStandby 3 -$TI=$Shutdown 1 -$TI=$Shutdown 2 -$TI=$Shutdown 3 -$TI=$SCRAM+LOFWPI
+$TI=$SCRAM+LOFWP2
-$TI=$SCRAM+LOFWP3
+$TI=$SCRAM+LOFWP4
+$TI=$SCRAM+LOFWP5
-$Ti=$SCRAM+LOFWP6
+$TI=$SCRAM+LOFWP7
+$TI=$SCRAM+LOFWP8 -s TI=$SCRAM+LOFWP9
+$TI=$SCRAM+LOFWP10+$
TI=$SCRAM+SRVBLDN1-$
TI:$SCRAM+SRVBLDN2-$
TI=$Hydro Test +$TI=$Hydro Test -$TI=$SCRAM+TG+OPresl
-$TI=$SCRAM+TG+OPres2
-$TI=$SCRAM+TG+OPres3
-$TI=$HotSbyFWcyc
+$TI=$HotSbyFWcyc
+$-5+$I I I I I I U I I I I I I***SEISMIC CASES****File No.: VY-16Q-311 Revision:
0 Page A3 of A38 F0306-O IRO I ~Structural Integrity Associates, Inc.RCAS CA=103 EQ=3 EV=1 TY= .SU=l LO=1 FX=1 FY=I FZ=I TI=$OBE INERTIA$**** LOAD COMBINATION CASES *CCAS RF=1 CA=104 ME=I FL=l CCAS RF=i CA=401 SS=I ME=I EQ=3 CCAS RF=I CA=402 SS=I ME=3 Fl=I CCAS RF=1 CA=403 SS=I ME=3 F1=-l LOAD SETS****C1=103 CY=10 TI=~$OBE$C1=102 C2=103 TI&#xfd;$EQUATION 9 LEVEL B$C1=.103 C2=6 C3=32 TI=$NORMAL+/-OBE$
C1=~103 C2=~6 C3&#xfd;32 TI=$NORMAL-OBE$
*RF field is the highest temperature and pressure of the transient*PR and MO LSE]LSET LSET LSET LSET LSET LSET LSET LSET LSET LSET LSET LSET LSET LSET LSET LSET LSET LSET LSET LSET LSET LSET LSET LSET LSET LSET LSET LSET LSET LSET LSET LSET LSET LSET LSET LSET LSET LSET LSET RF= 1 RF=&#xfd;2 RF&#xfd;3 RF=3 RF&#xfd;4 RF&#xfd;5 RF&#xfd;5 RF&#xfd;5 RF=5 RF=&#xfd;5 RF=&#xfd;8 RF'&#xfd;8 RF==5 RF'=5.RF==5 RP=5, RF==2 6*RF'=2 7 RF=10 RF==10 RF==3 RF~ll RF=-12 RF&#xfd;1l3 RF=13 RF~=15 RF=16 RF=16 RE'=17 RF=18.RF&#xfd; 18 RF=20 RF~=3 PF&#xfd;5 RE'=21*RF=22 RF~=2 RF=23 RF=24 fields are the final temperature and pressure of the transient RP=I CY=120 PR=1 MO=1 TR=+201 TI=$Design Hydrotest
+ LS RP=I CY=120 PR=2 MO=2 TR=-202 TI=$Design Hydrotest
-LS RP=4 CY=300 PR=3 MO=3, TR=+203 TI=$Startup
+ LS RP=I CY=610 PR=28 MO=28 TR=-204 TI=$TRoll
& Inc. PWRI -LS RP=1 CY=599 PR=4 MO&#xfd;4 TR=+205 TI=$TRoll
& Inc. PWR2 + LS-RP=I CY=599 PR=5 MO=5 TR=+206 TI=$TRoll
& Inc. PWR3 + LS-RP=I CY=10000 PR=6 .MO=6 TR=-207 TI=$DlyReduction to 75% -LS-RP=I CY=I0000 PR=5 MO=5 TR=+208 TI=$DlyReduction to 75% + LS-RP~= CY=2000 PR=7 MO=7 TR=-209 TI=$WklyReduct to 50% -LS-RP=I CY=-2000 PR=5 MO=5 TR=+210 TI=$WklyReduct to 50% + LS-RP=I CY=310 PR=8 MO=8 TR=-211 TI=$LOFWH+TT I -LS-RP~= CY=10 PR=9 MO=9 TR=-212 TI=$LOFWH+TT 2.- LS-RP=1 CY=10 PR=8 MO-=8 TR-=+213 TI=$LOFWH+TT 3 + LS-RP=I CY=10 PR=5 MO=5 TR=+214 TI=$LOFWH+TT 4 + LS-RP=1 CY=70 PR=8 MO=8 TR=-215 TI=$LOFWH+PFWHTR Byp -LS-RP~= CY=70 PR=5 MO=5 TR=+216 TI=$LOFWH+PFWHTR Byp + LS-RP=I CY=289 PR=26 MO=26 TR=-217 TI=$SCRAM+TT+AIIOtrScm
-LS-RP=I CY=289 PR=29 MO=29 TR=-218 TI=$SCRAM+TT+AllOtrScm
-LS--1$-2$-3$-4$-5$-6$-7$-8$-9$-10$-11$-12$-13$-14$-15$-16.$-17$-18$RP=1 RP~ 1 RP~=l RP=1 RP= 1 Rp~=1 RP=1 RP~=1 RP~l RP~l R IP--Rh= 1 RP=1 RP=1 RP~=1 RP~ 1 RP~=1 RP~=1 RP+1 RP= 1 RP=1 RP= 1 CY~=300 CY~=300 CY=~300 CY~=300 CY=300 CY=300 CY~=10 CY~=10 CY=10 CY=10 CY=10 CY=10 CY=10 CY=10 CY=1O CY=10 CY~1 CY= 1 CY=1 CY- 1 CY=289 CY=289 PR&#xfd;2 7 PR&#xfd; 10 PR=3 PR=11 PR~=12 PR~=2 PR=13 PR=14 PR=1,5 PR=16 PR=31 PR~=17 PR='18 PR~=19 PR=2 0 PRr=3 PR~=2 1 PR=2 PR=~22 PR~=2 PR=23 PR=24 MO~=2 7 MO~=10 MO=3 MO~=11.MO= 12 MO~=2 M0~=1 3 MO=1 4 MO~=15 MO~l 6 MO~=31 MO=17 MO=18 MO~=19 MO=2 0 MO=3, MO&#xfd;21 MO=2 MO=22 MO=~2 MO=~23 MO=~24 TR=+219 TR=+220 TR=- 221 TR=-222 TR=-223 TR=-224 TR=+225 TR=-226 TR=+227 TR=+228 TR=-229 TR=.+230 TR=+231 TR:-232 TR=+233 TR=+234 TR=-235 TR=-236 TR=+237 TR=-238 TR=-239 TR=-240 TI=$HotStandby 1 +TI=$HotStandby 2 +TI=$HotStandby 3 -TI=$Shutdown 1 -TI=$Shutdown 2 -TI=$Shutdown 3 -TI=$SCRAM+LOFWPI
+TI:$SCRAM+LOFWP2
-TI=$SCRAM+LOFWP3
+TI=$SCRAM+LOFWP4
+TI:$SCRAM+LOFWP5
-TI=$SCRAM+LOFWP6
+TI=$SCRAM+LOFWP7
+TI=$SCRAM+LOFWP8
-TI=$SCRAM+LOFWP9
+TI=$SCRAM+LOFWP10+
TI=$SCRAM+SRVBLDN1,-
TI=$SCRAM+SRVBLDN2.-
TI=$Hydro Test +TI=$Hydro Test -TI:$SCRAM+TG+OPresl
-TI=$SCRAM+TG+OPres2
-LS-19$LS-20$LS-21$LS-22$LS-23$LS-24$LS-25$LS-26$LS-27$LS-28$LS-29$LS-30$LS-31$LS-32$LS-33$LS-34$LS-35$LS-36$LS-37$LS-38$LS-39$LS-40$File No.: VY-16Q-31I Revision:
0 Page A4 of A38 F03 06-01 RO VStructural Integrity Associates, Inc.LSET RF&#xfd;25 RP=I CY=289 LSET RF=30 RP=1 CY=300 LSET RF=3 RP=1 CY=300 PR=25 PR=30 PR=3 MO=25 MO=30 MO=3 TR=-241 TI=$SCRAM+TG+OPres3
-TR=+242 TI=$HotSbyFWcyc
+TR=+243 TI=$HotSbyFWcyc
+LS-41$LS-42$LS-43$I I LSET RF&#xfd;6 CY=5 FL-=1 PR=6 MO=402 TI=$NORMAL+OBE LSET RFr6 CY=5 FL=I PR=6 MO=403 TI=$NORMAL-OBE LS-132$LS-133$RESPONSE SPECTRA****
***********
**************
*SSE response spectra conservatively used SPEC FS=OBE EV=I ME=3 FP=I TI=$RESPONSE$
LV=I DX=I DY=I DZ=I DI=X 0.30/0.125 0.80/0.300 2.00/0.6[5.00/1.900 5.75/2.850 6.00/3.3-14.00/1.325 19.00/1.600 21.00/1.0(DI=Y 50 75 00 0.30/0.075 1.25/0.2 4.40/0.500 4.80/0.6 12.00/1.450 16.00/1.9 36.00/0.325 36.10/0.3 DI=Z 0.30/0.150 1.00/0.3 5.75/2.950 6.00/3.4 15.00/1.300 17.50/1.4 50 00 00 25 50 5o 50 1.75/0.325 7.25/0.600 18.00/1.700 36.20/0.325 2.00/0.625
:6.25/3.800 20.00/0.875 3.00/0.725 8-.25/3.375 22.00/0.800 2.40/0.450 7.50/0.700 20.00/0.750
.36.30/0.325 4.00/1.000 8.75/3.800 30.00/0.650 3.50/1.000 9.00/3.000 30.00/0.700 2.75/0.475 8.50/0.700 25.00/0.4.50 36.40/0.325 4.50/1.400 10.00/2.625 36.00/0.650 4.40/1.200 10.00/2.400 36.00/0.650 3.80/0.500 10.00/0.925 30.00/0.350 36.50/0.325 5.00/2.000 12.0/2.150 36.10/0.650 I I I I I*** MATERIAL PROPERTIES
********* ** *** ** *********
* ****** SA-106 Grade B and SA-234 WPB MATH CD=106 EX=0 TY=I *C-Si*MATD TE=-100 EH=30.2 EX=0 SM=20 SY=35 MATO MATO MATO MATO MATD MATO MATD MATD TE=50 TE=70 TE=100 TE=2 00 TE=300 TE=400 TE=500 TE=600 EH=29. 6 EH=2 9.5 EH=29. 3 EH=28.8 EH=28 .3 EH=27 .7 EH=2 7.3 EH=26. 7 EX=0 SM=20 SY=35 EX=0 EX=0. 2 EX=I. 0 EX=1. 9 EX=2. 8 EX=3. 7 EX=4 .7 SM=20 SM=20. 0 SM=20..0 SM=20. 0 SM=20.O0 SM=18. 9 SM=17. 3 SY=35 SY=35 SY=32. 1 SY=31 SY=29. 9 SY=28.5 SY=26. 8 I I I I I I*** Cross Sectional Properties
*REGION I- LINE 16 INCH FDW-16 SCH. 120 Run from 5 to 10*Anchor HD36 to HPCI brnch CROS CD=I OD=16.0 WT=l.218 MA=204.28 SO= ST=1 IN=0*FEEDWATER Valves -V2-27A, V2-28A, V2-29A CROS CD=2 OD=24.0 WT=2.436 MA=0.12 SO= ST=I IN=0 KL=I*REGION III- LINE 16 INCH FDW-16 SCHR. 80*Piping Downstream of Valve V2-29A TO FW TEE CROS CD=3 OD=16.0 WT=0.843 MA=I51".SO=1 ST=I IN=0*REGION III- LINE 16 INCH FDW-16 SCR_ 120*Fittings Downstream of Valve V2-29A TO FW TEE CROS CD=4 0D=16.0 WT=1.218 MA=204.28 SO=1 ST=I INL0 File No.: VY-16Q-311 Revision:
0 Page A5 of A38 F0306-OIRO I &#xb6; Structural Integrity Associates, Inc.*REGION IV & V- LINES 10 INCH INCH FDW-21 AND 10 INCH FDW-19 SCH. 120*Piping Downstream of FW TEE TO NOZZLES CROS CD=5 OD=10.75 WT=0.843 MA=98.12-SO=l ST=1 IN=0*REGION II- LINE 14 INCH HPCI-15A SCH. 120 FROM NODE. 10 TO 547 CROS CD=6 0D=14.0 WT=1.093 MA=161.35 SO=I ST=1 IN=1*REGION II- HPCI Valves CROS CD=7 00=21.0 WT=2.186 MA=0.12 SO=I ST=I IN=1 KL=1* **** ** ** * **** **** *** ** STRUCTURE AND LOADS DESN TE=400.0 PR=1900.0
*FEEDWATER AND HPCI PIPING------------------------------------------------------------
*BEGIN REGION 1*-------------
*Same for all regions except II OPER CA=1 TE=100 PR=1100 OPER CA=22 TE-100 PR=1563 OPER CA=28 TE&#xfd;100'PR=1010 OPER CA=29 TE=100 PR=1010*Same for all regions OPER OPER OPER CA=2 CA=19 CA=31*Unique OPER CA=3 OPER. CA=4 OPER CA=5 OPER CA=6 OPER CA=7 OPER CA=8 OPER CA=9 OPER CA=10 OPER CA=II OPER CA=12 OPER CA=13 OPER CA=14 OPER CA=15 OPER CA=16 OPER CA=17 OPER CA=18 TE=100 TE=50 TE=50 TE=I50 TE=260 TE=392 TE=310 TE=280 TE=265 TE=90 TE=265 TE=150 TE=150 TE=392 TE=50 TE=150 TE=50 TE=150 TE=150 PR=50 PR=675 PR==885 PR=1010 PR=1010 PR=1010 PR=1010 PR=1010 PR=1010 PR=1010 PR=1010 PR=170 PR=8 8 PR=1190 PR=1135 PR=1135 PR=1135 PR=1060 PR=1135 OPER CA=2.0 TE=150 PR=675 OPER CA=21 TE=275 PR=885 OPER OPER OPER OPER OPER CA=23 CA=24 CA=25 CA=26 CA=27 TE=392 TE=392 TE=392 TE=275 TE=265 PR=1375 PR=940 PR=1010 PR=1010 PR=1010 File No.: VY-16Q-311 Revision:
0 Page A6 of A38 F0306-0I RO Structural Integrity Associates, Inc.OPER CA=30 .TE-125 PR=1010 TRAN CA=20 TRAN CA=20 TRAN CA=20 TRAN CA=20 TRAN CA=20 TRAN CA=20 TRAN CA=20'TRAN CA=20 TRAN CA=20 TRAN CA=20I TRAN CA=21L TRAN CA=21: TRAN CA=21i TRAN CA=21, TRAN CA=21i TRAN CA=21(TRAN CA=21I TRAN CA=21 TRAN CA=21&#xfd;TRAN CA=22(TRAN CA=22(TRAN CA=22M TRAN CA=227 TRAN CA=224 TRAN CA=22E TRAN CA=22E TRAN CA=227 TRAN CA=228 TRAN CA=229 TRAN CA=230 TRAN CA=231 TRAN CA=232 TRAN CA=233 TRAN CA=234 TRAN CA=235 TRAN CA=236 TRAN CA=237 TRAN CA=238 TRAN CA=239 TRAN CA=240 TRAN CA=241 TRAN CA=242 TRAN CA=243 PAIR CA=201 PAIR. CA=202 PAIR CA=203 PAIR CA=204 PAIR CA=205 PAIR CA=206.PAIR  PAIR CA=208 PAIR CA=-209 IS=1 I S= 1 IS=1 I S= 1 IS=1 IS=1 IS=1 IS=1 I S=1 IS= 1 IS-=1 IS=1 IS=1 IS=1 IS=1 IS=1 IS=1 IS=1 FS=1 FS=1 FS=1 FS=1 FS=1 FS=1 FS=1 FS=1 FS -I FS=1 FS=1 FS=1 FS=1 FS=1 FS=I FS=1 FS=1 FS=I IT=70 FT=100 TT=1800 FL=200 IP=15 FP=1115 TP=1800 IT=100 FT=1.0 IT=100 FT=15(IT=150 FT=10(IT=100 FT=26(IT=260 FT=392 IT=392 FT=310 IT=310 FT=392 IT=392 FT=280 IT=280 FT=392 IT=392 FT=265 IT=265 FT=90 IT=90 FT=265 IT=265 FT=392 IT=392 FT=265 IT=265 FT=392 IT=392 FT=275 IT=275 FT=100 TT=0 FL=200 IP=1115 FP=65 TP=0 TT=16164 FL=200 IP=65 FP=1025 TP=16164 TT=0 FL=1377 IP=1025 FP=1025 TP=0 TT=0 FL=1377 IP=1025 FP=1025 TP=0 TT=1800 FL=9180 IP=1025 FP=1025 TP=1800 TT=900 FL=6885 IP=1025.FP=1025 TP=900 TT=900 FL=6885 *IP=1025 FP=1025 TP=900 TT=1800 FL=4590 IP=1025 FP=1025 TP=1800 TT=1800 FL=4590 IP=1025 FP=1025 TP=1800 TT=1800 FL=4590 IP=1025 FP=1025 TP=1800 TT=360 FL=1377 IP=1025 FP=1025 TP=360 TT=900 FL=1377 IP=1025 FP=1025 TP=900 TT=1800 FL=4590. IP=1025 FP=1025 TP=1800 TT=90 FL=9180 IP=1025 FP=1025 TP=90.TT=180 FL=9180 IP=1025 FP=1025 TP=180 TT=60 FL=10098 IP=1025 FP=1025 TP=60 TT=900 FL=275.4 IP=1025 *FP=1025 TP=900 I I I I I I I I I*IS=I FS=1 IT=265 FT=265 TT=0 FL=200 IP=1025 FP=1025 TP=0*IS=I FS=1 IT=265&#xfd;.FT=265 TT=0 FL=200 IP=1025 FP=1025 TP=0 IS=1 I S= 1 IS=1 Is=1 Is=1 IS=1 Is=1 IS=E1 IS=1 Is=1 I S=1 I S=1 Is=1 I S=1 ISr=1 I S= 1 IS=1 I*S= 1 Is=1 Is=1 Is=1 I S= 1 Is.=1 FS=1 FS=I FS=1 FS=I FS'= 1 FS=1 FS=1 FS=I FS=I FS=I FS=I FS=I FS:I FS:I.FS=I F S=1-FS=I.FS=I FS=I FS=I FS=1 FS=I FS=1 FS=I" IT=265 IT=150 IT=150 IT=150 IT=392 IT=392 FT=150 TT=4140 FL=200 IP=1025 FP=1025 TP=4140 FT=150 TT=0 FL=200 IP=1025 FP=185 TP=0 FT=150 TT=0 FL=200 IP=185 FP=103 TP=0 FT=100 TT=8280 FL=200 IP=103 FP=65 TP=8280 FT=392 TT=12 FL=200 IP=1025 FP=1.205 TP=12 FT=50 TT=0 FL=3672 IP=1205 FP=1150 TP=0'1 IT=50 FT=150 TT=1380 FL=200 IP=1150 FP=1150 TP=1380 IT=150 FT=150 TT=0 FL=200 IP=1150 FP=1150 TP=0 IT=150 FT=50 TT=0 FL=2754 IP=1150 FP=900 TP=0 IT=50 FT=150 TT=3060 FL=200 IP=900 FP=1075 TP=3060 IT=150 FT=I50 TT=0 FL=200 IP=1075 FP=1150 TP=0 IT=150 FT=50 TT=0 FL=1560.6 IP=1150 FP=690 TP=0 IT=50 FT=150 TT=300 FL=200 IP=690 FP=690. TP=3M0 IT=150 IT=392 IT=275 IT=100 IT=100 IT=392 IT=392 IT=392 IT=100 IT=125 FT=150 FT=275 FT=100 FT=100 FT=100 FT=392 FT=392 FT=392 FT=125 FT=150 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6.4 EX=6. 4 EX=6. 4 EX=6. 4 TT=8964 FL=200 IP=255 FP=1025 TP=8964 TT=60 FL=10098 IP=1025 FP=900 TP=60 TT=900 FL=275.4 IP=900 FP=65.TP=900 TT=0 FL=200IP=65 FP=1578 TP=0 TT=O FL=200 IP=1578 FP=65 TP=0 TT=60.FL=10098.
IP=1025 FP=1390 TP=60 TT=900 FL=275.4 IP=1390 FP=955 TP=900 TT=900 FL=275.4 IP=955 FP=1025 TP=900 TT=60 FL=200 IP=1025 FP=1025 TP=60 TT=210 FL=200 IP=1025 FP=1025 TP=210* Tavg=85* Tavg=100* Tavg=125* Tavg=125" Tavg=180* Tavg=326* Tavg=351" Tavg=351* Tavg=336 I I I I I I I I I CO=27. 6 CO=27 .6 CO=27. 6 CO=27. 6 CO=27. 6 CO=2 7.1 CO=27.0 CO=27.0 CO=27. 1 DI=0.521 DI=0. 512 DI=0. 504 DI=0. 504.DI=0. 490 DI=0.446 DI=0.440 DI=0. 440 DI=0.444 File No.: VY-16Q-311 Revision:
0 Page A7 of A38 F0306-0IRO Structural Integrity Associates, Inc.PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR CA=210 CA=211 CA=212 CA=213 CA=214 CA=215 CA=216 CA=2 17 CA=218 CA=219 CA=220 CA=221 CA=222 CA=223 CA=224 CA=225 CA=226 CA=227 CA=228 CA=229 CA=230 CA=231 CA=232 CA=233 CA=2 34 CA=235 CA=2 36 CA= 237 CA=238 CA=2 39 CA=240 CA=224 1 CA=2 42 CA=2 43 CO=27. 1 CO=27. 1 CO=27. 6 CO=27. 6 CO=27. 1 CO=27 .1 CO=27. 1 CO=27 .1 CO=27.6 CO=27 .3 CO=2 7.3 CO=27.. 6 CO=27.6 CO=27.6 CO=27. 6.CO=26. 7 CO=27.5 CO=27.6 CO=27.16 CO=27. 6 CO=27. 6 CO=27.6 CO=27.6 CO=27.6 CO=27.6 CO=27. 1 CO=27. 6 CO=2 7. 6 CO=27. 6 CO=26 7 CO=2 6.7 CO=26.7 CO=27. 6 CO=27. 6.DI=0.444 DI=0. 445 DI=0.490 DI=0. 490 DI=0. 445 DI=0. 445 DI=0 .445 DI=0.444 DI=0. 488 DI=0. 463 DI=0.463 DI=0.4 83 DI=0.496.DI=0. 496 DI=0. 504 DI=0 .430 DI=0. 478 DI=0. 512 DI=0. 496 DI=0. 512 DI=0. 512 DI=0. 496 DI=0 .512 DI=0 , 512 DI=0.496 DI=0.444 DI=0. 488 DI=0. 512 DI=0. 512 DI=0.430 DI=0.430 DI=0. 430 DI=O. 508 DI=0 .500 EX=6. 4 EX=6. 4 EX=6.4 EX=6. 4 EX=6. 4 EX=6.4 EX=6.4 EX=6. 4 EX=6.4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6.4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=-6.4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 Tavg=336 Tavg=329 Tavg=178 Tavg=178 Tavg=329 Tavg=329 Tavg=329 Tavg=334 Tavg=188 Tavg=265 Tavg=265 Tavg=208 Tavg=150 Tavg=150 Tavg=125 Tavg=392 Tavg=221 Tavg=100 Tavg=150 Tavg=100 Tavg=100 Tavg=150 Tavg=100 Tavg=100 Tavg=150 Tavg=334 Tavg=188 Tavg=100 Tavg=100 Tavg=392 Tavg=392 Tavg=392 Tavg=113 Tavg=138*REGION I GEOMETRY* RUN 1 FROM ANCHOR.MATL CD=106 CROS CD=1 HD36 TO HPCI brnCH- FDW-16 LINE A COOR JUNC TANG TANG PT=5 AX=0 AY=0 AZ=0 *ANCHOR HD36 PT=5 PT=9 DZ=-2.75 EW=1l PT=10 DZ=-r *WELDING TEE PER ANSI B16.9-------------------------------------------------------
*END REGION I--------------------------------------------------------
*BEGIN REGION 3------------
*OPER cards same as those for region I TRAN TRAN TRAN TRAN TRAN T RAN CA=201 CA=202 CA=203 CA=204 CA=205 CA=206 IS=1 IS=1 IS=1 IS=1 IS=l IS=1 FS=1 FS=1 FS=1 FS=I FS=1 FS=1 IT=70 FT=100 TT=1800 FL=200 IP=15 FP=1115 TP=1800 IT=100 FT=100 TT=0 FL=200 IP=1115 FP=65 TP=0 IT=100 FT=150 TT=16164 FL=200 IP=65 FP=1025 TP=16164 IT=150 FT=100 TT=0 FL=1377 IP=1025 FP=1025 TP=0 IT=100 FT=260 TT=0 FL=1377 IP=1025 FP=1025 TP=0 IT=260 FT=392 TT=1800 FL=9180 IP=1025 FP=1025 TP=1800 Page A8 of A38 FileNo.: VY-16Q-311 Revision:
0 F0306-OIRO Structural lntegrifty AssoCiates, Inc.TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN-TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN T RAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN CA=207 CA=208 CA=209 CA=210 CA=211 CA=212 CA=213 CA=214 CA=215 CA=216 CA=217 CA=218 CA=219 CA=2 20 CA=221 CA=222 CA=223 CA=224 CA=225 CA=226 CA=227 CA=228 CA=229 CA=230 CA=231 CA=232 CA=233.CA=234 CA=235 CA=236 CA=237 CA=2 38 CA=239 CA=240 CA=241 CA=242 CA=243 I3=1 I3=1 13=1 I3=1 IS= 1 13=1 I3=1 I 3=1 13=1 13=1 13=1 13=1 FS=1 FS=1 FS=1 FS=1 FS=I FS=1 FS=1 FS=1 FS=1 FS&#xfd;=I FS=1 FS=1 IT=392 FT=310 TT=900 FL=6885 .IP=1025 FP=1025 TP=900 IT=310 FT=392 TT=900 FL=6885 IP1=025 FP=1025 TP=900 IT=392 FT=280 TT=1800 FL=4590 IP=1025 FP=1025 TP=1800 IT=280 FT=392 TT=1800 FL=4590 IP=1025 FP=1025 TP=18Q0 IT=392 FT=265 TT=1800 FL=4590 IP=1025' FP=1025 TP=1800 IT=265 FT=90 TT=360 FL=1377 IP=1025 FP=1025 TP=360 IT=90 FT=265 TT=900 FL=1377 IP=1025 FP=1025 TP=900 IT=265 FT=392 TT=1800 FL=4590 IP=1025 FP=1025 TP=1800 IT=3.92 FT=265 TT=90 FL=9180 IP=1025 FP=1025 TP=90 IT=265 FT=392 TT=180 FL=9180 IP=1025 FP=1025 TP=180'IT=392 FT=275 TT=60 FL=10098,IP=1025 FP=1025 TP=60 IT=275 FT=100 TT=900 FL=275.4 IP=1025 FP=1025 TP=900 I I I I I I*IS=1 .FS=1 IT=265-FT=265 TT=O FL=200 IP1=025 FP=1025 TP=0*IS=1 FS=1 IT=265 FT=265 TT=0 FL=200 IP=1025 FP=1025 TP=0 IS=1 FS=1 IT=265 FT=150 TT=4140 FL=200 IP=1025 FP=1025 TP=414 IS=1 FS=1 IT=150. FT=150 TT=0 FL=200 IP=1025 FP=485 TP=0 IS=1 FS=1 IT=150 FT=150 TT=0 FL=200 IP=185 FP=103 TP=0 IS=1 FS=1 IT=150 FT=100 TT=8280 FL=200 IP=103 FP=65 TP=8280 IS=1 FS=1 IT=392 FT=392 TT=12 FL=200 IP=1025 FP=1205 TP=12 IS=1 FS=1 IT=392 *FT=50 TT=0 FL=3672 IP=1205 FP=1150 TP=0 IS=1 FS=1 .IT=50 FT=150 TT=1380 FL=200.IP=1150 FP=1150 TP=1380*IS=I FS=1 IT=150FT=150 TT=0 FL=200 IP=1150 FP=1150 TP=0 IS=1 FS=I IT=150 FT=50 TT=0 FL=2754 IP=1150FP=900 TP=0 IS=1 FS=1 IT=50 FT=150 TT=3060 FL=200 IP=900 FP=1075 TP=3060 IS=1 FS=1 IT=150 FT=150 TT=0 FL=200 IP=1075 FP=1150-TP=0 IS=1 FS=1 IT=150 FT=50 TT=0 FL=1560.6 IP=1150 FP=690 TP=0 IS=21 FS=1 IT=50 FT=150 TT=300 FL=200 IP=690 FP=690 TP=300 IS=1 FS=1 IT=150 FT=150 TT=8964 FL=200 IP=255 FP=1025 TP=8964 IS=1 FS=1 IT=392 FT=275 TT=60 FL=10098 IP=1025 FP=900 TP=60 IS=1 FS=1 IT=275 FT=100 TT=900 FL=275.4 IP=900 FP=65 TP=900 IS=1 FS=i IT=100 FT=100 TT=0 FL=200 IP=65 FP=1578 TP=0 IS=1 FS=1 IT=100. FT=100 TT=0 FL=200 IP=1578 FP=65 TP=0 IS=1 FS=1 IT=392 FT=392 TT=60 FL=10098 IP=1025 FP=1390 TP=.60 IS=1 FS=1 IT=392 FT=392 TT=900 FL=275.4 IP=1390 FP=955 TP=900 IS=1 FS=1 IT=392 FT=392 TT=900 FL=275.4 IP2=955 FP=1025 TP=900 IS=1 FS=1 IT=I00 FT=125 TT=60 FL=200 IP1=025 FP=1025 TP=60 IS=1 FS=1 IT=125 FT=150 TT=210 FL=200 IP=1025 FP=1025 TP=210 0 I I I I I FAIR CA=201 PAIR CA=202 PAIR CA=203 PAIR CA=204 PAIR CA=205 PAIR CA=206 PAIR CA=207 PAIR CA=208 PAIR CA=209 PAIR CA=210 PAIR CA=211 PAIR CA=212 PAIR CA=213 PAIR CA=214 PAIR CA=215 CO=27. 6 CO=2 7.6 CO=27.6 CO=27 .6 CO=27.6 CO=27.1 CO=27 .0 CO=27 .0 CO=27.1 CO=27. 1 CO=27 .1 CO=27. 6 CO=27 .6 CO=27 .1 CO=27. 1 DI=0. 521 DI=0. 512 DI=0. 504 DI=0. 504 DI=0. 490 DI=0. 446 DI=0 440 DI=0. 440 DI=0. 444 DI=0 444 DI0 .445 DI=0. 490 DI=0. 490 DI=0. 445 DI=0.445 DI=0.445 DI=0. 444 EX=6.4 EX=6.4 EX=6.4 EX=6.4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6.4 EX=6.4 EX=6. 4 EX=6. 4 EX=6 .4 EX=6. 4 EX=6. 4 EX=6.4 EX=6. 4 EX=6. 4*******7*******Tavg=85 Tavg=100 Tavg=125 Tavg=.125 Tavg=180 Tavg=326 Tavg=351 Tavg=351 Tavg=336 Tavg=336 Tavg=329 Tavg=178 Tavg=178 Tavg=329 Tavg=329 I I I I U I I PAIR CA=216 CO=27.1 PAIR CA=217 CO=27.1* Tavg=329* Tavg=334 File No.: VY- 16Q-311 Revision:
0 Page A9 of A38 F0306-01 RO 3 Structural IntegrityAssociates, Inc.PAIR CA=218 PAIR CA=219 PAIR CA=220 PAIR CA=221 PAIR CA=222 PAIR CA=223 PAIR CA=224 PAIR CA=225 PAIR CA=226 PAIR CA=227 PAIR CA=228 PAIR CA=229 PAIR CA=230 PAIR CA=231 PAIR CA=232 PAIR CA=233 PAIR CA=234 PAIR CA=235 PAIR CA=236 PAIR CA=237 PAIR CA=238 PAIR CA=239 PAIR CA=240 PAIR CA=241 PAIR CA=242 PAIR CA=243 CO=27. 6 CO=27 .3 CO=27. 3 CO=27. 6 CO=27. 6 CO=27. 6 CO=27 .6 CO-=26. 7 CO=27 .5 CO=27 .6 CO=27 .6 CO=27 .6 CO=27. 6 CO=27. 6 CO=27 .6 CO=27 .6 CO=27 .6 CO=27 -1 CO=27.6 CO=27 .6 CO=27. 6 CO=2 6. 7 CO=26. 7 CO:26. 7 CO=27 .6 CO=27. 6 DI=0.488 DI=0.463 DI=0.463 DI=0. 483 DI=0.496 DI=0 .496 DI=0. 504 DI=0 .430 DI=0. 478 mI=0. 5i2 DI=0.496 DI=0. 512 DI=0. 512 DI=0. 496 DI=0. 512 DI=0.512 DI=0.496 DI=0. 444 DI=0. 488 DI=0. 512 DI=0. 512 DI=0.430 DI=0.430 DI00.430 DI=0 '508 DI=0. 500 EX=6. 4 EX=6. 4 EX=6.4 EX=6.4 EX=6.4 EX=6.4 EX=6. 4 EX=6.4 EX=6. 4 EX=6. 4 EX=6.4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6.4 EX=6.4 EX=6.4-EX=6.4 EX=6.4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6.4 EX-6. 4 EX=6. 4 Tavg=188 Tavg=265 Tavg=265 Tavg=208 Tavg=150 Tavg=150 Tavg=125 Tavg=392 Tavg=221 Tavg=100 Tavg=150 Tavg=100 Tavg=100 Tavg=150 Tavg=100 Tavg=100 Tavg=150 Tavg=334 Tavg=188 Tavg=100 Tavg=100 Tavg=392 Tavg=392 Tavg=392 Tavg=ll3 Tavg=138*REGION III GEOMETRY CROS CD=1*JUNC PT=10 TANG PT=11 TANG PT=15 TANG PT=20 CROS CD=2 VALV PT=22 VALV PT=25 CROS CD=1 TANG PT=30 LUMP PT=30 TANG PT=38 TANG PT=40 TANG PT=45 CROS CD=2 VALV PT=47 VALV PT=50 CROS CD=1*TANG PT=55 TANG PT=55*BRAD PT=65 DZ.=-I EW=1 DZ=-4.17 DZ=-0 333 EW=1 *TA=I DZ=-1.333 PL=1 MA=2.7 *VALVE V2-27A DZ=-1.333 PL=2 EW=1 *TA=I DZ=-2, 792 MA=1.285 DZ=-4 6 DZ=-6. 317 DZ=-0. 625 EW=1 *TA=I DZ=-1.792 PL=1 MA=2.7 *VALVE V2-28A DZ=-1.792 PL=2 EW=1 *TA=I DZ=-2.791 EW=I DZ=-.791 EW=1 RA=2 SD=2 EW=1 Used this to determine midpoint viw .prd output BEND PT=60 X1=0 Y1=0 Z1=-.828 X2=0 Y2=.586 Z2=-.586 BEND PT=65 X1=0 YI=.586 ZI=-.586 X2=0 Y2=.828 Z2=0*TANG PT=67 DY=2.084 EW=1 *TA=1 TANG PT=67 DY=.084 CROS CD=2 VALV PT=70 DY=1.333 PL=1 MA=3.25 *VALVE V2-29A File No.: VY-16Q-311 Revision:
0 Page A1O of A38 F0306-OIRO SStructurallIntegrity Associates, Inc.VALV PT=75 DY=1.333 PL=2 EW=l *TA=1 CROS CD=3 TANG PT=78 DY=I.25 TANG PT=80 DY=3.5 TANG PT=82 DY=2.667 EW=I CROS CD=4 BRAD PT=85 RA=2 EW=I CROS CD=3 TANG PT=90 DX=2.875 TANG PT=95 DX=2.875 EW=I CROS CD=4 BRAD PT=100 RA=2 EW=I CROS CD=3.TANG PT=105 DX=1.12 DZ=-1.12 TANG PT=110 DX=3.477 DZ=-3.477 EW=1 CROS CD=4 TANG PT=115 DX=0.7071 DZ=-0.7071.EW=l
------------------------------------------
*END REGION III------------------------------------------
-----------------
*BEGIN REGION IV---------------
*OPER cards same as those for regions I and III I U I I I I I TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN CA=201 CA=202 CA=203 CA=204 CA=205 CA=206 CA=207 CA=208 CA=209 CA=210 CA=211 CA=212 CA=213 CA=214 CA=215 CA=216 CA=2 17 CA=218 CA=219 CA=220 CA=221 CA=222 CA=223 CA=224 CA=225 CA=226 CA=227 CA=228 CA=229 CA=230 CA=231 Is=1 I5=1 Is=1 Is=1 1s=1 I5=1 I.s=1 15=1 Is=1 IS=d Is=1 IS=l FS=I FS=I FS=I1 FS=I FS=1 FS-1 FS=I FS=I FS=I FSI IT=70 FT=100 TT=1800 FL=100 IP=15 FP=1115 TP=1800 IT=100 IT=100 IT=150.IT=100 IT=260 IT=392 IT=310 IT=392 IT=280 IT=392 IT=265 FT=100 FT=150 FT=100 FT=260 FT=392 FT=3 10 FT=392 FT=280 FT=392 FT=265 TT=0 FL=100 IP=1115 FP=65 TP=0 TT=16164 FPL=100 IP=65 FP=1025 TP=16164 TT=0 FL=688.5 IP=1025 FP=1025 TP=0 TT=O FL=688.5 IP=1025 FP=1025 TP=0 TT=1800 FL=4590 IP=1025 FP=1025 TP:1800 TT=900 FL=3442.5 IP=1025 FP=1025 TP=900 TT=900 FL=3442.5 IP=1025 FP=1025 TP=900 TT=1800 FL=2295 IP=1025 FP=1025 TP=1800 TT=1800 FL=2295 IP=1025 FP=1025 TP-1800 TT=1800 FL=2295 IP=1025 FP=1025 TP=1800 I I I I I I FT=90 TT=360 FL=688.5 IP=1025 F8=1025 TP=360 IS=I FS=I IT=90. FT=265 TT=900 FL=688.5 IP=1025 FP=1025 TP=900 IS=I FS=I IT=265 FT=392 TT=1800 FL=2295 IP=1025 FP=1025 TP=1800 IS=I FS=I IT=392 FT=265 TT=90 FL=4590 IP=1025 FP=1025 TP=90.IS=I FS=1 IT=265 FT=392 TT=180 FL=4590 IP=1025 FP=1025 TP=180 IS=l FS=1 IT=392 FT=275 TT=60 FL=5049 IP=1025 FP=1025 TP=60 IS=I FS=1 IT=275 FT=100 TT=900 FL=137.7 IP=1025 FP=1025 TP=900*IS= FS=1 IT=265 FT=265 TT=0 FL=100 IP=1025 FP=1025 TP=0*IS=1 FS=I IT=265 FT=265 TT=0 FL=100 IP=1025 FP=1025 .TP=0 IS=I FS=I IS=l FS=1 IS=1 FS=1 IS=I FS=I IS=I FS=I IS=I FS=1*IS=1 85=1 Is=i PS=I1*IS=I FS=I IS:I FS=I IS=I FS=1 IS=I FS=IT=265 FT=150 TT=4140 FL=100 IP=1025 FP=1025 TP=4140 IT=150 FT=150 TT=0 FL=I100-IP=1025 FP=185 TP=0 IT=150 FT=150 TT=0 FL=100 IP=185 FP=103 TP=0 IT=150 FT=100-TT=8280 FL=100 IP1=03 FP=65 TP=8280 IT=392 FT=392 TT=12 FL-100 IP=1025 FP=1205 TP=12 IT=392 FT=50 TT=0 FL=1836 IP=1205 FP=1150 TP=0 IT=50 FT=150 TT=1380 FL=i00 IP=1150 FP=1150 TP=1380 IT=150 FT=150 TT=0 FL=100 IP=1150 FP=1150 TP=0'IT=150 FT=50 TT=0 FL=1377 IP=1150 FP=900 TP=0 IT=50 FT=150 TT=3060 FL=100 IP=900 FP=1075 TP=3060 IT=150 FT=150 TT=0 FL=100 IP=1075 FP=1150 TP=0.I I I I I File No.: VY-16Q-311 Revision:
0 Page All of A38 F0306-O1RO structural Integrity Associates,, Inc.! Structural lntegrity AssoCiates, Inc.TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN CA=232 CA=233 CA=234 CA=23 5 CA=2 36 CA=237 CA=238 CA=239 CA=240 CA=2 41 CA=242 CA=243 IS=1 IS--I IS=1 IS=1 IS=1 IS=1 IS=1 IS=1 IS=1 IS=1 IS=1 IS=1 FS=-1 FS=1 FS=1 FS=1 FS=-1 FS=1 FS=1 FS=1 FS=1 FS=1 FS=1 FS=1 IT=150 FT=50 TT=0 FL=780.3 IP=I150 FP=690 TP=0 IT=50 FT=150 TT=300 FL=100 IP=690 FP=690 TP=300 IT=150 IT=392 IT=275 IT=100 IT=100 IT=392 IT=392 IT=392 IT=I00 IT=125 FT=150 FT=2 7 5 FT=100 FT=100 FT=100 FT=392 FT=392.FT=392 FT=125 FT=150 TT=8964 FL=100 IP=255 FP=1025 TP=8964 TT=60 FL=5049 IP=1025 FP=900 TP&#xfd;60 TT=900 FL=137.7 IP=900 FP&#xfd;65 TP=900 TT=0 FL=100 IP=65 FP=1578 TP=0 TT=0 FL=100 IP=1578 FP=65 TP=0 TT=60 FL=5049 IP=1025 FP=1390 TP=60 TT=900 FL=137.7 IP=1390 FP=955 TP=900 TT=900 FL=137.7 IP=955 FP=1025 TP=900 TT=60 FL=100 IP=1025 FP=1025 TP=60 TT=210 FL=100 IP=1025 FP=1025 TP=210 PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PATIR PAIR PAIR CA=201 CA=202 CA=203 CA=204 CA=205 CA=206 CA=207* CA=208 CA=209* CA=210 CA=211 CA=212 CA=213 CA=214 CA=215 CA=216 CA=217 CA=218 CA=219 CA=220 CA=221 CA=222 CA=223 CA=224 CA=225 CA=226 CA=227 CA=228 CA=229.CA=230 CA=231 CA=232 CA=233 CA=234 CA=235 CA=236 CA=237 CA=238 CA=239 CA=240 CA=241 CA=242 i CO=27.,6* CO=27.6 CO=27.6 CO=27.6 CO=27.1 CO=27. 0 CO=27 .0 CO=27 .1 CO=27. 1 CO=27.1 CO=27,.6 CO=27 .6 CO=27 .1 CO=27. 1 CO=27.1 CO=27. 1 CO=27 .6 CO=27 .3 CO=27 .3 CO=27 .6 CO=27 .6 CO=27. 6 CO=27..6 CO=26. 7 CO=27. 5 CO=27 .6 CO=27. 6 CO=27. 6 CO=27. 6 CO=27.6 CO=27.6 CO=27. 6 CO=27
* 6 CO=27. 1 CO=27. 6 CO=27. 6 CO=27.6 6 CO=2 6. 7 CO=26.7 7 CO=26.7 7 CO=27.6 6 DI=0.521 DI=0. 512 DI=0. 504 DI=0.504 DI=0.490 DI=0. 446 DI=0.440 DI=0. 440 DI=0 .444 DI=0 .444 DI=0. 445 DI=0.490 DI=0. 490 DI=0.445 DI=0 .445 DI=0. 445 DI=0.444 DI=0.488 DI=0. 463 DI=0 .463 DI=0.483 DI:0 .496 DI=0.496 DI=0.504 DI=0. 430 DI=0 .478 DI=0.512 DI=0. 496 DI=0. 512 DI=0.512 DI=0.496 DI=0. 512 DI=0. 512 DI=0.496 DI=0.444 DI=0. 488 DI=0.512 DI=0.512 DI=0. 430)I=0.430)I=0.430)I=0. 508 EX=6. 4 EX=6.4 EX=6.4 EX=6.4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6.4 EX=6. 4 EX=6. 4 EX=6.4 EX=6. 4 EX=6.4 EX=6.4 EX=6. 4 EX=6.4 EX=6. 4 EX=6.4 EX=6. 4 EX=6. 4 EX=6.4 EX=6.4 EX=6.4 EX=6.4 EX=6.4 EX=6.4 EX=6.4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6.4 EX-6. 4 EX=6. 4 EX=6. 4 EX=6.4 EX=6.4 EX=6.4 Tavg=85 Tavg=100 Tavg=125 Tavg=125 Tavg=180 Tavg=326 Tavg=351 Tavg=351 Tavg=336 T avg=336* Tavg=329 Tavg=178 Tavg=178 Tavg=329 Tavg=329.Tavg=329 Tavg=334 Tavg=188 Tavg=265 Tavg=265 Tavg=208 Tavg=150 Tavg=150 Tavg=125 Tavg=392 Tavg=221 Tavg=100 Tavg150 Tavg=100 Tavg=100 Tavg=150 Tavg=100 Tavg=100 Tavg=150 Tavg=334 Tavg=188 Tavg=100 Tavg=-100 EX=6. 4 EX=6 .4 EX=6.4 EX=6. 4****Tavg=392 Tavg=392 Tavg=392 Tavg=113 FileNo.: VY-16Q-311 Revision:
0 Page A12 of A38 F0306-O1RO AStructural Integrity Associates, Inc..PAIR CA=243 CO,=27.6 DI=0.500 EX--6.4
* Tavg=138*REGION IV GEOMETRY DOWNSTREAM OF FW brnCH TEE/REDUCER
-10 INCH PIPING*RUN FROM FW TEE TO ELBOW BEFORE NOZZLE NBA, NODE 275 CROS CD=4 TANG PT=170 DX=0.7071 DZ=-0.7071 EW=I ERED PT=I75 DX=0.825 DZ=-0.825 AN=30 CROS CD=5*RUN FROM FW TEE TO ELBOW BEFORE NOZZLE N4B, NODE 152 BEND PT=190 X1=4.813 Y1=0 Z1=-4.813 X2=1.283 Y2=0. Z2=-6.685 BEND PT=200 X1=0.449 Y1=0 Z1=-2.342 X2=-0.059 Y2=0 Z2=-2.384 STRU PT=201 DX=.198 DZ=.9802 STRU PT=202 DX=.198 DZ-.9802 ANCH PT=202 JUNC PT=200 I I I 3 I I I BEND TANG TANG TANG BRAD TANG TANG TANG BRAD TANG TANG PT==220 PT=225 PT=2 30 PT=2 35 PT=2 4 PT=~24 5 PT=~250 PT=255 PT=&#xfd;260 PT=&#xfd;265 PT=2 70 X1=-0.2196 DX=-0.3388 DX=-0. 3388 DX=-I. 002 RA= 1 .25 DX=-2. 693 DX=-2. 693 DX=-2. 693 RA=1. 25 DY=3.958 DY=3.959 Y1=0 ZI=-8.859 X2=-6.266 Y2=DZ=-0.3388 DZ=-0.3388 DZ=-1.002=0 Z2=-6.266 DY=3. 196 DY=3.196 DY=3. 196 DZ-=2. 693 DZ=2. 693 DZ=2. 693------------------------------------------------------------
*END 'REGION IV*---------------------------------------------------------
*BEGIN REGION IVa I I I I I I OPER OPER OPER OPER OPER OPER OPER OPER OPER OPER OPER OPER OPER OPER OPER OPER CA=3 CA=4 CA=5 CA=6 CA=7 CA=8 CA- 9 CA=10 CA=11 CA=12 CA=13.CA= 14 CA=15 CA=16 CA=17 CA=18 TE=283 PR=1010 TE=260 PR=I010 TE=392 PR=I010 TE=310 PR=1010 TE=280 PR=1010 TE=265 PR=1010 TE=90 PR=1010 TE=360 PR=1010.TE=225 PR=170 TE=210 PR=88 TE=450 PR=1190 TE=50 PR=i135 TE=247 PR=1135 TE=288 PR=1135 TE=247 PR=1060 TE=283 PR=1135 I I OPER CA=20 TE=200 PR=675 OPER CA=21 TE=275 PR=885 OPER CA=23 OPER CA=24 OPER CA=25 OPER CA=26 TE=392 PR=1375 TE=392 PR=940 TE=392 PR=1010 TE=275 PR=1010 File No.: VY-16Q-311 Revision:
0 Page A13 of A38 I F0306-0IRO
* ~JJStructural Integrity Associatesinc.
OPER CA=27 TE=323 PR=1010 OPER CA=30 TE=180 PR=1010 TRAN CA=201 IS=1 FS=1 IT=70 FT=100 TT=1800 FL=100 IP=15 FP21115 TP=1800 TRAN CA=202 IS=1 FS=1 IT=100 FT=100 TT=0 FL=100 IP=1115 FP=65 TP=0 TRAN CA=203 IS=1 FS=1 IT=100 FT=283 TT=16164 FL=100 IP=65 FP=1025 TP=16164 TRAN CA=204 IS=1 FS=1 IT=283 FT=10.0 TT=0 FL=688.5 IP=1I)25 FP=1025 TP=0 TRAN CA=205 IS=1 FS=1 IT=100 FT=260 TT=0 FL=688.5 IP=1025 FP=1025 TP=0 TRAN CA=206 IS=1 FS=1 IT=26.0 FT=392 TT=1800 FL=4590 IP=1025 FP=1025 TP=1800 TRAN CA-=207 IS=1 FS=1 IT=392 FT=310 TT=900 FL=3442.5 IP=1025 FP=1025 TP=900.TRAN CA=208 IS=1 FS=1 IT=310 FT=392 TT=9Q0 PL=3442.5 IP=1025 "P=1025 TP=900 TRAN CA=209 IS=1 FS=1 IT=392 FT=280 TT=1800 FL=2295 IP=1025 I P=1025 TP=1.800 TRAN CA=210. IS=1 FS=1 IT=280 FT=392 TT=1800 FL=2295 IP=1025 FP=1025 TP=1800 TRAN CA=211 IS=1 FS=1 IT=392 FT=265 TT=1800 FL=2295 IP=1025 FP=1025 TP=1800* TRAN CA=212 IS=1 FS=1 IT=265 FT=90 TT=360 FL=688.5 IP1=025 FP=1025 TP=360 TRAN CA=213 IS=1 FS=1 IT=90 FT=265 TT=900 FL=688.5 IP=1025 FP=1025 TP=900 TRAN CA=214 IS=1 FS=1 IT:265 FT=392 TT=1800 FL=2295 IP=1025 FP=1025 TP=1800 TRAN CA=215 IS=1 FS=1 IT=392 FT=265 TT=90 FL=4590 IP1=025 FP=1025 TP=90 TRAN CA=216 IS=1 FS=1 IT=265 FT=392 TT=180 FL=4590 IP=1025 FP=1025 TP=180 TRAN CA=217 IS=1 FS=1 IT=392 FT=275 TT=60 FL=5049 IP=1025 FP=1025 TP=60 TRAN CA=218 IS=1 FS=1 IT=275 FT=100 TT=900 FL=137.7 IP=1025 FP=1025 TP=900 TRAN CA=219 IS=1 FS=1 IT=265 FT=323 TT=0 FL=100 IP=1025 FP=1025 TP=0 TRAN CA=220 IS=1 FS=1 IT=323 FTP360 TT=3924 FL=100 IP=10-25 FP=1025 TP=3924 TRAN CA=221 IS=1 FS=1 IT=360 FT=283 TT=4140 FL=100 IP=1025 FP=1025 TP=4140 T TRAN CA=222 IS=1 FS=1 IT=283 FT=225 TT=6264 FL=100 IP=1025 FP=185 TP=6264 TRAN CA=223 IS=1 FS=1 IT=225 FT=210 TT=600 FL=100 IP=185 FP=103 TP=600 TRAN CA=224 IS=1 FS=1 IT=210 FT=100 TT=8280 FL=100 IP=103 FP=65 TP=8280 TRAN CA=225 IS=1.FS=I IT=392 FT=450 TT=12 FL=100 IP=1025 .FP=1205 TP=12 TRAN CA=226 IS=1 FS=1 IT=450 FT=50 TT=0 FL=1836 IP=1205 FP=1-150 TP=0 TRAN CA=227 IS=1 FS=1 IT=50 FT=247 TT=1380 FL=100 IP=1150 FP=1150 TP=1380 TRAN CA=228 IS=1 FS=1 IT=247 FT=288 TT=0 FL=100 IP=1150 FP=1150 TP=0 TRAN CA=229 IS=1 FS=1 IT=288 FT=50 TT=0 FL=1377 IP=1150 FP=900 TP=0 TRAN CA=230 IS=1 FS=1 IT=50 FT=247 TT=3060 FL=100 IP-900 FP=1075 TP=3060 TRAN CA=231 IS=1 FS=1 IT=247 FT=283 TT=0 FL=100 IP=1075 FP=1150 TP=0 TRAN CA=232 IS=1 FS=1 IT=283 FT=50 TT=0 FL=780.3 IP=1150 FP=690 TP=0 TRAN CA=233 IS=1 FS=1 IT=50 FT=200 TT=300 FL=I00 IP=690 FP=690 TP=300 TRAN CA=234 IS= FS=1 IT=200 FT=283 TT=8964 FL=100 IP=255 FP=1025 TP=8964 TRAN CA=235 iS=1 FS=1 IT=392 FT=275 TT=60 FL=5049 IP=1025 FP=900 TP=60 TRAN CA=236 IS=1 FS=1 IT=275 7T=100 TT=900 FL=137.7 IP=900 FP=65 TP=900 TRAN CA=237 IS=1 FS=1 IT=100 FT=100 TT=0 FL=100 IP=65 FP=1578 TP=0 TRAN CA=238 IS=1 FS=1 IT1=00 FT=100 TT=0 FL=100 IP=1578 FP=65 TP=0 TRAN CA=239 IS=1 FS=1 IT=392 FT=392 TT=60 FL=5049 IP=1025 FP=1390 TP=60 TRAN CA=240 IS=1 FS=1 IT=392 FT=392 TT=900 FL=137.7 IP=1390 FP=955 TP=900 TRAN CA=241 IS=1 FS=1 IT=392 FT=392 TT=900 FL=137.7 I2=955 FP=1025 TP=900 TRAN CA=242 IS=1 FS=1 IT=100 FT=180 TT=60 FL=100 IP=1025.FP=1025 TP=60 TRAN CA=243 IS=1 FS=1 IT=180 FT=283 TT=210 FL=100 IP=1025 FP=1025 TP=210 PAIR CA=201 CO=27.6 DI=0.521 EX=6.4
* Tavg=85 PAIR CA=202 CO=27.6 DI=0.512 EX=6.4
* Tavg--100 PAIR CA=203 CO=27.6 DI=0.488 EX=6.4
* Tavg=192 PAIR CA=204 CO=27.6 DI=0.488 EX=6.4
* Tavg=192 PAIR CA=205 CO=27.6 DI=0.490 EX=6.4
* Tavg=180 PAIR CA&#xfd;-206 CO=27.1 DI=0.446 EX=6.4
* Tavg=326 PAIR CA=207 CO=27.0 DI=0.440 EX=6.4
* Tavg=351 PAIR CA=208 CO=27.0 DI=0.440 EX=6.4
* Tavg=351 File No.: VY-16Q-311 Page A14 of A38 Revision:
0 F0306-0IRO I Structural Integrity Associates, Inc.PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR*PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR CA=20 CA=2.1 CA=211 CA=212 CA=213 CA=214 CA=215 CA=216 CA=217 CA=218 CA=219 CA=220 CA=221 CA=222 CA=223 CA=224 CA=225 CA=226 CA=227 CA=228 CA=229 CA=230 CA=231 CA=232 CA=233 CA=234 CA=235 CA=236 CA=237 CA=238 CA=239 CA=2 40 CA=241.CA=242 CA=243 9 CO=27.1 CO=27.1-CO=27.1 CO=27.6 CO=2 7.6 CO=27.1 CO=2 7 1 CO=27.1* CO=27.1 ICO=27 .6 CO=27 .2 CO=27 .0 CO=27.1 CO=27 ,4 CO=27 .5 CO=27 .6 CO=26.5 CO=27 .4 CO=27. 6 CO=2 7.3 CO=27.6 CO=27 .6 CO=27. 3 CO=27.6 CO=27. 6 CO=27 .4 CO=27 .1 CO=27. 6 CO=27. 6 CO=27. 6 CO=2 6.7 CO=26. 7 CO=26.7 CO=27. 6 CO=27.5 DI=0.444 DI=0.444 DI=0.445 DI=0.490 DI=0.490 DI=0.445 DI=0.445 DI=0.445 DI=0. 4.44 DI=0. 488 DI=0.455 DI=0. 442 DI=0.447 DI=0. 466 DI=0.479 DI=0.495 DI=0. 422 DI=0. 467 DI=0. 496 DI=0.462 DI=0.492 DI=0.4 96 DI=0.463 DI=0.493 DI=0. 504 0I=0.470 DI=0.444 DI=0.488 DI=0. 512 DI=0. 512 DI=0.430 DI=0. 430 DI=0.430 DI=0.499 DI=0.474 EX=6. 4 EX=6. 44 EX=6. 4 EX=6.4 EX=6. 4 EX=6.4 EX=6. 4 EX=6.4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6.4 EX=6.4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6 .4 EX=6.4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6..4 EX=6. 4 EX=6,4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6 .4 EX=6.4 Tavg=336, Tavg=336 Tavg=329 Tavg=178 Tavg=178 Tavg=-32 9 Tavg=329 Tavg&#xfd;329 Tavg=334 ,Tavg=188 Tavg=294 Tavg=&#xfd;342 Tavg&#xfd;322 Tavg=254 Tavg==218 Tavg=155 Tavg=421 Targ~=250-Tavg~=14 9 Tavg=268 Tavg4 69 Tavq=14 9 Tavg=265 Tavg=167 Tavg=125 Tavg~=242 TavgQ-334 Tavg=188 Tavg=100 Tavg=100 Tavg=392 Tavg~=392 Tavg~=392 Tavg~=140 Tavg=232 I I I I I I I I I I I TANG PT=275 DY=6.583 EW=0-----------------------------------------------------------
*END REGION IVa*----------------------------------------------------------
*BEGIN REGION IVb------------------------------------------------------------
OPER CA=3 TE=416 PR=1010 OPER CA=4 TE=260 *PR=I010 OPER CA=5 TE=392 PR=1010 OPER CA=6 TE=310 PR=1010 OPER CA=7 TE=280 PR=1010 OPER CA=8 TE=265 PR=1010 OPER CA=9 TE=90 PR=1010 OPER CA=f0 TE=454 PR=l010 OPER CA=11 TE=300 PR=170 OPER CA=12 TE=270 PR=88 OPER CA=13 TE=507 PR=1190 OPER CA=14 TE=50 PR=1135 I I I I I I I File No.: VY-16Q-311 Revision:
0 Page A15 of A38 F0306-0 1 RO Structural Integrity Associates, Inc..l Structural Integrity Associates, Inc.OPER OPER OPER OPER CA=15 CA=16 CA=17 CA=18 TE=343 PR=1135 TE=427 PR=1135 TE=343 PR=1060 TE=416 PR=1135 OPER CA=20 TE=250 PR=675 OPER CA=21 TE=275 PR=885 OPEF OPER OPER OPER OPER OPER TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN CA=23 CA=24 CA=25 CA=r26 CA=27 CA=30 CA=201 CA=202 CA=203 CA=204 CA=205 CA=2 06 CA=207 CA=208 CA=209 CA=210 CA=211 CA=212 CA=213 CA=214 CA=215 CA=216 CA=217 CA=218 CA=219 CA=2 20 CA=221 CA=2 22 CA=223 CA=224 CA=225 CA=226 CA=227 CA=2128 CA=229 CA=.230 CA=231 CA=232 CA=233 CA=234 CA=235 CA=2 36 CA=237 CA=238 CA=2 39 CA=240 0 CA=24 1 CA=242 TE=392 TE=392 TEI=392 TE=275 TE=382 TE=235 PR=1375 PR=940 PR=1010 PR=1010 PR=1010 PR=1010 Is=1 Is=1 IS=1:rs=1 IS=1 Is=l Is~=1 TS=1 IS=1 Is=1 Is=1 Is=1 IS=1 Is=1 Is=1 is--1 I3=1 Is=l 15=1 Is=1 Is=1 I S=l I5=1 I 3=1 I3=1 I S= 1 I S=l 13=11 13=1 IS=1 I S= 1 I S= 1 is=1 Is=1 I S=1 I S= 1 Is=1 I 3=1 Is=1 IS=1.I S= 1 I S= 1* FS=1 FS=1 FS=1 FS=1 FS=1 FS =1 FS=l FS=1 FS=1 FS=1 FS=1 FS=I1 FS=1 FS=1 FS=1 FS=1 FS=1 FS=1 FS=1 FS=1 FS=1 FS=1* FS=1 FS=1 FS=1 FS=1 FS=1 FS=I1 FS=1 FS=1 FS=1 FS=1 FS=1 FS=1 FS=I1 FS=1 FS=1 FS=1 FS=1 FS=I FS=1 FS=1 IT=70 IT=100 IT=100 IT=416 IT=100 IT=260 iT=392 IT=310 IT=392 IT=280 IT=392 IT=265 FT=100 TT=1800 FL=100 IP=15 FP=1115 TP=1800 FT=100 FT=416 FT=100 FT=260 FT=392 FT=310 FT=392 FT=2 80 FT=392 FT=265 TT=0 FL=100 IP=1115 FP=65 TP=0 TT=16164 FL=100 IP=65 FP=1025 TP=16,164 TT=0 FL=688.5 IP=1025 FP=1025 TP=0 TT=0 FL=688.5 IP=1025 FP=1025 TP=0 TT=1800 FL=4590 IP=1025 FP=1025 TP=1800 TT=900 FL=3442.5 IP=1025 FP=1025 TP=900 TT=900 FL=3442.5 IP=1025 FP=1025 TP=900 TT=1800 FL=2295 IP=1025 FP=1025 TP=1800 TT=1800 FL=2295 IP=1025 FP=1025 TP=1800 TT=1800 FL=2295 IP=1025 FP=1025 TP=1800 FT=90 TT=360 FL=688.5 IP=1025 FP=1025 TP=360 IT=90 FT=265 TT=900 FL=688.5 !P=1025 FP=1025 TP=900 IT=265 IT=392 IT=265 IT=392 IT=27.5 IT=265 IT=382 IT=4-54 IT=416 IT=300 IT=270 IT=392 IT=507 FT=392 FT=265 FT=392 FT=275 FT=100 FT=382 FT=454 FT=416 FT=300 FT=270 FT=I00 FT=507 TT=1800 FL.=2295 IP=1025 FP=1025 TP=I800 TT=90 FL=4590 IP=1025 FP=1025 TP=90 TT=180 FL=4590 IP=1025 FP=1025 TP=180 TT=60 FL=5049 IP=1025 FP=1025 TP=60 TT=900 FL=137.7 IP=1025 FP=1025 TP=900 TT=0 FL=100 IP=1025 FP=1025 TP=0 TT=3924 FL=100 IP=1025 FP=1025 TP=3924 TT=4140 FL=100 IP=I025 FP=1025 TP=4140.TT=6264 FL=100 IP=1025 FP=185 TP=6264 TT=600 FL=100 IP=185 FP=103 TP=600 TT=8280 FL=100 IP=l03 FP=65 TP=8280 TT=12 FL=100 IP=1025 FP=1205 TP=12 FT=50 TT=0 FL=1836 IP=1205 FP=1150 TP=0 IT=50 FT=343 TT=1380 FL=100 IP=1150 FP=1150 TP=1380 IT=343 FT=427 TT=0 FL=100 IP=1150 FP=1150. TP=0 IT=427 FT=50 TT=0 FL=1377 IP=1150 FP=900 TP=0 IT=50 FT=343 TT=3060 FL=100 IP=900 FP=1075 TP=3060 IT=343 FT=416 TT=0 FL=100 IP=1075 FP=1150 TP=0 IT=416 FT=50 TT=0 FL=780.3 IP=1150 FP=690 TP=0 IT=50 FT=250 TT=300 FL=100 IP=690 FP=690 TP=300 IT=250 FT=416 TT=8964 FL=100 IP=255 FP=1025 TP=8964 IT=392 FT=275 TT=60 FL=5049 IP=1025 FP=900 TP=60 IT=275 FT=100 TT=900 EL=137.7 IP=900 FP=65 TP=900 IT=100 FT=100. TT=0 FL=100 IP=65 FP=1578 TP=0 IT=100 FT=100 TT=0 FL=100 IP=1578 FP=65 TP=0 IT=392 FT=392 TT=60 FL=5049 IP=1025 FP=1390 TP=60 IT=392 FT=392 TT=900 FL=137.1 IP=1390 FP=955 TP=900 IT=392 FT=392 TT=900 FL=137.7 IP=955 FP=1025 TP=900 IT=100 FT=235 TT=60 FL=100 IP=1025 FP=1025 TP=60 Page A16 of A38 File No.: VY-16Q-311 Revision:
0 F0306-01 RO I Structural Integrity Associates, Inc.TRAN CA=243 IS=1 FS=I IT=235 FT=416 TT=210 FL=100 IP=1025 FP&#xfd;1025 TP=210 I I PAIR PAIF PAIR PAIF PAIF PAIF PAIF PAIF PAIF PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR C CA=20 R CA=202.CA=203 CA=204 CA=205.CA=206 CA=207 CA=208 CA=209 CA=210 CA=211 CA=212-CA=213 CA=214 CA=215 SCA=216 CA=217 CA=218 CA=219 CA=220 CA=221 CA=222 CA=223 CA=224 CA=225 CA=226 CA=2 27 CA=228 CA=229 CA=230 CA=231 CA=232 CA=233 CA=234 CA=235 CA=236 CA=237 CA=238 CA=239 CA=240 CA=241 CA=24 2 CA=24 3 1 CO=27.6 CO=27.6 3 CO=27.4 I CO=27.4 CO=27.6 CO=27.1 CO=27.0 CO=27.0 CO=27.1 CO=27.1* CO27.1 CO=27.6 CO=27.6 CO=27 .1 CO=27.1* CO=27.1 CO=27 .1 CO=27.6 CO=27. 1 CO=26.6 CO=26.4 CO=27. 0 CO=27..3 CO=27 .6 CO=26.3 CO=27 .3 CO=27 .6 CO=26.8 CO=27.4 CO=27 .6 CO=26.8 CO=27 .5 CO=27 .6 CO27.1 CO=27 .1 CO=27 .6 CO=27.6 CO=27.6 CO=26.7 CO=2 6.7 CO=26.7 CO0=27.6 CO=27. 1 DI=0. 521 DI=0.512 DI=0.46&#xfd;DI=0 .-46E DI=0.49C DI=0.44E DI=0. 44C DI=0. 440 DI=0.444 DI=0. 4 44 DI=0.445 DI=0 .490 DI=0. 490 DI=0.445 DI=0. 445 DI=0. 445 DI=0.444 DI=0. 488 DI=0.447 DI=0.423 DI=0. 418 DI=0.438 DI=0.457 DI=0.489 DI=0.413 DI=0.459 DI=0.487 DI=0.432 DI=0.471 DI=0.487 DI=0.433 DI=0.473 DI=0.496 DI=0.444 DI=0.444 DI=0.488 DI=0,512 DI=0. 512 DI=0 -430 DI=0.430 DI=0. 430 DI=0.492 DI=0.446* EX=6.4 EX=6.4 EX=6.4 EX=6.4 1 EX=6.4 EX=6.4 EX=6.4 EX=6.4* EX=6. 4 EX=6. 4 EX=6.4 EX=6.4 E X=6.4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6.4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6.4 EX=6. 4 EX=6. 4 EX=6 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6 .4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4********************-k********************Tavg=85 Tavg=100 Tavg=258 Tavg=258 Tavg=180 Tavg=326 Tavg=351 Tavg=351 Tavg=336 Tavg=336 Tavg=329 Tavg=178 Tavg=178 Tavg=329 Tavg=329 Tavg=329 Tavg=334 Tavg=188 Tavg=324 Tavg=418 Tavg=435 Tavg=358 Tavg=285 Tavg=185*Tavg=450 Tavg=279 Tavg=197 Tavg=385 Tavg=239 Tavg=197 Tavg=380 Tavg=233 Tavg=150 Tavg=333 Tavg=334 Tavg=188 Tavg=100 Tavg=100 Tavg=392 Tavg=392.Tavg=392 Tavg=168 Tavg=326 I I I I TANG PT=280 DY=6.583------------------------------------------------------------
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I I I OPER .CA=.3 OPER CA=4 TE=549 PR=1010 TE=260 PR=1010 FileNo.: VY-16Q-311 Revision:
0 Page A17 of A38 I I.F0306-OIRO I V.Structural Integrity Associates, Inc.OPER OPER OPER OPER OPER OPER OPER OPER OPER OPER OPER OPER OPER OPER CA=5.CA=6 CA=7 CA=8 CA=9 CA=10 CA=I1 CA=12 CA=13 CA= 14 CA=15 CA=16 CA=17 CA=18 TE=392 TE=310 TE=280 TE=265 TE=90 TE=549 TE=375 TE=330 TE=565 TE=50 TE=440 TE=565 TE=440 TE=54 9 PR=1010 PR=1010 PR=1010 PR=1010 PR=1010 PR=1010 PR=170 PR=88 PR=I190 PR=1135 PR=1135 PR=1135 PR=1060 PR=1135 OPER CA=20 TE=300 PR=675 OPER CA=21 TE=275 PR=885 OPEF OPER OPER OPER OPER OPER TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRPAN TRAN TRAN TRAN TRAN TRAIN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRPAN TRAN CA=23 CA=24 CA=25 CA=26 CA=27 CA=30 CA=201 CA=202 CA=203 CA=204 CA=205 CA=206 CA=2107 CA=2 08 CA=209 CA=210 CA=211 CA=212 CA=213 CA=214 CA=215 CA=216 CA=217.CA=218 CA=219 CA=220 CA=221 CA=222 CA=223 CA=224 CA=225 CA=226 CA=227 CA=228 CA=229 CA=230 CA=231 CA=232 TE=392 TE=392 TE=392 TE=275 TE=440 TE=290 PR=1375 PR=940 PR=1010 PR=1010 PR=1010 PR=1010 IS=I FS=I IS=I FS=I IS=I FS=1 IS=I FS=1 IS=1 FS=1 IS=1 FS=I IS=1 FS=1 IS=I FS=1 IS=l FS=I IS=I FS=I IS= FS=I IS=1 FS=I IS=I FS=1 IS=I FS=1 IS=1 FS=1 IS=1 FS=1 IS=I FSP=is=I Fs=I IS=1 FS=I I8=1 FS=1*IS=1 FS=I IS= FS=1 IS=1 FS=1 IS=1 FS=IS=1 FS=I IS=I FS=1 IS=1 FS=1 IS=1 FS=1 IS=1 FS=1 IS=I FS=1 IS=I FS=I IS=1 FS=I IT=70 IT=100 IT=100 IT=549 IT=100 IT=260 IT=392 IT=310 IT=392 IT=280 IT=392.IT=265 FT=100 TT=1800 FL=100 IP=15 FP=1115 TP=1800 FT=100 FT=54 9 FT=100 FT=260 FT=392 FT=3 10 FT=392 FT=280 FT=392 FT=265 TT=0 FL=100 IP=1115 FP=65 TP=0 TT=16164 FL=100 IP=65 FP=1025 TP=16164 TT=0 FL=688..5 IP=1025 FP=1025 TP=0 TT=0 FL=688.5 IP=1025 FP=1025 TP=0 TT=1800 FL=4590 IP=1025 FP=1025 TP=1800 TT=900 FL=3442.5 IP1=025 FP=1025 TP=900 TT=900 FL=3442.5 IP=1025 FP=1025 TP=900 TT=1800 FL=2295 IP=1025 FP=1025 TP=1800 TT=1800 FL=2295 IP=1025 FP=1025 TP=1800 TT=1800 FL=2295 IP=1025 FP=1025 TP=1800 FT=90 TT=360 FL=688.5 IP=1025 FP=1025 TP=360 IT=90 FT=265 TT=900 FL=688.5 IP=1025 FP=1025 TP=900 IT=265 FT=392 IT=392 IT=265 IT=392 IT=275 IT=265 IT=440 FT=265 FT=392 FT=275 FT=100 FT=440 FT=54 9 TT=1800 FL=2295 IP=1025FP=I025 TP=1800 TT=90 FL=4590 IP=1025 FP=1025 TP=90 TT180 FL=4590 IP=1025 FP=1025 TP=180 TT=60 FL=5049. IP=1025 FP=1025 TP=60 TT=900 FL=137.7 IP=1025 FP=1025 TP=900 TT=0 FL=100 iP=1025 FP=1025 TP=0 TT=3924 FL=100 IP=1025 FP=1025 TP=3924 1 IT=549 FT=549 TT=0 FL=100 IP=1025 FP=1025 TP=0 IT=549 FT=375 TT=6264 FL=100 IP=1025 FP=185 TP=6264 IT=375 FT=330 TT=600 FL=100 IP=185 FP=103 TP=600 IT=330 FT=100 TT=8280 FL=100 IP=103 FP=65 TP=8280 IT=392 FT=565 TT=12 FL=100 IP=1025 FP=1205 TP=12 IT=565 FT=50 TT=0 FL=1836 IP=1205 FP=1150 TP=0 IT=50 FT=440 TT=1380 FL=100 IP=1150=1FP:150 TP=1380 IT=440 FT=565 TT=0 FL=100 IP=1150 FP=1150 TP=0 IT=565 FT=50 TT=0 FL=1377 IP=1150 FP=900 TP=0 IT=50 FT=440 TT=3060 FL=100 IP=900 FP=1075 TP=3060 IT=440 FT=549 TT=0 FL=100 IP=1075 FP=1150 TP=0 IT=549 FT=50 TT=0 FL=780.3 IP=1150 FP=690 TP=0 File No.: VY-16Q-311 Revision:
0 Page A18 of A38 F0306-OIRO Structural Integrity Associates, Inc.TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN T RAN TRAN CA=233 CA=234 CA=235 CA=236 CA=237 CA=238 CA=239 CA=240 CA=241 CA=242 CA=243 I S=1 Ts=1 I S=1 TS=1 Is=1 Is=1 Is=1 Is=1 Is=1 Is=1 Is=1 FS=1 FS=1 FS=1 FS=1 FS=1 FS=1 FS=1 FS=1 FS=1 FS=1 IT=50 FT=300 TT=300 FL=100 IP=690 FP=690 TP=300 IT=300 FT=549 TT=8964 FL=100 IP=255 FP=1025 TP=8964 IT=392 FT=275 TT=60 FL=5049. IP=1025 FP=900 TP=60 IT=275 FT=100 TT=900 FL=137.7 IP=900 FP=-65 TP=900 IT=100 FT=100 TT=O FL=100 IP=65 FP=1578 TP=0 IT=100 FT=100 TT=0 FL=100 IP=1578 FP=65 TP-=0 IT=392 FTh392 TT=60 FL=5049 IP=1025 FP=1390 TP=60 IT=392 FT=392 TT=900 FL=137.7 IP=1390 FP=955 TP=900 IT=392 FT=392 TT=900 FL=137..7 IP=955 FP=1025 TP=900 IT=100 FT=290 TT=60 FL=100 IP=1025 FP=1025 TP=60 IT=290 FT=549 TT=210 FL=100 IP=1025 FP=1025 TP=210 I I I I I PAIT PAIF PAIT PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR.PAIR PAIR PAIR&#xfd;PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR ,CA=20 CA=20 CA=20: CA=204 CA=205 KCA=20 CA=207 CA=208 CA=209* CA=210*CA=211 CA=212 CA=213 CA=214 CA=215 CA=216 CA=217 CA=218 CA=219 CA=220 CA=221 CA=222 CA=223 CA=224*CA=225 CA=226 CA=227 CA=228 CA=229 CA&#xfd;2 30 CA=231 CA&#xfd;232 CA=233 CA=234 CA&#xfd;235 CA=236 CA=237 CA=238 CA=239 CA=240 CA=241 CA=242 CA=243 1 CO=227.6 2, CO=27. 6 3 CO=27. 1 4 CO=27.1 5 CO=27.6 6 CO=27.1 CO=27.0 3 CO=27.0 CO=27.1 CO=27.I CO=27.1 CO=27.6 3 CO=27.6 CO=27.1 CO=27.1 CO=27.1 7CO=27.1 CO=27 .6 CO=27.0 CO=2 5. 9 CO=2 5.5 CO=26.2 CO=27.0 CO=27 .5 CO=2 6.1 CO=27.2 CO=27.4 CO=25.9 CO=27.2 Co=27. 4 CO=25. 9.CO=27.2 CO=27L 6 CO=26.5 CO=27 .1 CO=27. 6 C0=27. 6 CO=27.6 CO=26. 7 CO=26.7 CO=26.7 CO=27.6 CO=26.5 DI=Q0.52:]
DI=0. 51, DI=0. 44 DI=0. 44*DI=0.49(DI=0. 44 (DIT=0.44C DI=0. 44C DI=0.444 DI=0.444 DI=0.445 mI=0. 4 9C DI=0. 49C DI=0. 445 DI=0. 445 DI=0.445 DI=0.444 DI=0. 488 DI=0.439 DI=0.400 DI=0.387 DI=0.409 DI=0.439 DI=0.480 DI=0.404 DI=0. 451 DI=0. 469 DI=0. 397 DI=0.451 DI=0 *469 DI=0 400 DI=0. 453 DI=0. 491 DI=0. 421 DI=0. 444 DI=0. 488 DI0=. 512 DI=0. 512 DI=0. 430 DI=0. 430 DI=0.430 DI=0.487 DI=0.422 L EX=6.4 EX=6.4 7 EX=6.4 7 EX=6.4 EX=6.4 EX=6.4 EX=6.4 EX=6.4 EX=6.4 EX=6. 4 EX=6.4 1 EX=6.4 EX=6.4* EX=6.4* EX=6.4 EX=6.4 EX=6.4 EX=6.4 EX=6. 4 EXI=6. 4 EX=6.4 EX= 6. 4 EX=6. 4 EX=6.4 EX=6.4 EX=6. 4 ,EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6.4 EX-6. 4 EX=-6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX= 6.4 Tavg=85 Tavg=100 Tavg=325 Tavg=325 Tavg=180 Tavg=326 Tavg=351 Tavg=351 Tavg=336 Tavg=336 Tavg=329 Tavg=178 Tavg=178 Tavg=329 Tavg=329 Tavg=329 Tavg=334 Tavg=188 Tavg=353 Tavg=495 Tavg=549 Tavg=462 Tavg=353 Tavg=215 Tavg=479 Tavg=308 Tavg=245 Tavg=503 Tavg=308 Tavg=245 Tavg=495 Tavg=300 Tavg=175 I I I I I I********+Tavg=425 Tavg=334 Tavg=188 Tavg=100 Tavg=100 Tavg=392 Tavg=392 Tavg=392 Tavg=195 Tavg=420 U I I I I File No.: VY-16Q-311 Revision:
0 Page A19 of A38 F0306-0IRO Vstructural Integrity Associates, Inc.BRAD PT=285 TANG PT=290 NOZZ PT=290 AMVT " CA=1 AMVT CA=2 I AMVT CA=3 I AMVT CA=4 I AMVT CA=5 AMVT CA=6 AMVT CA=7 I AMVT CA=8 I AMVT CA=9 I AMVT CA=1 I AMVT CA=11 I AMVT CA=12 F AMVT CA=13 F AMVT CA=14 F AMVT CA=15 F AMVT CA=16 F AMVT CA=17 F AMVT CA=18 P AMVT CA=19 P AMVT CA=20 P AMVT CA=21 P AMVT CA=22 P AMVT CA=23 P AMVT CA=24 P AMVT CA=25 P AMVT CA=26 P AMVT CA=27 P AMVT CA-28 P.AMVT CA-29 P AMVT CA=30 P AMVT CA&#xfd;31 P RA=1 .25 DX=-4,007 DZ=4.007 EW=1*NOZZLE N4A PT=290 PT-2 9 0 PT=290?T=290?T=290?T=290~T=290~T=290~T=290?T=290~T=290~T=,290~T=290~T=290~T=2.9 0 T=290 T=290 T=290 T=290 T=290 T=290 T=290 T=290 T=290 T=290 T=290 T=290 T=290 T=290 T=290 T=290 DX=O, 0196 DX=O. 0196 DX=0, 3130 DX=0. 3130 DX=0. 3130 DX=0. 3130 DX=0.3130 DX==0.3130 DX=0.3130 DX=0.3130 DX=O0.1993 DX=0. 1699 DX=0, 3234 DX=0. 3234 DX=0.3234 DX=0.3234 DX=0, 3169 DX=0. 3234 DX=0, 2823 bx=o0 2823 DX=0.3130 DX=0. 0196 DX=0.3463 DX=0.3064 DX=0.3130 DX=0. 3064 DX=0.31.30 DX==0.3130 DX=0.3064 DX=0.3130 DX=0. 3019 DY0.1069 DY=0. 1069 DY=1. 7 067 DY.=. 70 67 DY=1 ,7067 DY=1. 7067 DY=1 .7067 DY=1. 7067 DY=1.7067 DY=1. 7067 DY=1. 0867 DY=0. 9264 DY=I. 7637 DY=1. 7637 DY=1, 7637 DY=1. 7637 DY=1. 7281 DY=. 7637 DY=I. 5392 DY=1. 5392 DY=I, 7067 DY=0.1069 DY=1. 8884 DY=1. 6711 DY=1. 7067 DY=1. 6711 DY=1I 7067 DY=1, 7067 DY=1, 67 11 DY=1, 7067 DY=1. 6461 DZ=-0.0196 DZ=-0.0196 DZ=-0, 3130 DZ=-0. 3130 DZ=-0. 3130 DZ=-0. 3130 DZ=-0.3130 DZ=-0.3130 DZ=-0.3130 DZ=-0.3130 DZ=-0.1993 DZ=-0.1699 DZ=-0.3234 DZ=-0.3234 DZ=-0.3234.DZ=-0.3234 DZ=-0.3169 DZ=-0.3234 DZ=-0.2823 DZ=-0.2823 DZ=-0.3130 DZ=-0.0196 DZ=-0.3463 DZ=-0.3064 DZ=-0.3130 DZ=-0.3064 DZ=-0.313.0 DZ=-0.3130 DZ=-0.3064 DZ=-0.3130 DZ=-0.3019 AMVT CA&#xfd;32 PT=290 DX=-.09 DY=.015---------------------------
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*BEGIN REGION IV DZ=-.093 OPER OPER OPER OPER OPER OPER OPER OPER OPER OPER OPER OPER OPER OPER OPER CA=3 CA=4 CA=5 CA=6 CA=7 CA= 8 CA= 9 CA=10 CA11 CA=12 CA=13 CA=14 CA=16 CA=17 TE=150 TE=260 TE=392 TE=310 TE=280 TE=265 PR=1010 PR=1010 PR=1010 PR=1010 PR=1010 PR=1010.TE=90 PR=1010 TE=265 PR=1010 TE=150 PR=170 TE=150 PR=88 TE=392 PR=1190 TE=50 PR=1135 TE=150 PR=1135 TE=150 PR=1135 TE=150 PR=1060 File No.: VY-16Q-311 Revision:
0 Page A20 of A38 F0306-01 RO Structural Integrity Associates, Inc.OPER CA=18 TE=150 PR=1135 OPER CA=20 TE=150. PR=675 OPER CA=21 TE=275 PR=885 OPER OPER OPER OPER OPER CA=2 3 CA=2 4 CA=2 5 CA=26 CA=27 TE=392 TE=392 TE=392 TE=275 TE=265 PR=1375 PR=940 PR=1010 PR=1010 PR=1010 I I I I I I I OPER CA=30 TE=125 PR=1010 TRAt TRAP TRAN TRAP TRAN'TRAN TRAN TRAP'TRAN~TRAN'T RAN'TRAN TRAN T RAN TRAN T RAN T RAN TRAN TRAN T RAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN*TRAN TRAN TRAN T RAN TRAN TRAN TRAN TRAN TRAN T RAN TRAN TRAN N CA=201 N CA=202 1 CA=203 CA=204 CA=205 CA=206 CA=207 CA=208 CA=209 CA=210 CA=211 CA=212 CA=213 CA=214 CA=215 CA=216 CA=217 CA=218 CA=219 CA=220 CA=221 CA=222 CA==223 CA=224 CA=225 CA=226 CA=227 CA=228 CA=229 CA=2 30 CA=231 CA=232 CA=233 CA=234 CA=235 CA=236 CA=237 CA=238 CA=239 CA='240 CA=241 CA=242 2 CA=243 IS=IS=: is=I IS=I IS=I IS=I IS=I IS=I IS=I IS=1 IS=I1 IS=1 IS=1 IS=l IS=l IS=1 IS=I IS=1*IS=*IS=IS=l IS=]IS=l IS=I IS=I IS=I IS=I IS=I IS=I IS=I IS=I IS=I IS=I IS=I IS=I 1S=I IS=I IS:I IS=1 IS=I IS=1 IS=1 IS=1 1 FS=1 1 FS=1 1 FS=1 L FS=1 iFS=1 i FS=1! FS=1-FS=1-FS=1 FS=1 FS=1 FS=1 FS=1* FS=1* FS=1 FS=1[FS=I.FS=I1 1 FS=1 FS=: FS=1 FS=1 FS=1 FS=1* FS=1 FS=I FS=1 FS=1 FS=1 FS=I1 FS=1 FS=1 FS=1 FS=I FS=I FS=1 FS=I FS=I FS=I FS=I FS=I FS=1 FS=1 1 1~IT=70 FT=100 TT=18.00 FL=100 IP=15 FP=1115 TP=1800 IT=100 FT=100 TT=O FL=10.0 IP=1115 FP=65 TP=0 IT=100 FT=150 TT=16164 FL=100 IP=65 FP=1025 TP=16164 IT=150 FT=100 TT=0 FL=688.5 IP=1025 FP=1025 TP=0 IT=100 FT=260 TT=0 FL=688.5 IP=1025 FP=1025 TP=0 IT=260 FT=392 TT=1800 FL=4590 IP=1025 FP=1025 TP=1800 IT=392 FT=310 TT=900 FL=3442.5 IP=1025 FP=1025 TP=900 IT=310 FT=392 TT=900 FL=3442.5 IP=1025 FP=1025 TP=900 IT=392 FT=280 TT=1800 FL=2295 IP=1025 FP=I025 TP=1800 IT=280 FT=392 TT=1800 FL=2295 IP=1025 FP=4025 TP=1800 IT=392 FT=265 TT=1800 FL=2295 IP=1025 FP=1025 TP=1800 IT=265 FT=90 TT=360 FL=688.5 IP=1025 FP=1025 TP=360 IT=90 FT=265 TT=900 FL=688.5 IP=1025 FP=1025 TP=900 IT=265 FT=392 TT=1800 FL=2295 IP=1025 FP=1025 TP=1800 IT=392 FT=265 TT=90 FL=4590 IP=1025 FP=1025 TP=90 IT=265. FT=392 TT=180 FL=4590 IP=1.025.
FP=1025 TP=180 IT=392 FT=275 TT=60 FL=5049 IP=1025 FP=1025 TP=60 IT=275 FT=100 TT=900 FL=137.7 IP=I025 FP=102.5 TP=900 IT=265 FT=265 TT=0 FL=100 IP=1025 FP=1025 TP=0 IT=265 FT=265 TT=0 FL=100 IP=1025 FP=1025 TP=0 U I I I I I IT=265 IT=150 IT=150 IT=f150 IT=392 IT=392 FT=150 TT=4140 FL=100 IP=1025 FP=1025 TP=4140 FT=150 TT=0 FL=100 IP=1025 FP=185 TP=0 FT=150 TT=0 FL=100 IP=185 FP=103 TP=0 FT=100 TT=8280 FL=100 IP=103 FP=65 TP=8280 FT=392 TT=12 FL=100 IP=1025 FP=1205 TP=12 FT=50 TT=0 FL=1836 IP=1205 FP=1150 TP=0 IT=50 FT=150 TT=1380 FL=100 IP=1150 FP=1150 TP=1380 IT=150 FT=150 TT=0 FL=100 IP=1150 FP=1150 TP=0 IT=150 FT=50 TT=0 FL=1377 IP=1150 FP=900 TP=0 IT=50'FT=150 TT=3060 FL=100 IP=900 FP=1075 TP=3060 IT=150 FT=150 TT=0 FL=100 IP=1075 FP=1150.TP=0 IT=150 FT=50 TT=0 FL=780.3 IP=1150 FP=690 TP=0 TT=50 FT=150 TT=300 FL=100 IP=690 FP=690 TP=300 IT=150 IT=392 IT=275 IT=100 IT=100 IT=392 IT=392 IT=392 IT=100 IT=125 FT=150 FT=275 FT=100 FT=100 FT=100 FT=392 FT=392 FT= 392 FT=125 FT=150 TT=8964 FL=l00 IP=255 FP=1025 TP=8964 TT=60 FL=5049 IPI1025 FP=900 TP=60 TT=900 FL=137.7 IP=900 FP=65 TP=900 TT=0 FL=100 IP=65 FP=1578 TP=0 TT=0 FL=100 IP=1578 FP=65 TP=0 TT=60 FL=5049 IP=1025 FP=1390 TP=60 TT=900 FL=137.7 IP=1390 FP=955 TP=900 TT=900 FL=137.7 IP=955 FP=1025 TP=900 TT=60 FL=100 IP=1025 FP=1025 TP=60 TT=210 FL=100 IP=1025 FP=1025 TP=210 I I I I File No.: VY- 16Q-31 1 Revision:
0 Page A21 of A38 I I F0306-0 I RO UStructural Integrity Associates, inc.*k PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR CA=201 CA=202 CA=203 CA=2 04 CA=205 CA=206 CA=2 07 CA=2 08 CA=209 CA=210 CA=211 CA=212 CA=213 CA=214 CA=215 CA=216 CA=217 CA=218 CA=219 CA=220 CA=221 CA=222 CA=223 CA=224 CA=225 CA=226 CA=227 CA=228 CA=229 CA=230 CA=231 CA=232 CA=233 CA=234 CA=2 35 CA=236 CA=2 37 CA=238 CA=239 CA=240 CA=241 CA=2 42 CA=243* CO=27.6* CO=27.6 CO=27.6* CO=27.6 CO=27.6 CO=27.1 CO=27.0 CO=27 0 CO=27.1 CO=27 .1 CO=27. 1 CO=27 .6 CO=27. 6 CO=27 .1 CO=27. 1 CO=27. 1 CO=27. 1 CO=27- 6 CO=27. 3 CO=27. 3.CO=27. 6 CO=27. 6 CO=27. 6 CO=27 .6 CO=26. 7 CO=27 .5 CO=27. 6 CO=27 .6 CO=2 7.6 CO=27 .6 CO=27. 6 CO=27 .6 CO=27. 6 CO=27. 6 CO=27. 1 CO=27. 6 CO=27. 6 CO=27 .6 CO=2 6.7 CO=26.7 CO=2 6. 7 CO=27. 6 CO=27. 6 DI=0. 521 DI=0. 512 DI=0.504 DI=0 .504 DI=0.490 DI=0.446 DI=0. 440 DI=0. 440 DI=0.444 DI=0. 444 DI=0. 445 DI=0.490 DI=0*490 DI=0.445 DI=0.445 DI=0.445 DI=0. 444 DI=0.488 DI=0. 463 DI=0.463 DI=0.483 DI=0. 496 DI=0.496 DI=0 .504 DI=0. 430 DI=0 .478 DI=0. 512 DI=0. 496 DI=0. 512 DI=0. 512 DI=0. 496 DI=0 512 DI=0. 512 DI=0 496 DI=0. 444 DI=0. 4.88 DI=0.512 DI=0. 512 DI=0.430 DI=0.430 DI=0. 430 DI=0. 508 DI=0.500 EX=6. 4 EX=6. 4 EX=6.4 EX=6. 4 EX=6. 4 EX=6.4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6.4 EX=6. 4 EX=6.4 EX=6. 4 EX=6.4 EX=6.4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6.4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6.4 EX=6. 4 EX=6.4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6.14 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 Tavg=85 Tavg=100 Tavg=125 Tavg=125 Tavg=180 Tavg=326 Tavg=351 Tavg=351 Tavg=336 Tavg=336 Tavg=329 Tavg=178 Tavg=178 Tavg=329 Tavg=329 Tavg=329 Tavg=334 Tavg=188 Tavg=265 Tavg=265 Tavg=208 Tavg=150 Tavg=150 Tavg=125 Tavg=392 Tavg=221 Tavg=100 Tavg=l50 Tavg=100 Tavg=100 Tavg=150 Tavg=100 Tavg=100 Tavg=150 Tavg=334 Tavg=188 Tavg=100 Tavg=100 Tavg=392 Tavg=392 Tavg=392 Tavg=113 Tavg=138*REGION IV GEOMETRY DOWNSTREAM OF FW brnCH TEE/REDUCER
-10 INCH PIPING*RUN FROM FW TEE TO ELBOW BEFORE NOZZLE N4A, NODE 155 JUNC PT=115 CROS CD=5 BRAN PT=120 DX=-0.5022 DY=0.596 DZ=-0.5022 TE=1 EW=1 TANG PT=125 DX=-2.594 DY=3.078 DZ=-2.594 TANG PT=130 DX=-2.594 DY=3.078 DZ=-2.594 TANG PT=135 DX=-2.594 DY=3.078 DZ=-2.594 EW=0 File No.: VY-16Q-311 Revision:
0 Page A22 of A38 F0306-01 RO Structural Integrity Associates, Inc.BRAD PT_1 4 0 RA= 1. 25 EW=O0 TANG PT=1 42 DY=-4 TANG PT=145 DY=4 TANG PT=150. DY=2. 53------------------------------------------------------------------------------------------------------------
*END REGION IV*-----------------------------------------------------------------------------------------------------------
*BEGIN REGION IVa*------------------------------------------------------------------------------------------------------------
I I I I I OPER OPER OPER OPER OPER OPER OPER OPER OPER OPER OPER OPER OPER OPER OPER OPER CA=3 CA=4 CA=5 CA=6 CA=7 CA=8 CA= 9 CA=10 CA=11 CA=12 cA=I 3 CA=14 CA- 15 CA=16 CA=17 CA=18 TE=283 PR=1010 TE=260 PR=1010 TE=392 PR=1010 TE=310 PR=1010 TE=280 PR=1010 TE=265 PR=1010 TE=90 PR=1010 TE=360 PR=1.010 TE=225 PR=170 TE=210 F.R=88 TE=450 PR=1190 TE=50 PR=1135 TE=247 PR=1135 TE=288 PR=1135 TE=247 PR=1060 TE=283 PR=1135 I U I I I I I OPER CA=20 TE=200 PR=675 OPER CA=21 TE=275 PR=885 OPER CA=23 TE=392 PR=1375 OPER CA=24 TE=392 PR=940 OPER CA=25 TE=392 PR=1010 OPER CA=26 TE=275 PR=1010 OPER CA=27 TE=323 PR=1010 OPER CA=30TE=180 PR=1010 TRAN CA=201 TRAN CA=202 TRAN CA=203 TRAN CA=204 TRAN CA=205 TRAN CA=206 TRAN CA=207 TRAN CA=208 TRAN CA=209 TRAN CA=210 TRAN CA=211 TRAN .CA=212 TRAN CA=213 TRAN CA=214 TRAN CA=215 TRAN CA=216 TRAN CA=217 TRAN CA=218 TRAN CA=219 TRAN CA=220 I5=1 I5=4 I5=1.1S=1 I5=1 IS=1 IS=1 15=1 15=1 IS=1 15=1 15=1 IS=1 I5=1 IS=1 I*5=1 I5=1 I5=1 15=1 I5=1 FS=1 FS=1 FS=1 FS=I FS=I FS=I FS=I.FS=I1 FS=I FS=I FS=I F.S=I FS=I FS=I FS=I FS=I1 FS=I FS=I FS=1 FS=1 IT=70 FT=100 TT=1800 FL=100 IP=15 FP=1115 TP=1800 IT=100 FT=10 IT=100 FT=28 IT=283 FT=10 IT=100 FT=26 IT=260 FT=39 IT=392 FT=31 IT=310 FT=39 IT=392 FT=28 IT=280 FT=39;IT=392 FT=26.IT=265 FT=90 IT=90 FT=265 IT=265 FT=39 IT=392 FT=26[IT=265 FT=39 IT=392 FT=27[IT=275 FT=10(IT=265 FT=32[IT=323 FT=36(0 3 0 0 2 0 2 0 2 5 TT=0 FL=100 IP=1115 FP=65 TP=0 TT=16164 FL=100 iP=65 FP=1025 TP=16164 TT=0 FL=688.5 IP=1025 FP=1025 TP=0 TT=O FL=688.5 IP=1025 FP=10.25 TP=0 TT=1800 FL=4590 IP1=025 FP=1025 TP=1800 TT=900 FL=3442.5 IP1I025 FP=1025 TP=900 TT=900 FL=3442.5 IP=1025 FP=1025 TP=900 TT=1800 FL=2295 IP=1025 FP=1025 TP=1800 TT=1800 FL=2295 IP=I025 FP=1025 TP=1800 TT=1800 FL=2295 IP=1025 FP=1025 TP=1800 I I I I I TT=360 FL=688.5 IP-1025 FP=1025 TP=360 TT=900 FL=688.5 IP=1025 FP=1025 TP=900 2 5 2 TT=1800 FL=2295 IP=1025 FP=1025 TP=1800 TT=90 FL=4590 IP=1025 FP=1025 TP=90 TT=180 FL=4590 IP=1025 FP=1025 TP=180 TT=60 FL=5049 IP=1025 FP=1025 TP=60 TT=900 FL=137.7 IP=1025 FP=1025 TP=900 TT=0 FL=100 IP=1025 2P=1025 TP=0 TT=3924 FL=100 IP=1025 FP=1025 TP=3924 FileNo.: VY-16Q-311 Revision:
0 Page A23 of A38 I I F0306-0 IRO
* Structural IntegrityAssociates, Inc.TRAN CA=221 TRAN CA=222 TRAN CA=223 TRAN CA=22.4 TRAN CA=225 TRAN CA=226 TRAN CA=227 TRAN CA=228 TRAN CA=229 TRAN CA=230 TRAN CA=23.1 TRAN CA=232 TRAN CA=233 TRAN CA=234 TRAN CA=235 TRAN CA=236 TRAN CA=237 TRAN CA=-238 TRAN CA=239 TRAN CA=240 TRAN CA=241 TRAN CA=242 TRAN CA=243 Is=l IS= 1 1 S= 1 I5=i IS=1 Is=1 Is=.1 IS=1 Is=1 Is= 1 Is=-1 Is=1 IS=1.Is=1 Is=1 IS=1 I S= 1 Is=1 I S=1 IS=4.I5=4 Is=1 Is=1 FS=1 FS=1 FS=1 FS=1 FS=1 FS=1 FS=I FS=I1 FS=T FS=I FS=I FS=I FS=I FS=I FS=I FS=I FS=I FS=I FS=1 FS=I FS=I FS=I.IT=360 FT=283 TT=4140 FL=100 IP=1025 FP=1025 TP=4140 IT=283 FT=225 TT=6264 FL=100 IP=1025 FP=185 TP=6264 IT=225 FT=210 TT=600 FL=100 IP=185 PP=103 TP=600 IT=210 FT=100 TT=8280 FL=100 IP=103 FP=65 TP=8280 IT=392 FT=450 TT=12 FL=100 IP=1025 FP=1205 TP=12 IT=450 FT=50 TT=0 FL=1836 IP=1205 FP=1150 TP=0.IT=50 FT=247 TT=1380 FL=100 IP=1150 FP=1150 TP=1380 IT=247 FT=288 TT=0 FL=100 .IP=1150 FP=1150 TP=0 IT=288 FT=50 TT=0 FL=1377 IP=1150 FP=900 TP=0 IT=50 FT=247 TT=306.0 FL=100 IP=900 FP=1075 TP=3060 IT=247 FT=283 TT=0 FL=100 IP=1075 FP=1150 TP=0 IT=283 FT=50 TT=0 FL=780.3 IP=1150 FP=690 TP=0 IT=50 Ff=200 TT=300 FL=100 IP=690 FP=690 TP=300 IT=200 FT=283 TT=8964 FL=100 IP=255 FP=1025 TP=8964 IT=392 FT=275 TT=60 FL=5049 IP=1025 FP=900 TP=60 IT=275 FT=100 TT=900. FL=137.7 IP=900 FP=65 TP.=900 IT=100 FT=100 TT=0 FL=100 IP=65 FP=1578 TP=0 IT=100 FT=100 TT=0 FL=100 IP=1578 FP=65 TP=0 IT=392 FT=392 TT=60 FL=5049 IP=1025 FP=1390 TP=60 IT=392 FT=392 TT=900 FL=137.7 IP=1390 FP=955 TP=900 IT=392 FT=392 TT=900 FL=137.7 IP=955 FP=1025 TP=900 IT=100 FT=180 TT=60 FL=100 IP=1025 FP=1025 TP=60 IT=180 FT=283 TT=210 FL=100 IP=1025 FP=1025 TP=210 PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR*PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR CA=201 CA=202 CA=203 CA=204 CA=205 CA=206 CA=207 CA=208 CA=209 CA=2 10 CA=211 CA=212 CA=213 CA=214 CA=215 CA=216 CA=217 CA=218 CA=219 CA=2 20 CA=221 CA=222 CA=223 CA=224 CA=225 CA=226 CA=227 CA=228 CA=229 CA=230 CA=231 CO=27. 6 CO=27. 6 CO=27. 6 C0=27. 6 C0=27. 6 CO=27. 1 CO=27. 0 CO=27.0 CO=27.1 CO=27. 1 CO=27. 1 CO=27. 6 CO=27.6.CO=27. 1 C0=27-.I CO=27.1 CO=27.1 CO=27. 6 CO=27 .2 CO=27.0 C0=27. 1 CO=27.4 CO=27.5 CO=27. 6 CO=26.5 CO=27. 4 CO=27. 6 CO=27.3 CO=27.6 CO=27. 6 CO=27.3 DI=0. 521 DI=0.512 DI=0. 488 DI=0. 488 DI=0.490 DI=0. 446 DI=0. 440 DI=0.440 0I=0.444 DI=0.444 DI=0.445 DI=0.490 DI=0.490 DI=0.445 DI=0.445 DI=0.445 DI=0.444 DI=0.. 488 DI=0. 455 DI=0.442 DI=0. 447 DI=0.466 DI=0.479 DI=0.4 95 DI=0.422 DI=0. 467 DI=0. 496 DI=0. 462 DI=0. 492 DI=0.496 DI=0. 463 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6 .4 EX=6. 4 EX=6. 4 EX=6 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX-6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6.4 EX=6.,4 EX=6. 4 EX=6. 4 EX=6.4 Tavg=85 Tavg=100 Tavg=192 Tavg=192 Tavg=180 Tavg=326 Tavg=351 T avg=351 Tavg=336 Tavg=336 Tavg=329 Tavg=178 Tavg=178 Tavg=329 Tavg=329 Tavg=329 Tavg=334 Tavg=188 Tavg=294 Tavg=342 Tavg=322 Tavg=254 Tavg=218 Tavg=155 Tavg=421 Tavg=250 Tavg=149 Tavg=268 Tavg=169 Tavg=149 Tavg=265 File No.: VY-16Q-311 Revision:
0 Page A24 of A38 F0306-01RO VStructural Integrity Associates, Inc.PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAI R PAIR C2&#xfd;=232 CA=2 3 3 CA=23 4 CA=2 35 CA=236-CA=23 7 C A=2 3 8 CA=2 39 CA=2 40 GA=24 1 CA2 4 2 CA=24 3 CO=27. 6 CO=27 .6 CO=27 .4 CO=27. 1 CO=27.6 CO=27.6 CO=27. 6 CO=26. 7 CO=2 6.7 CO=2 6.7 CO=27. 6 CO=2 7.5 DI=0.493 DI=0 .504 DI=0.470 DI=0 444 DI=0.488 DI=0.512 DI=0.512 DI=0. 430 DI=0.430 DI=0. 430 DI==0.499 DI=. 474 EX=6. 4 EX=6.4 EX=6. 4 EX=6. 4 EX=6.4 EX=6.4.EX=6. 4 EX=6.4 EX=6.4 EX=6.4 EX=6.4 EX=6. 4************Tavg=167 Tavg=125 Tavg=242 Tavg=334 Tavg=188 Tavg=100 Tavg=100 Tavg=39.2 Tavg=392 Tavg=392 Tavg=140.Tavg=232 I U I I TANG PT=152 DY=6.53 EW=0------------------------------------------------------------
*END REGION IVa*BEGIN REGION IVb------------------------------------------------------------
OPER OPER OPER OPER OPER OPER OPER OPER OPER OPER OPER OPER OPER OPER OPER OPER CA=3 CA=4 CA=5 CA=6 CA=7 CA=8 CA= 9 CA=10 CA=f1 CA=12 CA=I 3 CA=14 CA=15 CA=16 CA=17 CA=18 TE=416 TE=260 TE=392 TE=310 TE=280 TE=265 TE=90 TE=454 TE=300 TE=270 TE=507 TE=50 TE=343 TE=427 TE=343 TE=416 PR=1010 PR=I010 PR=1010 PR=1010 PR=1010 PR=1010 PR=1010 PR=I010 PR=170 PR=88 PR=1190 PR=1135 PR=1135 PR=1135 PR=1060 PR=1135 I I I I I I OPER CA=20 TE=250 PR=675 OPER CA=21 TE=275 PR=885 OPER OPER OPER OPER OPER OPER TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN CA=23 CA=2 4 CA=2 5 CA=26 CA=27 CA=30 CA=201 CA=202 CA=203 CA=204 CA=2 05 CA=206 CA=207 CA=208 CA=209 TE=392 TE=392 TE=392 TE=275 TE=382 TE=235 PR=1375 PR=94 0 PR=1010 PR=1010 PR=1010 PR=1010 IS=I IS=1 IS=1 IS=I I S= 1 IS=l IS=I IS=1 IS=1 IS=1 FS~1 FS~=1 FS~=1 Ps~=1 FS=1 FS= 1 FS~1 Ps 1 PS~1 IT=&#xfd;70 I T= 100 IT=100 IT=416 IT=100 IT=260 IT=~392'ITh310 IT=392 E'T&#xfd;100 TT=4800 FN=100 IP=&#xfd;15 FP=1115 TP=1800 FT=100 FT=416 FT=100 FT~=260 FT= 392 FTh310 FT=~392 FT=280 TT=O FL=100 IP=1115 FP=65 TP~=0 TT=16164 FL-100 IP=65 FP=1025 TP=16164 TT=0 E'D=688.5 IP=1025 FP=l025 TP=0 TT=0O FL=688.5 IP==1025 EP=~1025 TP=0 TT=1800 FL=4590 IP=1025 FP=1025 TPh=1800 TT=900 FL=3442.5 IP=~1025 FP=~1025 TP=900 TT=900 FL=3442.5 IP=1025 FP=1025 TP~=900 TT=1800'FEL=22.95 IP=1025 FP=1025 TP=1800 I I I I I I File No.: VY-16Q-311 Revision:
0 Page A25 of A38 F0306-0 IRO Structural Integrity Associates, Inc.TRAN CA=210 TRAN CA=211 TRAN CA=212 TRAN CA=213 TRAN CA=214 TRAN.CA=215 TRAN CA=216 TRAN CA=217 TRAN CA=218 TRAN CA=219 TRAN CA=220 TRAN CA=221 TRAN CA'=222 TRAN CA=223 TRAN CA=224 TRAN CA=225 TRAN CA=226 TRAN CA=.227 TRAN CA=228 TRAN CA=229 TRAN CA=230 TRAN CA=231 TRAN CA=232 TRAN CA=233 TRAN CA=234 TRAN CA=235 TRAN CA=236 TRAN CA=237 TRAN CA=238 TRAN CA=239 TRAN CA=240 TRAN CA=241 TRAN CA=242 TRAN CA=243 1s=1 IS=1 Is=1 1S=1 15=1 I5=1 IS=1 I 5=1 15=1 IS=1 I5=1 I5=1 15=1 IS=1 15=1 15=1 I5=1 15=1 IS=1 I 5=1 1S=1 15=1 15=1 IS=1 I5=1 I S= 1 I5=1 1S=1*15=1 IS=1 I 5=1 IS =1*IS=1 IS=1 FS=1 FS=1 FS=1 FS=1 FS=1 FS=1 FS=1 FS=1 FS=1 FS=1 FS=1 FS=1 FS=1 FS=I FS=I FS=1 FS=1 FS=1 FS=1 FS=I FS=1 FS=1 FS=1 FS=1 FS=1 FS=I FS=1 FS=I FS=1 FS=I FS=1 FS=I FS=1 FS=1 IT=280 FT=392 TT=1800 FL=2295 IP=1025 FP=1025 TP=18 IT=392 FT=265 TT=1800 FL=2295 IP=1025 FP=1025 TP=18 IT=265 FT=90 TT=360 FL=688.5 IP=1025 FP=1025 TP=360 IT=90 FT=265 TT=900 FL=688.5 IP=1025 FP=1025 TP=900 IT=265 FT=392 TT=1800 FL=2295 IP=1025 FP=1025 TP=18 IT=392 FT=265 TT=90 FL=4590 IP=1025 FP=1025 TP=90 IT=265 FT=392 TT=180 FL=4590 IP=1025 FP=I025 TP=180 IT=392 FT=275 TT=60 FL=5049 IP=1025 FP=1025 TP=60 IT=275 FT=100 TT=900 FL=137.7 IP=1025 FP=1025 TP=90 IT=265 FT=382 TT=0 FL=100 IP=1025 FP=1025 TP=0 IT=382 FT=454 TT=392,4 FL=100 IP=1025 FP1025 TP=392 IT=454 FT=416 TT=4140 FL=100 IP=1025 FP=1025 TP=414 IT=416 FT=300 TT=6264 FL=100 IP=1025 FP=185 TP:6264 IT=300 FT=270 TT=600 FL=100 IP=185 FP=103 TP=600 IT=270 FT=100 TT=8280 FL=100 IP=103 PP=65 TP=8280 IT=392 FT=507 TT=12 FL=100 IP=1025 FP=1205 TP=12 IT=&#xfd;507 FT=50 TT=0'FL=I836 IP=1205 FP=1150 TP=0 IT=50 FT=343 .TT=1380 FL=100 IP=1150 FP=1150 TP=1380 IT=343 FT=427 TT=0 FL=100 IP=1150 FP=1150 TP=0 IT=427 FT=50 TT=0 FL=1377 IP=1150 FP=900 TP=0 IT=50 FT=343 TT=3060 FL=100 IP=900 FP=1075 TP=3060 IT=343 FT=416 TT=0 FL=100 IP=1075 FP=1150 TP=0 IT=416 FT=50 TT=0 FL=780.3 IP=1150 FP=690 TP=0 IT=50 FT=250 TT=300 FL=100 IP=690 FP=690 TP=300 00 00 00 0 4 0 IT=250 IT=392 IT=275 IT=100 IT=100 IT=392 IT=392 IT=392 IT=100 IT=235 FT=416.FT=275 FT=100 FT=100 FT=100 FT=392 FT=392 FT=392 FT=235 FT=416 TT=8964 FL=100 IP=255 FP=1025 TP=8964 TT=60 FL=5049 IP=1025 FP=900 TP=60 TT=900 FL=137.7 IP=900 FP=65 TP=900 TT=0 FL=100 IP=65 FP=1578 TP=0 TT=0 FL=100 IP=1578 FP=65 TP=0 TT=60 FL=5049 IP=1025 FP=1390 TP=60 TT=900 FL=137.7 IP=1390 FP=955 TP=900 TT=900 FL=1'37.7 IP=955 FP=1025 TP=900 TT=60 FL=I00 IP=I025 FP=1025 TP=60 TT=210 FL=100 IP=1025 FP=1025 TP=210 PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR CA=201 CA=202 CA=203 CA=204 CA=205 CA=206 CA=207 CA=208 CA=209 CA=210 CA=211 CA=212 CA=213 CA=214 CA=215 CA=216 CA=217 CA=218 CA=219 CA=220 CA=221 CO=27.6 CO=27. 6 CO=27 .4 CO=27.4 CO=27.6 CO=2 7.1 CO=27.0 CO=27 .0 CO=27.1 CO=27.1 CO=27 .1 CO=27.6 CO=27. 6 CO=27.1 CO=27. 1 CO=27 .1 CO=27. 1 CO=27. 6 CO=27.1 CO=26. 6 CO=26. 4 DI=0. 521 DI=0.512 DI=0.465 DI=0. 465 DI=0.490 DI=0. 446 DI=0. 440 DI=0. 440 DI=0.444 DI=0.444 DI=0.445 DI=0.490 DI=0.490 DI=0.445 DI=0. 445 DI=0.445 DI=0. 444 DI=0. 488 DI=0.. 447 DI=0. 423 DI=0. 418 EX=6. 4 EX=6. 4 EX=6. 4 EX= 6.4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4* Tavg=85* Tavg=100* Tavg=258* Tavg=258* Tavg=180* Tavg=326* Tavg=351* Tavg=351* Tavg=336* Tavg=336* Tavg=329* Tavg=178* Tavg=178* Tavg=329" Tavg=329* Tavg=329* TaIvg=334* Tavg=188 Tavg=324" Tavg=418* Tavg=435 File No.: VY- 16Q-311 Revision:
0 Page A26 of A38 F0306-OIRO I Structural Integriy Associates, lnc.PAIR CA=222 PAIR CA=223 PAIR CA=224 PAIR CA=225 PAIR CA=226 PAIR CA=227 PAIR CA=228 PAIR CA=229 PAIR CA=230 PAIR CA=231 PAIR CA=232 PAIR CA=233 PAIR CA=234..PAIR CA=235 PAIR CA=236 PAIR CA=237 PAIR CA=238.PAIR CA=239 PAIR CA=240 PAIR CA=241 PAIR CA=242, PAIR CA=243 CO=27.. 0 CO=27. 3 CO=27. 6 CO=26. 3 CO=27.3 CO=27. 6 CO=26.8 C0=27. 4 CO=27 .6 CO=26.8 C0=27.5 C0=27.6 CO=2.7. 1 C0=27. 1 c0=27 .6 co=27. 6 C0=27.6 c0=26.7 c0=26.7 c0=26.7 c0=27. 6 C0=27. 1 DI=0.438 DI=0. 457 DI=0.489 D1=0. 413 DI=0.459 DI=0. 487 DI=0. 432 DI=0.471 DI=0. 487 DI=0.433 DI=0.473 DI=0. 496 DI=0.444 DI=0.444 DI=0.488 DI=0.512 DI=O. 512 DI=0.430 DI=0.430 DI=0.430 DI=0.492 DI=0.446 EX=6.4 EX=6. 4 EX=6. 4 EX=6.4 EX=6.4 EX=6. 4 EX=6.4 EX=6. 4 EX=6.4 EX=6.4 EX=6. 4 EX=6. 4 EX= 6. 4 EX=6.4 EX=6. 4 EX=6. 4 EX=6. 4.EX=6. 4 EX=6. 4 EX=6. 4 EX=6: 4 EX=6. 4 Tavg=358 Tavg=285 Tavg=185 Tavg=450 Tavg=279 Tavg=197 Tavg=385 Tavg=239 Tavg=197 Tavg=380 Tavg=233 Tavg=150 Tavg=333 Tavg=334 Tavg=188 Tavg=100 Tavg=100 Tavg=392 Tavg=392 Tavg=392 Tavg=168 Tavg=326 I I I I I I I TANG PT=155 DY=6.523-----------
*END REGION IVb* REGION 7 --------------------------------
*BEGIN REGION V GEOMETRY TO NOZZLE N4B, NODE 165-------------------------------------
OPER CA=3 OPER CA=4 OPER CA=.5 OPER CA=6 OPER CA=7 OPER CA=8 OPER CA=9 OPER CA=10 OPER CA=II OPER CA=12 OPER CA=13 OPER CA=14 OPER CA=15 OPER CA=16 OPER CA=17 OPER CA=18 TE=549 TE=260 TE=392 TE=310 TE=280 TE=265 TE=90 TE=549 TE=375 TE=330 TE=565 TE=50 TE=440 TE=565 TE=440 TE=549 PR=1010-PR=1010 PR=1010 PR=1010 PR=1010 PR=1010 PR=1010 PR=1010 PR=170 PR=88 PR=1190 PR=1135 PR=135 PR=1135 PR=1060 PR=1135 I I OPER CA=20 TE=300 PR=675 OPER CA=21 TE=275 PR=885 OPER OPER OPER OPER OPER OPER CA=2 3 CA=24 CA= 25 CA=26 CA=27 CA=30 TE=392 TE=392 TE=392 TE=275 TE=440 TE=290 PR=1375 PR=940 PR=1010 PR=1010 PR=1010 PR=1010 I I I I File No.: VY- 16Q-31 I Revision:
0 Page A27 of A38 F0306-0IRO Structural Integrity Associates, Inc..* RAN CA=201 IS=l FS=1 IT=70 FT=100 TT=1800 FL=100 IP=I5 FP=1115 TP=1800 TRAN CA-202* IS=I FS=1 IT=100 FT=100 TT=0 FL=100 IP=1115 FP=65 TP=0 TRAN CA=203 IS=I FS=I IT=100 FT=549 TT=16164 FL=100 IP=65 FP=1025 TP=16164 TRAN CA=204 IS=I FS-I IT=549 FT=100 TT=0 FL=688.5 IP=1025 FP=1025 TP=0 TRAN CA=205 IS=1 FS=1 IT=100 FT=260 TT=0 FL=688.5 IP=1025 FP=1025 TP=0&#xfd;TRAN CA=206 IS=1 FS=1 IT=260 FT=392 TT=1800 FL=4590 IP=1025 FP=1025 TP=1800 TRAN CA=207 IS=1 FS=I IT=392 FT=310 TT=900 FL=3442.5 IP=1025 FP=1025 TP=900.TRAN CA=208 IS=1 FS=1 IT=310 FT=392 TT=900 FL=3442.5 IP=1025 FP=1025 TP=900 TRAN CA=209 .IS=1 FS=1 IT=392 FT=280 TT=1800 FL=2295 IP=1025 FP=1025 TP=1800 TRAN CA=210 IS=1 FS=1 IT=280 FT=392 TT=18.00 FL=2295 IP=1025 FP=1025 TP=I800 TRAN CA=211 IS.=1 FS=1 IT=392 FT=265 TT=1800 FL=2295 IP=1025.FP=1025 TP=1800* TRAN CA=212 IS=1 FS=1 IT=265 FT=90 TT=360 FL=688.5 IP=1025 PP=1025 TP=360 TRAN CA=213 IS=1 FS=1 IT=90 FT=265 TT=900 FL=688.5 IP=102.5 FP=1025 TP=900 TRAN CA=214 IS=1 FS=1 IT=265 FT=392 TT=180.0 FL=2295 IP=1025 FP=1025 TP=1800 TRAN CA=215 IS=I FS=1 IT=392 FT=265 TT=90 FL=4590 IP=1025 FP=1025 TP=90 TRAN CA=216 IS=1 FS=1 IT=265 FT=392 TT=180.FL=4590 F==1025 FPP1025 TP=180 TRAN CA=217 IS=1 FS=1 IT=392 FT=275 TT=60 FL=5049 IP=1025 FP=1025TP=60 TRAN CA=218 IS=1 FS=1 IT=275 FT=100 TT-=900 FL=137.7 IP=1025 FP=1025 TP=900.TRAN CA=219 IS=1 FS=1 IT=265 FT=440 TT=0 FL=100 IP1=025 FP=1025 TP=0 TRAN CA=220 IS=I FS=I IT=440 FT=549 TT=3924 FL=100 IP=1025 FP=1025 TP=3924 TRAN CA=221 *IS=I FS=I IT=549 FT=549 TT=0FL=I00 IP=1025 FP=1025 TP=0 TRAN CA=222 IS=1 FS=1 IT=549 FT=375 TT=6264 FL=100 IP=1025 FP=185TP=6264 TRAN CA=223 IS=1 FS=1 IT=375 FT=330 TT=600 FL=100 IP=185 FP=103.TP=600 TRAN CA=224 IS=I FS=1 IT=330 FT1=00 TT=8280 FL=100 IP=103 FP=65 TP=8280 TRAN CA=225 IS=1 FS=1 IT=392 FT=565 TT=12 FL=100 IP=1025 FP=1205 TP=12 IRAN CA=226 IS=I FS=1 IT=565 FT=50 TT=0 FL=1836 IP=1205 FP=1150 TP=0 TRAN CA=227 IS=1 FS=11 IT=50 FT=440 TT=1380 FL=100 IP=I150 FP=1150 TP=1380 TRAN CA=228 IS=1 FS=1 IT=440 FT=565 TT=0 FL=I00 IP=1150 FP=1150 TP=0 TRAN CA=229 IS=I FS=1 IT=565 FT=50 TT-0 FL=1377 IP=1150 FP=900 TP=0 TRAN CA=230 IS=1 FS=1 IT=50 FT=440 TT=3060 FL=100 IP=900 FP=1075 TP=3060 TRAN CA=231 IS=1 FS=1 IT=440 FT=549 TT=0 FL=100 IP=1075 FP=1150 TP=0 TRAN CA=232 IS=1 FS=1 IT=549 FT=50TT=0 FL=780.3 IP=1150 FP=690 TP=0 TRAN CA=233 IS=I FS=1 IT=50 FT2=300 TT=300 FL=100IP=690 FP=690 TP=300 TRAN CA=234 IS=1 FSS=1 IT=300 FT=549 TT=8964 FL=100 IP=255 FP=1025 TP=8964 TRAN CA=235 IS=1 FS=1 IT=392 FT=2.75 TT=60 FL=504.9 IP=1025 FP=900 TP=60 TRAN CA=236IS=1 FS=1 IT=275 FT=100 TT=900 FL=137.7 IP=900 FP=65 TP=900 TRAN CA=237 IS=1 FS=1 IT=100 FT=100 TT=0 FL=100 IP=65 FP=1578 TP=0 TRAN CA=238 IS=1 FS=i IT=100 FT=100 TT=0 FL=100 IP=1578 FP=65 TP=0 TRAN CA=239 IS=1 FS=I IT=392 FT=392 TT=60 FL=5049 IP=1025 FP=1390 TP=60 TRAN CA=240 IS=1 FS=1 IT=392 FT=392 TT=900 FL=137.7 IP=1390 .FP=955 TP=900 TRAN CA=241 IS=1 FS=1 IT=392 FT=392 TT=900 FL=137.7 IP=955 FP=1025 TP=900* TRAN CA=242 IS-1 FS=1 IT=100 FT=290 TT=60 FL=100 IP=1025 FP=1025 TP=60 TRAN CA=243 IS=1 FS=I IT=290 FT=549 TT=210 FL=100 IP=1025 FP=1025 TP=210 PAIR CA=201 CO=27.6 DI=0.521 EX=6.4 T Tavg=85 PAIR CA=202 CO=27.6 DI=0.512 EX=6.4
* Tavg=100 PAIR CA=203 CO=27.1 DI=0.447 EX=6.4
* Tavg=325 PAIR CA=204 CO=27.1 DI=0.447 EX=6.4
* Tavg=325 PAIR CA=205 CO=27.6 DI=0.490 EX=6.4
* Tavg=180 PAIR CA=206 CO=27.1 DI=0.446 EX=6.4
* Tavg=326 PAIR CA=207 CO=27.0 DI=0.440 EX=6.4
* Tavg=351 PAIR CA=208 CO=27.0 DI=0.440 EX=6.4
* Tavg=351.PAIR CA=209 CO=27.1 DI=0.444 EX=6.4 T Tavg=336 PAIR CA=210 CO=27.1 DI=0.444 EX=6.4
* Tavg=336 PAIR CA=211 CO=27.1 DI=0.445 EX=6.4 Tavg=329 PAIR CA=212 CO=27.6 DI-=0.490 EX=6.4
* Tavg=178 File No.: VY-16Q-311 Page A28 of A38 Revision:
0 F0306-OIRO Structural Integrity Associates, inc.PAIR PAIR PAIR PAIR PAIR PAI R PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR.PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR BRAD TANG NOZZ CA=213* CA=214* CA=215* CA=216 CA=217 CA=218 CA=219 CA=2120 CA=221 CA=222 CA=223 CA=2 24 CA=225 CA=22 6*CA=227 CA=228 CA=229 CA=2 30 CA=231 CA=232 CA=2 33 CA=234 CA=235 CA=236 CA=237 CA=2 38 CA=239 CA=240 CA=241 CA=242 CA=243 PT=160 PT=165 PT=165 CO=27 .6 CO=27 .1 CO=27 .1 CO=27 .1 CO727.1 CO=27 .6 CO=27 .0 CO=25.9 CO=25 .5 CO=2 6.2 CO=27 .0 CO=27 ' 5 CO=26. 1 CO=277. 2 CO=27 .4 CO=25. 9 CO=27.2 CO=27 .4 CO=25.9 CO=27.2 CO=27. 6 CO=26.5 CO=27. 1 CO=27.,6 CO=27. 6 CO=27. 6 CO=26.7 CO=2 6.7 CO=2 6.7 CO=27. 6 CO=2 6.5 DI=0.490 DI=0. 445 DI=0. 445 DI=0. 445 DI=0.444 DI=0.488 DI=0.439 DI=0.400 DI=0. 387 DI=0. 409 DI=0-439 DI=0.480 DI=0 .404 DI=0. 451 DI=0. 469 DI=Q. 397 DI=0.451 DI=0.469 DI=0. 400 DI=0.453 DI=0.491 DI=0. 421 DI=0.444 DI=0.488 DI=0. 512 DI=0. 512 DI=0.430 DI=0.430 DI=0.430 DI=0.487 DI=0.422 EX=6.4 EX=6. 4 EX=6.4 EX=6. 4 EX=6.4 EX=6.4 EX=6.4 EX=6.4 EX=6.4 EX=6. 4 EX=6.4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6.4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX= 6.4 EX=6.4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6 .4 Tavg=178 Tavg=329 Tavg=329 Tavg=329 Tavg=334 Tavg=188 Tavg=353 Tavg=495 Tavg=549 Tavg=462 Tavg=353 Tavg=215 Tavg =479 Tavg=308 Tavg=245 Tavg=503 Tavg=308 Tavg=245 Tavg=495 Tavg=300 Tavg=175 Tavg=425 Tavg=334 Tavg=188 Tavg=100 Tavg:100 Tavg=392 Tavg=392 Tavg=392 Tavg=195 Tavg=420 I I I I I I I I RA=1.25 DX=-4.007 DZ=-4.007 EW=!*NOZZLE N4B U I AMVT CA=1 AMVT CA=2 AMVT CA=3 AMVT CA=4 AMVT CA=5 AMVT CA=6 AMVT CA=7 AMVT CA=8 AMVT CA=9 AMVT CA=10 AMVT CA=11 AMVT CA=12 AMVT CA=13 AMVT CA=14 AMVT CA=15 AMVT CA=16 AMVT CA=17 AMVT CA=18 AMVT CA=19 AMVT CA=20 AMVT CA=21 AMVT CA-22 PT=165 DX=0.0196 PT=165 DX=0.0196 PT=165 DX=0.3130 PT=165 DX=0.3130.PT=165 DX=0.3130 PT=165 DX=0.3130 PT=165 DX=0.3130 PT=165 DX=0.3130 PT=165 DX=0.3130 PT=165 DX=0.3130 PT=165 DX=0.1993 PT=165 DX=0.1699 PT=165 DX=0.3234 PT=165 DX=0.3234 PT=165 DX=0.3234 PT=165 DX=0.3234 PT=165 DX=0.3169 PT=165 DX=0.3234 PT=165 DX=0.2823 PT=165 DX=0.2823 PT=165 DX=0.3130 PT=165 DX=0.0196 DY=0. 1069 DY=O.1069 DY=1. 7067 DY=I. 7067 DY=1. 7067 DY=1. 7067 DY=I. 7067 DY=1. 7067 DY=I. 7067 DY=I. 7067 DY=I. 0867 DY=0. 9264 DY=1I.7637 DY=1.7637 DY=1.7 637 DY=1.7 637 DY=I.7281 DY=1 .7637 DY=1. 5392 DY=1. 5392 DOY= .7067 DY=0.1069 DZ=0 .0196 DZ=0*. 0196 DZ=0 .3130 DZ=0. 3130 DZ=0. 3130 DZ=0. 3130 DZ=0. 3130 DZ=0 .3130 DZ=0. 3130 DZ=0. 3130 DZ=0. 1993 DZ=0. 1699 DZ=0. 3234 DZ=0. 3234 DZ=0.3234 DZ=0. 3234 DZ=0. 3169.DZ=0. 3234 DZ=0. 2823 DZ=0.2823 DZ=0. 3130 DZ=0.0196 File No.: VY-16Q-311 Revision:
0 Page A29 of A38 F0306-0I RO I " Structural Integrity Associates, Inc.AMVT AMVT* AMVT AMVT AMVT AMVT AMVT AMVT AMVT AMVT CA=23 CA=24 CA=25 CA=26 CA=2 7 CA=28 CA=29 CA=30 CA=31 CA=32 PT=165 PT=i65 PT=I65 PT=165 PT=I65 PT=165 PT=165 PT=165 PT=-165 PT=165 DX=O.33463 DX0=0.3064"'
DX=.03130 DX=0. 3064 DX=0. 3130 DX=O..3130 DX=0. 3064 DX=O. 3130 DX=0. 3019 DX=-. 09 DY=1. 8884 DY=I. 6711, DY=I. 7067 DY=I. 6711 DY=I. 7067 DY=I. 7067 DY=I. 6711*DY=I. 7067 DY=I. 6461 by=. 015 DZ=0.3463 DZ=0. 3064 DZ=0. 3130 DZ=0. 3064 DZ=0. 3130 DZ=0. 3130 DZ=0.3064 DZ=0. 3130 DZ=0.3019 DZ=-. 093------------------------------------------------------------
*END REGION V----------
*----- -------------------------------------------
*REGION II GEOMETRY -HPCI Line brnch CROS CD=6 JUNC PT=10*-----------------------------------------
*BEGIN REGION Iha------------------------------------------------------------
OPER OPER OPER OPER OPER OPER OPER OPER OPER OPER OPER OPER OPER OPER OPER OPER CA=3 CA=4 CA=5 CA=6 CA=7 CA=8 CA= 9 CA=f0 CA=11 CA=12 CA=13 CA=I4 CA=I5 CA=16 CA=17 CA=18 TE=150 PR=1010 TE=260 PR=1010 TE=392 PR=1010 TE=310 PR=1010 TE=280 PR=1010 TE=265 PR=1010 TE=90 PR=1010 TE=265 PR=1010 TE=150 PR=170 TE=150 PR=88 TE=-392 PR=1190 TE=50 PR=1135 TE=I50 PR=1135 TE=150 PR=1135 TE=150 PR=1060 TE=150 PR=1135 OPER CA=20 TE=150 PR=675 OPER CA=21 TE=275 PR=885 OPER OPER OPER OPER OPER CA=23 CA=24 CA=25 CA=26 CA=27 TE=392 TE=392 TE=392 TE=275 TE=265 PR=1375 PR=940 PR=1010 PR=1010.PR=I010 OPER CA=30 TE=125 PR=1010 TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN CA=201 CA=202 CA=2 03 CA=204 CA=205 CA=206 CA=2 07 CA=208 CA=209 I5=1 I S=1 IS=1 I S= 1 I S= 1 IS=1 I S= 1 Is=1 I S~=1 FS=1 FS= 1 FS=1 FS=1 FS=I FS=1 FS=I FS=1 FS=1 IT=70 IT=100 IT=100 IT=150 IT=00 IT=260 IT=392 IT=310 IT=392 FT=100 TT=1800 FL=I50 IP=15 FP-1115 TP=1800 FT=100 FT=150 FT=100 FT=260 FT=392 FT=3 10 FT=392 FT=2 80 TT=0 FL=150 IP=1115 FP=65 TP=0 TT=16164 FL=150 IP=65 FP=1025 TP=16164 TT=O FL=150 IP=1025 FP=I025 TP=0 TT=0 FL=150 IP=i025 FP=1025 TP=0 TT=1800 FL=150 IP=I025 FP=I025 TP=1800 TT=900 FL=150 IP=1025 FP=1025 TP=900 TT=900 FL=150 IP=1025 FP=1025 TP=900 TT=1800 FL=150. IP=I025 FP=1025 TP=1800 File No.: VY-16Q-311 Revision:
0..Page A30 of A38 F0306-O1RO Structural Interity Associates, Inc.TRAJ TRA]TRA]TRA]TRAL TRAI TRAI TRAT TRAN TRAN TRAI TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR N CA=210 NCA=211 N CA=212 N CA=213 q CA=214 q CA=215 N CA=216 N CA=217 N CA=218 CA=219 N CA=220 CA=221 CA=222 CA=223 CA=224 CA=225 CA=226.CA=22.7 CA=228 CA=229 CA=230 CA=231 CA=232 CA=233 CA=234 CA=235 CA=236 CA=237 CA=238 CA=239 CA=240 CA=241 CA=242 CA=243 CA=201 CA=202 CA=203 CA=204 CA=205 CA=206 CA=207 CA=208 CA=209 CA=210 CA=211 CA=212 (CA=213 (CA=214 (CA=215 C CA=216 C CA=217 C CA=218 C CA=219 C CA=220 C CA=221 C IS=1 IS=1 I S=I1 IS=1 IS=1 IS=1 IS=1 IS=l FS=1 FS=1 FS=1 FS=1 FS=I FS=1 FS=I FS=1 FS=1 IT=280 FT=392 TT=1800 FL=150 IP=1025 FP=1025 TP=1800 IT=392 FT=265 TT=1800 FL=150 IP=1025 FP=1025 TP=1800 IT=265 FT=90 TT=360 FL=150 IP=1025 FP=1025 TP=360 IT=90 FT=265 TT=900 FL=150 IP=1025 FP=IOZ5 TP=900.IT=265 IT=392 IT=265 IT=392 IT=275 IT=265 IT=265 FT=392 FT=265 FT=392 FT=275 FT=100 FT=265 FT=265 TT=1800 FL=150 IP=1025 FP=1025 TP=1800 TT=90 FL=150 IP=1025 FP=1025 TP=90 TT=180 FL=150 IP=I025 FP=1025 TP=180 TT=60 FL=150 IP=1025 FP=1025 TP=60 TT=900 FL=150 IP=1025 rP=1025 TP=900 TT=0 FL=150 IP=1025 FP=1025 TP=0 TT=0 FL=150 IP=1025 FP=1025 TP=0 I I*IS=I FS=I*IS=I FS=1 I S= 1 IS=1 IS=1 IS=1 I5=1 IS=1 I5=1 IS~=1 I 5=1 I5=1 IS=1 I S= 1 I S=1 IS=1 I5=1 IS=1 I5=1 I5=1 IS=1 I S= 1 I5=1 IS=1 I S= 1 FS=1 FS=I FS=1 FS=1 FS=1 FS=I FS=1 FS=1 FS=1 FS=1 FS=1 FS=I FS=1 FS=1 FS=1 FS=1 FS.-I FS=1 FS=1 FS=1 FS=1 FS=I FS=1 IT=265 FT=150 TT=4140 FL=150 IP=1025 FP=1025 TP=4140 IT=150 FT=150 TT=0 FL=150 IP=1025 FP=185 TP=0 IT=150 FT=150 TT=O .FL=150 IP=1I85 FP=103 TP=0 IT=150 FT=100 TT=8280 FL=150 IP=103 FP=65 TP=8280 IT=392 FT=392 TT=12 FL=150 iP=1025 FP=1205 TP=12 IT=392 FT=50 TT=0 FL=3672 IP=120.5 FP=1150 TP=0 IT=50.FT=150 TT=1380 FL=150 IP=1150 FP=1150 TP=.1380 IT=150 FT=150 TT=0 FL=150 IP=1150 FP=1150 TP=0 IT=150 FT=50 TT=0 FL=2754 IP=1150 FP=900 TP=0 IT=50 FT=150 TT=3060 FL=150 IP=900 FP=1075 TP=3060 IT=150 FT=150 TT=0 FL=150 IP=1075 FP=1150 TP=0 IT=150 FT=50 TT=0 FL=1560.6 IP=1150 FP=690 TP=0 IT=50 FT=150 TT=300 FL=150 IP=690 FP=690 TP=300 I I I I I I I I IT=150 IT=392 IT=275 IT=100.IT=100 IT=392 IT=392 IT=392 IT=100 IT=125 CO=27. 6 CO=27 .6 CO=27. 6 CO=27.6 CO=27. 6 CO=27. 1 CO=27. 0 CO=27. 0 CO=27.1 C0=27. 1 C0=27. 1'0=27. 6'0=27.6:0=27. 1:0=27. 1 20=27 .1 20=27.1 20=27. 6:0-!27 .3 20=27.3:0=27. 6 DI=0.521 DI=0. 512 DI=0 .504 DI=0.504 DI=0.490 DI=0. 446 bI=0.440 DI=0.440 DI=0. 444 DI=0.444 DI=0.445.DI=0.490 DI=0. 490 DI=0. 445 DI=0. 4 45 DI=0.445 DI=0. 444 DI=0.488 DI=0. 463 DI=0. 463 DI=0.483 F PT=150 FT=275 FT=100 FT=100 I FT=100 FT=392 FT=392 FT=392 FT=125 FT=150 EX=6. 4 EX=6. 4 EX=6.4 EX=6. 4 EX=6.4 EX=6. 4 EX=6.4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6.4 EX=6. 4 EX=6. 4 EX=6.4 EX=6. 4 EX=6. 4 EX=6 .4 TT=8964 FL=150 IP=255 FP=1025 TP=8964 TT=60 FL=150 IP=1025 FP=900 TP=60 TT=900 FL=150 IP=900 FP=65 TP=900 TT=0 FL=150 IP=65 FP=1578 TP=0 TT=0 FL=150 IP=1578 FP=65 TP=0 TT=60 FL=150 IP=1025 FP=1390 TP=60 TT=900 FL=150 IP=1390 FP=955. TP=900 TT=900 FL=150 IP=955:FP=1025 TP=900 TT=60 FL=150 IP=1025 FP=1025 TP=60 TT=210 FL=150 IP=1025 FP=1025 TP=210*******************Tavg=85 Tavg=100 Tavg=125 Tavg=125 Tavg=180 Tavg=326 Tavg=351 Tavg=351 Tavg=336 Tavg=336 Tavg=329 Tavg=178 Tavg=178 Tavg=329 Tavg=329 Tavg=329 Tavg=334 Tavg=188 Tavg=265 I I I U I EX=6.4
* Tavg=265 EX=6.4
* T avg=208 File No.: VY-16Q-311 Revision:
0 Page A31 of A38 I I F0306-0 IRO Structural Integrity Associates, Inc.PAIR CA=222 CO=27.6 DI=0.496.EX=6.4
* Tavg=150 PAIR CA=223 CO=27.6 DI=0.496 EX=6.4
* Tavg=150 PAIR CA=224 CO=27.6 DI=0.504 EX=6.4
* Tavg=125 PAIR CA=225 CO=26.7 DI=0.430 EX=6.4
* Tavg=392* PAIR CA=226 CO=27.5 DI=0.478 EX=6.4
* Tavg=221 PAIR CA=227 CO=27.6 DI=0.512 EX=6.4
* Tavg=100 PAIR CA=228 CO=27.6 DI=0.496 EX=6.4
* Tavg=150 PAIR CA=229 CO=27-6 DI=0.512 EX=6.4
* Tavg=100* PAIR CA=230 CO=27-6 DI=0.512 EX=6.4
* Tavg=100 PAIR CA=231 CO=27.6 DI=O0496 EX=6.4
* Tavg=150 PAIR CA=232 CO=27.6 DI=0.512 EX=6.4
* Tavg=100 PAIR CA=233 CO=27-6 DI=0.512 EX=6.4
* Tavg=100 PAIR CA=234 CO=27.6 DI=0.496 EX=6.4
* Tavg=150 PAIR CA=235 CO=27.1 DI=0.444 EX=6.4
* Tavg=334 PAIR CA=236 CO=27.6 DI=0.488 EX=6.4
* Tavg=188 PAIR CA=237 CO=27.6 DI=0.512 EX=6.4
* Tavg=100 PAIR CA=238 CO=27.6 DI=0.512 EX=6.4
* Tavg=100 PAIR CA=239 CO=26.7 DI=0.430 EX=6.4
* Tavg=392 PAIR CA=240 CO=26.7 DI=0.430 EX=6.4.
* Tavg=392 PAIR CA=241 CO=26.7 DI=0.430 EX=6.4
* Tavg=392 PAIR CAI242.CO=27.6 DI=0.508 EX=6.4
* Tavg=ll3 PAIR CA=243 CO=27.6 DI=0.500 EX=6.4
* Tavg=138 BRAN PT=301 DY=I TE>=I EW=l TANG PT=302 DY=2.333 TANG PT:305 DY=2.333 EW=1 BRAD PT=310. RA=I.75 EW=l TANG PT=315 DX=-2.333 EW=1 CROS CD=7 VALV PT=317 DX=-1.167 PL=lI MA=2.05---------------------------------------------------------------
* BEGIN REGION IIb OPER CA=3 TE=125 PR=I010 OPER CA=4 TE=180 PR=I010 OPER CA=5 TE=246 PR=i010 OPER CA=6 TE=205 PR=I010 OPER CA=7 TE=I90 PR=I010 OPER CA=8 TE=182.5 PR=I010 OPER CA=9 TE=95 PR=I010 OPER CA=I0 TE=182.5 PR=I010 OPER CA=1 TE=125 PR=170 OPER CA=I2 TE=I25 PR=88 OPER CA=I3 TE=246 PR=1190 OPER CA=14 TE=50 PR=1135 OPER CA=15 TE=I25 PR=1135 OPER CA=16 TE:I25 PR=II35 OPER CA=17 TE=I25 PR=I060 OPER CA=18 TE=125 PR=1I35 OPER CA=20 TE=125 PR=675 OPER CA=21 TE=187.5 PR=885 OPER CA=23 TE=246 PR=1375 File No.: VY-16Q-311 Page A32 of A38 Revision:
0 F0306-O1RO
* I Structural Integrity Associates, Inc.OPER CA=24 TE=246 PR=940 OPER CA=25 TE=246 PR=l010 OPER CA=26 TE=187.5 PR=1010 OPER CA=27 TE=182.5 PR=l010 OPER CA=30 TE=112.5 PR=I010 3 TRAN CA=201 ISm1 F.S=1 IT=70 FT=l00 TT=1800 FL=150 IP=15 FP=1115 TP=IS00 TRAN CA=202 IS=I FS=l IT=I00 FT=I00 TT=0 FL=150 IP=1115 FP=65 TP=0 TRAN CA=203 IS=I FS=1 IT=100 FT=125 TT=16164 FL=150 IP=65 FP=1025 TP=16164 TRAN CA=204 IS=l FS=I IT=125 FT=I00 TT=0.FL=I0 IP=I025 FP--1025 TP=0n TRAN CA=205 IS=1 FS=1 IT=100 FT=180 TT=0 FL=150 IP=1025 FP=1025 TP=0 TRAN CA=206 IS=I FS=I IT=180 FT=246 TT=I800 FL=50 IP=1025 FP=1025 TP=I800 TRAN CA=207 IS=l FS=l IT=246 FT=-205 TT=900 FL=150 IP=1025 FP=1025 TP=900 TRAN CA=208 IS=I FS=l IT=205 FT=246 TT=900 FL=150 IP=1025 FP=1025 TP=900 TRAN CA=209 IS=1 FS=1 IT=246 FT=I90 TT=I800 FL=150 IP=1025 FP=1025 TP=IS00 TRAN CA=210 IS=1 FS=I IT=I90 FT=246 TT=1800 FL=150 IP=1025 FP=1025 TP=l800 TRAN CA=211 IS=1 FS=I IT=246 FT=182.5 TT=1800 FL=50 IP=1025 FP=1025 TP=I800 TRAN CA=2i2 IS=I FSI IT=182,5.
FT-95 TT=360 FL=I50 IP=I025 FP=I025 TP:360 TRAN CA=213 IS=l FS=I IT=95 FT=182.5 TT=900 FL=150 IP=1025 FP=1025 TP=900i TRAN CA=214 IS=1 FS=1 IT=182.5 FT=246 TT=I800 FL=50 IP=1025 FP=1025 TP=I800 TRAN CA=215 IS=1 FS=- IT=296 FT=182.5 TT=90 FL=l50 IP=l025 FP=1025 TP=90 TRAN CA=216 IS=l FS=1 IT=182.5 FT=246 TT=180 FL=150 IP=1025 FP=1025 TP=180 TRAN CA=217 IS-I1 FS=I IT=246 FT=187.5 TT=60 FL=150 IP=1025 PP=I025 TP=60 TRAN CA=218 IS=1 FS=I IT=187.5 FT=I00 TT=900 FL=150 IP=1025 FP=1025 TP=900 TRAN CA=219 *IS=I FS=l IT=1824 5 FT=182.5 TT=0 FL=150 IP1=025 FP=1025 TP=0 TRAN CA=220 *IS=1 FS=1 IT=182.5 FT=182.5 TT=0 FL=150 IP=1025 FP=1025 TP=0 TRAN CA=221 IS=l FS=1 IT=182.5 FT=125 TT=4140 FL=150 IP=I025 FP=1025 TP=4140 TRAN CA=222 IS=I FS=1 IT=12.5 FT=125 TT= O FL= 150 IP=1025 TP=102 iP=0 TRAN CA=223 IS=1 FS=1 IT=125 FT=125 TT=10F FL=150 I P=1 03 TP=0 TRAN CA=224 IS=1 FS=1 IT=125 FT=100 TT=8280 FL=50 IP=103 FP=65 TP=8280 TRANCA=225
*-IS=I FS=I IT=246 FT=246 TT=I2 FL=I50 IP=1025 FP=I205 TP=I2 TRAN CA=226 IS=l- FS=1 IT=246 FT=50 TT=0 FL=3672 IP=1205 FP=1I50 TP=0 TRAN CA=227 IS=1 FS=1 IT=50 FT=i25 TT=1380 FL=150 IP=1I0 FP=6I50 TP=I380 TRAN CA=228 *IS=I FS=1 IT=125 FT=I25 TT=1 FL=150 IP=I1S0 FP=I1I0 TP=12 TRAN CA=229 IS=I1 FS=1 IT=125 FT=50 TT=0 FL=2754 IP=l250 FP=900 TP=0 TRAN CA=230 IS=1 FS=l IT=50 FT=125 TT=3060 FL=150 IP=900 FP=1075 TP=3060 TRAN CA=231 IS=I FS=l IT=125 FT=125 1TT=0 FL=150 IP=1075 FP=1150 TP=0 TRAN CA=232 IS-I FS=I IT=125 FT=50 TT=0 FL=1560.6 IP=1150 FP=690 TP=0 TRAN CA=233 IS=l FS=1 IT=50 FT=125. TT=300 FL=I50 IP=690 FP=690 TP=300 TRAN CA=234 IS=1 FS=1 IT=125 FT1=25 TT=8964 FL=50 IP=255 8P=1025,TP=8964 TRAN CA=235 IS=1 FS=1 IT=246 FT=187.5 TT=60 FL=50 IP=1025 FP8=900 TP=60 I TRAN CA=236 IS=1 FS= IT=187.5 FT=100 TqT=900 FL=50 1IP=900 FP=65 TP=300 TRAN CA=237 IS=1 FS=1 IT=100 FT=100 TT=0 FL=150 IP=65 FPI=1578 TP=0 TRAN CA=238 IS=I FS=I IT=200 FT=100 TT=0 FL=I50 IP=1578 FP=65 TP= 60 TRAN CA=239 IS=1 FS=1 IT=246 FT=246 TT=60 FL=150 IP=I025 FP=6390 TP=60 I TRAN CA=240 IS=1 FS=I IT=246FT=246 TT=900 FL=150 IP=1390 FP=955 TP=900 TRAN CA=241 IS=I FS=1 IT=246 FT=246 TT=900 FL=150 IP=955 FP=1025 TP=900 TRAN CA=242-IS=I FS=1 IT=100 FT=112.5 TT=60 FL=150 IP=1025 FP=1025 TP=60 TRAN CA=243 IS=I FS=1 IT=112.5 FT1=25 TT=210 FL=l50 IP=1025 FP=1025 TP=210 PAIR CA=201 CO=27.6 DI=0.521 EX=6.4
* Tavg=85 PAIR cA=202 CO=27.6 DI=0.512 EX=6.4
* Tavg=100I PAIR CA=203 CO=27.6 DI=0.508 EX=6.4
* Tavg=113 PAIR CA=204 CO=27.6 DI=0.508 EX=6.4
* Tavg=113 PAIR CA=205 CO=27.6 DI=0.499 EX=6.4
* Tavg=140 File No.: VY-16Q-311 Page A33 of A38 Revision:
0 F0306-01 RO
* ~ Structural Integrity Associates, Inc.PAIR PAIR PAIR PAIF PAIT PAIF PAIF PATF PAIR PAI R PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAI R PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR VALV CROS TANG TANG BRAD TAN P BRAD TANG CROS VALV R CA=206 RCA=207 R CA=208 CA=209.CA=210 CA=211 CA=212 CA=213 CA=214 CA=215 CA=216 CA=217* CA=218 SCA=219 CA=220 CA=221* CA=222 CA=223 CA=224 CA=225 CA=226 CA=227 CA=228 CA=229 CA=230 CA=231 CA=232 CA=233 CA-234 CA=235 CA=236 CA=237 CA=238 CA=239 CA=240 CA=241 CA=242 CA=243 3 PT=320 CD=6 PT=325 PT=330 PT=335 PT=340 PT=345 CD=7 PT=34 6 CO=27.5 CO=27 .5 CO=27 .5 CO=27 .5 CO=27 .5 CO=27 .5 CO=27. 6 CO=27. 6 CO=27.5 CO=27.5 CO=27 .5 CO=27 .5 CO=27 .6 CO=27 .6 CO=27. 6 CO=27. 6 CO=27 .6 CO=27..6 CO=27 .6 CO=27.4 CO=27. 6 CO=27. 6 C0=27. 6 CO=27 .6 CO=27 .6 CO=27 .6 CO=27 .6 CO=27. 6 CO=27 .6 CO=27.5 CO=27 .6 CO=27 .6 CO=27. 6 CO=27. 4 CO=27 .4 CO=27,.4 CO=27 .6 CO=27. 6 DI=0.481 DI=0 476 DI=0.476 DI=0.479 DI=0.479 DI=0. 481 DI=0. 500 DI=0. 500 DI=0 .481 DI=0. 481 DI=0 .481 DI=0.480 DI=0. 498 DI=0 .489 DI=0. 489 DI=0. 495 DI=0 .504 DI=0.504 DI=0. 508 DI=0.469 DI=0.497 DI=.0.519 DI=0 .504 DI=0.519 DI=0. 5i9.DI=0. 504 DI=0 .519 DI=0.519 DI=0. 504 DI=0.480 DI=0. 498 DI=0. 512 DI=0. 512 DI=0-469 DI=0 .4.69 Di=0.469 DI=0.510 DI=0.506 EX=6.4 EX=6.4 EX=6.4 EX=6. 4 EX=6.4 EX=6.4 EX=6.4 EX=6.4 EX=6.4 EX=6.4 EX=6.4 EX=6.4 EX=6.4 EX=6.4 EX=6.4 EX=6.14 EX=6. 4 EX=6.4 EX=6.14 EX=6.4 EX=6.4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6.4 EX=6.4 EX=6. 4 EX=,6.4 EX=-6.4 EX=6.4 EX=6. 4 EX=6.4 EX=6.4 EX=6. 4 EX=6. 4.EX=6.4 EX=6. 4 EW=1 Tavg=213 Tavg=226 Tavg=22 6 Tavg=218*Tavg=218 Tavg=214 Tavg=139 Tavg=139 Tavg=214 Tavg=214 Tavg=214 Tavg=217 Tavg=144 Tavg=!83 Tavg=183 Tavg=154 Tavg=125 Tavg=125 Tavg=113 Tavg=246 Tavg=148 Tavg=88 Tavg=125 Tavg=88 Tavg=88 Tavg=125 Tavg=88 Tavg=88 Tavg=125 Tavg=217 Tavg=144 Tavg=100 Tavg=100 Tavg=246 Tavg=246 Tavg=246 Tavg=106 Tavg=119 DX=-1.167 PL-2 DX=-0. 666 DX=-2.667 EW=1 RA=1.75 EW=1 DZ=-3.5 RA=1.75 EW=1 DX=3.333 EW=I DX=1.167 PL=1 KA=1.725------------------------------------------------------------
*END REGION IIb*--------------------------------------------
---------------
*BEGIN REGION II* ---------------------------
--- --- --- --- ----- ------ ----- -- -- -- ------OPER CA=1 TE=100 PR=50 OPER CA=3 TE=100 PR=50 File No.: VY-16Q-311 Revision:
0 Page A34 of A38 F0306-O1RO Structural Integrity Associates, Inc.OPER OPER OPER OPER OPER OPER OPER OPER OPER OPER OPER OPER OPER OPER OPER OPER OPER OPER OPER OPER OPER OPER OPER OPER OPER OPER CA=4 CA-=5 CA=6 CA=7 CA=8 CA= 9 CA=10 CA=11 CA=12 CA=13 CA=14 CA= 15 CA= 16 CA= 17 CA=18 CA=20 CA=21 CA=2 2 CA=23 CA=2 4 CA=25 CA=26 CA=27 CA=28 CA=2 9 CA=30 TE=100 TE=100 TE=100 TE=100 TE=100 TE=100 TE=100 TE=100 TE=100 TE=100 TE=50 TE=100 TE=100 TE=.100 TE=100 TE=100 TE=100 TE=100 TE=100 TE=100 TE=100 TE=100 TE=10 0 TE=100 TE=100 TE=100 PR=50 PR=50 PR=50 PR=50 PR=50 PR=50 PR=50 PR=50 PR=50 PR=50 PR=1135 PR=50 PR=50 PR=50 PR=50 PR=50 PR=50 PR=50 PR=50 PR=50 PR=50 PR=50 PR=50 PR=50 PR=50 PR=50 I 1 I I I I I TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN T RAN TRAN CA=201 CA=202 CA=203 CA=204 CA=205 CA=206 CA=207 CA=208 CA= 209 CA=210 CA=211 CA=212 CA=213 CA=214 CA=215 CA=216 CA=217 CA=218 CA=219 CA=220 CA=221 CA=222 CA=223 CA=224 CA=225 CA=226 CA=227 CA=228 IS=1 FS=1 IT=70 FT=100 TT=1800 FL=150 IP=15 FP=65 TP=1800*IS=1*IS=I*IS=I*IS=I*IS=I*IS=I*IS=I*IS=I*IS=I*IS=I*IS=I*IS=I*IS=I*I S=I*IS=I*IS=I*IS=I*IS=I*IS=I*IS=I*IS=I*IS=1*IS=I 28=1 28=1 8 = 1 28=1 28=1 28=1 28=1 28=1 28=1 28=1 8 = 1 28=1 28=1 28=1 28=1 28=1 28=1 28=1 28=1 28=1.8 = 1 28= 1 28=1 28=1 IT=100 IT=100 IT= 100 IT=100 IT=100 IT=100 IT=100 IT=100 IT=100 IT=100 IT=100 IT=100 IT=100 IT=100 IT=100 IT=100 IT=100 IT=100 IT=100 IT=100 IT=100 IT=100 IT=100 IT=100 FT=1100 FT=100 FT=100 FT=100 FT=100 FT=100 FT=100 FT=100 FT=100 FT=100 FT=100 FT=100 FT=100 FT=100 FT=100 FT=100 FT=100 FT=100 FT=100 FT=100 FT=100 FT=100 FT=100 FT=100 TT=0 FL=150 IP=65 FP=65 TP2=0 TT=16164 FL=150 IP=65 FP=65 TP=16164 TT=0 FL=150 IP=65 FP=65 TP=0*TT=0 FL=150 IP=65 FP=65 TP=0 TT1=800 FL=150 IP=65 FP=65 TP=1800 TT=900 FL=150 IP=65 FP=65 TP=900 TT=900. FL=150 IP=65 FP=65 TP=900 TT=1800 FL=150 IP=65 FP=65 TP=1800 TT=1800 FL=150 IP=65 FP=65 TP=1800 TT=1800 FL=150 IP=65 FP=65 TP=1800 TT=360 FL=150 IP=65 FP=65 TP=360 TT=900 FL=150 IP=65 FP=65 TP=900 TT=1800 FL=150 IP=65 FP=65 TP=1800 TT=90 FL=150 IP=65 FP=65 TP=90 TT=180 FL=150 IP=65 FP=65 TP=180 TT=60 FL=150 IP=65 FP=65 TP=60 TT=900 FL=150 IP=65 FP=65 TP=900 TT=0 FL=150 IP=65 FP=65 TP=0 TT=0 FL=150 IP=65 FP=65 TP=0 TT=0 FL=150 IP=65 FP=65 TP=0 TT=0 FL=150 IP=65 FP=65 TP=0 TT=0 FL=150 IP=65 FP=65 TP=0 TT=8280 FL=150 IP=65 FP=65 TP=8280 TT=12 FL=150 IP=65 FP=65 TP=12 I U I IS=1 FS=1 IS=1 FS=1*IS=I FS=1 IT=100 FT=50 TT=0 FL=3672 IP=65 FP=1150 TP=0 IT=50 FT=100 TT=1380 FL=150 IP=1150 FP=65 TP=1380 IT=100 FT=100 TT=0 FL=150 IP=65 FP=65 TP=0 I I I File No.: VY-16Q-311 Revision:
0 Page A35 of A38 F0306-01RO I I I ~J~Structural Integrity Associates, Inc.I I TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN TRAN CA=229 CA=230 CA=231 CA=232 CA=233 CA=234 CA=235 CA=236 CA=237 CA=2 38 CA=239 CA=2 40 CA=241 CA=242 CA=2 43 IS=l FS=I IT=100 FT=50 TT=O FL=2754 IP=II50 FP=900 TP=0 IS=1 FS=1 IT=50 FT=100 TT=3060 FL=150 IP=900 FP=65 TP=3060*IS=I FS=I.IT=l00 FT=100 TT=0 FL=150 IP=65 FP=65 TP=0 IS=I FS=1 IT=l00 FT=50 TT=0 FL=1560.6 IP=65 FP=690 TP=0 IS=l FS=1 IT=50 FT=100 TT=300 FL=150 IP=690 FP=65 TP=300*IS=1*IS=l*IS=I*IS=l*IS=Ir*Is=I*IS=l*IS=1*IS=I*IS=I FS=I FS=1 FS=1 FS=I FS=I FS=1 FS=1 FS=1 FS=1 FS=1 IT=100 IT=100 IT=100 IT=100 IT=100 IT=100 IT=100 IT=100 IT=100 IT=I00 FT=100 FT=100 FT=100 FT=100 FT=100 FT=100 FT=100 FT=100 FT=100 FT=100 TT=8964 FL=150 IP=65 FP=65 TP=8964 TT=60 FL=150 IP=65 FP=65 TP=60 TT=900 FL=150 IP=65 FP=65 TP=900 TT=O FL=150 IP=65 FP=65 TP=O TT=0 FL=150 IP=65 FP=65 TP=0 TT=60 FL=150 IP=65 FP=65 TP=60 TT=900 FL=150 IP=65 FP=65 TP=900 TT=900 FL=150 IP=65 FP=65 TP=900 TT=60 FL=150 IP=65 FP=65 TP=60 TT=210 FL=150 IP=65 FP=65 TP=210 PAIF PAIR PAIF PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR PAIR CA=201 CA=202 CA=203 CA=204 CA=205 CA=206 CA=207* CA=208*CA=209 CA=2 10 CA=211 CA=212 CA=213 CA=214 CA=215 CA=216 CA=217 cA=218 CA=219 CA=220 CA=221 CA=222 CA=2 23 CA=224 CA=225 CA=226 CA=227 CA=228 CA=229 CA=230.CA=231 CA=232 CA=233 CA=234.CA=235 CA=236 CA=237 I CO=27.6 CO=27..6 CO=27.6 ICO=27.6 CO=27.6 CO=27.6 CO=27 .6 CO=27. 6 CO=27.6 CO=27. 6 C0=27. 6 CO=27. 6 CO=27.6 CO=27. 6 CO=27. 6 CO=27. 6 CO=27. 6 CO=27 .6 CO=27. 6 CO=27. 6 CO=27 .6 CO=27 .6 CO=27. 6 CO=27 .6 CO=27. 6 CO=27 .5 CO=27.5 CO=27. 6 CO=27 .5 CO=27 .5 CO=27. 6 CO=27 .5 CO=27.5 CO=27. 6 CO=27. 6 CO=27.6 CO=27, 6 C0=27. 6 CO=27. 6 CO=27. 6 DI=0.521 DI=0. 512 DI=0. 512 DI=0. 512 DI=0.512 DI=0.512 DI=0.512 DI0=.512 DI=0.512 0D=0.512 DI=0.512 DI=0.512 DI=0.512 DI=0.512 DI=0. 512 DI=0. 512 DI=0. 512 DI=0.512 DI=0. 512 DI=0. 512 DI=0. 512 DI=0. 512 DI=0. 512 DI=0. 512 DI=0. 512 DI=0. 526 DI=0.526 DI=0. 512 DI=0. 526 DI=0.526 DI=0. 512 DI=0.526 DI=0.526 Di=0.512 DI=0. 512 DI=0. 512 DI=0. 512 DI=0. 512 D0=0.512 DI=0. 512[ EX--6.4 EX=6.4 EX=6.4 EX=6.4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6.4 EX=6.4 EX=6 .4 EX=6 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6- 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6.4 EX=6.4 EX=6.4 EX=6. 4 EX=6. 4 EX=6. 4 EX=6.4 EX=6.4 EX=6.4****************************-k***Tavg=85 Tavg=100 Tavg=100 Tavg=100 Tavg=100 Tavg=100 Tavg=100 Tavg=100 Tavg=100 Tavg=100 Tavg=100 Tavg=100 Tavg=100 Tavg=100 Tavg=100 Tavg=100 Tavg=100 Tavg=100 Tavg=100 Tavg=100 Tavg=100 Tavg=100 Tavg=100 Tavg=100 Tavg=100 Tavg=75 Tavg=75 Tavg=100 Tavg=75 Tavg=75 Tavg=100 Tavg=75 Tavg=75 Tavg=100 Tavg=100 Tavg=100 Tavg=100 Tavg=100 Tavg=100 Tavg=100 PAIR CA=238 PAIR CA=239 PAIR CA=240 File No.: VY-16Q-311 Revision:
0 Page A36 of A38 F0306-01 RO Structural Integrity Associates, Inc.PAIR CA=241 PAIR CA=242 PAIR CA=243 VALV PT=350 CROS CD=6 TANG PT=355 TANG PT=360 BRAD PT=380 TANP BRAD PT.=390 TANG PT=392 TANG PT=395 BRAD PT=400 TANG PT=405 BRAD PT=410 TANG PT=415 TANG PT=420 TANG PT=425 BRAD PT=430 TANG PT=435 TANG PT=440 TANG PT=445 TANG PT=450 BRAD PT=455 TANG PT=460 BRAD PT=465 TANG PT-470 TANG PT=480 TANG PT=485 BRAD PT=490 TANG PT=495 TANG PT=500 BRAD PT=505 TANG PT=510 TANG PTh515 TANG PT=520 TANG PT=525 BRAD PT=535 TANG PT=540 TANG PT=545 STRU PT=546 STRU 'PT=547 ANCH PT=547.CO=2746 DI=0.512 EX=~6.4
* Tavg=100 CO=27.6 DI=0.512 EX=6.4 *Tavg&#xfd;100 CO~=27.6 DI=0.512 EX=6 .4
* Tavg'=100 DX=1. 167 PL=2 EW=1 DX=0. 167 DX=2.083 EW=1 RA=1.75 EW=1 DY=-2.479
, RA=1.75 EW=1 DX=2.585 DY=-2 DX=2.585 DY=-2 RA=1.75 EW=1 DZ=-3.417 RA=1.17 EW=1 DY=-3 DY=-5.25 DY=-2.417 RA=1.75 EW=1 DZ=2.333 DZ=4.757 DZ=4.757 DZ=4. 757 RA=1.75 EW=1 DX=-1.989 DZ=: RA=1.75 EW=1 DY=-5.722 DY=-5.722 DY=-5.722 RA=1.17 EW=1 DZ=1. 667 DZ=2.0833 RA=1.75 EW=1 DX=3. 682 DX=3. 682 DX=3. 682 DX=3. 682 RA= 1i. 75 DX=2.556 DZ=-2 DX=2.555 DZ=-2 DX=-.7071 DZ=-.DX=-.7071 DZ=-.I I I I I I I I I.585.585 EW=1 1.989.556&#xfd;.555 7071 7071 I I I I I I I I------------------------------------------------------------
*END REGION II------------------------------------------------------------
*** VALVE OPERATOR ***CROS CD=7 JUNC PT=346 VALV PT=348 DY=5.567 P.L=3 MA=2.52*** SUPPORTS AND ANCHORS ***CSUP PT=I05 DY=1 KP=5000 PI=0 *FW-9 CSUP PT=190 DY=1 KP=1000 PI=0 *FW-6 CSUP PT=220 DY=-I KP=1000 PI=0 *FW-4 File No.: VY- 16Q-311 Revision:
0 Page A37 of A38 F0306-0 1 RO I Structural Integrity Associates, Inc.CSUP PT=270 DY=1 CSUP PT=145 DY=1 KP=1000 PI=0 *FW72 KP=1000 PI=0 *FW-7 RSTN PT=230 DX=-0.6123 DY=-0.5 DZ=0.6123 SP=370 *FW-3*RSTN PT=80 DX=I. 0 SP=200 *FDW-H10 RSTN RSTN RSTN RSTN RSTN ROTR RSTN RSTN ROTR ENDP PTh201 PTh546 PT=355 PT=415 PT=30 PT=30 PT=60 PT=5 DX PT=5 RZ DX=0.198 DZ=0.9802 DX=-0.7071 DZ=-0.7071 DY=I.0 DX=1.0 DZ=1.0 DX=1.0 DY= 1.0 RZ=1 DX=1.0 DY==1.0 SP=1000 *FDW-H23 SP=I000 *BELLOWS*HPCI-H31*HPCI-H32*FDW-HD37*FDW HD37 SP=200 *FDW-H24 FLUED HEAD FLUED HEAD 7_=1 DY=I DZ=1 File No.: VY-16Q-311 Revision:
0 Page A38 of A38 F0306-OIRO Structural Integrity Associates, Inc.APPENDIX B PIPESTRESS OUTPUT FILE ("F WHPCI.PRF")
I I I I i I I I I I p~ o i File No.: VY-16Q-311 Revision:
0 Structural Integrity Associates, Inc.DST COMPUTER SERVICES S.A.F-4 PAGE NO. 97++ DST/PIPESTRESS
++ Vermont Yankee Version 3.5.1+026 PC-EXE Release: Jun* CALCOLATION NUMBER 2 CODE SECTION III CLASS 1 ASME-1998.Vermont Yankee Feedwater PipingSI Fatigue. Analysis
 
==SUMMARY==
OF LOAD SETS AT POINT 155 LR ELBOW KRE 2007/07/11 11:35:07 [1 DELTA T1 IN DEGREES PRESSURES IN PSI STRESSES IN PSI 155 TO 160 GLOBAL MOMENTS IN FT-LB LOAD SET NO.DYNAM.CYCLES CYCLES PRESSURE MOMENT MOMENT MOMENT X Y Z TRANSIENT STRESSES DELTA LOAD SET DESCRIPTION EQ. 10 EQ. 11 EQ. 13 TI 1 Design Nydrotest
+2 Design Nydrotest-3 Startup +4- TRoll & Inc. PWR1-5 TRoll & Inc. PWR2 +6 TRoll & Inc. PWR3 +17 DlyReduction to 75%.8 OlyReduction to 75%9 WklyReduct to 50% -10 WklyReduct to 50% +11 LOF`WN+TT 1 -12 LOFWN+TT 2 -13 .LOFWH+/-TT 3 +14 LOFWN+TT 4 +15 LOFWH+PFWHTR Ryp -16 LOFWN-lPFWHTR Byp +.17 SCRAI4+TT+AllOtrScm
-.18 SCRAI4+TT+AlIOtrScm
-19 NotStandby 1 +.20 NotStandby 2 +21 NotStandby 3 22 Shutdown I -23 Shutdown 2 -24 Shutdown 3 -25 SCRAM+/-LOFWP1
+26 SCRAI4+LOFWP2
-27 SCRA94+/-LOFWP3
+28 *SCRAM+/-LOFWP4
+29 SCRAM+/-LOFWFS
-3O SCRAl4+/-LOFWP6
+31 SCRAM+/-LOFWP7
+* LS-I LS-2 LS-3 LS-4 LS-5 LS-6-LS-7+ LS-8 LS-9 LS-10 120 120 300 610 599 599 10000 10000.2000 2000 LS-11 310 LS-12 LS-13 LS-14 LS-15 LS-16 LS-17"LS-18 LS-19 LS-20 LS-21 LS-22 LS-23 LS-24 LS-25 LS-26 LS-27 LS-28 LS-29 LS-30 LS-31 10 10 10 70.70 289 289 300 300 300 300 300 300 10 10 10 10 10 10 10 1100.50.1010.1010.1010.1010.1010.1010.1010.1010.1010.1010.1010.1010.1010.1010.1010.1010.1010.1010.1010.170.88.50.1190.1135.1135.1135.885.1060.1135.55.56.14505.24012.13760.4661.10313.4661.12381.4661.13415.24520.13415.4661.13415.4661.12192.23480.10450.8500.14505.7904.6239.56.2347.26504.17301.15136.24686.16738.15415.22.21.-695.-983.-442, 45.-259.45.-369.45.-424.-1009.-424.45.-424.45.-365.-960.-359.-316.-695.-355.-269.21.86.-1110.-771.-727.-1036.-747.-733.54.54.-12403.-21319.-11409.-2630.-8082.-2630.-10078.-2630.-11077.-21810.-11077.-2630.-11077.-2630.-9935.-20844.-8332.-6524.-12403.-6594.-5132.54.-451.-23646.-14962.-12959.-22025.-14459.-13217..0.0.25110.-25109.0.0.* 0.0.b .0.0.0.0.0.0.0.0.0.10951.17948.0.-25111.-14160.-11328.10950.-10950.18318.26076.-26053.18317.25130.50.0.25114.-54064.15049.252.-317.317.-215.215.-243.-1480.619.243.-4784.2433.-6434.-593.10969.17967.0.-25113.-14241.-11330.10965.-57147.18515.26097.-64906.18413.25158.0.0.12555.-12555.0.0.0.0.0.0.0.0.0.0.0.0.0.0.5476.8974.0.-12555.-7080.-5664.5475.-5475.9159.13038.-13027.9159.12565.0.0.0.-169.78.1.I -.-7.1.-1.-7.3.3.-25.13.-34.-3.39.0.0.-0.-1.-0.42.-251.5.31.-223.2.27.File No.: VY-16Q-311 Revision:
0 Structural integrity Associates, Inc.DST COMPUTER SERVICES S.A.F-4 PAGE NO. 97++ DST/PIPESTRESS
+4 Vermont Yankee Version 3.5.1+026 PC-EXE Release: Ju 1----CALCULATION NUMBER 2 CODE SECTION III CLASS 1 ASME-1998 Vermont Yankee Feedwater PipingS1 Fatigue Analysis KRE E 2007/07/11 11:35:07 [1 DELTA TI IN DEGREES PRESSURES IN PSI STRESSES IN PSI 1 155 TO 160 GLOBAL MOMENTS IN FT-LB MOMENT TRANSIENT STRESSES DELTA Z EQ. 10 EQ. 11 EQ. 13 Ti
 
==SUMMARY==
OF LOAD SETS AT POINT 155 LR ELBOW LOAD SET NO.DYNAM.CYCLES CYCLES PRESSURE MOMENT MOMENT X Y LOAD SET DESCRIPTION 32 33 34 35 36 37 38 39 40 41 42 43 44 45 SCRAM+LOFWP8
-SCRAM+LOFWP9
+SCRAM+LOFWP10+
SCRAM+SRVBLDNI-SCRAM+SRVBLDN2-Hydro Test +Hydro Test -SCRAM+TG+OPresl
-SCRAM+TG+OPres2
-SCRAM+TG+OPres3
-HotSbyFWcyc
+HotSbyFWcyc
+NORMAL+OBE LS-132 NORMAL-OBE LS-133 LS-32 LS-33 LS-34 LS-35 LS-36 LS-37 LS-38 LS-39 LS-40 LS-41 LS-42 LS-43 10 10 10 1 1 1 1 289 289 289 300 300 5 5 675.675.1010.885.50.1563.50.1375.940.1010.1010.1010.1010.1010.23044.16095.14505.12714.56.54.56.7411.4126.4661.20056.14505.14078.10494.-968.-672.-695.-388.21.22.21.-66.66.45.-857.-695.-2008.1458.-20560.-13953.-12403.-10400.54.54.54.-5088.-2152.-2630.-17600.-12403.-11434.-8380.-25110. -53661. -12555.9507.25119.0 : 0.0.0.0.;0.0.10427.25130.0.0.10417.25126.-6434.-593.0.0.0.0.0.10652.25446.0.0.4754.12559.0.0.0.0.0.0.0.5214.12565.0.0.-1671 151 0.-34.-3 0 of 0 23 01 10(1)10(1)101 WEIGHT 10013. .720. -7200.1792. 1733.- 1527.104 DYNAMIC FLAG= 1 B1 Ci K1 B2 C2 K2 C3 K3 C3PRIM C4 Z DIAM/TH MATERIAL E 0.106 1.247 1,000 2.022 3.034 1.,000 1.000 1.000 0.500 1.100 0.60321E+02 12.752 CARBON STEEL 0.2951 THIS ANALYSIS IS FOR THE BODY OF THE FITTING.I I File No.: VY-16Q-311 Revision:
0 I I I U I I I Structural Integrity Associates, Inc.DST. COMPUTER SERVICES S.A.F-4 .1 PAGE NO. 97++ DST/PIPESTRESS
++ Vermont Yankee CALCULATION NUMBER 2 CODE SECTION III CLASS 1 ASME-19 98 Vermont Yankee Feedwater PipingSI Fatigue Analysis Version 3.5.1+026 PC-EXE Release: Jun-_ --. ...-. ...- ....- ....-. ...-. ..KRE FATIGUE ANALYSIS AT POINT -155, LR ELBOW INDIVIDUAL STRESS RANGE CHECK 155 TO 160 2007/07/11 11:35:07 [i DELTA TI IN DEGREES STRESSES IN PSI LOAD SET SN SE DELTA Ti PAIR EQN.10 EQN.12 RANGE SP EQN.13 EQN.11 SALT KE EQN .14 28 29 29 29 3 28 20 25 31 4 32 32.3 4 4 4 3 25 20 26 26 3 26 27 2 24 29 31 43 34 29 32 29 29 32 28 43 34 32*1 43 34 4.32 32 43 34 26 28 29 29 29 62066.b 608 90.b 60634 .b 60622.b 60614.b 61463.b 58527.b 58182.b 60288. b 59539.b 60031.b 60020.b.60011.b 58364.b 58108.b 58096.b 58088.b 57580.b 57925.b 47001.g 46989.g 46980.g 46445.g 52528.g 52662.g 52662.g 7949.7720.8457.8457.8457.6621.13533.18755.6392.7360..7129.7129.7129.7131.7868.7868.7868.17427.12205.9927..9927.9927.9419.6169.19973.19973.255.1 251.0 247.4 224.3 224.3 198.3 224.4 266.0 194.2 201.2 190.6 167.6 167.6 197.0 193.5 170.4 170.4 209.2 167.6 274.8 251.8 251.7 282.5 229.1 223.8 223.3 35508.35035.34041.34035.34031.36705.30450.28382.36232.34042.35238.35233: 35228.33569.32576.32570.32566.29579.31647.26489.26484.26479.25969.31629.27119.27119.100939.99771.99802.99482.99470.90035.97400.97049.88867.88515.88898.88578'.88566.87347.87378.87058.87046.86146.86496.93513.93193.93181.92663.91578.91515.91515.1.317 1.273 1.263 1.263 1.263 1.294 1*185 1.172 1.219 1.222 1.209 1.209 1.208.1.148 1.138 1.138 1.138 1.149 1.132 1.000 1.000 1.000 1.000 1.000 1.000 1.000 66456.63498.63040.62816.62793.58265.57693.56861.54146.54103.53745.53533.53512.50128.49733.49533.49512.49505.48941.46757.46597.46591.46332.45789.45758.45758.ALLOW CYCLES 1808.2050.2098.2122.2125.2697.2783.2915.3406.3415.3488.3532.3536.4354.4465.4523.4529.4531.4700.5404.5460.5462.5553.5750.5762.5762.53580.53580.53580.53580.53580.53580.53580.53580.54348.53580.54348.54348.54348.54348.54348.54348.54348.53580.54348.53580.53580.53580.53580.53580.53580.53580.ALLOWABLE FOR 3*SM DELTA Tl RANGE 759.3 763.1 763:1 763.1 763.1 763.1 763.1 759.3 766.8 7 63. 1 766.8 766.8 766.8 766:8 766.8 766.8 766.8 763.1 766.8 763.1 763.1 763.1 759.3 788.7 849.3 810.3 Notes b,d,e,k: Fails g: Weld ISI h,i: Rupture Location L: Information File No.: VY-16Q-311 Revision:
0 V Structural Integrity Associates, Inc.DST COMPUTER SERVICES S.A.F-4.1 PAGE NO. 97 ,++ DST/PIPESTRESS
++ Vermont Yankee--Vrin -3.-5.+ 6 C-E- --Rele-se:-JuJ CALCULATION NUMBER 2 CODE SECTION III CLASS 1 ASME-1998 KRE Vermont Yankee Feedwater PipingSI Fatigue Analysis FATIGUE ANALYSIS AT POINT 155, LR ELBOW 155 TO *160 2007/07/11 11:35:07 DELTA Ti IN DEGREESE STRESSES IN PSI INDIVIDUAL STRESS RANGE CHECK LOAD SET SN SE DELTA Ti PAIR EQN.. 10 EQN.12 RANGE SP EQN.13 EQN.11 SALT KE EQN. 14 ALLOW ALLOWABLE FOR CYCLES 3*SM DELTA Ti RANGE 29 29 22 26 29 4 20 29 5 4.19 25 2 24 26 1 22 23 16 22 26 29 5 29 26 36 38 28 31 30 25 26 37 29 20 29 26 26 26 36 38 29 31 29 29 29 30 33 26 39 27 52662.g 52662.g 64676.b 45270.g 52386.g 55656.b 44893.g 514215.g 36248.56000. b 49926.g 42561.41017.41395.41017.41017.47735.g 63959.b 47490.g 43884.-g 45501.g 37958..44347 .g 22614.44560.g 36908.19973..19973.5819.9190.6625.18165.15003.19974.12943.11928.19973.6048.15103.16837.13765.7118.14613.220.6 223.8 31.9 278.4 226.2 212.0.251.8 223.8 302.3 170.5 263.5 293.4 251.2 250.8 248.0 251.2 224.1 27.7 222.4 236.9 223.2 253.6 238.8 329.7 223.8 256.6 27119.27119.40719.25496.31032.26916.22898.25871.28984.26952.22191.40246.26817.21476.26165.26905.24377..91515.91515.64699.91495.91335.84625.91110.90268.90149.84975.88796.88773.87213.87213.87213.87213.86638.63989.86343.85169.84354.84251.84109.83859.83413.83301.1.000 1.000 1.414-1.000.1.000 1.077 1.000 1.000 1.000 1.061 1.000 1.000.1.000 1.000 1. o00 1.000 1.000 1.354 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 45758.45758.45748.45747.45668.45590.45555.45134.45075.45071.44398.44386.43607.43607.43607.43607.43319.43310.43172.42585.42177.42125.42055: 41930.41706.41651.5762.5782.5766.5766.5796.5825.5638.6002.6025.6026.6302.6307.6647.6647.6647.6647.6779.6783.6848.7132.7338.7365.7402.7467.7587.7617.53580.53580.53580.53580.53580.53580.53580.53580.53580.54348.53580.53580.53580.53580.53580..53580.53580.54348.53580.53580.53580.53580.53580.53580.53580.53580.821.0 849.3 763.1 763.1 788.7 763.1 763.1 784.2 823.9 766.8 788.7 759.3 849.3 810.3 821.0 849.3 849.3 766.8 801.6 798.3 763.1 788.7 816.1 823.9 787.5 788.7 I I I I I I I Notes b,d,e,k: Fails g: Weld ISI h,i: Rupture Location L: Information I File No.: VY-16Q-31 1 Revision:
0 I I I I I I Structural Integrity Associates, Inc.D S T C O M P U T E R S E R V I C E S S.A.F-4.1 PAGE NO.. 97++ DST/PIPESTRESS
++ Vermont Yankee Version 3.5.1+026 PC-EXE Release: Jun----_ -------- -................-. .-. .- -. .- -. .-. .- -. .- -. .-. .- -. .- -. .-. .- -. .- -. .-. .- -. .- -CALCULATION NUMBER 2 CODE SECTION III CLASS 1 ASME-1998 KRE Vermont Yankee Feedwater PipingSI Fatigue Analysis FATIGUE ANALYSIS AT POINT 155, LR ELBOW INDIVIDUAL STRESS RANGE CHECK 155 TO 160 2007/07/11 11:35:07 [1 DELTA Ti IN DEGREES STRESSES IN PSI LOAD SET SN SE DELTA Ti PAIR EQN.10 EQN.12 RANGE SP EQN.13 EQN.11 SALT KE EON. 14 8 6 14 10 29 29 19 23 26 2 4 4 4 22 27 30 29 22 3 22 26 32 5 4 1 4 29 ,29 29 29 41 40 26 26 37 4 24 36 38 43 32 32 42 34 22 26 33 37 32 27 26 30 43884.g 43884.g 43884.g 43884.g 43884.g 43760.g-36292..39055.35796.52124.g 52124.g 52124.g 52124.g 62228.b 51926.g 51784.g 41341.62217.b 62208.b 48016.g 32701.50812.g 35646, 50002.g 32672.49860.g 16837.16837.16837.16837.16837.17270.19385.19385.19385.19385.5311.4842.5297.5311.5311.15236.18645.5580.6036.225.5 225.2 225.1 225.0 223.8 223.8 290.9 249.8 251.2 169.9 169.4 166.7"169.9 24.1 172.4 169.4 253.0 11 1.1 250.7 266.2 167.0 245.5 175.2 251.5 172.2 21476.21476.21476.21476.21476.20920.27641.27641.27641.27641.39253.32826.32229.39247.39243.27681.27068.30163.29566.83053.82988.82979.82951.82736.82613.82507.82041.81993.81079.81079.81079.81079.62546.80674.80431.80418.62226.62214.80052.79807.79364.79246.79153.78918.78911.1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.290 1.000 1.000 1.000 1.290 1.289 1.000 1.000 1.000 1.000 1.000 1.000 1.000 41527.41494.41490.41475.41368, 41307.41253.41021.40996.40539.40539.40539.40539.40342.40337.40216.40209.40123.40105.40026.39904.39682.39623.39577.39459.39455.ALLOW CYCLES 7684.7702.7705.7713.7772.7807.7836.7969.7983.8253.8253.8253.8253.8374.8377.8452.8456.8510.8521.8571.8649.8794.8832.8863.8942.8944.ALLOWABLE FOR 3*SM DELTA TI RANGE 53580.53580.53580.53580.53580.53580.53580.53580.53580.54348.54348.54-348.54348.54348.54348.54348.53580.54348.54348.53580.53580.54348.54348.54348, 53580.54348.798.3 798.3 798.3 798.3 798.3 798.3 788.7 801.6 784.2 851.7 813.4 824.1 851.7 766.8 792.1 792.1 818.0 766.8 766.8 763.1 816.1 788.7 827.0 792.1 849.3 792.1 Notes b d,e,k: g: h,i: L : Fails Weld ISI Rupture Location Information File No.: VY-16Q-311 Revision:
0 VStructural integrity Associates, Inc.D S T C O M P U T E R S E R V I C E S S. A.F-4.1 PAGE NO. 97++ DST/PIPESTRESS
++ Vermont Yankee Version 3.5.1+026 PC-EXE Releaee: Ju-.. .-- -..--- -....-........--. .--.. ...--....-:- -----CALCULATION NUMBER 2 CODE SECTION III CLASS 1 ASME-1998 KRE Vermont Yankee Feedwater PipingSI Fatigue Analysis FATIGUE ANALYSIS AT POINT 155, LR ELBOW 155 TO 160 2007/07/11 11:35:07 []i DELTA TI IN DEGREES*STRESSES IN PSI INDIVIDUAL STRESS RANGE CHECK LOAD SET SN SE DELTA TI PAIR EQN.10 EQN.12 RANGE 16 7 19.29.4 4 26 2 24 32.32 6 14 10 26 17 4 9 13 4.1 1i 15 26 29 26 29 32 45 37 5 40 32 32 36 38 26 26 26 26 41 29 19 29 29 23 32 29 29 39 35 30250.39141.49324 .g 39023.48890.g 33721.-31239.48721.g 48721.g 48721.g 48721.g 30250.30250.30250.30250.30250.37547.47399.9 37405.36537.46952.9 47132.g 36537.36537.28939.36132.10600.19386.18644.18644.18644.18644.11338.14514.18645.264.3 222.1 206.7 223.8 169.9 248.4 251.2 167.0 166.6 163.9 167 '0 252.9 252.6 252.5 252.4 251.2 189.4 209.6 222.7 227.1 168.5 167.3 222.5 198.1 251.2 189.4 SP EQN.13 EQN.11 78880.77994.28149. 77893.77876..24406. 77845.77724.77436.24978. 77272.2.4978. 77272.24978. 77272.24978. 77272.76764.76698.76689.76661.76447.76400.25486. 76372.76258.76009.27338. 75906.23388. 75733.75390.75390-75136.74985.1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 39440.38997.38946.38938.38922.38862.38718.38636.38636.38636.38636.38382.38349.38345.38331.38223.38200.38186.38129.38004..37953.37867.37695.37695.37568.37492.SALT KE EQN. 14 ALLOW CYCLES 8955.9260.9296.9302.9313.9356.9459.9519.9519.9519.9519.9707.9732.9735.9746.9827.9845.9856.9899.9996.10042.10120.10278.10278.10397.10468.ALLOWABLE FOR 3*SM DELTA TI RANGE 53580.53580.54348.53580.54348.54348.53580.54348.54348.54348.54348.53580.53580.53580.53580.53580.53580.54348.53580.53580.54348.54348.53580.53580.53580.53580.798.3 798.3 792.1 814.2 788.7 827.0 798.3 851.7 813.4 824.1 851.7 798.3 798.3 798.3 798.3 798.3 798.3 792.1 798.3 822.9 804.7 851.7 798.3 798.3 787.5 798.3 I I I U Notes b,d,e,k: Fails g: Weld ISI h,i: Rupture Location L: Information I I I File No.: VY-16Q-311 Revision:
0 I I I I U U Structural Integrity Associates, Inc.DST COMPUTER SERVICES S.A.F-4 .1 PAGE NO. 97++ DST/PIPESTRESS
++ Vermont Yankee CALCULATION NUMBER 2 CODE SECTION III CLASS 1 ASME-1998 Vermont Yankee Feedwater PipingSI Fatigue Analysis FATIGUE ANALYSIS AT POINT 155, LR ELBOW 155 T*****************************
INDIVIDUAL STRESS RANGE CHECK Version 3.5.1+026 PC-EXE Release: Jun KRE 0 160 2007/07/11 11:35:07 [1 DELTA TI IN DEGREES STRESSES IN PSI LOAD SET SN SE DELTA T1 PAIR EQN.10 EQN.12 RANGE SP EQN.13 EQN.11 SALT KE EON. 14 29 44 21 29 16 32 1 4 26 42 4 22 4 33 4 16 32 39 8 32 23 32 6 32 14 32 10 32 32 41 32 40 7 26 26 45 4 40 4 39 26 35 4 8 4 6 4 14 4 10 4 41 36112.35503.43282.45210.g 27708.44964.g 43808.g 41357.43959.g 43282.43549,g 43282.43282.43282.43282.43158.25507.25383.42346.42033.24485.41357.41357.41357, 41357.41357, 19385.13177.6529.13286.13774.223.8 223.8 180.1 170.1 280.4 169.3 184.9 182.9 167.0 168.7 165.6 168.4 168.3 168.2 167.0 167.0 249.5 251.2 169.9 169.9 216.8 171.6 171.2 171.2 171.0 169.9 20726.26687.27427.25574.24676.74965.74356.74266.74214.74129.73917.73672.72745.72510.72150.72100.72085.72076.72048.71833.71710.71704.71580.71301.70988.70682.70629.70563.70554.70526.70312.1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 37482.37178.37133.37107.37064.36959.36836.36372 36255.36075.36050.36042.36038.36024.35917.35855.35852.35790.35651.35494.35341.35314.35282.35277.35263.35156.ALLOW CYCLES 10477.10772, 10817.10843.10885.10992.11117.11607.11735.11936.11964.11972.11978.11993.12116.12187.12190.12262.12426.12614.12801.12834.12874.12880.12897.13032.ALLOWABLE FOR 3*SM DELTA TI RANGE 53580. 814.2 53580. 763.1 54348. 801.4 54348. 851.7 53580. 818.0 54348. .766.8 54348. 819.2 54348. 801.4 54348. 793.6 54348. 801.4 54348. 804.7 54348. 801.4 54348. 801.4 54348. 801.4 54348. 801.4 54348. 801.4 53580. 798.3 53580. 814.2 54348. 801.4 54348. 793.6 53580. 798.3 54348. 801.4 54348. 801.4 54348. 801.4 54348. 801.4 54348. 801.4 Notes b,d,e,k: Fails g: Weld ISI h,i: Rupture Location L: Information File No.: VY-16Q-311 Revision:
0 structural Integrity Associates, Inc.DST COMPUTER SERVICES S. A.F-4.1 PAGE NO. 98++ DST/PIPESTR9SS
++Vermont Yankee Version.3.5.1+026 PC-EXE Release: Jur CALCULATION NUMBER 2 CODE SECTION III CLASS 1 ASME-1998 Vermont Yankee Feedwater PipingSI Fatigue Analysis FATIGUE ANALYSIS AT POINT 155, LR ELBOW INDIVIDUAL STRESS RANGE CHECK KRE 155 TO 160 2007/07/11 11:35:07 DELTA TI IN DEGREES3 STRESSES IN PSI I LOAD SET SN SE DELTA T1 PAIR EQN.10 EQN.12 RANGE 22 32 41561. 166.5 17 26 23913. 216.8 9 26 23771. 250.1 32 33 40406. 182.1 13" 26 22903. 254.6 32 42 40739. 196.2 11 26 22903. 249.9 15 26 22903. 225.6 26 44 22472. 251.2 26 29 29511. 27.4 22 27 58697.b 7598. 5.9 21 26 21870. 251.2 4 42 38815. 199.0.29 32 .29051. 56.8 24 28 58057.b 12029. 31.8 7 32 38539. 165.3 32 45 38428. 167.0 18 29 28066. 220.6 4 29 27637. 53.9 12 29 27212. 215.9 4 7 36614. 168.2 17 32 36945. 132.6 4 45 36498. 169.9 9 32 36804. 165.9* 13 32 35935. 170.4 22 30 57644.b 7142. 2.9 SP EQN.13 EQN.11 70111.70110..69968.69867.69719.69515.69100.69100.68669.68364.36840. 58896.68067..67994.67904.34782. 58080.67091.66979.66919.66490.66064.65569.65496.65453.65355..65106..36243. 57742.SALT KE EQN. 14 1.000 1.000 1.000 1.000 1.000 1.000*1.000 1.000 1.000 1.000 1.160 1.000 1.000 1.000 1.167 1.000 1.000.1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.121 35056.35055.34984.34934.34860.34757.34550.34550.34334.34182.34161.34034.33997.33952.33893.33545.33489.33459.33245.33032.32785.32748.32726.32677.32553.32373.ALLOW CYCLES 13159.13160.13251.1'3316.13413.13548.13826.13826.14124.14340.14370.14554.14607.14674.14760.15288.15375.15422.15763.16111.16530.16592.16630.16715.16934.17257.ALLOWABLE FOR 3*SM DELTA T1 RANGE 54348. 766.8 53580. 798.3 53580. 798.3 54348. 819.2 53580. 822.9 54348. 821.2 53580. 798.3 53580. 798.3 53580. 814.2 53580. 759.3 54348.- 792.1 53580. 763.1 54348. 821.2 53580. 763.1 53580. 810.3 54348. 801.4 54348. 817.3 53580. 821.0 53580. 763.1 53580. 822.9 54348. 801.4 54348. 801.4 54348. 817.3 54348. 801.4 54348. 826.0 54348. 792.1 I I I I I Notes b,d,e,k: h,i: L: Fails Weld IS]Rupture Location Information I I I File No.: VY-16Q-311 Revision:
0 I I I I I I Structural Integrity-Associates, Inc.D S T C O M P U T E R S E R V I C E S S.A.F-4.1 PAGE NO. 98 Release: Jun++ DST/PIPESTRESS
++ Vermont Yankee Version 3.5.1+026 PC-EXE CALCULATION NUMBER 2 CODE SECTION III CLASS 1 ASME-1998 KRE Vermont Yankee Feedwater PipingSI Fatigue Analysis FATIGUE ANALYSIS AT POINT 155, LR ELBOW 155 TO 160 2007/07/11 11:35:07 [1 DELTA TI IN DEGREES STRESSES IN PSI INDIVIDUAL STRESS RANGE.CHECK LOAD SET SN SE DELTA Ti PAIR EQN.10 EQN.12 RANGE 4*15 32 32 4 4 24 26 4 21 4 4 4.4 18 23 4 12 24 24 3 12 4 18 23 35 32 32 35 44 17 9 31 32 13 32 11 15 44 21 26 28 26 26 43 34 24 32 32 32 31 35592.35935.35935.35530.35518.35020.34878.57340.b 31565.34010.34901.34010.34010.33589.32977.14433.55715.b 28162.13576.55610.b 55598 .b 55590.b 28939.28514.28086.54998.b 135.4.165.7 141.4 132.6 167.0 135.4 168.7 12259. 27.6 84.2 173.2 167.0 168.6 144 .2 169.9 169.9 248.0 7157. 32.7 81.3 243.3 11521. 24.0 11521. 1.0 11521. 1.0.159.1 2.8.163.9 7386. 28.5 SP EQN.13 EQN.11 64547.64487.64487.64082.64070.63975.63833.34309. 57370.63602.63584.63452.62965.62965.62544.61932.60630.35896. 55816.60199.59773.33315. 55927, 33309. 55607.33305. 555.95.57491.57469.56638.35423. 55107.1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.110 1.000 1-. 000 1.000 1.000 1.000 1.000 1.000 1.000 1.080 1.000 1.000 1.046.1.046 1.046 1.000 1.000 1.000 1.024 32273.32243.32243.32041.32035.31987.31917.31844.31801.31792.31726, 31483.31483.31272.30966.30315.30132.30100.29886.29262.29083.29068.28745.28735.28319 28212.SALT KE EQN.14 ALLOW CYCLES 17438.17493.17493.17873.17884..17974.18111.18252..18336.18353.18484.18975.18975.19413.20067..21420.21821.21893.22376.23875.24329.24367.25217.25246.26401.26708.54348.54348.54348.54348.54348.54348.54348.54348.53580.54348.54348.54348.54348.54348.54348.53580.53580.53580.53580.54348.54348.54348.54348.'54348.54348.54348.801.4 801.4 801.4 801.4 817.3 801.4 801.4 813.4 763.1 826.0 766.8 801.4 801.4 817.3 766.8 821.0 801.6 763.1 822.9 813.4 813.4 813.4 826.0 766.8 824.1 804.7 ALLOWABLE FOR 3*SM DELTA TI RANGE File No.: VY-16Q-311 Revision:
0 Notes b,d,e,k: Fails g: Weld ISI h,i: Rupture Location L: Information.File No.: VY-16Q-31 1 Revision:
0 I Structural Integrity Associates, inc.PAGE NO. 98 D S T C O M P U T E R S E R V I C E S S.A.F-4 .1++ DST/PIPESTRESS
++ Vermont Yankee V- e -si.n.3.5.1+02
-.E e ----Version 3.5.1+026 PC-EXE Release: Jui--------- --CALCULATION NUMBER 2 CODE SECTION III CLASS 1 ASME-1998 Vermont Yankee Feedwater PipingSI Fatigue Analysis FATIGUE ANALYSIS AT POINT 155, LR ELBOW INDIVIDUAL STRESS RANGE CHECK KRE 155 TO 160.2007/07/11 11:35:07 [I DELTA -TI IN DEGREEUI STRESSES IN PSI LOAD SET PAIR 4 18 4 12 23 43 23 34 3 23 22 42 24 27 5 22 24. 30 20 22 23 .27 22- 25 23 30 28 36 2 28 28 38 31 36 22 33 2 31 31 38 24 42 12 22 36 43 34 36 3 36 5 .24 SN SE DELTA Ti EQN.10 EQN.12 RANGE SP EQN.13 EQN.11 SALT KE EQN.14 25540.25536.53267.g 53256*g 53247.9.52114 .g-52078.g 36363.51025.g 50097.g 49 7 36.g 49174 .g 48683.g 46729.g 467.29. g 46729.g 46012.g 45280. g 46012.g 46012. g 45494.45390.g 44282.g 44270.9 44262.g 29744.6649.6649.6649.9899.13808.-13352.3.63.8936.5006.8480.12029.12029.12029.12259.6649.12259.12259.13603.11521.11521.11521.166.7 161.9 25.0 1.9 1.9 29.7 5.8 79.1 2.8 1.1 6.7 42.7 3.8 34.5 31.3 31.3 30.3 15.6 27.2 27.2 29.6 7.4 26.8 3.7 3.7 79.0 34429.34423.34419.31901.30903.30306.35661.32017.33593.31420.29118.29118.29118.28644.28778.28644.28644, 26687.27651.27645.27641.54495.54491.53664.53344.53332.52341.52277..51414.51123.50120.50014.49190.48860.47343.46750.46750.46633.46192 46040.46040.45720.45392.45190.44871.44859.44794.1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1. OQO 1.000 1.000 1.000 27247.27245.26832.26672.26666.26170.26138.25707.25561.25060.25007.24595.24430.23672.23375.23375.23317.23096.23020.23020.22860.22696.22595.22435.22429.22397.ALLOW CYCLES 29720.29726.31155.31732.31754:.33637..33763.35533.36158.38425.38676.40698.41549.45771.47577.47577.47944.49364.49865.49865.51538.53409.54602.56559.56635.57040.54348.54348.54348.54348.54348.54348.58680.54348.58680.54348.58680.53580.58680.53580.53580.53580.54348.54348.54348.54348.60000.54348.54348.54348.54348.60000.824.1 826.0 804.7*804.7 804.7 821.2 833.3 827.0 833.3 766.8 825.8 763.1 825.8 821.0 849.3 849.3 824.1 819.2 851.7 851.7 856.2 826.0 824.1 824.1 824.1 860.7 ALLOWABLE FOR 3*SM DELTA Ti RANGE I I I I I I Notes b,d,e,k: Fails g: Weld ISI h,i: Rupture Location L: Information I I File No.: VY-16Q-311.
Revision:
0 I I U U I I Structural Integrity Associates, Inc.D S T CO M P U T E R S E R V I C E S S.A.F-4.1 PAGE NO. 98++ DST/PIPESTRESS
++ Vermont Yankee-. -.....- ..- ..- ..- ..- ....- ..- ..- ..- ..- ..- ....- ..- --. ...Version 3.5.1+026 PC-EXE Release: Jun CALCULATION NUMBER 2 CODE SECTION Ill CLASS I ASME-1998 KRE 2007/07/11 11:35:07 [1 Vermont Yankee Feedwater PipingSI Fatigue Analysis FATIGUE ANALYSIS AT POINT 155, LR ELBOW INDIVIDUAL STRESS RANGE CHECK 155 TO 160 DELTA TI IN DEGREES STRESSES IN PSI LOAD SET SN SE DELTA TI PAIR EQN.10 EQN.12 RANGE SP EQN.13 EQN.11 SALT KE EON. 14 19 2 38 18 2 34 2 3 23 20 5 22 27 28 37 20 34 3 2 27 31 30 2 30 24 12 22 43 43 22 34 38 3 38 42 24 23 37 36 37 43 23 37.37 27 38 37 36 30 38 33 24 44599.g 44282.g 442 8 2.g 44533.g 442 7 0.g 44270.g 44262.9 44262.g 43153.43368.27401.42394.40750.41509.41048.41038.41036.41028.40750.40750.40792.*39697.39697.39697.38661.38769.1861.11521.11521.12746.11521.11522.11521.11521.40.2 23.6 23.6 2.66 0.5 0.5 0.5 0.5 30.5 1.0 79.9 0.6 8.5 31.3 23.6 2.0 0.5 0.5 5.3 5.3 27.2 5.6 2.4 2.4 15.5 7.5 32163.27651.27651.26687.27645.27645.27641.27641., 44619.44597.44597.44536.44278.44278.44266.44266.43458.43390.42530.42396.41540.41529.41364.41138.41044.41032.40947.40947.40820.40386.39793.39793.39572.38770.1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 22310.22299.22299.22268.22139.22139.22133.22133.21729.21695.21265.21198.20770.20765.20682.20569.20522.20516.20473.20473.20410.20193.19897.19897.19786.19385.ALLOW CYCLES 58159.58299.58299.58701.60417.60417.60499.60499.66286.66803.73771.74933.82915.83019.84683.87007.88005.88134.89044.89044.90429.95348.101886.101886.103950.111907.ALLOWABLE FOR 3*SM DELTA TI RANGE 54348.54348.54348..54348.54348.54348.54348.54348.60000.54348.60000.54348.58680.53580.54348.54348.54348.54348.58680.58680.54348.58680.58680.58680.60000.60000.792.1 851.7 851.7 824.1.851.7 851.7 851.7 851.7 849.3 813.4 853.9 788.7 841.7 784.2 788.7 804.7 788.7 788.7 868.4 868.4 788.7 841.7 868.4 868.4 854.6 860.0 Notes b,d,e,k: Fails g: Weld ISI h,i: Rupture Location L: Information File No.: VY-16Q-311 Revision:
0 I CStructural Integrity Associates, Inc.PAGE NO. 98 D S T C O M P U T E R S E R V I C E S S.A.F-4.1...T ---.-..................V .r o. a nk er i-o- 3.5 .6 C-E. ..R e.e. ..-r-++ DST/PIPESTRESS
++ Vermont Yankee :Version 3.5.1+026 PC-EXE Release':
JulCALCULATION NUMBER 2 CODE SECTION III CLASS 1 ASME-1998 Vermont Yankee Feedwater PipingSI Fatigue Analysis FATIGUE ANALYSIS AT POINT 155, LR ELBOW INDIVIDUAL STRESS RANGE CHECK KRE 155 TO 160 2007/07/11 11:35:07 [DELTA.TI IN DEGREESU STRESSES IN PSI LOAD SET SN SE DELTA TI PAIR EQN.10 EQN.12 RANGE 1 23 19 18 1 1 23 1 1 25 16 23 25 21 28 25 3 13 28 25 22 12 12 31 17 13 22 28 24 24 31 43 25 34 3 28 22 33 43 22 40 34 25 22 35 31 44 23 28 40 28 22 38714.38385.37973.37912.37668.37368.37549.37356.37348.37321.34887.36319.36861.37098.36950.36849.36841.36074.30200.36604.36626.36429.34857.36233.29626.36074.0.8 31.1 40.1 2.7 26.9 23.3 43.5 0.3 0.3 10.8 13.6 16.4 18.6 0.6 31.3 41.6 41.6 3.9 65.8 15.0 0.6 6.5 39.3 27.2 65.8 0.7 SP EQN.13 EQN.11 38766.38406.37992.37914.37696.37683.37644.37364.37352.37342.37322.37309.37176.37100.36971.36857.36845.36696.36655.36632.36628.36509.36357.36261.36082.36077.SALT KE EQN.14 1.000 1.000 1.000 1.000 1.000 1.000 1 .000 1.000 1.000 1.000 1.000 1.000 1.000 3.000 1.000 1.000 1.000 1,000*1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 29383.19203.18996.18957.18848.18842.18822.18682.18676.18671.18661.18655.18588.18550.18485.18428.18422.18348.18328.18316.18314.18255.18179.18130, 18041, 18038, ALLOW CYCLES 111954.115784.120392.1212868 123834.123981.124447.127846.127996.128119.128359.128517.130181.131149.132812.134297.134456.136430.136979.137291.137342.138959.141064.142421.144986..145056.3*SM 54348.53580.58680.60000.54348.54348.53580.54348.54348.53580.54348.60000.53580.54348.53580.53580.53580.54348.53580.53580.54348: 60000.53580.54348.53580.54348.ALLOWABLE FOR DELTA T1 RANGE 851.7 849.3 833.3 858.4 851.7 851.7 801.6 851.7 851.7 759.3 801.4 847.8 763.1 766.8 798.3 763.1 763.1 826.0 798.3 763.1 817.3 853.1 822.9 801.4 798.3 801.4 I I I I I I Notes b,d,e,k: Fails g: Weld ISI h, i: Rupture Location L: Information I I File No.: VY- 16Q-311 Revision:
0 I I I I I I CStrucural integrity Associates, Inc.D S T C 0 M P U T E R S E R V I C E S S. A.F-4.1 PAGE NO. 98++ DST/PIPESTRESS
++CALCULATION NUMBER 2 Vermont Yankee Version 3.5.1+026 PC-EXE Release: Jun CODE SECTION III CLASS 1 "ASME-1998 KRE 2007/07/11 11:35:07 [1 Vermont Yankee Feedwater PipingSI Fatigue Analysis FATIGUE ANALYSIS AT POINT 155, LR ELBOW 155 TO 160 INDIVIDUAL STRESS RANGE CHECK DELTA T1 IN DEGREES STRESSES IN PSI LOAD SET SN SE DELTA T1 PAIR EQN..10 EQN.12 RANGE 15 28 6 8 10 14 16 31 30 19 27 22 18 17 31 6 8 10 14 16 12 9 8 12 6 14 22 41 28 28 28 28 28 35 37 23 37 39 23 31 41 31 31 31 31 31 43 22 22 31 22 22 36074.35960.35960.35960.35960.35960.35960.29482.35668.35632.35529.35660.35572.28909.35243.35243.35243.35243.35243.35243.33425.35211.34887.33681.34887.34887.25.1 31.3 30.0 29.6 30.2 30.0 18.3 61.6 2.4 41.1 5.3 0.6 1.8 61.6 27.2 25.8 25.5 26.0 25.9 14.1 31.5 0.6 2.3 35.1 1.9 1.9 SP EQN.13 EQN.11 36077.35981.35981.35981.35981.35981.35981.35944 .35764.35730.35726.35662.35653.35371.35272.35271.35271.35271.35271.35271.35220.35213.35206.35189.35141, 35132.SALT E EON. 14 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1..000 18038.17991.17991.17991.17991.17991.17991.17972.17882.17865..17863.17831.17826.17686.17636.17636.17636.17636.17636.17636.17610.17606.17603.17595.17570.17566.ALLOW CYCLES 145056.146447.146449.146449.146449.146449.146449.146991.149673.150191.150253.151224.151370.155755.157347.157350..157350.157350.157350.157350.158176.158293..158403.158680.159466.159612.ALLOWABLE FOR 3*SM DELTA TI RANGE 54348.53580.53580.53580.53580.53580.53580.54348.58680.58680.58680.54348.60000.54348.54348.54348.54348.54348.54348.54348.54348.54348.54348.54348.54348.54348.801.4 798.3 798.3 798..3 798.3 798.3 798.3 801.4 819.88 825.8 819.8 793.6 851.6 801.4 801.4 801.4 801.4 801.4 801.4 801.4 826.0 801.4 801.4 826.0.801.4 901.4 Notes b,d,e,k: Fails g: Weld ISI h,i: Rupture Location L: Information File No.: VY-16Q-311 Revision:
0 cStructural integrity Assoc iatets, Inc., DS T C O M P U T E R S E R V I C E S S.A.F-4.1 PAGE NO. 98++ DST/PIPESTRESS
++ Vermont Yankee Version 3.5.1+026 PC-EXE Release: Jul--------------------CALCULATION NUMBER 2 CODE SECTION III CLASS 1 ASME-1998 Vermont Yankee Feedwater PipingSI Fatigue Analysis FATIGUE ANALYSIS AT POINT 155, LR ELBOW INDIVIDUAL STRESS RANGE CHECK KRE 155 TO 160 2007/07/11 11:35:07 DELTA TI IN DEGREESm STRESSES IN PSI 3 LOAD SET SN SE DELTA Ti PAIR EQN.10 EQN.12 RANGE 10 17 36 12 22 3 40 22 28 18 39 35 34 22 3 2 38 34 34 3 3.5 22 31 17 41 22 22 42 34 41 12 43 40 39 28 4.3 43 40 35 40 42 42 39 35 39 35 36 45 39 43 43 34887.35068.34166.33413.34887.33405.34503.34759.34652.34000.34193.27756.34491.34495.34483.34166.34166.34181.27745.34173.27736.184 16./33979.33935.27181.33514.1.7 33.9 32.3 8.5 0.6 8.5 23.6 0.6 31.'3 34.5 23.6 58.0 0.5 33.9 0.5 29.2 29.2 0.5 35.0 0.5 35.0 81.7 0.6 27.2 58.0 23.6 SP EQN.13 EQN.11 35104.35070.34983.34900.34889.34888.34819.34761.34673.34614.34509.34506.34499.34498.34487.34390.34390.34189.34186.34177.34174.34057.33981.33963.33931.33829.SALT KE EQN. 14 1.000 1.000 1.000 1.000 1.000 2.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 17552.17535.17492.17450.17445.17444.17409.17381.17337.17307.17254.17253.17249.17249.17243.17195.17195.17095.17093.17089.17087.17029.16990.16982.16966.16915.ALLOW CYCLES 160075.160627..16207 1.163460.163651.163664.164848.165831.167354.168392.17.0242.170292.170419.170442.170635.172368.172368.176049.176101.176274.176326.178513.179967.180307.180916.182887.ALLOWABLE FOR 3*SM DELTA TI RANGE I 54348.54348.60000.54348.54348.54348.54348.54348.53580.53580.54348.54348.54348.54348.54348.60000.60000.54348..54348.54348.54348.60000.54348.54348.54348.54348.801.4 801.4 864.5 826.0 801.4 826.0 801.4 801.4 787.5 821.0 793.6 801.4 801.4 801.4 801.4 893.7 893.7 793.6 801.4 793.6.801.4 869.1 817.3 793.6 801.4 801.4 I I I U I I Notes b,d,e,k: Fails g: Weld ISI h,i: Rupture Location L: Information I File No.: VY-16Q-31 1 Revision:
0 I I I I I U I VJStructural Integrity Associates, Inc.D S T C 0 M P U T E R S E R V I C E S S. A.F-4 .1 PAGE NO. 98++ DST/PIPESTRESS
++ Vermont Yankee CALCULATION NUMBER 2 CODE SECTION III CLASS 1 ASME-1998 Vermont Yankee Feedwater PipingSI Fatigue Analysis FATIGUE ANALYSIS AT POINT 155, LR ELBOW 155 TO INDIVIDUAL STRESS RANGE CHECK** *****************************
Version 3.5.1+026 PC-EXE Release: Jun KRE 2007/07/11
.11:35:07
[1 160 DELTA Ti IN DEGREES STRESSES IN PSI LOAD SET SN SE DELTA TI PAIR EQN.10 EQN.12 RANGE 6 8 10 14 16 17 3 34 6 8 10 14 16 7 3 3 3 3 3 3 18 2 5 18 15 1i 43 43 43 43 43 34 17 41 34 34 34 34 34 22 41 6 8 10 14 16 43 5 38 31 28 34 33514.33514.33514.33514.33514.27170.27161.33502.33502.33502.33502.33502.33502.33497.33494.33494.33494.33494.33494.33494 32568.18416.18416.32824.28620.32556.22.2 21.9 22.4 22.3 10.5 35.0 35.0 0.5 0.8 1.2 0.6 0.8 12.5 1.1 0.5 0.8 1.2 0.6 0.8 12.5 26.8 78.5 78.5 30.3 57.0 3.7 SP EQN.13 EQN.1i 33829.33829.33829.33829.33829.33632.33599.33510.33510.33510.33510.33510.33510.33499.33498.33497.33497.33497.33497.33497.33477.33465.33465.33445.33425.33157.SALT KE EQN. 14 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000*1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 16915.16915.16915.16915.16915.16806.16800.16755.16755.16755.16755.16755.16755.16750.16749.16749.16749.16749.16749, 16749, 16738.16732, 16732.16723.16713.16578.ALLOW* CYCLES 182890.182890.182890.182890.182890.187194.187437.189252.189256.189256.189256.189256.189256.189470.189499.189503.189503.189503.189503.189503.189930.190176.190176.190566.190984.196612.ALLOWABLE FOP, 3*SM DELTA TI RANGE 54348.54348.54348.54348.54348.54348.54348.54348.54348.54348.54348.54348.54348.54348.54348.54348.54348.54348.54348.54348.54348.60000.60000.54348.53580.54348.801.4 801.4 801.4 801.4 801.4 801.4 801.4 801.4 801.4 801.4 801.4 801.4 801.4 801.4 801.4 801.4 801.4 801.4 801.4 801.4 824.1 905.8 905.8 824.1 798.3 824.1 Notes b,d,e,k: Fails g: Weld ISI h,i: Rupture Location L:. Information File No.: VY-16Q-311 Revision:
0 l Structural Integrity Associates, Inc.D S T C 0 M P U T E R S E R V I C E S ' S. A.F-4 .1 PAGE NO. 98++ DST/PIPESTRESS
++ Vermont Yankee_ Version 3.5.1+026
-PC-EXE- --Release:-JuI CALCULATION NUMBER 2 CODE SECTION III CLASS 1 ASME-1998 KRE Vermont Yankee Feedwater PipingSI Fatigue Analysis FATIGUE ANALYSIS AT POINT 155, LR ELBOW*NIVDU**TR***SS***GE*******E*
INDIVIDUAL STRESS RANGE CHECK******************
115,5 TO 160 2007/07/11 11:35:07 DELTA Ti IN DEGREESI STRESSES IN PSI LOAD SET SN. SE DELTA Ti PAIR EQN.10 EQN.12 RANGE 3 12 24 15 20 20 1 12 2 22 22 22 1 2 20 20 25 7 25 15 28 28 27 37 18 19"18 20 25 31 28 36 27 25 22 24 36 38 30 20 38 31 30 28 27 43 45 42 40 42 20 28 32548.31318.32755.27902.32655.32040.32405.30973.32275.32275.32275.32275.31988.32040.32040.31938.31481.31219.31341.26180.31220.31152.30970.30932.30461.31051.3.7 8.5 42.6 52.8 30.7 3.8 5.1 50.1 0.6 0.1 2.6 0.6 2.1 0.6 0.6 26.6 39.8 33.0 36.8 49.2 31.3 2.2 5.3 29.2 3.8 8.4 SP EQN.13 EQN.11 33145.32817.32771.32714.32675.32653.32602-32467.32278.32278.32278.32278.32084.32060.32060.31966.31577.31557.31538.31279.31241.31173.31167.31156.31074.31071.SALT KE EQN. 14 ALLOW ALLOWABLE FOR CYCLES 3*SM DELTA TI RANGE I 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1:000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 16572.16409.16386.16357.16338.16327.16301.16233.16139.16139.16139.16139.16042..16030.16030.15983.15789.15779.15769.15640.15620.15587.15583.15578.15537.15536.196871.205131.206456.208114.209234.209888.211385.215442.221264.221264.221264.221264.227424.228208.228208.231302.*244590.245285.245964.255410.256841.259394.259631.260037.263206.263297.54348.54348.53580.54348.53580.54348.58680.53580.54348.54348.54348.54348.58680.54348.54348.54348.53580.53580.53580.54348.53580.53580..58680.60000.54348.53580.824 .1 826.0 810.3 801.4 763.1 824 .1 868.4 822.9 851.7 813.4 824.1 851.7 868.4 851.7 851.7 766.8 788.7 798.3 788.7 801.4 814.2 818.0 822.5 868.4 824.1 788. 7 I I U I I Notes b,d,e,k: Fails g: Weld ISI h,i: Rupture Location L; Information I I File No.: VY-16Q-311 Revision:
0 I I 1 I I I I Structural Integrity Associates, inc.D S T. COMPUTER S E RV I C E'S S.A.++ DST/PIPESTRESS
++ Vermont Yankee-. -.....- ..- ..- ..- ..- ..- ..- ....- ..- ..-F-4.1 PAGE NO. 98 Version 3.5.1+026 PC-EXE Release: Jun CALCULATION NUMBER 2 CODE SECTION III CLASS 1 ASME-1998 KRE 2007/07/11 11:35:07 (1 Vermont Yankee Feedwater PipingSI Fatigue Analysis FATIGUE ANALYSIS AT POINT 155, LR ELBOW 155 TO 160 INDIVIDUAL STRESS RANGE CHECK DELTA T1 IN DEGREES STRESSES IN PSI LOAD SET SN SE. DELTA T1 PAIR EQN.10 EQN.12 RANGE 15 3 27 7 23 18 28 20 31 21 19 33 17, 5 20 3 27 6 8 10 14.16 13 42 30 31 34 15 35 31 37 25 33 43 45 24 31 37 27 37 3.4 20 41 27 27 27 27 27 24 43 40 42 26168.26159.24217.30502.30758.30116.30567.30208.30493.30480.30333: 29424.23644.15182.30196.30188.29980.29980.29980.29980.29980.29980.29455.29721.29917.29977.26.2 26.2 39.8 28.9 1.4 45.3 16.3 23.0 27.2 0.5 12.5 15.0 39.8 78.5 0.0 0.1 5.3 4.0 3.6 4.2 4.0 7.7 3.8 5.6 2.4 2.0 SP EQN.13 EQN.11 30959.30947.30848.30847.30838.30723.30588.30523.30521.30481.30362.30334.30276.30231.30203.30191.30178.30177.30177.30177.30177.30177.30076.30036.30014.30005.SALT KE EQN. 14 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 15480.15474.15424.15424.15419.15362.15294..15262.15260.15241.15181.15167.15138.15115.15102.15096.15089.15089.15089.15089.15089.15089.15038.15018.15007.15003: ALLOW CYCLES 267678.268157: 272130.272146.272503.277200.282853.285593.285693.287400.292600.293826.296416;298432.299660.300210.300835.300844.300844.300844.300844.300844.305510.307361.308417.308818.ALLOWABLE FOR 3*SM DELTA T1 RANGE 54348.*54348.58680.54348.60000.53580.53580.54348.54348.54348.54348.60000.58680.60000.54348.54348.58680.58680.58680.58680.58680.58680: 60000.54348.58680.54348.801.4 801.4 822.5 801.4 838.6 821.0 816.1 766.8 817.3 813.4 792.1 860.6 822.5 892.0 766.8 766.8 822.5 822.5 822.5 822.5 822.5 822.5 860.0 821.2 822.5 821.2 Notes b,d,e,k: Fails g: Weld ISI h,i: Rupture Location L: Information File No.: VY-16Q-31 1 Revision:.
0 Structural Integrity Associates, Inc.D S T C O M P U T E R S E R.V I C E S S.A.F-4 .1 PAGE NO. 99++ DST/PIPESTRESS"++
Vermont Yankee Version 3.5.1+026 PC-EXE Release: Ju3 CALCULATION NUMBER 2 CODE SECTION III CLASS 1 ASME-1998 Vermont Yankee Feedwater PipingSI Fatigue Analysis FATIGUE ANALYSIS-AT POINT 155, LR ELBOW INDIVIDUAL STRESS RANGE CHECK KRE 155 TO 160 2007/07/11 11:35:07 DELTA Ti IN DEGREES STRESSES IN PSI LOAD SET. SN SE DELTA TI PAIR EQN.10 EQN.12 RANGE 24 9 34 3 30 11 15 33 31 7 33 17 3 43 7 3 30 6 8 10 14 16 9 2 12 12 44 28 42 42 35 24 24 43 33 43 34 30 33 45 34 7 41 30 30 30 30 30 31 12 36 38 29966.29486.29709.29701.23164.29455.29455.29133..29392.28774.29122.22592.29113.28797.28762.28753.28928.28928.28928.28928.28928.28928.28768.27441.27441.27.441.0.5*32.5 28.6 28.6 36.8 0.8 25.2 8.6 12.1 25.3 14.5 36.8 14.5 23.6 2.2 2.2 2.4 1.0 0.7 1.2 1. 1 10.7 28.3 7.9 4.8 7.9 SP EQN.13 EQN.1l 29968.29721.29716.29704.29695.29457.29457.29449.29420.29406.29129.29122..29117.29112.29086.29074.29024.29024.29024.29024.29024.29024.29011.28921.28921.28921.SALT KE EQN. 14 1.000 1.000 1.000 1.000 1.000 1.0OG 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 14984.'14861.14858.14852.14847.14728.14728, 14724.14710.14703.14565.14561.14559.14556.14543.14537.14512.14512.14512.14512.14512.14512.14505.14460.14460.14460.ALLOW CYCLES.310575.322516.322754.323355.323829.335946.335946.336356.337846.338595.353547.353924.354220.354495.355926.356604.359424.359435.359435.359435.359435.359435.360192.365335.365335.365335.ALLOWABLE FOR 3*SM DELTA TI RANGE I 60000.53580.54348.54348.58680.60000.60000.54348.54348.54348.54348.58680.54348.54348, 54348.54348.58680.58680.58680.58680.58680.58680.54348.60000.60000.60000.853.1 798.3 821.2 821.2 822.5 840.6 840.6 819.2 819.2 801:4 819.2 822.5 819.2 817.3 801.4 801.4 822.5 822.5 822.5 822.5 822.5 822.5 801.4 903.8*868.4 903.8 I I I I I I I Notes b,d,e,k: Fails g: Weld ISI h,i: Rupture Location L: Information File No.: VY-16Q-31 1 Revision:
0 I I I U I I Structural Integrity Associates, Inc.D S T C O M P U T E R S E R V I C E S S.A.F-4.1 PAGE NO. 99++ DST/PIPESTRESS
++ Vermont Yankee Version 3.5.1+026 PC-EXE Release: Jun-. -.....- ..- ..- ..- ..- ..- ..- ..- ..- --. -.....- ..- ..- ..- ..- ..- ..- ..- ..- ..- ..- ..- ..- ..- ..- ..- ..-CALCULATION NUMBER 2 CODE SECTION III CLASS 1 ASME-1998 KRE 2007/07/11 11:35:07 [1 Vermont Yankee Feedwater PipingSI Fatigue Analysis FATIGUE ANALYSIS AT POINT 155, LR ELBOW 155 TO 160 INDIVIDUAL STRESS RANGE CHECK***************************
DELTA TI IN DEGREES STRESSES IN PSI LOAD SET SN SE DELTA TI PAIR EQN.1O EQN.12 RANGE 19 30 11 27 20 33 20 34 3 27 13 19 9 3 25 28 17 27 3 5 2 33 21 11 28 13 43 39 28 39 35 36 37 45 45 43 28 34 24 19 35 44 24 34 27 28 33 38 23 33 30 31 28604.28811.28620.28671.22397.27333-28806.28785.28777.28412.28620.28592.28590.28584.22050.28431.28447.28400.28392.28333.27333.27333.28137.27902.27997.27902.16.1 2.4 32.6 5.3 35.0 18.2 0.6 0.5 0.5 18.2 28.0 39.1 0 -7 39.2 76.6 31.3 34.0 4.8 418 47.2 15.0 15.0 1.4 28.5 28.9 23.8 SP EQN.13 EQN.11 28920.28907.28884.28868, 28851.28836.28826.28792.28780.28727.28641.28600.28591.28588.2849.9.28451.28449.28407.28395.28354.28243.28243.28218.28173.28018.27930.SALT KE EQN. 14 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1,000 1.000 1.000 1.000 1.000 1.000 1.000 1.000.1.i000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 14460.14454.14442.14434.14425.14418.14413.14396.14390.14364.14321.14300.14296.14294.14249.14226.14224.14204.14198.14177.14121.14121.14109.14086.14009.13965.ALLOW CYCLES 365397.366116.367461.368386.369387.370288.370834.372829.373546.376708.381903.384425.384960.385169.390691.393669.393854.396461.397234.399912.407140.407140.408793.411773.422270.428376.ALLOWABLE FOR 3*SM DELTA TI RANGE 54348.58680.53580.58680.54348, 60000.54348.54348.54348.54348.53580.54348.60000.54348.53580.53580.60000.54348.54348.535o0.60000.60000.54348.54348.53580.54348.792.1 822.5 798.3 822.5.801.4 863.0 788.7 817.3 817.3 792.1 822.9 792.1 840.6 792.1 798.3 814.2 840.6 792.1 792.1 823.9 889.7 889.7 804.7 8Q1.4 788.7 826.0 Notes b,d,e,k: Fails.g: Weld IS1 h,i: Rupture Location L: Information File No.: VY-16Q-311 Revision:
0 qStructural Integrity Associates, Inc.D S T C OM P U T E R S E R V I C E S S. A. .F-4.1 PAGE NO. 99++ DST/PIPESTRESS
++ Vermont Yankee Version 3.5.1+026 PC-EXE Release: Juj CALCULATION NUMBER 2 CODE SECTION III CLASS 1 ASNE-1998 Vermont Yankee Feedwater PipingSI Fatigue Analysis FATIGUE ANALYSIS AT POINT 155, LR ELBOW KRE 55 TO, 160 2007/07/11 11:35:07 [fl DELTA TI IN DEGREES STRESSES IN PSI 3 INDIVIDUAL STRESS RANGE CHECK LOAD SET SN SE DELTA T1 PAIR EQN.10 EQN.12 RANGE 27 24 13 23 31 30 5 20 15 3 21 28 28 9 1 17 30 3 25 24 19 9 3 1 21 15 28 35 23 44 44 43 31 42 27 28 28 34 43 43 42 20 34 30 42 39 36 34 9 23 23 23 27856.27875.27112.27648.27673.27360.27614.27614.22635.27578.27578.27578.27578.27041.27252.20982.27348.27340.27269.27275.26645.27030.27023.27078.27112.27112.26.0 34.0 4.7 1.4 27.2 21.2 51.4 28.6 31.0 30.8 31.3 30.8 7.7 24,7 28.9 35.0 1.8 1.9 13.0 0.5 42..9 1.7 1.7 1.7.0.1 24.3 SP EQN.13 EQN.11 27877.27877.27812.27729.27701.27675.27642.27634.27616.27599.27599.27599.27599.27572.27476.27436.27356.27344.27283.27276.27255.27252.27240.27208.27193.27193.SALT KE EQN. 14 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1:000 1.000 1. 000 1..000 1.000 1.000 1.000 1.000"1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 13939.13938.13906.13864.13851.13838.13821.13817.13808.13799.13799.13799.13799..13786.13738.13718.13678.13672.13642.13638.13628.13626.13620.13604.13597.13597.ALLOW CYCLES 432081.432125.436721.442732.444748.446650.449150.449757.451074.452344.452344.452344.452344.454392.461639.464734.470989.471943.476732.477271.478974.479249.480224.482793.483997.483997.ALLOWABLE FOR 3*SM DELTA Ti RANGE 53580.60000.60000.60000.54348..54348.54348.54348.58680.53580.53580.53580.53580.54348.60000.54348.54348.54348.53580..60000.58680.54348.54348.60000.60000.60000.788.7 840.6 853:1 846.3 817.3 792.1 827.0 821.2 822.5 763.1 763.1 763.1 763.1 801.4 893.7 801.4 792.1 792.1 818.0 840.6 841.7 801.4 801.4 878.3 833.8 833.8 I U I I U U I Notes b,d,ek: Fails g:. Weld ISI h,i: Rupture Location L: Information I File No.: VY-16Q-311 Revision:
0 I I I I I I Structural Integrity Associates, Inc.D S T C 0 M P U T E R S E R V I C E S S. A.F-4.1 PAGE NO. 99++ DST/PIPESTRESS
++ Vermont Yankee Version 3.5.1+026 PC-EXE Release: Jun CALCULATION NUMBER 2 CODE SECTION III CLASS 1 ASME-1998 Vermont Yankee Feedwater PipingSI Fatigue Analysis FATIGUE'ANALYSIS AT POINT 155, LR ELBOW INDIVIDUAL STRESS RANGE CHECK*********************************
KRE 55 TO 160 2007/07/11 11:35:07 [1 DELTA TI IN DEGREES STRESSES IN PSI LOAD SET SN SE DELTA Ti PAIR EQN.10 EQN.12 RANGE 18 2 18 31 24.22 17 20 12 3 21 31 20 7 30 15 12 11 27 25 2 19 1 1 13 43 36 18 38 43 45 23 25 33 27 31 31 34 27 24 31 20 30 43 31 33 19 38 33 5 43 44 26584.26584.26584.26861.27103.27100.20635.27026.25319.26861.26861.26861.26676.26861.26821.21992.25177.26180.26681.26682.26645.26645.25744.11502.26180.26148.0.0 3.2 3.2 3.6 0.5 0.8 76.6 14 .4 13.3 26 6 27.2 26.6 4.8 1.2 24 .8 26.2 10.3 24.9.21.8 27.1 39.7 39.7 14,8 78,2 20.3 23,6 SP EQN.13 EQN.11 27177.27177.27177.27177.27105.27103.27084.27046.26996.26889.26889.26889.26872.26862.26850.26795.26753.26738.26709.26696.26662.26662.26654.26550.26495.26464.SALT KE EQN. 14 1.000 1.000 1.000 1.000 1.000 1.000.1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 13589.13589: 13589.13588, 13552.13551.13542.13523.13498.13445.13445..13445.13436.13431.13425.13398.13376.13369.13355.13348.13331.13331.13327.13275.13248.13232.ALLOW CYCLES 485280.485286.485286.485321.491227.491420.492958.496131.500727.518868..518868.518868.521787.523582.525802.535458.543158.545912.551258.553668.560023.560023.561655.581619.592663.599029.* ALLOWABLE FOR 3*SM4 DELTA TI RANGE 60000.60000.60000.54348.60000.54348.53580.54348.58680.54348.54348.54348.54348.60000.54348.54348.58680.54348.54348.53580.58680.58680.60000.60000.54348.54348.866.8 899.7 899.7 766.8 853.1 804.7 798.3 819.2 843.2 766.8 766.8 766.8 792.1 840.6 792.1 801.4 843.2 801.4 792.1 816.1 868.4 868.4 889.7 905.8 826.0 817.3 Notes b,d,e,k: g: h,i: L: Fails Weld ISI Rupture Location Information File No.: VY-16Q-311 Revision:
0 I V Structural Integrity Associates, Inc.I D S T' C O M P U T E R S E R V I C E S S.A.F-4.1 PAGE NO. 99++ DST/PIPESTRESS
++ Vermont Yankee Version 3.5.1+026 PC-EXE Release: Ju CALCULATION NUMBER 2 CODE SECTION III CLASS 1 ASME-1998 Vermont Yankee Feedwater PipingSl Fatigue Analysis FATIGUE ANALYSIS AT POINT 155, LR ELBOW INDIVIDUAL STRESS RANGE CHECK KRE 155 TO 160 2007/07/11 11:35:07 [DELTA TI IN DEGREES*STRESSES IN PSI LOAD SET SN SE bELTA Ti PAIR EQN.10 EQN.12 RANGE 15 15 11 3 9 28 5 17 13 3 34 3 5 5 3 16 7 20 12 23.5 3 21 34 27 19 30 25 34.11 23 31 43 23 34 13 44 44 25 34 5 23 27 30 37 35 12 43 43 43 45 27 21583.21645.26168.26159.26247.2.6306.258 95: 26105.26168.26159.26137.26128.21935.25884.25875.23283.25238.25623.24207.25532.9038.25130.25130.25130.25182.25071.28.0 67.8 1.8 1.8 0.2 4.2 54.9 33-1 2.8 2.8 0.5 0.5 36.4 78.0 78.0 14.4 7.0 1.8 7.9 33.1 86.5 23.1 23.6 23.0 5.3 34.3 SP EQN.13 EQN.11 26463.26444.26418.26406.26328.26327.26211.26185.26175.26163.26144.26132.26033.25891.25879.25797.25752.25719.25687.25613.25567.25446.25446.25446.25379.25268.SALT KE EQN. 14 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 I. o00*0 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 13232.13222.13209.1-3203.13164.13163.13106.13093.13088.13082.13072.13066.13017.12946.22940.12899.12876.12859.12843.12807.12783.12723.12723.12723.12690.12634.ALLOW CYCLES 599165.603148.608383.610902.627410.627701.653074.658887.661145.663907.668334.671130.694402.729405.732486.753773.765629.774672.783405.803942.817215.852773.152773.852773.873244.908503.ALLOWABLE FOR 3*SM DELTA Ti RANGE 58680. 822.5 53580. 798.3 54348. 801.4 54348. 801.4 60000. 833.8 53580. 763.1 54348. 827.0 60000. 833.8 54348. 826.0 54348. 826.0 54348. 817.3 54348. 817.3 53580. .823.9 54348. 827.0 54348. 827.0 60000. 833.8 58680. 822.5 54348 ,. 792.1 60000. 888.0 60000. 833.8 60000. 870.6 54348. 766.8 54348. 766.8 54348. 766.8 58680. 836.3 58680. 813.2 Notes b,d,e,k: Fails 9: Weld ISI h,i: Rupture Location L: Information I I I I U U I I File No.: VY-16Q-3I 1 Revision:
0 I I I I I I Structural integrity Associates, Inc.D S T C O M P U T E R S E R V I C E S S.A.F-4 .1 PAGE NO. 99++ DST/PIPESTRESS
++ Vermont Yankee Version 3.5.1+026 PC-EXE RePease: Jun CALCULATION NUMBER 2 CODE SECTION III CLASS 1 ASME-1998 KRE 2007/07/11 11:35:07 (1 Vermont Yankee FeedwaterPipingSI Fatigue Analysis FATIGUE ANALYSIS AT POINT 155, LR ELBOW 155 TO 160 INDIVIDUAL STRESS RANGE CHECK DELTA TI IN DEGREES STRESSES IN PSI LOAD SET SN SE DELTA TI PAIR EQN.10 EQN.12 RANGE 18 23 1 3 21 3 18 23 20 40 16 7 7 39 35 30 12-19 18 9 5 17 8 5 41 6 27 39 20 34 34 21 30 45 25 42 24-23 30 42 42 45 19 30 37 27 18 42 23 40 42 42 24462.25107.*25126.25119..25119.25110.24320.24883.24601.24388.22175.24523.24186.24075.17634.24139.22716.24018.23350.23503.8182.17061.23283.8626.23398.23398.8.5 1.4 0.3 0.0 0.5 0.5 5.5 1.4 41.6 29.2 13.5 0.3 4.1 29.2 63.6 2.4 47.6 37.3 3.2 6.5 81.7*63.6 3.1 78.5 29.2 27.8 SP EQN.13 EQN.II"25252.25188.25146.25126.25126.25114.25009.24963.24621.24612.246.09;24604.24599.24300..24292.24235.24214.24114.2394 .23914.23823.23720.23681.23674.23623.23622.SALT KE. EQN.14 1.000 1.000 1.000 1.000 1.000 1.000 1.000-1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 12626.12594.12573.12563.12563..12557.12505.12482.12310.12306.12305.12302.12300.12150.12146.12118.12107.12057.11972.11957.11912.11860.11841.11837.11811.11811.ALLOW CYCLES 913613.934874.948882.955635.955635.959796.996650.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000..
>I000000.>1000000.>1000000.ALLOWABLE FOR 3*SM DELTA Ti RANGE 58680.60000.54348.54348.54348.54348.58680.60000..53580.60000.60000.60000.58680.60000.60000.58680.58680.58680.60000.58680.60000.60000.60000.60000.60000.60000.841.7 833.8 851.7 766.8 766.8 766.8 841.7 846.3 763.1 846.7 840.6 833.8 822.5 846.7 846.7 836.3 843.2 813.2 880.1 822.5 869.1 846.7 833.8 851.3 846.7 846.7 Notes b,d,e,k: Fails g- Weld ISI h,i: Rupture Location L: Information File No.: VY- 16Q-311 Revision:
0 I V Structural Integrity Associates, Inc.II D S T C O M P U T E R S E R V I C E S S.A.F-4. 1 PAGE NO. 99++ DST/PIPESTRESS
++ Vermont Yankee Version 3.5.1+026 PC-EXE Release: Juj CALCULATION NUMBER 2 CODE SECTION III CLASS 1 ASME-1998 KRE Vermont Yankee Feedwater PipingSI Fatigue Analysis FATIGUE ANALYSIS AT POINT 155, LR ELBOW INDIVIDUAL STRESS RANGE CHECK 155 TO 160 2007/07/11 11:35:07 1 DELTA TI IN DEGREES STRESSES IN PSI LOAD SET .SN SE DELTA TI PAIR EQN.10 EQN.12 RANGE 8 10 14 16 6 14 10 2 17 17 33 19 23 5 24 5 23 27 11 20 2 35 35 2 15 15 42 42 42 42'23 23 23 17 36 38 39 37 41 39 37 35 40 33 27 21 35 36 38 15 36 38 23398.23398.23398.23398.23283.23283.23283.17119.17119.17119.22569.23411.23283.8313.23355.1871.23146.22925.22635.23025.16547.16547.16547.18127.18127.18127.27.5 28.0 27.8 16'.1 2.7 2.7 2.5 34.4 31.3 34.4 15.0 39.7 1.4 78.5 0.5.113.0 1.4 9.7 6.6 0.6 34.4 31.3 34.4 25.7 22.5 25.7 SP EQN.13 EQN.11 23622.23622.23622.23622.23616.23607.23579.23553.23553.23553.23479.23428..23364.23362..23356.23354.23227.23122.23075.23045.22981.22981.22981.22911.22911.22911.SALT KE EQN.14 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1i000 1.000 1.000.1.000 1.000 1.,000.1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 11811.11811.11811.11811.11808.11803.11789.11777.11777.11777..11740.11714.11682.11681.11678.11677.11613.11561.11537.11522.13491.11491.11491.11456.11456.11456.ALLOW CYCLES>1000000.>1000000.>1000000.>1000000.>1000000&#xfd;>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000..
>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.ALLOWABLE FOR 3*SM DELTA Ti RANGE I 60000.60000.60000.60000.60000.60000.60000.60000.60000.60000.60000.58680.60000.60000.60000.60000.60000.58680.58680.54348..60000.60000.60000.60000.60000.60000.846.7 846.7 846.7 846.7 833.8 833.8 833.8 875.7 849.0 875.7 8A5.2 819.8 833.8 851.3 851.8 851.3 833.8 837.9 822.5 766.8 875.7 849.0 875.7 875.7 849.0 875.7 U I I I I Notes b,d,e,k: Fails g: Weld II h,i: Rupture Location L: Information I I File No.: VY- 16Q-311 Revision:
0 I I I I 1 1 Structural Integrity Associates, Inc.D S T C O M P U T E R -S E R V I C E S S. A.F-4.1 PAGE NO. 99 Release: Jun++ DST/PIPESTRESS
++ Vermont Yankee .Version 3.5.1+026 PC-EXE CALCULATION NUMBER 2 CODE SECTION III CLASS 1 ASME-1998 Vermont Yankee Feedwater PipingSI Fatigue Analysis FATIGUE ANALYSIS AT POINT 155, LR ELBOW INDIVIDUAL STRESS RANGE CHECK KRE 155 TO 160 2007/07/11 11:35:07 11 DELTA Ti IN DEGREES STRESSES IN PSI LOAD SET SN I SE DELTA TI PAIR EQN.10 EQN.12 RANGE 17 13 33 6 8 10 14 16 5 9 21 5 5 5 5 5 5 33 20 5 8 27 18 6 14 10 33 27 41 33 33 33 33 33 17 30 25 41 6 8 10 14 16 40 44 27 24 44 19 24 24 24 15555.22635.218.91.21891.21891.21891.21891.21891.1299.22450.22681.76368 7636.7636.7636.7636.7636.21767.22548.22346.22175.22291.21860.22175.22175.22175.49.5 2.0 15.0 13.7 13.3 13.9 13.7 2.0 113.0 3.5 42.2 78.5 77.2 76.8 77.4 77.2 65.5 15.0 0.6 73.2 2.2 5.3 42.9 1.8 1.8 1.6 SP EQN.13 EQN.11 22900.22832.-22801.22801.22801.22801.22801: 22801.22783.22761..22695.22685.22685.22685.22685.22685.22685.22677.22567.22543.22493.22488.22470.22428.22419.22391.SALT KE EQN. 14 1.000 1&#xfd;000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 11450.11416..11400..11400.11400.11400.11400.11400.11391.11381.11348.11342.11342..11342.11342".11342.11342.11339.11284.11271.11247.11244.11235.11214.11210.11195.ALLOW CYCLES>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.ALLOWABLE FOR 3*SM DELTA Ti RANGE 60000.58680.60000.60000.60000.60000.60000.60000.60000.58680.53580.60000.60000.60000.60000..60000.60000.60000.54348.58680.60000.58680.58680.60000.60000.60000.845.2 843.2 845.2 845.2 845.2 845.2 845.2 845.2 851.3 822.5 763.1 851.3 851.3 851.3 851.3 851.3 851.3 845.2 817.3 844.0 840.6 836.3 841.7 840.6 840.6 840.6 Notes b,d,e,k: Fails g: Weld ISI h,.i: Rupture Location L: Information File No.: VY-16Q-3 11 Revision:
0 Structural Integrity Associates, Inc.D S T C O M P U T E R S E R V I C E S S. .A F-4 .I.PAGE NO. 99++ DST/PIPESTRESS
++ Vermont Yankee Version 3.5.1+026 PC-EXE Release: Jun CALCULATION NUMBER 2 CODE SECTION III CLASS 1 ASME-1998 Vermont Yankee Feedwater PipingSI Fatigue Analysis FATIGUE ANALYSIS AT POINT 155, LR ELBOW INDIVIDUAL STRESS RANGE CHECK KRE 55 TO 160 2007/07/11 11:35:07 [I.DELTA TI IN DEGREESI STRESSES IN PSI LOAD SET SN SE DELTA Ti* PAIR EQN.10 EQN.12 RANGE 5 20 11 24 25 1 25 13 30 20 11 11 27 21 35 13 13 30 12 33 2 25 5 9 30 20 20 40 20 41 44 12 36 20 33 39 30 25 42 27 37 30 25 42 33 35 25 38 30 20 44 41 22281.22243.21992.22175.22161.20527.21427.21992.21873.21947.21583.21645.21615.21600.15300.21583.21645.21473.19125.14141.21427.21427.21294.21124.21261.21254.77.9 0.6 1.9 0.5 42.2 8.2 45.3, 2.8 12.6.0.6 3.7 43.5 23.8 5.3 34.4 1.0 38.8 26.8 23.0*49.5 42.2 42.2 76.1 1.7 2.4 0.6 SP EQN.13 EQN.11 22301.22263.22254.22176.22175.22056.22035.22011.21969.21967.21922.21902.21812.21797.21734.21679.21660.21569.21514.21486.21442.21442.21390.21358.21358.21274.SALT KE EQN. 14 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 11150.11132.11127, 11088.11088.11028.11017.11006.109.84.10983.10961.10951.10906.10898.10867.10840.10830.10784.10757.10743.10721.10721.10695.10679.10679.10637.ALLOW CYCLES>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>i000000.>1000000.>1000000.ALLOWABLE FOR 3*SM DELTA TI RANGE I 54348.54348.54348.60000.53580.60000.53580.54348.58680.54348.58680.53580.58680.54348.60000.58680.53580.58680.60000.60000.53580.53580;&#xfd;58680.54348.58680.54348.827.0 801.4 801.4 840.6 814.2 903.8 821.0 826.0 837.9 793.6 822.5 798.3 839.4 792.1 833.7 843.2 822.9 839.4 864.5 845.2 849.3 849.3 844.0 801.4 836.3 801.4 I I U U I I-Notes b,d,e,k: Fails g: Weld ISI h,i: Rupture Location L: Information I File No.: VY-16Q-311 Revision:
0 I I I I I I
!C~Structura~l integrity Associates, Inc.D S T C O M P U T E R S E R V I C E S S.A.F-4 .1 PAGE NO. 99++ DST/PIPESTRESS
++ Vermont Yankee Version 3.5.1+026 PC-EX8 Release: Jun CALCULATION NUMBER 2 CODE SECTION III CLASS 1 ASME-1998 Vermont Yankee Feedwater PipingSI Fatigue Analysis FATIGUE ANALYSIS AT POINT 155, LR ELBOW KRE.55 TO 160 2007/07/11 11:35:07 (1 DELTA TI IN DEGREES STRESSES IN PSI INDIVIDUAL STRESS RANGE CHECK LOAD SET SN SE DELTA TI PAIR EQN.10 EQN.12 RANGE 6 8 10 14 16 24 15 9 21 12 5 17 1 19 15 5 20 5 18 1 21 7 1 15 19 27 20 20 20 20 20 40 42 25 30 16 42 37 18 35 33 15 45 33 33 19 36 20 24 37 20 30 21254.21254.21254.21254.21254.21195.16052.20777.20547.16674.15762.13885.19670.13795.14547.289.19910.14258.18268.19731.19151.19391.19674.14893.19553.19370.0.8 1.1 0.6 0.7 12.5 0.5 54.8 43.3 2.4 21.0 49.4 34 .4 3.4 74 .1 40.7 104.2 0.6 63.5 18.2 39.4 3.2 2.3 0.7 25.7 39.1 3.0 SP EQN.13 EQN.11 21274.21274.21274.21274.21274..21197.21060.21006.20643.20587.20384.20319.20313.20247.20241.20122.19930.19800.19771.19748.19744.19728.19726.19677: 19573.19567.SALT KE EQN. 14 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 10637.10637.10637.10637.10637.10598: 10530..10503.10321.10294.10192.10160.10156.10124.10121.10061.9965.9900.9885.9874.9872.9864.9863.9839.9786.9784.ALLOW CYCLES>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000..
>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.ALLOWABLE FOR 3*SM DELTA TI RANGE 54348.54348.54348.54348.54348.60000.60000.53580.54348.60000.60000.60000.60000.58680.60000.60000.54348.60000.60000.58680.54348.54348.60000.60000.54348.58680.801.4 801.4 801.4 801.4 801.4 840.6 846.7 798.3 792.1 850.5 866.8 833.7*899.7 822.5 845.2 851.3 817.3 865.3 863.0 868.4 824.1 801.4 885.1 833.7 792.1 813.2 Notes b,d,e,k: Fails g: Weld ISI h,i: Rupture Location L: Information File No.: VY-16Q-31 1 Revision:
0 AoStructural Integrity Associates, Inc.D S T C O M-P U T E R S E R V I C E S S.A.F-4.1 PAGE NO. 100++ DST/PIPESTRESS
++ Vermont'Yankee-Version 3.5.1+026 PC-EXE Release: Juj CALCULATION NUMBER 2 CODE SECTION III CLASS 1 ASME-1998 Vermont Yankee Feedwater PipingSI Fatigue Analysis FATIGUE ANALYSIS AT POINT 155, LR ELBOW INDIVIDUAL STRESS RANGE CHECK KRE 155 TO 160 2007/07/11 11:35:07 1 DELTA Tl IN DEGREES.STRESSES IN PSI LOAD SET SN SE DELTA TI PAIR EQN.10 EQN.12 RANGE 2 23 23 23 7 13 25 36 19 7 2 21 12 19 16 17 12 42 2 13 11 2 38 8 19 6 23 24 36 38 25 36 45 44 25 42 21 38 40 42 18 19 39 45 13 38 36 44 44 12 33 12 19336.19336.19336.19336.19041.18127.19292.18638.19209.18656.19151.19151.17663.19013.15818.12380.17350.18564, 18127.18127.18127.18638.18638.16674.18426.16674.1.4 0.9 1.8 1.4 43.9 6.5 42.2 3.2 2.5 30.9 0.0 0.0 7.9 10.5 16.2 74.1 7.9 29.2 3.3 3.3 1.9 0.0 0.0 9.6 24.7 9.3 SP EQN,13 EQN.11 19416.19416.19416.19416.19373.19339.19306.19231.19227.19197.19151.19151.19143.19030.18843.18832.18830.18789.18746.18746.18720.18638.18638.18471.18443.18406.SALT KE EQN. 14 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 9708.9708.9708.9708.9686.9670.9653.9616.9613.9599.9576.9576.9572.9515.9422.9416.9415.9394.9373.9373.9360.9319.9319.9235.9222.9203.ALLOW CYCLES>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000:>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>2000000.>1000000.>1000000.>1000000.>1000000.ALLOWABLE FOR 3*SM DELTA TI RANGB.*60000.60000.60000.60000.53580.60000.53580.60000.53580.60000.54348.54348.60000.58680.60000.58680.60000.60000.60000.60000.60000.60000.60000.60000.58680.60000.878.3 843.2 851.6 878.3 798.3 868.4 814.2 861.5 788.7 846.7 851.7 851.7 850.5 839.4 849.0 822.5 850.5 859.2 903.8 903.8 849.0 888.2 888.2 850.5 837.9 850.5 I I I I I I I Notes b,d,e,k: Fails g: Weld ISI h,i: Rupture Location L: Information I File No.: VY-16Q-31 1 Revision:
0 I I I I I U I Structural Integrity Associates, Inc.D S T .C O M P U T E R. S E R V I C E S S. A.F-4:1 PAGE NO. 100++ DST/PIPESTRESS
++ Vermont Yankee Version 3.5.1+026 PC-EXE Release: Jun CALCULATION NUMBER 2 CODE SECTION III CLASS 1 ASME-1998 Vermont Yankee Feedwater PipingSl Fatigue Analysis FATIGUE ANALYSIS AT POINT 155, LR ELBOW I INDIVIDUAL STRESS RANGE CHECK KRE 2007/0.7/11 11:35:07 (i.55 TO 160 DELTA TI IN DEGREES STRESSES IN PSI LOAD SET SN SE DELTA TI PAIR EQN.IO EQN.12 RANGE 12 7 2 11 10 5 15 12 1 33 5 9 5 2 9 18 9 12 18 19 12 8 1 6 14 10 14.33 11 38 12 7 19 41 35 45 45 36 19 9 38 40 42 35 39 40 1,7 18 17 18 18 18 16674.17149.18127.18127.16674.2894.13.390.16674.11.620.17108.2922.17262.13679.17262.17262.16807.16920.10909.16494.16851.10337.15818.10205.15818.15818.15818..9.2 16.7 1.3 1.3 9.1 80.2 65.3 7.9 34 .7 15.0 78.5 2.0 38.8 1.2 1.2 3.2 30.3 26.5 3.2 39.7 26.5 4.9 34.7 4.5 4.5 4.3 SP EQN.13 EQN.11 18397.18376.18370.18370.18368.18259.18192.18154.18104;18018.17971.17855.17777.17476.17476.17400.17359.17343.17087.16868.16772.16727.16689.16662.16653.16625.SALT KE EQN. 14 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 i.000 1.000 1.000 1.000 i.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 9198.9188.9185.9185.9184.9130.9096.9077.9052.9009.8985.8927.8888.8738.8738.8700.8679.8672.8543.8434.8386.8364.8344.8331.8327.8312.ALLOW CYCLES>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.,>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000,>1000000.>1000000.>1000000.>1000000.ALLOWABLE FOR 3*SM DELTA T1 RANGE 60000.60000.60000.60000.60000.60000.58680.60000.60000.60000.60000.60000.58680.60000.60000.60000.60000.60000.60000.58680.60000.60000.60000.60000.60000.60000.850.5 845.2 875.7 875.7 850.5 851.3 822.5 850.5 875.7 857,7 863.8 849.0 844.0 875.7 875.7 849.0 846.7 850.5 849.0 822.5 850.5 849.0 875.7 849.0 849.0 849.0 Notes b,de,k: Fails q: Weld ISI h,i: Rupture Location L: Information File No.: VY-16Q-311 Revision:
0 I Structural Integrity Associates, Inc.I D S T C O M P U T ER S E R V I C E S S.A.F-4.1 PAGE NO. 100++ DST/PIPESTRESS
++ Vermont Yankee Version 3.5.1+026 PC-EXE Release: Ju------------------------------------- -- ---- -U CALCULATION NUMBER 2 CODE SECTION III CLASS 1 ASME-1998 Vermont Yankee Feedwater PipingSI Fatigue Analysis FATIGUE ANALYSIS AT POINT 155, LR ELBOW 1 INDIVIDUAL STRESS RANGE CHECK******************************
[KRE 155 TO 160 2007/07/11 11:35:07 f DELTA TI IN DEGREES STRESSES IN PSI LOAD SET SN SE DELTA TI PAIR, EQN.10 EQN.12 RANGE 16 25 33 19 36 9 11 18 5 1i 36 13 7 1 5 2 38 21 17 42 19 6 8 10 14 16 35 39 42 39 39 33 42 35 9 41 45 42 36 15 44 39 39 37 18 44 41 19 19 19 19 7752.16565.16341.16541.15947.15414.16052, 10053.1158.15818.15775.16052.15533.11213.964.15947.15947.15918.9481.15657.15861.15861.15861.15861.15861.15861.47.5 42.2 14.1 39.7 3.2 16.2 30.5 31.3 79.7 3.2 3.2 25.8 1.5 25.9 78.5 0.0 0.0 0.0 31.3 29.2 39.7 38.3 38.0 38.5 38.4 2.6.6 SP EQN.13 EQN.II 16619.16580.16565.16559.16540.16539.16519.16487.16421.16410.1,6368.16276.16126.16047.16013.15947.15947.15918.15915.15881.15879.15879.15879.15879.15879.15879.SALT KE EQN. 14 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 8309.8290;8283.8280.8270.8269.8259.8244.8210.8205.8184.8138.8063.8023.8007.7974.7974-7959.7958.7940.7940.7939.7939.7939.7939.7939.ALLOW CYCLES>1000000.>1000000.>1 000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>I000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>i000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.ALLOWABLE FOR 3*SM DELTA Ti RANGE.I 60000.53580.60000.58680.60000.60000.60000.60000.60000.60000.60000.60000.60000.60000.60000.60000.60000.54346.60000.60000.58680.58680.58680.58680.58680.58680: 831.2 787.5 860.7 822.5 849.0 845.2 846.7 849.0 851.3 849.0 861.5 866.1 849.0 875.7 863.8 875.7 875.7 788.7 849.0 859.2 822.5 822.5 822.5 822.5 822.5 822.5 I I I U I Notes b,d,e,k: g: h, i: L: Fails Weld ISI -Rupture Location Information I File No.: VY-16Q-31 1 Revision:
0 U I I I
* ~3Structural Integrity Associates, Inc.DST COMPUTER-SERVICES S.A.F-4.I PAGE NO. 100++ DST/PIPESTRESS
++ Vermont Yankee Version 3.5.1+026 PC-EXE Release: Jun CALCULATION NUMBER 2 CODE SECTION III CLASS 1 ASME71998 Vermont Yankee Feedwater PipingSI Fatigue Analysis FATIGUE ANALYSIS AT POINT 155, LR ELBOW.INDIVIDUAL STRESS RANGE CHECK KRE 2007/07/11 11:35:07 [1[55 TO 160 DELTA TI IN DEGREES STRESSES IN PSI LOAD SET SN SE DELTA T1 PAIR EQN.10 EQN.12 RANGE 2 7 12 5 2 38 11 5 13 13 37 25 5 21 16 33 11 35 15 8 19 6 25 14 21 10 7 38 42 21 45 45 33 11 37 33 44 37 13 42 17 44 37 39 16 35 21 35 40 35 33 35 15533.15533.14132.1765.15775.15775.14547.289.14893.14547.15404.15333.289.15018..6337.14277.14893.8429.7347.7752..14425.7752.14423.7752.13510.7752.1.7 1.7 37.1 78.5 0.0 0.0 16.3 79.8 3.3 11.7 0.0 42.2 75.2 29.2 47.5 15.0 1.3 34.4 38.7 36.1 39.7 35.8 42.2 35.8 15.0 35.6 SP EQN.13 EQN.11 15850.15850.15836.15814.15775.15775.15700.15581.15512.15457.15404.15347.15338.15242.15204.15187;15136.14863.14564.14503.14443.14438.14437.14429.14420.14400.SALT KE EQN. 14 ALLOW ALLOWABLE FOR CYCLES 3*SM DELTA T1 RANGE 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1..000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000.1.000 1.000 1.000 1.000 1.000 7925.7925.7918.7907.7888.7888.7850.7790.7756.7729.7702.7673.7669.7621.7602.7594.7568.7431.7282.7251.7221.7219.7218.7214.7210.7200.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>100000,0.
>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.60000.60000.60000.54348.60000.60000.60000.60000.60000.60000.60000.53580.60000.54348.60000.60000.60000.60000.60000.60000.54348.60000.53580.60000.54348.60000.875.7 875.7 866.1 827.0 888.2 888.2 845.2 851.3 888.0 864.5 857.6 784.2 870.6 821.2 831.2 857.7 833.7 831.2 831.2 831.2 792.1 831.2 798.3 831.2 819.2 831.2 Notes b,d,e,k: Fails g: Weld ISI h,i: Rupture Location L: Information File No.: VY-16Q-311 Revision:
0 V Structural Integrity Associates, Inc.I DST. COMPUTER SERVICES S.A.F-4.1 PAGE NO. 100++ DST/PIPESTRESS
++ *Vermont Yankee Version 3.5.1+026 PC-EXE Release: Jun-. .-...-.......-...-. ..----------: -..--..............- -----CALCULATION NUMBER 2 , CODE SECTION III CLASS, 1 ASME-1998 Vermont Yankee Feedwater PipingSI Fatigue Analysis.FATIGUE ANALYSIS AT POINT 155, LR ELBOW INDIVIDUAL STRESS RANGE CHECK KRE 155 TO 160 2007107/11 11:35:07[
1 DELTA T1 IN DEGREES STRESSES IN PS I, LOAD SET SN SE DELTA TI PAIR EON.10 EQN.12 RANGE 25 6 8 10 14 16 9 35 12 18.35 19 16 17 11 17 7 13 12 2 16 15 15 1 8 6 41 25 25 25 25 25 37 41 15 42 40 44 36 40 19 39 12 19 45'16 38 18 40 25 17 17 14299.14299.14299.14299.-14299.14299.14028.7752.9327.13275.7628.13999.10847.7326.13390..7014.11932.13390.11813.10847.10847.8471.8336.13083.6337.6337.42.2 40.8 40.5 41.0 40.8 29.1 1.2 34 .4 17.7 32.3 34.4 39.7 16.2 34..4 41.0 34.4 6.2 36.3 7.9 13.1 13.1 22.5 25.7 41.9 36.2 35.8 SP EQN.13 EQN.11 14314.14314.14314.14314.14314.14314.14242.14186.14111.14092.14063.14017.13873.13761.13651.13448.13411.13408.13293.13280.13280.13255.13120.13097.13088..13023.SALT KE EQN. 14 1.000 1.000 1.000 1.000 1.000.1.000 1.000 1.000 1.000 1.000 1.000 1.000.1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 7157.7157.7157.7157: 7157.7157.7121.7093.7056.7046.7031.7008.6936.6880.6825.6724.6706.6704.6647.6640.6640.6627.6560.6549.6544.6511.ALLOW CYCLES>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000 '>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000o ALLOWABLE FOR 3*SM DELTA TI RANGE I 53580.53580.53580.53580.53580.53580.60000.60000.60000.60000.60000.58680.60000.60000.58680.60000.60000.58680.60000.60000.60000.60000.60000.53580.60000.60000.798.3 798.3 798.3 798.3 798.3 798.3 833.7 831.2 850.5 864.5 831.2 836.3 849.0 831.2 822.5 831.2 850.5 843.2 863.0 875.7 875.7 849.0 831.2 849.3 831.2 831.2 I I I I I Notes b,d,e,k: Fails g: Weld ISI h,i: Rupture Location L:1 Information I I File No.: VY-16Q-311 Revision:
0 I I I I I I
* Structural Integrity Associates, Inc.D S T C O M P U T E R S E R V I C E S S. A.F-4.1 PAGE NO. 100++ DST/PIPESTRESS
++ Vermont Yankee Version 3.5.1+026 PC-EXE Release: Jun CALCULATION NUMBER 2 CODE SECTION III CLASS 1 ASME-1998 Vermont Yankee Feedwater PipingSI Fatigue Analysis FATIGUE ANALYSIS AT POINT 155, LR ELBOW KRE 155 TO 160 2007/07/11 11:35:07 (I DELTA T1 IN DEGREES STRESSES IN PSI INDIVIDUAL STRESS RANGE CHECK LOAD SET SN SE DELTA Ti PAIR EQN.10 EQN.12 RANGE 14 17 10 17 15 39 17 41 9 19 36 37 7 37 37 45 8 15 6 15 14 15 10 15 1 21 15 41 19 45 2 37 37 38 1 13 1 44 8 36 6 36 14 36 9 .12 7 18 10 36 18 45 6337.6337.8023.6337.12522.12027.12299.12541.7347.7347.7347.7347.12237.7347.12049.12027.12027.11213.11724.10847.10847.10847.10196.11075.10847.10961.35.8 35.6 25.7 34.4 40.8 3.2 1.7 0.0 27.4 27.0 27.0 26.8 0.3 25.7 39.7 0.0 0.0 3.1 0.3 4.9 4.5 4.5 6.8 1.5 4.3 3.2 SP EQN.13 EQN.11 13014.12986.12807.12771.12755.12620.12616.12541.12448.12382.12373.12345.12287.12131.22066.12027.12027.11832.11774.11757.11691.11682.11676.11668.11654.11553.SALT FE EQN. 14 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1,000 1.000 1.000 1.000 1.000 1.000 1.000"1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 6507.6493.6404.6386.6377.6310.6308.6271.6224.6191.6187.6i73.6144.6065.6033.6013.6013.5916.5887.5878.5846.5841.5838.5834.5827.5777.ALLOW CYCLES>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>10000QO.>1000000.>1000000.>1000000.>1000000.>i000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1ooo00o.>1000000.ALLOWABLE FOR 3*SM DELTA T1 RANGE 60000.60000.60000.60000.58680.60000.60000.60000.60000.60000.60000.60000.54348.60000.58680.60000.60000.60000.60000.60000.60000.60000.60000.60000.60000.60000.831.2 831.2 831.2 831.2 822.5 880.1 833.7 857.6 831.2 831.2 831.2 831.2 851.7 831.2 836.3 970.1 970.1 903.8 888.2 849.0 849.0 849.0 850.5 849.0 849.0 861.5 Notes b,d,.e,k:
Fails g: weld ISI h,i: Rupture Location L: Information FileNo.: VY-16Q-311 Revision:
0
{I Structural Integrity Associates, Inc.D S T C O M P U T E R S E R V I C E S S.A.F-4 .1 PAGE NO. 100.++ DST/PIPESTRESS
++ Vermont Yankee Version 3.5.1+026 PC-EXE Release: Juf CALCULATION NUMBER 2 CODE SECTION III CLASS 1 ASME-1998 Vermont Yankee Feedwater PipingSl Fatigue Analysis.FATIGUE ANALYSIS AT POINT 155, LR ELBOW ERE 155 TO 160 2007/07/11 11:35:07 [I DELTA Ti IN DEGREESm STRESSES IN PSI I INDIVIDUAL STRESS RANGE CHECK LOAD SET SN SE DELTA Ti PAIR EQN.10 EQN.12 RANGE 12 7 36 12 2 24 24 2 8 2 6 2 14 2 10 2 38 16 11 1 36 12 16 16 11 9 11 19 41 13 24 36 38 8 38 6 38 14.38 10 38 41 41 21 12 9 40 44 44 37 16 18 11213.11134.10847.9327.11328.11328.11328.10847.10847.10847.10847.10847.10847.10847.10847.10847.10847.8383.9327.10348.9867.8904.7878.7613.7347.9339.1.6 41.4 3.2 11.3 0.5 2.7 0.5 1.7 1.7 1.4 1.4 1.3 1.3 1.2 1.2 0.0 0.0 13.1 6.6 1.4 3.2 7.9 13.1 13:1 14.4 2.0 SP EQN.13 EQN.11 11506.11469.11440.11426.11330..11330.11330.11164.11164.11098.11098.11090.11090.11061;11061.10847.10847.10816.10807.10612.10460.10384.10311.10046.10023.9932.SALT KE EON.14 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000.1.000 1.0DOD 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 5753.5734..5720.5713.5665.5665.5665.5582.5582.5549.5549.5545.5545.5531.5531.5423.5423.5408.5404 5306.5230.5192.5156.5023.5011.4966.ALLOW CYCLES>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>i0o0000.>1000000.>1000000.>1000000.>1000000.>1000000,>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.ALLOWABLE FOR 3*SM DELTA Ti RANGE 60000.58680.60000.60000, 60000.60000.60000.60000.60000.60000.60000.60000.60000.60000.60000.60000.60000.54348.60000.60000.60000.60000.60000.60000.60000..60000.875.7 822.5 849.0 869.9 885.1 858.4 885.1 875.7 875.7 875.7 875.7.875.7 875.7 875.7 875.7 875.7 875.7 801.4 850.5 875.7 849.0 863.0 843.7 833.7 831.2 849.0 I I I I U Notes b;d,e,k: Fails g: Weld ISI h,i: Rupture Location L:' Information I I I File No.: VY-16Q-31 1 Revision:
0 I I I I I U I V Structural Integrity Associates, Inc.D S T C O M P U T E R S E R V I C E S S.A.F-4.1 PAGE NO. 100-++ DST/PIPESTRESS
++ Vermont Yankee Version 3.5.1+026 PC-EXE Release: Jun CALCULATION NUMBER 2 CODE SECTION III CLASS 1 ASME-1998 Vermont Yankee Feedwater PipingSI Fatigue Analysis FATIGUE ANALYSIS AT POINT 155, LR ELBOW INDIVIDUAL STRESS RANGE CHECK KRE 155 TO 160 2007/07/11 11:35:07 [1 DELTA Ti IN DEGREES STRESSES IN PSI LOAD SET SN SE DELTA TI PAIR EQN.10 EQN.12 RANGE 2 38 13 12 13 35 21 21 21 13 1 40.35 8 18 13 13 6 14 10 11 40 40 16 21 18 45 35 40 16 18 39.35 36 7 40 45 44.44 21 44 39 35 21 21 21 40 9867.9867.7347.8294.8471.3119.3009.9372.6478.8471.9063.2626.8346.8619.8336.8861.8864.2416.8383.8053.8023.1582.8383.8383.8383.8336.0.0 0.0 9.7 7.9 6.5 34 .4 32.7 0.0 14.2 1.9 0.0 34.4 3.4 2.0 3.3 0.3 0.0 34.4 1.7 3.2 3.3 37.8 1..4 1.3 1.2.1.3 SP EQN.13 EQN.11 9867.9867.9780.9774.9683.9554.9443.9373.9126.9064.*9063.9060.8989.8985.8955.8911.8865.8850.8700.8646.8643.8635.8635.8626.8598.8579.SALT KE EQN. 14 1.000 1.000 1.000 1.000 1.000 1.000.1&#xfd;000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 4934.4934.4890.4887..4841.4777.4722.4686.4563.4532.4531.4530.4494.4493..4478.4455.4432.4425.4350.4323.4321.4318.4317.4313.4299.4289.ALLOW CYCLES>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>i000o0o.>1000000.>1000000.>1000000.>1000000.>1.000000.
>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.ALLOWABLE FOR 3*SM' DELTA Ti RANGE 60000.60000.60000.54348.60000.60000.60000.54348.600oo.60000.54348.54348.60000.60000.60000.60000.60000.60000.54348.60000.60.000.60000.54348.54348.54348.60000.875.7 875.7 850.5 826.0 868.4 843.7 831.2 801.4 831.2 849.0 793.6 801.4 899.7 875.7 850.5.888.2 843.7 843.7 801.4 861.5 850.5 850.5 801.4 801.4 801.4 831.2 Notes bd,e,k: Fails q: Weld ISI h,i: Rupture Location L: Information File No.: VY-16Q-311 Revision:
0 VStructural Integrity Associates, Inc.DST COMPUTER SERVICES S.A.F-4 .1 PAGE NO. 100++ DST/PIPESTRESS
++ Vermont Yankee -Version 3.5.1+026 PC-EXE Release: Ju CALCULATION NUMBER 2 CODE SECTION III CLASS 1 ASME-1998 Vermont Yankee Feedwater PipingSI Fatigue Analysis FATIGUE ANALYSIS AT POINT 155, LR ELBOW KRE 155 TO. 160 2007/07/11 11:35:07 [3 DELTA T1 INDEGREESE STRESSES IN PSI INDIVIDUAL STRESS RANGE CHECK LOAD SET SN SE DELTA Ti PAIR EQN.10 EQN.12 RANGE 39 17 1 11 17 8 17 6 14 10 13 18 7 11 15 13 6 8 10.13 8 8 41 6 44 21 2 38 41 39 45 44 44 44 44 44 17 21 17 35 35 41 13 13 13 14 37 11 44 37 8578.2051.8346.8346.8383.8023.1772.7878.1760.7878.7878.7878.1010.7438.1594.1582.1582.7347.7347.7347.7347.7347.7613.7347.7878.7613.0.0 34.4 0.3 0.3 0.0 1.3 34 .4 1.7 34 .4 1.4 1.3 1.2 37.8 3.2 32.7 33.1 8.8 3.3 2.0 1.6 2.2 2.0 1.7 3.0 0.0 1.4 SP EQN.13 EQN.1I.8579.8485.8396.8396.8383.8266.8206.8195.8194.8130.8121.8093.8064.8031.8029.8016.8016.7966.7966.7966.7966.7966.7930.7906.7878.7865.SALT KE EQN.14 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 4289.4243.4198.4198.4192.4133.4103.4098.4097.4065.4060.4046.4032.4015.4014.4008.4008.3983.3983.3983.3983.3983, 3965.3953.3939.3932.ALLOW CYCLES>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.ALLOWABLE FOR 3*SM DELTA TI RANGE 60000.54348.60000.60000.54348.60000.60000.60000.60000.60000.60000.60000.60000.54348.60000.60000.60000.60000.60000.60000.60000.60000.60000.60000.60000.60000.843.7 801.4 970.1 970.1 801.4 831.2 843.7 843.7 843.7 843.7 843.7 843.7 850.5 824.1 831.2 831 2 831.2 850.5 850.5 850.5 850.5 850.5 833.7 831.2 843.7 833.7 I I I I I I I Notes b,d,e,k: Fails g: Weld IS]h~i: Rupture Location L: Information I File No.: VY-16Q-311 Revision:
0 I I I I I I IVStructural Integrity Associates, inc.D S T C O M P U T E R S E R V I C E S S.A.F-4.1 PAGE NO. U00++ DST/PIPESTRESS
+4 Vermont-Yankee Version 3.5,1+026 PC-EXE Release: Jun CALCULATION NUMBER 2 CODE SECTION III CLASS I ASME-1998-Vermont Yankee Feedwater PipingSI Fatigue Analysis FATIGUE ANALYSIS AT POINT 155, LR ELBOW I IIDLTSRC*********************
INDIVIDUAL STRESS RANGE CHECE KRE 155 TO. 160 2007/07/11 11:35:07 [1 DELTA TI IN DEGREES STRESSES IN PSI LOAD SET SN SE DELTA TI PAIR EQN.10 EQN.12 RANGE 14 17 6 10 10 37 9 9 1 37 11 16 7 16 11 15 15 7 9 8 6 9 37 9 9 37 35 11 14 37 11-40 35 40 39 41 41 39 16 45 17 17 45 15 39 9 9 14 39 10 41 7613.1415.7347..7347.7613.7347.7746.1273.7468.7602.7613.7347.5128.4742.5016.1010.1010.2654.2604.7155.6478.6478.6478.6911.6478.6478.1.3 0.0 2.7 2.6 1.2 2.5 0.0 33.3 1.2 0.3 0.0 1.3 13,1 14 .8 13.1 33.1 8.8 25.7 24.0 1.2 2.9 2.5 2.5 0.0 2.3 1.2 Sp EQN.13 EQN.11 7856.7850.7841.7832.7828.7804.7746.7707.7683.7652.7613.7589.7561.7493.7449.7444.7444.7438.7388.7370.7010.6945.6936.6911.6908.6693.SALT KE EQN. 14 1.000 1.000 i.00o 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 3928.3925.3921.3916.3914-3902.3873.3854.3841.3826.3807.3795.3780.3746.3725.3722.3722.3719.3694.3685.3505.3472.3468.3456.3454.3347.ALLOW CYCLES>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>i~oooo00.
>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.ALLOWABLE FOR 3*SM DELTA TI RANGE 60000.60000.60000.60000.60000.60000.60000.60000.60000.60000.60000.60000.60000.60000.60000.60000.60000.60000.60000.60000.60000.60000.60000.60000.-60000.60000.833.7 831.2 831.2 831.2 833.7 831.2 833.7 831.2 831.2 875.7 833.7 831.2 831.2.831.2 843.7 831.2 831.2 843.7 831.2 831.2 831.2 831.2 831.2 833.7 831.2 831.2 Notes b,d,e,k: Fails g: Weld ISI h,i: Rupture Location L- Information File.No.:
VY-16Q-31 1 Revision:
0 I Structural Integrity Associates, Inc.I U D S T C O M P U T E R S E R V I C E S S. A.F-4.1 PAGE NO. 101++ DST/PIPESTRESS
++ .Vermont Yankee Version 3.5.1+026 PC-EXE Release: Jul CALCULATION NUMBER 2 CODE SECTION III CLASS 1 ASME-1998 Vermont Yankee Feedwater PipingSI Fatigue Analysis FATIGUE ANALYSIS AT POINT 155, LR ELBOW INDIVIDUAL STRESS RANGE ChECK KRE 155 TO 160 2007/07/11 1i:35:07 DELTA TI IN DEGREES STRESSES IN PSI 5 LOAD SET SN -SE DELTA Ti PAIR EQN.10 EQN.12 RANGE SP EQN.13 EQN.11 SALT KE EON. 14 ALLOW CYCLES ALLOWABLE FOR 3*SM DELTA TI RANGE I 9 1 39 7 40 15 15 39 7 9 8 13 6 7 14 10 8 6 7 7 6 14 10 39 7 17 16 40 40 ,45 44 21 45 39 15 39 15 39 8 39 39 45 7 14 10 45 45 45 41 41 143.3933.6117.5732.5998.1059.i049.5775.5420.868.5128.0.5128.4742.5128.5128.5016.4742.4742.4742.5016.5016.5016.5128.4742.33.3 12.8 o1o 1.7 0.0 25.7 25.7 0.0 1.7 24.5 1.7 29.0 1.4 3.4 1.3 1.2 1.7 3.1 3.0 2.9 1.4 1.3 1.2 0.0 1.7, 0.0 6577. 1 000 3289. o100000o.6366. 1.000 3183. >1000000.6118. 1.000 3059.. >1000000..
6049. 1.000 3025. >1000000.5998. 1.000 2999. >1000000.5843. 1.000 2921. >1000000.5833. 1.000 2917. >1000000.5775. 1.000 2887. >1000000.5737. 1.000 2869. >1000000.5652. 1.000 2826. >1000000.5445. 1.000 2722. >1000000.5403. 1.000 2702, >1000000.5380. 1.000 2690. >1000000.5377. 1.000 2688. >1000000.5371. 1.000 2685. >1000000.5342. 1.000 2671. >1000000.5333. 1.000 2667. >1000000.5311. 1.000 2656. >1000000.5302. 1.000 2651. >1000000.5274. 1.000 2637. >1000000.5268. 1.000 2634. >1000000.5259. 1.000 2630. >1000000.5231. 1.000 2615. >1000000.5128. 1.000 2564. >1000000.5060. 1.000 2530. >1000000.5016. 1.000 2508. >1000000.60000.60000.60000.60000.60000.60000.54348.60000.60000.60000.60000.60000.60000.60000.60000.60000.60000.60000.60000.60000.60000..60000.60000.60000.60000.60000.831.2 875.7 831.2 831.2 843.7 843.7 801.4 843.7 831.2 831.2 831.2 850.5 831.2 831.2 831.2 831.2 843.7 831.2 831.2 831.2 843.7 843.7 843.7 831.2 831.2 843.7 I I U U 41 45 5016.Notes b,de,k: Fails g: Weld ISI h,i: Rupture Location L: Information I I I FileNo.: VY-16Q-311 Revision:
0 I I I I I I V StructuraI Integrity Associates, Inc.D S T COtMPUTER S E R V I C E S S. A.F-4 .1 PAGE NO. 101++ DST/PIPESTRESS
++ Vermont Yankee Version 3.5.1+026 PC-EXE Release: Jun-.......-. ..--. .--. ....------------------------CALCULATION NUMBER 2 CODE SECTION III CLASS 1 ASME-1998" KRE Vermont -Yankee Feedwater PipingSI Fatigue Analysis FATIGUE ANALYSIS AT POINT 155, LR ELBOW 155 TO 160 2007/07/11 11:35:07 11 DELTA Ti IN DEGREES STRESSES IN PSI INDIVIDUAL STRESS RANGE CHECK LOAD SET PAIR 11 15 1 8 1 6 1 14 1 10 1 40 1 41 7 21 1 37 21 45 7 13 7 44 44 45 16 40 13 45 7 11 11 45 16 41 6 16 8 16 i0 16 14 16 12 18 9 21 9 45 7 9 SN SE DELTA Ti EQN.10 , EQN.12 RANGE 0.3933.3933.3933.3933.4066.3933.3643.3680.3666.2604.3221.3528.990.2654.2604.2654.0.0.0.0.0.857.1911.1887.1736.24.4 1.4 1.1 1.0 0.9 0.3 0.3 1.7 0.3 0.0 5.0 1.7 0.0 13.1 3.3 0.4 1.3 13.1 11.7 11.4 11.9 11.8 4.8 1.2 1.2 0.5 SP'EQN.13 EQN.11 4784.4250.4184.4176.4147.4116.3983.3960.3730.3666.3540.3538.3528.3423.3273.2921.2897.2433.2433.2433.2433.2433.2337.2126.2102.2053, SALT KE" EQN.14 1.000.1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 2392.2125.2092.2088.2074.2058.1991.1980.1865.1833.1770.1769.1764.1712.1636.1461.1448.1217.1217..1217.1217.1217.1168.1063.1051.1027.ALLOW CYCLES>1000000;>1000000.>2000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.ALLOWABLE FOR 3*SM DELTA TI RANGE 60000.60000.60000.60000.60000.60000.60000.54348.60000.54348.60000.60000.60000.60000.60000.60000.60000.60000.60000.60000.60000.60000.60000.54348.60000.60000.831.2 875.7 875.7 875.7 875,7 875.7 875,7 801.4 970.1-0.0 850.5 843.7 0.0 831.2 863.0 831.2 843.7 831.2 831.2 831.2 831.2 831.2 868.4 801.4 843.7 831.2 Notes bd,e,k: Fails-g: Weld. ISl h'i: Rupture Location L: Information File No.: VY- 16Q-31 1 Revision:.
0 VStru ctural Integrity Associates, Inc.D S T C O M P U T E R S E R V I C E S S.A.F-4.1 PAGE NO. 101++ -DST/PIPESTRESS
++ Vermont Yankee --........ -Version -3.5.1+026-PC-EXE- --Release:-Jui CALCULATION NUMBER 2 CODE SECTION III CLASS 1 ASME-1998 Vermont Yankee Feedwater PipingSI Fatigue Analysis FATIGUE ANALYSIS AT POINT 155, LR ELBOW INDIVIDUAL STRESS RANGE CHECK KRE 155 TO 160 2007/07/11 11:35:07 (3 DELTA T1 IN DEGREESE STRESSES IN PSI LOAD SET SN SE DELTA Ti PAIR EQN.10 EQN.12 RANGE 9 9 13 13 7 8 11 ii 6 14 10 9 21 40 11 2 36 8 6 8 8 6 6 6 14 10 44 13 44 21 45 40 44 21 40 40 40 11 44 41 13 36.38 41 8.10 14 41 10 14 41 14 1642.868.1059.1049.-1057.990.1059.1049.990.990.990.868.1018.990.0.0.0.0.0.0.0.0.0.0.0.0.1.2 4.5 3.3 3.3 1.7 1.7 1.3 1.3 1.4 1.3 1.2 0.2 0.0 0.0 4.6 3.2 3.2 1.7 0.4 0.5 0.4 1.4 0.2 0.0 1.3 0.2 SP EQN.13 EQN.11 1857.1702.1678.1668.1374, 1307.1301.1292.1242.1233.1205.1111.1018.990.862.593.593.317.317.317.317.252.252.252.243.243.SALT KE EQN.14 1.000 1.000 1.000 1.000 1.000 1.000 1.000 I 000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1;000 1.000 1.000 1.000 929.851.839.834.687.654.651%646.621.616.602.556.509.495.431.296.296.159.159.159.159.126.126.126.121.121.ALLOW CYCLES>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>I000009.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.ALLOWABLE FOR 3*SM DELTA T1 RANGE 60000.60000.60000.54348.60000.60000.60000.54348.60000.60000.60000.60000.54348.60000.60000.60000.60000.60000.60000.60000.60000.60000.60000.60000.60000.60000.843.7 850.5 863.0 826..0 843.7 831.2 843.7 801.4 831.2 831.2 831.2 831.2 0.0 831.2 850.5 899.7"899.7 831.2 831.2 831.2 831.2 831.2 831.2.831.2 831.2 831.2 I I I I I I I Notes b,d,e,k: Fails g: Weld ISI h,i: Rupture Location L: Information I File No.: VY-16Q-311 Revision:
0 I I I I I I Structural Integrity Associates, Inc.D S T C 0 M P U T E R S E R V I C E S S. A.F-4 .1 PAGE NO. 101++ DST/PIPESTRESS
++ Vermont Yankee Version 3.5.1+026 PC-EXE Release: Jun CALCULATION NUMBER 2 CODE SECTION III CLASS I ASME-1998 Vermont Yankee Feedwater PipingSI Fatigue Analysis FATIGUE ANALYSIS AT POINT 155, LR ELBOW INDIVIDUAL STRESS RANGE CHECK KRE 155 TO 160 2007/07/11, 11:35:07 [1 DELTA TI IN DEGREES STRESSES IN PSI LOAD SET SN SE DELTA TI PAIR EQN.10 EQN.12 RANGE SP~EQN.13 EQN.ll SALT KE EQN. 14 ALLOW ALLOWABLE FOR CYCLES 3*SM DELTA TI RANGE 10 41 2 38 0-0.1.2 0.0 215. 1.000 0. 1.000 107. >1000000.
60000.0. >1000000.
60000.831.2 0.0 Notes b,d,e,k: Fails g: Weld ISI h,i: Rupture Location L: Information File No.: VY-16Q-31 1 Revision:
0 I vStructural Integrity Associates,Inc.
I U DST COMPUTER SERVICES S.A.F-4,2 PAGE NO. 101++/- DST/PIPESTRESS
++ Vermont Yankee Version 3.5.1+026 PC-EXE Release: Juj CALCULATION NUMBER .2 CODE SECTION III CLASS 1 ASME-1998 Vermont Yankee Feedwater PipingSI Fatigue Analysis FATIGUE ANALYSIS AT POINT 155, LR ELBOW INDIVIDUAL STRESS RANGE CHECK KRE 155 TO 160 2007/07/11 11:35:07 [DELTA Ti IN DEGREES STRESSES IN PSI LOAD SET PAIR I J.28 29 31 32 4 43 4 34 3 4 20 26 22 27 22 30 22 42 24 42 5 24.5 23 5 36 2 5 12 20 SALT EQN. 14 66456.54146.49733.49533.49512.45555.34161.32373.26170, 22860, 22397.21265.17029.16732.16409.NI 10 D 10 0 610 310 310 300 300 0 300 290 300 290 290 280 280 0 300 280 599 319 319 19 19 18 120 102 To 0 OCCURENCES
------NJ 10 0 10 0 300 0 10 0 300 0 10 0 10 0 10 0 300 20 20 0 280 0 300 0 1 0 18 0 290 280 NUMBER USED 10 10 300 10 300 10 10 10 280 20 280.300 1 18 10 SETS ELIMINATED DYNAM.28,29.31,32 43 34 3, 4 26 27 30 NO. CYCLES TO FAILURE 1808.3406.4465.4523.4529.5838.14370.172.57.USAGE FACTOR 0.0055 0.0029 0.0672 0.0022 0.0662 0.0017 0.0007 0.0006 0.0083 0.0004 0.0049 0.0041 0.0000 0.0001 0.0000 REMARKS I I I I 22 42 24 23 36 5 12 33637..51538..57040.73771.178513.190176, 205131.I I I I File No.: VY-16Q-311 Revision:
0 I I I I I V Structurallntegrity Associates, Inc.D S T C O M P U T E R S E R V I C E S S.A.F-4 .2 PAGE NO. 101++ DsT/PIPESTRESS
++ Vermont Yankee Version 3.5.1+026 PC-EXE Release: Jun CALCULATION NUMBER 2 CODE SECTION III CLASS 1 ASME-1998 Vermont Yankee Feedwater PipingSI Fatigue Analysis FATIGUE ANALYSIS AT POINT 155, LR ELBOW I INDIVIDUAL STRESS RANGE CHECK KRE 55 TO 160 2007/07/11 11:35:07 11 DELTA Ti IN DEGREES STRESSES IN PSI LOAD I 2 20 18 18 33 1 18 19.1 17.16 17 15 21 21 SET PAIR J 20 38 20 25 37 33 19 35 19 19 17 40 40 40 39 SALT EQN. 14 16030.16030.15537.15362.15167.13327.11235.10124.9874.9416.7602.6880.6560.4686.4531.NI 102 0 178 177 289 112 112 102 10 9 120 Iil 102 0 198 197 ill 0 289 203 70 0 133 0 70 0 300 214 214 0 OCCURENCES
-NJ 280 178 1 0 177 0 10 0 1 0 9 0 300 198 1 0 197 86 86 0 203 133 289 156 156 86 86 0 289 75 NUMBER USED 102 1 177 10 1 9 102 1 ill 86 70 133 70 86 214 SETS ELIMINATED DYNAM.2 38 20 25 37 33 18 35 1 19 16 17 15 40 21 NO. CYCLES TO FAILURE 228208.228208.263206.277200.-293826.561655.>1000000,.>1000000.
>1000000.>1000000.>1000000.>1000000.>1000000.>1000000.>i000000.USAGE FACTOR 0.0004 0.0000 0.0007 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 REMARKS File No.: VY-16Q-311 Revision:
0 Structural Integrity Associates, inc.I I D S T C 0 M P U T E R S E R V I CE S S.'A. F-4.2 PAGE NO. 101---S-"-I-STR-ES
-Ver"-nt Y anke Version 3.5.1+026 PC-EXE Release: Ju-++ DST/PIPESTRESS
++ Vermont YankeeVeso3.102 CEE Rlae:J CALCULATION NUMBER 2 CODE SECTION III CLASS 1 ASME-1998 Vermont Yankee Feedwater PipingSI.
Fatigue Analysis FATIGUE ANALYSIS AT POINT 155, LR ELBOW INDIVIDUAL STRESS RANGE CHECK KRE.55 TO 160 2007/07/11 11:35:07 [3 DELTA TI IN DEGREESE STRESSES IN PSI LOAD I 13 39 11 8 8 7 6 7 7 10 44 10 SET PAIR SALT J EQN.14 39 4321.44 4289.39 4133.11 3953.9 3505.8 2688.7 2656.14 2651.10 2637.5 2615.5 1764..1 107.NI 10 0 65 60 310-250 10000 9750 9750 7750 10000 2250 599.0 1651 1641 1641 S0 359 354 45 0 354 65 OCCURENCES
------ NUMBER SETS NO. CYCLES USAGE NJ USED ELIMINATED TO FAILURE FACTOR 75 65" 5 60 0 250 0 2000 0 7750 0 2250 1651 1.0 0 2000 359.E 0 45 0 289 0 10 5 45 60 250 2000 7750 599 10 1641 5 45 45 289 DYNAM.13 >1.000000.
44 >1000000.39 >i000000.11 >1000000.9 >1000000..
8 >1000000.6 >1000000.14 >1000000.7 >1000000.45 >1000000.45 44 >1000000.41 >1000000.0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000.0.0000 0.0000 0.0000 0.0000 REMARKS DYN. RANGE OF EVENT NO.I I I I 4 4 4 I TOTAL USAGE FACTOR =0.1661j I U I File No.: VY- 16Q-311 Revision:
0 I I I U I I NEC-JH_15 REDACTED VERSION Report No.: SIR-07-130-NPS Revision No.: 0 Project No.: VY-16Q File No.: VY-16Q-401 July 2007 Environmental Fatigue Analysis for the Vermont Yankee Reactor Pressure Vessel Feedwater Nozzles NOTE hi th Lidnr,,,,,,n,-,',, , -,-, t -,J"" ,f-'x; .44 d. ;04 .i04........
..........
_' i n a'cw rdan(c'_with uqir ;' ,tl, , ,,,, ,ir :roI -,_,'r., , .,, Preparedjbr:
Entergy Nuclear Operations, Inc.(Contract No. 10.150394)
Prepared by: Structural Integrity Associates, Inc.Centennial, CO%~>-r- ~-~9 Prepared by: Reviewed by: Approved by: M. Qyin Date: 7/26/2007 Date: 7/26/2007 Date: 7/26/2007 J. F.Spies -7 T. J."&#xfd;xrrmann, P.E.V Structural Integrity Associates, Inc.NEC066026 REVISION CONTROL SHEET Document Number: SIR-07-130-NPS Title: Environmental Fatigue Analysis for the Vermont Yankee Reactor Pressure Vessel Feedwater Nozzles Client: Entergy Nuclear Vermont Yankee. LLC-SI Proj2ectNumber:
MY-416 Section Pag(es Revision ]~Date Comments 1.0 1-1 8 0 07/26/07 Initial Issue 2.0 2-1 4 3.0 3-1 34 4.0 4-1-4-11 5.0 5-1-5-2 6.0 6-1 7.0 7-1 3 v Structural Integrity Associates, Inc.NEC066027 Table of Contents Section Page
 
==1.0 INTRODUCTION==
 
..........................................................................................................
1-1 1.1 Green's Function M ethodology
....................................................................................
1-2 2.0 FINITE ELEMENT M ODEL .....................................................................................
2-1 3.0 LOAD DEFINITIONS
.....................................................................................................
3-1 3.1 Thermal Loading ................................................
3-1 3.1.1 Heat Transfer Coefficients and Boundary Fluid Temperatures
..........................
3-1 3.1.2 Green's Function's
..............................................................................................
3-2 3.1.3 Thermal Transients (for grogram STRESS.EXE)
................................................
3-3 3 .2 P ressure L oading .........................................................................................................
3-4 3.3 Piping Loading .....................................................................................................
3-5 4.0 STRESS AND FATIGUE ANALYSIS RESULTS ..........
................
4-1 5.0 ENVIRONM ENTAL FATIGUE ANALYSIS ................................................................
5-1 6 .0 C O N C L U S IO N S ..............................................................................................................
6-1 7.0 R E F E R E N C E S ................................................................................................................
7-1 SIR-07-130-NPS, Rev. 0 iii V Structural Integrity Associates, Inc.NEC066028 Table Table 2-i.Table 3- 1: Table 3-2: Table 3-3: Table 3-4: Table 3-5: Table 4-1: Table 4-2: Table 4-3: Table 4-4: Table 4-5: List of Tables Page Material Properties
@ 300&deg;F ................
...... -Nodal Force Calculation for End Cap Load..............................................................
3-9 Maximum Piping Stress Intensity Calculations
...................................
...................
3-10 Heat Transfer Coefficients for Region 1 (40% Flow) .........................................
3-11 B lend R adius T ransients
..........................................................................................
3-12 S afe E nd T ransient ..................................................................................................
3-13 Feedwater Nozzle Blend Radius Stress Summary ....................................................
4-3 Feedwater Nozzle Safe End Stress Summary ...........................................................
4-5 Fatigue Parameters Used in the Feedwater Nozzle Fatigue Analysis .......................
4-7 Fatigue Results for Feedwater Nozzle Blend Radius ................................................
4-8 Fatigue Results for the Feedwater Nozzle Safe End ......................
4-10 I I I I I I I SIR-07-130-NPS, Rev. 0 iv Structural Integrity Associates, Inc.I I NEC066029 List of Figures Figure Page Figure 1-1. Typical Green's Functions for Thermal Transient Stress ........................................
1-7 Figure 1-2. Typical Stress Response Using Green's Functions
................................................
18 Figure 2-1: V Y Feedw ater N ozzle FEM .....................................................................................
2-3 Figure 2-2: VY Feedwater Nozzle FEM -Safe End/Nozzle Region .........................................
2-4 Figure 3-1: Feedwater Nozzle Internal Pressure Distribution
..................................................
3-14 Figure 3-2: Feedwater Nozzle Pressure Cap Load ...................................................................
3-15 Figure 3-3: Feedwater Nozzle Vessel Boundary Condition
.....................................................
3-16 F igure 3-4: T herm al R egions ....................................................................................................
3-17 Figure 3-5: Safe End Critical Thermal Stress Location and Linearized Stress Paths ...............
3-18 Figure 3-6: Brand Radius Critical Thermal Stress Location and Linearized Stress Paths ....... 3-19 Figure 3-7: Safe End Total Stress History for 100% Flow .......................................................
3-20 Figure 3-8: Safe End Membrane Plus Bending Stress History for 100% Flow ........................
3-20 Figure 3-9: Safe End Total Stress History for 40% Flow .........................................................
3-21 Figure 3-10: Safe End Membrane Plus Bending Stress Histoiy for 40% Flow ........................
3-21 Figure 3-11: Safe End Total Stress History for 25% Flow .......................................................
3-22 Figure 3-12: Safe End Membrane Plus Bending Stress History for 25% Flow ........................
3-22 Figure 3-13: Blend Radius Total Stress History for 100% Flow ..........................
3-23 Figure 3-14: Blend Radius Membrane Plus Bending Stress History for 100% Flow ..............
3-23 Figure 3-15: Blend Radius Total Stress History for 40% Flow ................................................
3-24 Figure 3-16: Blend Radius Membrane Plus Bending Stress History for 40% Flow ................
3-24 Figure 3-17: Blend Radius Total Stress History for 25% Flow ..... : .............
.........
3-25 Figure 3-18: Blend Radius Membrane Plus Bending Stress History for 25% Flow ................
3-25 F igure 3-19: T ransient 1, B olt-up .............................................................................................
3-26 Figure 3-20: Transient 2, D esign H Y D Test .............................................................................
3-26 F igure 3-2 1: T ransient 3, Startup ..............................................................................................
3-27 Figure 3-22: Transient 4, Turbine Roll and Increased to Rated Power ....................................
3-27 Figure 3-23: Transient 5, Daily Reduction 75% Power ............................................................
3-28 Figure 3-24: Transient 6, Weekly Reduction 50% Power ........................................................
3-28 Figure 3-25: Transient 9, Turbine Trip at 25% Power ..............................................................
3-29 Figure 3-26: Transient 10, Feedw ater Bypass .........................................................................
3-29 Figure 3-27: Transient 11, Loss of Feedwater Pumps ..............................................................
3-30 Figure 3-28: Transient 12, Turbine G enerator Trip ..................................................................
3-30 Figure 3-29: Transient 14, SRV B low dow n .............................................................................
3-31 Figure 3-30: Transient 19, Reduction to 0% Power .................................................................
3-31 Figure 3-31: Transient 20, Hot Standby (Heatup Portion) .......................................................
3-32 Figure 3-32: Transient 20A, Hot Standby (Feedwater Injection Portion) ................................
3-32 Figure 3-33: Transient 21-23, Shutdow n ..................................................................................
3-33 Figure 3-34: Transient 24, H ydrostatic Test .............................................................................
3-33 Figure 3-35: T ransient 25, U nbolt ...........................................................................................
3-34 Figure 3-36: External Forces and Moments on the Feedwater Nozzle .....................................
3-34 SIR-07-130-NPS, Rev. 0 v U Structural Integrity Associates, Inc.NEC066030
 
==1.0 INTRODUCTION==
 
In Table 4.3-3 of the Vermont Yankee (VY) License Renewal Application (LRA), the 60-year cumulative usage factor (CUF) value for the reactor pressure vessel (RPV) feedwater nozzle (FW) is reported as 0.750. Application of an environmentally assisted fatigue (EAF) multiplier, as required for the license renewal period, resulted in an unacceptable EAF CUF value of 2.86.Therefore, further refined analysis was necessitated to show acceptable EAF CUF results for this component.
REDACTED The VY FW nozzles were re-evaluated in detail by SI in 2004 for EPU and 60 years of operation.
However, that analysis used conservative transient definitions and cyclic projections for 60 years of operation that have since been updated as a part of LRA development.
This report documents a refined fatigue evaluation for the VY FW nozzle. The intent of this evaluation is to use refined transient definitions and the revised cyclic transient counts for 60 years for a computation of CUF, including EAF effects, that is more refined than previously performed fatigue analyses.
The fatigue-limiting locations in the FW nozzle and safe end are included in the evaluation, to be consistent with NUREG/CR-6260
[161 needs for EAF evaluation for license renewal.
The resulting fatigue results will be used as a replacement to the values previously reported in the VY LRA.I I I I I I I I I I I 1-I@F !f tritrfurrd Intpairitv
.4 z&#xfd;nrbn~ q n SIR-07-130-NPS, Rev. 0 (such information is marked with a "bar" in the right-hand margin)NEC066031 The refined evaluation summarized in this report included development of a detailed finite element model of the FW nozzle, including relevant portions of the safe end, thermal sleeve, and the RPV wall. Thermal and pressure stress histories were developed for relevant transients affecting the FW nozzle, including any effects of EPU, as specified by the VY RPV Design Specification
[3], the VY EPU Design Specification
[17] and other boiling water reactor (BWR)operating experience.
The thermal and pressure stress histories were used to determine total stress and primary plus secondary stress for use in a subsequent fatigue evaluation.
Stresses were also included due to loads from the attached piping for application in the stress/fatigue analysis based on the bounding reaction loads obtained from the relevant design documents.
The revised fatigue calculation was performed using Section III methodology from the 1998 Edition, 2000 Addenda of the ASME Code [15], and was performed using actual cycles from past plant operation projected out to 60 years of operation.
 
===1.1 Green's===
Function Methodology In order to provide an overall approach and strategy for evaluating the feedwater nozzle, the Green's Function methodology and associated ASME Code stress and fatigue analyses are described in this section.Revised stress and fatigue analyses are being performed for the feedwater nozzle using ASME Code, Section III methodology.
These analyses are being performed to address license renewal requirements to evaluate environmental fatigue for this component in response to Generic Aging Lessons Learned (GALL) Report [22] requirements.
The revised analysis is being performed to refine the fatigue usage so that an environmental fatigue factor can be determined for subsequent license renewal efforts.Two sets of rules are available under ASME Code, Section Il1, Class 1 [15]. Subparagraph NB-3600 of Section III provides simplified rules for analysis of piping components, and NB-3200 allows for more detailed analysis of vessel components.
The NB-3600 piping equations combine by absolute sum the stresses due to pressure, moments and through wall thermal gradient effects, regardless of where within the pipe cross-section the maximum value of the components of stress 1-2 Structural Integrity Associates, Inc.SIR-07-130-NPS, Rev. 0 NEC066032 are located. By considering stress signs, affected surface (inside or outside and azimuthal position, the stress ranges can be significantly reduced. In addition, NB-3600 assigns stress indices by which the stresses are multiplied to conservatively incorporate the effects of geometric discontinuities.
In NB-3200, these are not required, as the stresses are calculated by finite element analysis and any applicable stress concentration factors. This generally results in a net reduction of the stress ranges and consequently, in the fatigue usage. Article 4 [27]methodology was originally used to evaluate the feedwater nozzle. NB-3200 methodology, which is the modern day equivalent to Article 4, is used in this analysis to be consistent with the Section III design bases for this component, as well as to allow a more detailed analysis of this component.
In addition, several of the conservatisms originally used in the original feedwater nozzle evaluation (such as grouping of transients) are removed in the current evaluation so as to achieve as accurate a CUF as reasonably achievable.
For the feedwater nozzle evaluated as a part of this work, stress histories will be computed by a I time integration of the product of a pre-determined Green's Function and the transient data. This Green's Function integration scheme is similar in concept to the well-known Duhamel theory I used in structural dynamics.
A detailed derivation of this approach and examples of its application to specific plant locations is contained in Reference
[4]. A general outline is provided in this section.I The steps involved in the evaluation are as follows: I* Develop finite element model,* Develop heat transfer coefficients and boundary conditions for the finite element model* Develop Green's Functions* Develop thermal transient definitions" Perform stress analysis to determine stresses for all thermal transients
* Perform fatigue analysis I 1-3 Structural Integrity Associates, Inc.SINR-07-130-NPS, Rev. 03 NEC066033 A Green's Function is derived by using finite-element methods to determine the transient stress response of the component to a step change in loading (usually a thermal shock). The critical location in the component is identified based on the maximum stress, and the thermal stress response over time is extracted for this location.
This response to the input thermal step is the"Green's Function." Figure 1-1 shows a typical set of two Green's Functions, each for a different set of heat transfer coefficients (representing different flow rate conditions).
To compute the thermal stress response for an arbitrary transient, the loading parameter (usually local fluid temperature) is deconstructed into a series of step-loadings.
By using the Green's Function, the response to each step can be quickly determined.
By the principle of superposition, these can be added (algebraically) to determine the response to the original load history. The result is demonstrated in Figure 1-2. The input transient temperature history contains five step-changes of varying size, as shown in the upper plot in Figure 1-2. These five step changes produce the five successive stress responses in the second plot shown in Figure 1-2. By adding all five response curves, the real-time stress response for the input thermal transient is computed.The Green's Function methodology produces identical results compared to running the input transient through the finite element model. The advantage of using Green's Functions is that many individual transients can be run with a significant reduction of effort compared to running all transients through the finite element model. The trade-off in this process is that the Green's Functions are based on constant material properties and heat transfer coefficients.
Therefore, these parameters are chosen to bound all transients that constitute the majority of fatigue usage, i.e., the heat transfer coefficients at 300'F bound the cold water injection transient.
In addition, the instantaneous value for the coefficient of thermal expansion is used instead of the mean value for the coefficient of thermal expansion.
This conservatism is more than offset by the benefit of not having to analyze every transient, which was done in the VY reactor feedwater nozzle evaluation.
1-4 Structural Integrity Associates, Inc.SIR-07-130-NPS, Rev. 0 NEC066034 Once the stress history is obtained for all transients using the Green's Function approach, the remainder of the fatigue analysis is carried out using traditional methodologies in accordance with ASME Code, Section III requirements.
Fatigue calculations are performed in accordance with ASME Code, Section III, Subsection NB-3200 methodology.
Fatigue analysis is performed for the three limiting locations (two in the safe end and one in the nozzle forging, representing the three materials of the nozzle assembly)using the Green's Functions developed for the three feedwater flow conditions and 60-year projected cycle counts. 3 Three Structural Integrity utility computer programs are used to facilitate the fatigue analysis process: STRESS.EXE, P V.EXE, and FATIGUE.EXE.
The first program, STRESS.EXE, calculates a stress history in response to a thermal transient using a Green's Function.
The second program, P-V.EXE, reduces the stress history to peaks and valleys, as required by ASME Code fatigue evaluation methods. The third program, FATIGUE.EXE, calculates fatigue from the reduced peak and valley history using ASME Code, Section III range-pair methodology.
All three programs are explained in detail and have been independently verified for generic use in the Reference
[14] calculation.
I In order to perform the fatigue analysis, Green's Functions are developed using the finite I element model. Then, input files with the necessary data are prepared and the three utility computer programs are run. The first program (STRESS.EXE) requires the following three input I files: I Input file "GREEN.DAT":
This file contains the Green's Function for the location being evaluated.
For each flow condition, two Green's Functions are determined:
a membrane plus bending stress intensity Green's Function and a total stress intensity Green's Function.
This allows computation of total stress, as well as membrane plus bending stress, which is necessary to compute Ke per ASME Code, Section Ill requirements.
SIR-07-130-NPS, Rev. 0 1-5 V Structural Integrity Associates, Inc.NEC066035
* Input file "GREEN.CFG":
This file is a configuration file containing parameters that define the Green's Function (i.e., number of points, temperature drop analyzed, etc.)." Input file "TRANSNT.INP":
This file contains the input transient history for all thermal transients to be analyzed for the location being evaluated.
Pressure and piping stress intensities are also included for each transient case, based on pressure stress results from finite element analysis and attached piping load calculations.
The second program (P-V.EXE) simply extracts only the maxima and minima stress (i.e., the peaks and valleys) from the stress histories generated by program STRESS.EXE.
The third program (FATIGUE.EXE) performs the ASME Code peak event-pairing required to calculate a fatigue usage value. The input data consists of the output peak and valley history from program P-V.EXE and a configuration input file that provides ASME Code configuration data relevant to the fatigue analysis (i.e., Ke parameters, S.,, Young's modulus, etc.). The output is the final fatigue calculation for the location being evaluated.
The Green's Function methodology described above uses standard industry stress and fatigue analysis practices, and is the same as the methodology used in typical stress reports. Special approval for the use of this rnethodology is therefore not required.1-6 STR-07-130-NPS, Rev. 0 U Structural Integrity Associates, Inc.NEC066036 U-aI)a)U.)a)--U, Time (sec)92825f0 Note: A typical set of two Green's Functions is shown, each for a different set of heat transfer coefficients (representing different flow rate conditions).
Figure 1-1. Typical Green's Functions for Thermal Transient Stress I I I I I 1-7 V Structural Integrity Associates, Inc.STR-07-130-NPS, Rev. 0 NEC066037 4kMI 0 300.0250 zoo.+50S -50Stop~-25 Stop 50 _1q 1 200 AN0 600 800 1000 1200 1400 1600 1100 2000 ThW*m-a.~ to, 2*I-* 5.Figure 1-2. Typical Stress Response Using Green's Functions 1-8 V Structural Integrity Associates, Inc.SIR-07-130-NPS, Rev. 0 NEC066038 I I 2.0 FINITE ELEMENT MODEL A previously generated ANSYS [5] finite element model (FEM) of the VY feedwater nozzle and safe 3 end was used to perform the updated stress and fatigue analyses.
The details of the model development ire documented in the Reference
[6] calculation.
u A few key points with respect to model development are as follows:* The model is identical to the geometry and mesh of the model previously developed for feedwater nozzle fracture mechanics work performed for VY [7].* The boundary condition corresponding to the location of the start of the thermal sleeve in the FEM are consistent with Reference
[8].The materials of the various components of the model are listed below: I* Reactor Pressure Vessel -SA533 Grade B I* Reactor Pressure Vessel Cladding-Stainless Steel* Nozzle Forging -ASTM A508 Class II I* Safe End Forging -ASTM A508 Class I* Feedwater Piping -ASTM A106 Grade B I The FEM model the radius of RPV was increased by a factor of two to account for the fact that the vessel portion of the finite element model is a sphere and the actual geometry is a cylinder.I Material properties were based upon the 1998 ASME Code, Section II, Part D, with 2000 Addenda [9], and are shown in Table 2-1. The properties were evaluated at an average temperature of 300'F. This average temperature is based on a thermal shock of 500'F to 100&deg;F which was applied to the FEM model for Green's Function development.
The finite element model is shown in Figures 2-1 and 2-2.SIR-07-130-NPS, Rev. 0 2-1 Structural Integrity Associates, Inc.NEC066039
-m m -m- m-- -m- -m -m Table 2-1. Material Properties
@ 300'F ()Instantaneous Young's Coefficient of Density, Conductivity, Specific Heat, Poisson's Material Modulus, Thermal pDiffusivity,, d Rati Ident. E x 106 Expansion, (lb/in 3) (BTU/hrifiFit) (BTU/Ibm-dF) (assRat (psi) Ct x 10-6 (assumed) (see Note 5) (assumed)(in/in-&deg;F)
SA533 Grade B, A508 Class II 26.7 7.3 0.283 23.4 0.401 0.119 0.3 (see Note 2)SS Clad 27.0 9.8 0.283 9.8 0.160 0.125 0.3 (see Note 3)A508 Class I 2.7 28.1 7.3 0.283 32.3 0.561 0.118 0.3 (see Note 4)A10 GrdB 106 Grade B 28.3 7.3 0.283 32.3 0.561 0.118 0.3 (see Note 4)Notes I. The material properties applied in the analyses are taken from ASME Section II Part D 1998 Edition with 2000 Addenda. This is consistent with information provided in the Design Input Record (page 13 of VY EC No. 1773, SI File No. VY-16Q-209).
The use of a later code edition than that used for the original design code is acceptable since later editions typically reflect more accurate material properties than was published in prior Code editions.
Material Properties are evaluated at 300'F from the 1998 ASME Code, 2000 Addenda, Section II, Part D [9], except for density and Poisson's ratio, which are assumed typical values.2. Properties of A508 Class Hare used (3/4Ni-1/2Mo-1/3Cr-V).
: 3. Properties of 18Cr- 8Ni austenitic stainless steel are used.4. Composition
= C-Si.5. Calculated as k/(pd)/12 3.SIR-07-130-NPS, Rev. 0 2-2 V Structural Integrity Associates, Inc.NEC066040 ELEMEN T&#xfd;AN'SEP 6 2002 62 3 :5 1 Feedwater Nozzle--inite Element Model Figure 2-1: VY Feedwater Nozzle FEM SIR-07-130-NPS, Rev. 0 2-3 V Structural Integrity Associates, Inc.NEC066041 ELEMENTS Feedwater Nozzle Finite Element Model AN'SE , 2002 16:2 5: 12 Figure 2-2: VY Feedwater Nozzle FEM -Safe End/Nozzle Region SIR-07-130-NPS, Rev. 0 2-4 V Structural Integrity Associates, Inc.NEC066042 I 3.0 LOAD DEFINITIONS The pressure and thermal stresses for the feedwater nozzle for the revised fatigue evaluation 3 were developed using the axisymmetric FEM model described in Section 2.0 of this report. The details of the Green's function development and associated stress evaluation are documented in the Reference
[10] calculation.
 
===3.1 Thermal===
Loading I Thermal loads are applied to the feedwater nozzle model. The heat transfer coefficients after 3 power uprate were determined in Reference
[10]. These values were determined for various regions of the finite element model and for 100% (4,590 GPM), 40% (1836 GPM) and 25%(1,148 GPM) [10]. The annulus leakage flow rate is assumed to be 25 GPM for non-EPU conditions and 31 GPM for EPU conditions.
The 25 GPM value is calculated by scaling the 23 GPM [Page 6, 13] value up by approximately 9%. The 23 GPM value is scaled up to provide some conservatism and allow for inaccuracies in the determination of leakage flow. The 31 GPM value is calculated by multiplying the 25 GPM value by 1.25 [Page 6, 13]. Based on this, the annulus leakage flow rate is assumed to be 8 GPM for EPU conditions with 25% flow rate and 13 GPM for EPU condition with 40% flow rate. The temperatures used are based upon a thermal shock from 500OF to 100 0 F.3.1.1 Heat Transfer Coefficients an.d Boundaty Fluid Temperatures RefelTing to Figure 3-4, heat transfer coefficients were applied as follows: " The heat transfer coefficient for the outside surfaces of the FEM (Region 8) was a constant value of 0.2 BTU/hr-ft 2-&deg;F (3.858x10-7 BTU/sec-in 2-&deg;F).* Table 3-3 shows a sampling of the heat transfer coefficient calculations for Region 1 for the 40% flow case.For all Green's Functions, a 500'F to 100l F thermal shock was run to determine the stress response.SIR-07-130-NPS, Rev. 0 3-1 Structural Integrity Associates, Inc.NEC066043 The applied heat transfer coefficients and the initial temperatures for all regions are contained in Reference
[10].3.1.2 Green's Function's Three flow dependent thermal load cases were run on the FEM model with the heat transfer coefficients and the fluid temperature conditions listed above. Two locations were selected for analysis (see Figures 3-5 and 3-6): 1. The critical safe end location was chosen as the node with the highest stress intensity due to thermal loading under high flow conditions.
The highest stress intensity due to thermal loading occurred at Node 192 (see Figure 3-5), on the inside diameter of the nozzle safe end, and therefore, this node was selected for analysis.
Because the safe end stress response is affected by flow, three flow conditions were analyzed (100%, 40% and 25%).2. The critical blend radius location was chosen, based upon the highest pressure stress.Conservatively assuming the cladding has cracked, the critical location is selected as node 657 at base metal of the nozzle, as shown in Figure 3-6. Because the~blend radius stress response is affected by flow, three flow conditions were analyzed (100%, 40% and 25%).Two stress intensity time history were developed for each location and each flow case: (1) total stress intensity, and (2) membrane plus bending stress intensity.
The stress time histories for the safe end location, where the maximum stress was obtained for each of the flow conditions, are shown in Figures 3-7 through 3-12. The stress time histories for the blend radius location, where the maximum stress was obtained for each of the flow conditions, are shown in Figures 3-13 through 3-18.SIR-07-130-NPS, Rev. 0 3-2 17- Structural Integrity Associates, Inc.NEC066044 I I I 3.1.3 Thermal Transients (for program STRESS.EXE)
The program STRESS.EXE requires the following three input files for analyzing an individual transient:
* Green.dat.
There are 12 stress history functions obtained from Reference
[10]. They represent the membrane plus bending and total stress intensities at the blend radius and safe end locations.
Both of the blend radius and the safe end have two stress history functions for each of the following flow conditions; 100%, 40%, and 25% flow.* Green.cfg is configured as described in Reference
[14].* Transnt.inp.
These files are created to represent the transients shown on the thermal cycle diagrams and redefined by power uprate. Note that transients 12, 13, and 15 are nearly identical on the thermal cycle diagram [19] and the results from running transient 12 will be used for all three transients.
Transient 16, 17 and 18 will not be considered since there is no temperature change. Tables 3-4 and 3-5 show the thermal history used to represent each transient.
Based upon the thermal cycle diagram for the feedwater nozzle [19], the transients are split into the following groups based upon flow rate: o Transients 3, 20, 20A, and 21-23 are run at 25% flow. Although Reference
[19]shows 15% flow rate, it is conservative to use 25% flow rate for these transients.
Transient 20, Hot Standby, is split up into two parts. The first portion is "Heatup portion" and the second portion is "Feedwater Injection portion" that are defined from Reference
[19].o Transient 11 is run at 40% flow. Transient 11 starts off and ends at 100% flow.o Transients 5, 6, 9, 10, and 19 are run at 100% flow.o Transient 4 is run at 100% flow only to obtain the last stress point. The remainder of the stress points for transient 4 is obtained from the 25% flow stress results.The results are pulled from the two flow case results based upon the flow rates defined in the thermal cycle diagram [19].o Transients 12, 13, 14 and 15 were run at 100% flow. Heat transfer coefficients were not re-calculated for the 1 minute intervals each of these transients is at 110% flow. The effect of this small flow rate increase for such a relatively short duration should be minor.SIR-07-130-NPS, Rev. 0 3-3 Structural Intearitv Asson I I I I I I I I I I I I I I~iafe' Inc U I NEC066045 o Transients 1, 2, 24, and 25 are set as no thermal stress due to very small temperature changes (70'F to 100'F) at these transients.
 
===3.2 Pressure===
Loading A uniform pressure of 1,000 psi was applied along the inside surface of the feedwater nozzle and the vessel wall. A pressure load of 1,000 psi was used because it is easily scaled up or down to account for different pressures that occur during transients.
In addition, a cap load was applied to the piping at the end of the nozzle. The nodal forces shown in Table 3-1 [10] are defined by the following equation: S= )((R)R P f(/2 -I1 2)). (OR 2 _ IR 2 where: P unit pressure load = 1,000 psi IR inner pipe radius = 4.8345 in OR outer pipe radius = 5.42 in R = inside radius of element that node is attached to R, outside radius of element that node is attached to Fnofe average of the element forces on either side of the node.Note: The force on the innermost and outermost nodes is calculated as one haIf of theJbrce on the element that they are attached to.The calculated nodal forces were applied as positive values so they would exert tension on the end of the model. Figures 3-1, 3-2, and 3-3 show the internal pressure distribution, cap load, and syrnmetry condition applied to the vessel end of the model, respectively.
The pressure stress associated with a 1000 psi internal pressure was determined in Reference[10]. These values are as follows: Pressure stress for the safe end: SIR-07-130-NPS, Rev. 0 3-4 Structural Integrity Associates, Inc.NEC066046
* 8693 psi membrane plus bending stress intensity.
* 8891 psi total linearized stress intensity.
I Pressure stress for the blend radius:* 36653 psi membrane plus bending stress intensity.
0 37733 psi total linearized stress intensity.
I These pressure stress values for each location were linearly scaled with pressure.
The actual pressure for column 6 of Tables 4-1 and 4-2 is obtained from Tables 3-4 and 3-5. The scaled 3 pressure stress values are shown in columns 7 and 8 of Tables 4-1 and 4-2.The pressure stress is combined with the thermal and piping loads to calculate the final stress U values used for fatigue analysis.
The piping load sign is set as the same a's the thermal stress sign.I 3.3 Piping Loading I Additionally, the piping stress intensity (stress caused by the attached piping) was determined.
These piping forces and moments are determined as shown in Figure 3-36. I The following formulas are used to determine the maximum stress intensity in the nozzle at the two locations of interest.
From engineering statics, the piping loads at the end of the model can I be translated to the first and second cut locations using the following equations:
For Cut I: M .M,-FYL, (M, )t=M., -/F, L, For Cut 11: (My)) = M +/- + FrL, SIR-07-130-NPS, Rev. 0 3-5 Structural Integrity Associates, Inc.NEC066047 The total bending moment and shear loads are obtained using the equations below: M: /(Mv)L +(M.)z 2 For Cut I: M = (F)) +(F,))For Cut II: F,&#xfd;, = 2 + (F,)2 The distributed loads for a thin-walled cylinder are obtained using the equations below: N_ = I [I + F_1iF MI qN = V To determine the primary stresses, PM, due to internal pressure and piping loads, the following equations are used.For Cut I, using thin-walled equations:
SIR-07-130-NPS, Rev. 0 3-6' Structural Integrity Associates, Inc.NEC066048 I PaNz 2t. tv O = Pau I tN ("l )R = -_Pa q,v= qN MA XP,,) + (rM )orI SI " 2 Al ) Z ,9 where: L = The length fromn the end of the nozzle where the piping loads are applied to the location of interest in the safe end.L-, The length from the end of the nozzle where the piping loads are applied to the location of interest in the blend radius.Mxy = The maximum bending moment in the xy plane.Fyx = The maximum shear force in the xy plane.N, = The normal force per inch of circumference applied to the end of the nozzle in the z direction.
qN = The shear force per inch of circumference applied to the nozzle.RN = The mid-wall nozzle radius.Because pressure was not considered in this analysis, the equations used for Cut I are valid for 1 Cut II. Furthermore, since the pressure was not considered in this analysis, the equations can be simplified as follows: SIR-07-130-NPS, Rev. 0 3-7 Structural Integrity Associates, inc.NEC066049 Nz Ix () =0 tN 5'IMAX 2(r = ) (z)Per Reference
[11.]l, the feedwater nozzle piping loads are as follows: F, = 3,000 lbs M, = 28,000 ft-lb = 336,000 in-lb F, = 15,000 lbs MY = 13,000 ft-lb = 156,000 in-lb F, = 3,200 lbs M, = 40,000 ft-lb = 480,000 in-lb The loads are applied at the connection of the piping and safe end. Therefore, the L, is equal to 12.0871 inches and the L&#xfd; is equal to 27.572 inches. The calculations for the safe end and blend radius are shown in Table 3-2. The first cut location is the same as the Green's Function cross.section per [ 1 0] at the safe en ,d, and the second cut is fromn Node 645 (outside) to Node 501 (inside).
Tile maximum stress intensities due to piping loads are 5707.97 psi at the safe end and 265.47 psi at die blend radius, respectively.
These piping stress values are scaled assumning no stress occurs at an ambient temperature of 70'F and the full values are reached at reactor design temperature, 575TF. The scaled piping stress values are shown in columns 9 and 10 of Tables 4-1 and 4-2. Columns I11 and 1.2 of Tables 4-1 and 4-1 show the summation of all stresses for each thermal peak and valley stress point.SIR-07-130-NPS, Rev. 0 3-8 Structural Integrity Associates, Inc.NEC066050 Table 3-1: Nodal Force Calculation for End Cap Load Node Element Radius A Radius R2 -Ri2 Felement Fnode Number Number (in) (in) (in2) (b) (Ib)1 5.42 7678.0 1022 0.1171 1.25565 15356.1 2 5.3029 15188.4 1021 0.1171 1.22823 15020.7 3 5.1858 14853.0 1020 0.1171 1.20080 14685.3 4 5.0687 14517.6 1019 0.1171 1.17338 14349.9 5 4.9516 14182.2 1018 0.1171 1.14595 14014.5 6 4.8345 1 7007.3 SIR-07-130-NPS, Rev. 0 3-9 C Structural Integrity Associates, Inc.NEC066051 Table 3-2: Maximum Piping Stress Intensity Calculations Safe End External Piping Loads Parameters Fx 3.00 kips F = 15.00 kips Fz = 3.20 kips Mx= 336.00 in-kips My= 156.00 in-kips Mz= 480.00 in-kips OD= 11.86 in ID= 10.409 in RN= 5.57 in L = 12.09 in tN = 0.72 in (Mx)i = 154.69 in-kips (M')1 = 192.26 in-kips Mx_ = 246.77 in-kips Fxv = 15.30 kips N, 2.63 kips/in qN -1.59 kips/in Primary Membrane Stress Intensity PMz= 3.63 ksi"C =: -2.20 ksi Simax = 5.71 ksi SImax = 5707.97 psi Blend Radius External Piping Loads Pa ra meters Fx = 3.00 kips Fy= 15.00 kips Fz = 3.20 kips MX= 336.00 in-kips M = 156.00 in-kips Mz= 480.00 in-kips OD= 22.67 in ID= 10.750 in RN= 8.35 in L = 27.57 in tN = 5.96 in (M.)2 = -77.58 in-kips (M)2 = 238.72 in-kips Mxy = 251.01 in-kips Fx = 15.30 kips Nz = 1.21 kips/in qN= -0.51 kips/in Primary Membrane Stress Intensity PMz= 0.20 ksi S:-0.09 ksi Simax 0.27 ksi Slmax = 265.47 psi Note: The locations for Cut I and Cut II were defined in Reference radius paths, respectively.
[10] for safe end and blend Structural Integrity Associates, Inc.SIR-07-130-NPS, Rev. 0 3-10 NEC066052 Table 3-3: Heat Transfer Coefficients for Region 1 (40% Flow)Calculation of Heat Transfer Coefficients for Feedwater Nozzle Flow Path Pipe Inside Diameter, D = 9,69 1, inches=0.806 It 0.246 m Flow. % of rated = I > -40 .Fluid Velcity. V = 8.022 It/sec 1,836.0 gPm.Characteristic Length, L = D = 0.806 It = 0,246 r T.,&#xfd; -T,. AT = assumed to be 12% of fluid temperature 8.40 12.00 24.00 36.00 48 ,*t==:
4.67 6.67 13.33 20.00 26 100% rated floa = 74- 65'9 9 pm Denit4, 9/95867V Ibm/IS'0.793742524 Mttl/hr.00 60.00 72.00 'F.67 33.33 40.00 C mt ev 'r..ru,.m~m~.-
Value at Fluid Temperature, T [261 Units Conlversio 70 100 200 300 400 500 600 'F Water Property Factor [241 21 .11 37.78 93.33 148.89 204.44 260.00 315.56 C k 1.7307 0.5997 0.6300 0.6784 0.6836 0.6611 0,6040 0.5071 Wlm-*C.OL0ioiii0.3465 0.3640 0.3920 0.3950 0 3820 0.3490 0.2930 BTa/h,-ftt'F
.. ..... .. ... ....... ..! z a... .&#xa3; l t .................
..... .. ..... ... ........ ... .............
.. .... ..... .............
1 9 I R ..... ... ... ... ... ... ........ .... ... ... ...9.. L M... ... ... ... .............
... ... ... ... ...... .! J... ... .... ... ... ... ..... ...... ... ... ... .... ....... ...... ... .t. / I lh b -' F.E .14 4.1869 4.105 4.179 4.229 4.313 4.523 4.982 6.322 kJ/lg-'C p 16,018 997.1 994.7 "902 7 917.8 858.6 784.9 679.2 1r9/tm .(Demuiy) 62.3 62. 60. 57.3 53. 4904. bmill t 3 11 1.8 1.89E-04 3.24E-04 6.66E-04 1.01E-03 1.40E-03 1.986E-03 3.15E-03 m'/nt.'C_Volutttettic, Rate o1 Expansion)
I &#xfd;050-04 1.80E-4 3704 5600 .9-04 1.10E0-3 1.750-03 f1/t'lt-~F
..........
(. o &#xa3; e n ...........
.... ..n.".............
.............
.... .............................
... ...4........
........ ...8.... .................
....... I .. ..... ..... .....................
............
....... ..... ......: ......8 0.3048 9080 9.806 9.806 8.806 9.800 9.800 9.806 rl1.(G2ravita~tioeeat1.Coe~sta~nt) 32.17 32.17 32.17 32.17 32.17 32.17 32.17 Ivut.1.481 9.68-04 6.82E-04 3.07-E04 1.93E-04 1.38E-04 1.044-04 6.620-05 kg/r-s S(ol ~ocs.1)66004 400-4 2.060-54&#xfd; 1.30E-04 9.300-05 7.000-05 5.79E-05 lborIS-s Pr 6.980 4.510 1.910 1.220 0.906 0.859 .070 -IPrandtl Number)Calculated Parameter Formula 70 100 200 300 400 500 600 0F Reynold's Number, Re pVD/u 6.0147E-05 8.7645E005 1.8859E006 2.8491E006 3.7255E006 4.5248E+06 4.7336E-06 GrashoutNumber.
Dr g]14TL /(t: 1' 1.2852E008 6,6834E+08 1.2721E010 6.5918E+10 2.0931E+11 5.4429E+11 1.1372Er12
--Ra eiqh Number, Ra Gror 9.9710E+08 3.0142E009 2.4297E-10 8.0420E+10 1.9880E011 4.6755E+11 1.2168E+12
--From [24): Inside Surface Forced Convection Heat Transfer Coefficient:
Hur = 0.023Re'-PrWk;o 5.132.76 6.119.10 8,626.61 10,107.03 10,960.57 11,236.63 10 678.39 W/mt.9c-90-3 .90.]o:7.
1,0//so2.
i'v ru ls 930~r 31 1~ q,78 92 '-i71,90.61 ti B tulhr-1`12 0'F-.1704E03 .- 0E0 2.93100 3 3 434E.9$i3 -J7240-03-.
3 817F 03 ;i3 C28L 03v Btu/sec-irt'-&#xfd;F From [24]: Inside Sur/rce Natural Convection Heat Transfer Coefficient.
Case: Enclosed cyliuder C 0 11 L55 e 02 eepge 29 f [25])~H-,., C(GrPr)"k/L 232.43 330.57 59905 81628 988069 1,18154 1,192.73 W/m2-C 10 143 , 1741 5196 "10 06- u/s F 7 OSS71tOS -l:1236-04~
20390-041 2 7700-04 3 33090-00 3 4uu-L4- A 40020E-04 use-'F I I I I I I I I I I I I I I I SIR-07-130-NPS, Rev. 0 3-Hl Structural Integrity Associates, Inc.NEC066053 Table 3-4: Blend Radius Transients T s, i e ll 0 l : oepP e t r n lo c Te ' p T Sli e , Pr p r e s ur er [ Te. T-,t. p T h.t, S to p P , o -ll.rill06 O o. ..IP .. ... 'i .r,.,be, ".1h! Lk'11 b r...2. 0eoag.20 Cycrle 10 00 30 100o .....0 026 00 '0 3600 1100 00 100 4000 ::"7 '5......~l.P 5$00 Cycles 1900 2" 0 .. .. ' 610.... 070,; '" .... ....7i6 6... f60 302 laO"; 60,0,, 0 7" 000 .. .. IS OslIrhioc ioo% 0 302 11 300 W l 602 602....
0000 1013 300 Cycls 1014 } 040 ,13$64 i 1010 4. OTene Fla0 0 $40 i l010 0i- 2601 10 100 11 Ponr 102 26002 1 1010.... 25 100 0002... ! 000 1010[' 6i 10,0 $01011,..... .z% o,b., 0...... 21 1,6 7 :" i O........ ,0 20.k0,00 ,' 101 10000ly0 edu6 .o$ 002 000 1010 0ip0at05$
1060 200 1001. 1010 2000.. P0,11 .....003 1 100> 0 T] q : 1010, 1000 0 307 901, 1010 10.C........
00 00 '6o0 1010 10003 302 0000 1010 12, ,10lbm.5,r'01h. ,p 00 C~ycles..... l ... ." 1010 2 0 20 10 40 1100 0.1 $ 130 -152364 a " 40 1080 1130, 62100 000 60130 1135 2160 0 10 00 97305 S0 11,0 1100 1,Q ....14400 402 400 000o 1212115 0002 1010 o 302 1010......10 ' <'' "0# : " 7.j' 0 ._. 3.7 .13001...... q -_
00( %0 10 900 0: 43 2001 2600 i 4 4001 302 0301 1010 0001{"" " 302 00 ....... 710 0 ...20014Ol 5 1dby 0 265 6 1013 300 Cycks 0020 1104 304 10.. ...... O -.... ............
39ii"!
76..L-20 8925 040 0000 1010 20A I01 0l1016 0 0 540 1010 (FO'1~i, :lo .PorOn,.7 I..... " I 1' ' " 010 ..3201 CyI 101 100 , 0 ni10125 241 l20 00 10o 0 001 040 210 11 A90 040 0000 1010 223 Sh06owo 0 040 0 1010 30C,,-o 7. 0 3' 6264 0 IF 21, 604 33 0.0 00)5240 100C 20)5 24 1I1410o10110 0 l Ol 00 000$ 060X 100 0130 1064 00 100 00 0 25 1700 0 100 123.. Cyclesi 10...... ... $5" -" r." " 6' ..... .............
.... ....0" 0: -" 06 6 0 6....Note: 1. The indicated lime or presStrIe was assumed.2. 1375 psi is,1or Transient 13 only.I I SR0-3-PRv 3-12 C Structural Integrity Associates, Inc.NEC066054 Table 3-5: Safe End Transient T- T 1,ill 7 7- 1,100-. OoP.-T',,~,l 3o.p '<1007, a",os, 0017 010 Tol OLS~.P~o1
~1 0 10 B1Z031l 10 0 ,a 0 6 ........1" W H- I- 0 a 92 Oroi -- 000 dP 1-0 1 1000 I7 1: IO 2070 1, Y1...... ..... .... ..05 TotO -10705i ..11' $R0 -1 a 392 1 7l0 I10001i0 '. 00 .2.0. I 0 0 .a .HF-00 Go -,03 6 50&#xfd; 0 50 101, Teol 12' "vole 52oo0 100 , 3000 1 l00 5 a 000 1 -I .I 0 -0 ," o 0310 100 "X " 5.. .-I -' -, __ "-- _FVY Pu,,s IA.. F HP 16a 4 'u -e~l 0 -100 -0 0 F 0,1,OO 1010 I, 1 h 00 11 1, :100o 1, 1ola... ... ',10. ........ .,0,; ........000..1 .......... ,7o+ 1%.:; 412$... .. .02 500.1..Red to 0 I0 I a1010 L ' 2000 01-1 $ --70... ._ 07 ..., , , 3, ,1 000 1, ...10 41131. Rcu! 4032 500 1 101.... '"00,+7 U" 7010....f 2.. 203.... .t.... "0 1, .... ... 20 ... ..........
''+. ... 10.......
..H?)o 5000 -310 -500 101o 1 53 1 67271 101 a104 40 1 1 00..2' 501 1' .2- ice ].]]!]111405 -so 300 70072 5 54 1k----------+540145 000 1 210745 302 1000 1010 1010;3 1100 1135 r. HO I 21:I S n7 a) 4 L4) OlS 350 04045 04 7101 2 45 509 500 -110.0.1000. 6 13110,1 7 10 lO I 137 o5 33 00 7310 058 701 T0 l 600 : 100 0. 00 1503................
0.. .. ~ 10 600 ......70134923 0135- 000 7-270 OF '00 2~2- 005- 500 1270.1 C.[. -0 i1 o T 2s, is~ ....1171. 05 700 17010 252 0 03 .1 4'W' 1010 5300 ! 300 >1500 7Q00 13o..0'0707 0~p 001,70770 13100 '-I 00117 0 0 077.07 0 64730 0 320 3 -7010 010 500 lo ........ 70 900"' -' " -.: + + -" -93 ...990 103 79O -94 0510 75071 7 01.0 5097 092 000C 11i713 I I I I I I I I I I I I I I I I I Note: 1, These transients are the same as in Table 3-4 with the exception of lhe 500 second steady state time increment that is used. The transients in Table 3-4 are plotted using a 5000 second steady state increment.
The diffeorence is due to the length of the Green's Function for the safe end which is shorter compared to the blend Radius.2. The indicated tine or pressure was assumed.3. 1375 psi isbor iransient 13 only.SIR-07-130-NPS, Rev. 0 3-13 Structural Integrity Associates, Inc.NEC066055 I Figure 3-1: Feedwater Nozzle Internal Pressure Distribution SIR-07-130-NPS, Rev. 0 3-14 C Structural Integrity Associates, Inc.NEC066056
''ELEMENTS SEP 13 2002 12:17:30 Feedwater Nozzle Finite Element Model Figure 3-2: Feedwater Nozzle Pressure Cap Load SIR-07-130-NPS, Rev. 0 3-15 I structural in tegrity Associates, hnc.I NEC066057 ELEMENTS SEP 13 2002 12:20:02 Feedwater Nozzle Finite Element Model Figure 3-3: Feedwater Nozzle Vessel Boundary Condition SIR-07-130-NPS, Rev. 0 3-16 V Structural Integrity Associates, Inc.NEC066058 Region 7 Region 8 Regian I Regioni 4 Region 5 Region 6 I I I I I I I I I I I I I I I I I Notes: Point A: Point B: Point C: Point D: Point E: Point F: A B C B End of thermal sleeve = Node 204 = 0.25" from feedwater inlet side of thermal sleeve flat per Reference
[8].Beginning of annulus = Node 252.Beginning of thermal sleeve transition
= approximately 4.0" from Point A per Reference
[8] = Node 294, End of thermal sleeve transition
= approximately 9.5" from Point A per Reference
[8] = Node 387.End of inner blend radius (nozzle side) = Node 553.End of inner blend radius (vessel wall side) = Node 779.Figure 3-4: Thermal.Regions SIR-07-130-NPS, Rev. 0 3-17 V Structural Integrity Associates, Inc.I I NEC066059 p ~-t, p A VAP ': Figure 3-5: Safe End Critical Thermal Stress Location and Linearized Stress Paths.S1R-07-130-NPS, Rev. 0 3-18 V Structural Integrity Associates, Inc.NEC066060 AN.APR 11 Go,'15"2 5'940 7009 14278 ' 20747 27216 4574 11043 17512 23582 30451 Feedwaoer Nozzle Finite Element Model Figure 3-6: Brand Radius Critical Thermal Stress Location and Linearized Stress Paths SIR-07-130-NPS, Rev. 0 3-19 Structural Integrity Associates, Inc.NEC066061 Total Stress Intensity 70000 F~s-E x I 500000 _________
_________40(000 _________
_________20000 ______________________________
10000 4- _________
__________________
0-10000~- I- I 100 200 300 400 Time (sec)Figure 3-7: Safe End Total Stress History for 100% Flow Total Stress Intensity 50000-sz-sx 30000 20000 10000-1000o F I- I-F -0 100 200 300 400 500 Time (sec)Figure 3-8: Safe End Membrane Plus Bending Stress History for 100% Flow SIR-07-130-NPS, Rev. 0 3-20 U Structural Integrity Associates, Inc.NEC066062 Total Stress Intensity 50000 300130 *2O0OO 10000&#xfd;=J00 0 20000 10000 0 100 200 300 400 500 Ti-e (sec)Figure 3-9: Safe End Total Stress History for 40% Flow Total Stress Intensity 40000 3U0U 200S 1000 0 O0 0 100 200 300 400 500 Time (see)Figure 3-10: Safe End Membrane Plus Bending Stress History for 40% Flow SIR-07-130-NPS, Rev. 0 3-21 C Structural Integrity Associates, Inc.NEC066063 Total Stress Intensity 50000 40000 30000 20000 10000 0-10000 100 200 300 400 500 Tire (sec)Figure 3-11: Safe End Total Stress History for 25% Flow Total Stress Intensity 0 100 200 300 400 500 Time (ses)Figure 3-12: Safe End Membrane Plus Bending Stress History for 25% Flow SIR-07-130-NPS, Rev. 0 3-22 U .Structural Integrity Associates, Inc.NEC066064 Total Stress Intensity 30000 0 1000 2000 3000 4000 5000 Time (sec)Figure 3-13: Blend Radius Total Stress History for 100% Flow Total Stress Intensity 1000 2000 5000 Time (sect Figure 3-14: Blend Radius Membrane Plus Bending Stress History for 100% Flow S.IR-07-130-NPS, Rev. 0 3-23 V Structural Integrity Associates, Inc.NEC066065 Total Stress Intensity 0 1000 2000 3000 4000 Time (sec)Figure 3-15: Blend Radius Total Stress History for 40% Flow Total Stress Intensity 5000 30000 15000-1000 2000 3000 4000 5000 Time (sec)Figure 3-16: Blend Radius Membrane Plus Bending Stress History for 40% Flow SIR-07-130-NPS, Rev. 0 3-24 C Structural Integrity Associates, Inc.NEC066066 Total Stress Intensity 1000 2000 3000 4000 5000 Time (sec)Figure 3-17: Blend Radius Total Stress History for 25% Flow Total Stress Intensity 30000 15000 0 1000 2000 3000 4000 5000 Ti.e (sec)Figure 3-18: Blend Radius Membrane Plus Bending Stress History for 25% Flow SIR-07-130-NPS, Rev. 0 3-25 C Structural Integrity Associates, Inc.NEC066067
-Temp (&deg;F) 7- -Pressure (psig)I 80-I 60 50 S40.30 20 10-oJ=8-Stress.exe program calculates steady state values at beginning of transients.
The time length for this transient can therefore be any value greater than zero.The chosen length of 10 seconds has no significance as there is no temperature change during this transient.
-1 0 2 3 4 5 6 7 8 Time (seconds)Figure 3-19: Transient 1, Bolt-up[- Temp fFf) --Pressure (psig)]10 120 100 I----------------
an 6 60 40 20 o.-50 1000 2000 3000 4000 5000 6000 0 Time (seconds)Figure 3-20: Transient 2, Design HYD Test SIR-07-130-NPS, Rev. 0 3-26 C Structural Integrity Associates, Inc.NEC066068
[m-Temnp --- -- Pressure (pslg)]600 I I I I I I E o.o_5000 10000 15000 20000 Time (seconds)Figure 3-21: Transient 3, Startup 600 500 400 ,i 300 E"Stress e pregarattafi ycary J~e 'ready state condions at beginning b _ins mt 549 and sieps of transients.
This fnanien eginstha atad 54" adstp dss-med thatinea.y sace i...... ....... .... ;2,s 10800 1040 1000 960 920 880-840-000 760 7 20 680 6400 00 , 520 480 440 400 360 320 280 240 20 160 120 80 40 0 I I I I I I I I I 200 100 0 1000 2000 3000 4000 5000 6000 Tim. (seonds)7000 000 Figure 3-22: Transient 4, Turbine Roll and Increased to Rated Power SIR-07-130-NPS, Rev. 0 3-27 Structural Integrity Associates, Inc.I NEC066069
-- -- Pressre (psi9)00o -700 600 500 -"6 400-300 200-100 -1200 1160 1120 1080 1040 1000 00 920 880 840 800 760 720 680 640 600 5 580 520 T 480 a 440 400 360 320 200 240 200 100 120 80 40 0 Stress.exe program calculates steady slate values at beginning of transients, The time length tor this transient can thelrefoe be any value greater than zero. The chosen length of 10 seconds has no significance as here is no temperature change during this traensient.
0 1000 2000 3000 4000 5000 6000 7000 8000 Time (seconds)o00 500 Figure 3-23: Transient 5, Daily Reduction 75% Power[-Temp (-F) ---Pressure-(-si-400 300 E 200 1080 1040 1000 960 920 880 840 800 760 720 68o 640 600 560 520 480 440 400 360 320 280 240 200 160 120 8O 40 0 00.1 100.1 0 0 500 1000 1500 2000 2500 3000 3500 4000 4500 5000 5500 6000 6: Ti me (seconds)5 Figure 3-24: Transient 6, Weekly Reduction 50% Power SIR-07-130-NPS, Rev. 0 3-28 C Structural Integrity Associates, Inc.NEC066070 I- Temp ('F) -- Pressure (psig)450 400 350 300 o 250 200 1080 1040 1000=Q_0 1000 2000 3000 4000 5000 6000 7000 8000 9000 10000 Time (seconds)Figure 3-25: Transient 9, Turbine Trip at 25% Power 500-450-400-350-C 300 -250-200 150 100: 5o, I- Temp ('F) -Pressure (psig)1080 900 920 880 840 800 760 720 680 640 600 " 560 520 480 440 a 400 360 320 280 240 200 160 120 80 40 0 7000 1000 2000 3000 4000 5000 6000 Time (seconds)Figure 3-26: Transient 10, Feedwater Bypass SIR-07-130-NPS, Rev. 0 3-29 C Structural Integrity Associates, Inc.NEC066071 I-Temp (&deg;F) :- -Pressure (psig)600 550 500 450 400 350 1 300 a 250 200 1200 1000 B00 600 2 400 200-10 5000 10000 15000 20000 25000 Time (seconds)Figure 3-27: Transient 11, Loss of Feedwater Pumps I-Temp (-F) --Pressure (psig) ]6 1060 1020 980 940 900 860 820 a 780 740 o'700 660 620 580 540 500 4970-30 970 1970 2970 3970 Time (seconds)Figure 3-28: Transient 12, Turbine Generator Trip SIR-07-130-NPS, Rev. 0 3-30 C Structural Integrity Associates, Inc.NEC066072
[- Temp (-F) --Pressure (psig)1100 400 350 300 250 200 150 100 50 700 650 600 550 L 500 450 400 350 300 250 200 150 100 50 1000 2000 3000 4000 5000 Time (seconds)Figure 3-29: Transient 14, SRV Blowdown I-- Temp (') -- [ Pressure (Psig)]450 400 350 -300 250 200 -150-1060 1040 1000 960 920 880 840-800-760-720-680-640-600 560 ;-520-480-440 -400 360-320-280 240-200-160* 120-80-40 0 000 1000 1500 2000 2500 3000 3500 4000 4500 5000 5500 6000 6500 Time (seconds)Figure 3-30: Transient 19, Reduction to 0% Power SJR-07-130-NPS, Rev. 0 3-31 S Structural Integrity Associates, Inc.NEC066073 I I U I I I I I I I U I I I I U I Tem (&#xb6;rt f)&#xfd;- Presare(psi) 600 550 500 aSO400 350 1100 1000 900 800 T 600 S000 1000 100 200 300 400 500 600 700 600 900 Time (seconds)Figure 3-31: Transient 20, Hot Standby (Heatup Portion)I- Temp (*F) --Pressure (psig)600 500 400 300 200 1100 1000 This trnesi~en conteos at stead, 900 state to05451 seconds. d 800 700 600 500 700 800 900 1000 100 0 100 200 300 400 500 600 Time (seconds)
.Figure 3-32: Transient 20A, Hot Standby (Feedwater Injection Portion)I I SIR-07-130-NPS, Rev. 0 3-32 V Structural Integrity Associates, Inc.NEC066074 600 500 400 i 300 200 100 S1150-1100 1050 1000 950 900 850 800-750-700 650 6 800 550* 500 4150 400 350 300* 250 200 ,50 100&I I I I I I I I I I I I 20050 20000 0 2000 4000 6000 8000 10000 12000 14000 16000 18000 Time (seconds)Figure 3-33: Transient 21-23, Shutdown I- Temp (&deg;F) -- Pressure (psig)150 -130-110-90-is 70-E 50 30 10 --10-//////Si////1600 1500 1400 1300 1200 1100 1000 900 800 700 600 500 400 300 m///////f 200 100 0 100 200 300 400 500 600 700 800 Time (seconds)900 1000 1100 1200 1300 I I I I I Figure 3-34: Transient 24, Hydrostatic Test STR-07-130-NPS, Rev. 0 3-33 Structural Integrity Associates, Inc.1 NEC066075
-- Temp (&deg;F) --Pressure (psig), 150 13o0 110-p 90 70 500 400 300 200 a 100 30 10--10 5000 6000 0 1000 2000 3000 4000 Time (seconds)Figure 3-35: Transient 25, Unbolt Figure 3-36: External Forces and Moments on the Feedwater Nozzle STR-07-130-NPS, Rev. 0 3-34 C Structural Integrity Associates, Inc.NEC066076
 
===4.0 STRESS===
AND FATIGUE ANALYSIS RESULTS Fatigue calculations for the VY FW nozzle were performed in accordance with ASME Code, Section III, Subsection NB-3200 methodology (1998 Edition, 2000 Addenda) [15]. Fatigue analysis was performed in the Reference
[23] calculation for the two locations identified in Section 3.1.2 using the Green's Functions developed for these two locations and the 60-year projected cycle counts from Reference
[19].Tables 4-1 and 4-2 show the stresses for each location that were used in the fatigue analysis.Columns 2 through 5 of Table 4-1 (for the blend radius) and Table 4-2 (for the safe end) show I the final thermal peak and valley output. The pressure values for Column 6 in each table were determined from the transient pressures specified in Tables 3-4 and 3-5. The pressure stress 3 intensities from Section 3.2 were scaled appropriately for each transient case. The scaled piping stress values are shown in Columns 9 and 10 of Tables 4-1 and 4-2. The piping stress intensities from Section 3.3 were scaled based on the transient case RPV fluid temperature and assuming no stress occurs at an ambient temperature of 70 0 F. Both of these stress intensities were then added to the thermal stress intensity peak and valley points to calculate the final stress values used for the fatigue analysis.
In the case of the piping load stress intensities, the sign of the stress intensity was conservatively set to the same sign as the thermal stress intensity to ensure bounding fatigue usage results. Columns 11 and 12 of Tables 4-1 and 4-2 show the summation of all stresses for each thermal peak and valley stress point. The last column shows the number of cycles associated with each peak or valley based on the cycle counts shown in Tables 3-4 and 3-5.The program FATIGUE.EXE performs the ASME Code peak event-pairing required to calculate a fatigue usage value. The input data for the configuration input file for FATIGUE.EXE, which is named FATIGUE.CFG, is shown in Table 4-3.I SIR-07-130-NPS, Rev. 0 4-1 Structural Integrity Associates, Inc.NEC066077 The results of the fatigue analysis are presented in Tables 4-4 and 4-5 for the safe end and blend radius for 60 years, respectively.
The blend radius cumulative usage factor (CUF) from system cycling is 0.0636 for 60 years. The safe end CUF is 0.1471 for 60 years.SIR-07-130-NPS, Rev. 0 4-2 U Structural Integrity Associates, Inc.NEC066078 Table 4-1: Feedwater Nozzle Blend Radius Stress Summary 1- 2 3 4 5 6 7 8 1 9 10 1 11 12 13 Total M+B Total M+B Total Total Number Total M+B Pressure Pressure Piping Piping Total M+B of Transient Time Stress Stress Temperature Pressure Stress Stress Stress Stress Stress Stress Cycles Number is (psi) ( F (psi _) s (psi) (p i .(.psi) ( ) (psi) (60 years 1 0 0 0 70 0 0 0 0 0 0.00 0.00 123 0 0 0 70 0 0 0 0 0 0.00 0.00 120 2 1680 t 0 0 100 1100 41506.3 40318.3 15.77042 15.77042 41522.07 40334.07 120 108802 01 0 0 100 50 1886.65 1832.65 15.77042 15.77042 1902.42 1848.42 120 0 29166 23676 100 50 1886.65 1832.65 15.77042 15.77042 31068.42 25524.42 300 3 16782.8 -3577 -3138 549 1010 38110.33 37019.53 -251.801 -251.801 34281.53 33629.73 300 21164 -3532 -3138 549 1010 38110.33 37019.53 -251.801 -251.801 34326.53 33629.73 300 0 -3530 -3158 549 1010 38110.33 37019.53 -251.801 -251.801 34328.53 33609.73 300 4 1801.9 29465 22266 244.004 1010 38110.33 37019.53 91.47053 91.47053 67666.80 59377.00 300 8602 7720 6749 392 1010 38110.33 37019.53 169.2692 169.2692 45999.60 43937.80 300 0 7720 6752 392 1010 38110.33 37019.53 169.2692 169.2692 45999.60 43940.80 10000 5 2229.8 13598 11941 311.002 1010 38110,33 37019.53 126.6901 126.6901 51835.02 49087.22 10000 8600 7720 6752 392 1010 38110.33 37019.53 169.2692 169.2692 45999.60 43940.80 10000 0 7720 6752 392 1010 38110.33 37019.53 169.2692 169.2692 45999.60 43940.80 2000 6 2820.3 15742 13892 280.691 1010 38110.33 37019.53 110.7562 110.7562 53963.09 51022.29 2000 10400 7720 6752 392 1010 38110.33 37019.53 169.2692 169.2692 45999.60 43940.80 2000 0 7720 6752 392 1010 38110.33 37019.53 169.2692 169.2692 45999.60 43940.80 10 9 2524 29006 23417 118.311 1010 38110.33 37019.53 25.39616 25.39616 67141.73 60461.93 10 10400 7720 6752 392 1010 38110.33 37019.53 169.2692 169.2692 45999,60 43940.80 10 0 7720 6752. 392 1010 38110.33 37019.53 169.2692 169.2692 45999.60 43940.80 70 10 1632.4 16828 14701 267.399 1010 38110.33 37019.53 103.7688 103.7688 55042.10 51824.30 70 7070 7720 6752 392 1010 38110.33 37019.53 169.2692 169.2692 45999.60 43940.80 70 0 7720 6752 392 1010 38110.33 37019.53 169.2692 169.2692 45999.60 43940.80 10 3.5 6620 6632 565 1190 44902.27 43617.07 260.2119 260.2119 51782.48 50509.28 10 4.5 6190 6608 50 1185 44713.61 43433.81 10.51361 10.51361 50914.12 50052.32 10 194.5 31720 21067 109.348 1135 42826.96 41601.16 20.68448 20.68448 74567.64 62688.84 10 2166.3 -4761 -1859 513.483 972 36676,48 35626.72 -233.1304
-233.1304 31682.35 33534.59 10 11 2362.5 31268 22070 102.255 1010 38110.33 37019.53 16.95583 16.95583 69395.29 59106.49 10 6728.3 -4913 -3149 513.448 1010 38110.33 37019.53 -233.112 -233.112 32964.22 33637.42 10 7149.9 32114 21472 83.333 1010 38110.33 37019.53 7.0089 " 7.0089 70231.34 58498.54 10 18213.3 -3565 -3162 503.978 1010 38110.33 37019.53 -228.1338
-228.1338 34317.20 33629.40 10 19122.6 29156 23083 100.048 1010 38110.33 37019.53 15.79565 15.79565 67282.13 60118.33 10 26814.5 7720 6410 392 1010 38110.33 37019.53 169.2692 169.2692 45999.60 43598.80 10 0 7720 6752 392 1010 38110.33 37019.53 169.2692 169.2692 45999.60 43940.80 60 10 7720 6752 392 1135 42826.96 41601.16 169.2692 169.2692 50716.22 48522.42 60 12 30 7720 6752 392 940 35469.02 34453.82 169.2692 169.2692 43358.29 41375.09 60 2033.7 28648 25301 132.007 940 35469.02 34453.82 32.59588 32.59588 64149.62 59787.42 60 9591 7720 6752 392 1010 38110.33 37019.53 169.2692 169.2692 45999.60 43940.80 60 0 7720 6752 392 1010 38110.33 37019.53 169.2692 169.2692 45999.60 43940.80 1 10 7720 6752 392 1375 51882.88 50397.88 169.2692 169.2692 59772.14 57319.14 1 13 30 7720 6752 392 940 35469.02 34453.82 169.2692 169.2692 43358.29 41375.09 1 2033,7 28648 25301 132.007 1010 38110.33 37019.53 32.59588 32.59588 66790.93 62353.13 1 9591 7720 6752 392 1010 38110.33 37019.53 169.2692 169.2692 45999.60 43940.80 1 0 7720 6752 392 .1010 38110.33 37019.53 169.2692 169.2692 45999.60 43940.80 1 5960 28487 25650 100 50 1886.65 1832.65 15.77042 15.77042 30389.42 27498.42 1 0 7720 6752 392 1010 38110.33 37019.53 169.2692 169.2692 45999.60 43940.80 228 10 7720 6752 392 1135 42826.96 41601.16 169.2692 169.2692 50716.22 48522.42 228 15 30 7720 6752 392 940 35469.02 34453.82 169.2692 169.2692 43358.29 41375.09 228 2033.7 28648 25301 132.007 1010 38110.33 37019.53 32.59588 32.59588 66790.93 62353.13 228 9591 7720 6752 392 1010 38110.33 37019.53 169.2692 169.2692 45999.60 43940.80 228 0 7720 6752 392 1010 38110.33 37019.53 169.2692 169.2692 45999.60 43940.80 300 6800 16752 14971 265 1010 38110.33 37019.53 102.5077 102.5077 54964.84 52093.04 300 0 17151 13815 265 1010 38110.33 37019.53 102.5077 102.5077 55363.84 50937.04 300 20 8925 -3531 -3146 549 1010 38110.33 37019.53 -251.801 -251.801 34327.53 33621.73 300 0 -3530 -3158 549 1010 38110.33 37019.53 -251.801 -251.801 34328.53 33609.73 300 20A 183 28102 12153 233 1010 38110.33 37019.53 85.68595 85.68595 66298,02 49258.22 300 5451 -3530 -3158 549 1010 38110.33 37019.53 -251.801 -251.801 34328.53 33609.73 300 0 -3530 -3158 549 1010 38110.33 37019.53 -251.801 -251.801 34328.53 33609.73 300 20144 29168 23656 100 50 1886.65 1832.65 15.77042 15.77042 31070.42 25504.42 300 0 0 0 100 50 1886.65 1832.65 15.77042 15.77042 1902.42 1848.42 1 24 600 0 0 100 1563 58976.68 57288.64 15.77042 15.77042 58992.45 57304.41 1 2400 0 0 100 50 1886.65 1832.65 15.77042 15.77042 1902.42 1848.42 1 0 0 0 100 0 0 0 15.77042 15.77042 15.77 15.77 123 1580 01 0 70 0 0 0 0 0 0.00 0.00 123 I I I I I I I I I I I I I I I I For notes, see last page of table...I SIR-07-130-NPS, Rev. 0 4-3 Structural Integrity Associates, Inc.I NEC066079 Table 4-1: Feedwater Nozzle Blend Radius Stress Summary (continued)
NOTES: Column 1: Transient number identification.
Column 2: Time during transient where a maxima or minima stress intensity occurs fromP-V.OUT output file.ColuMn 3: Maxima or minima total stress intensity from P-V.OUT outpul file.Column 4: Maxima or minima membrane plus bending stress intensity from P-V.OUT output file.Column 5: Temperature per total stress intensity.
Column 6: Pressure per Table 3-4.Column 7: Total pressure stress intensity from the quantity (Column 6 x 37733)/1000
[Table3, 101.Column 8: Membrane plus bending pressure stress intensity from the qtuautity (Column 6 x 36653)/1000
[Table 3, 10].Column 9: Total external stress from calculation in Table 3-2, 265.47 psi*(Colunn 5-70'F)/(575 0 F-70F).Column 10: Same as Column 9, but for M+B stress.Column 11: Sum of total stresses (Columns 3, 7, and 9).Column 12: Sum of membrane plus bending stresses (Columns 4, 8, and 10).Column 13: Number of cycles for the transient (60 years).SIR-07-130-NPS, Rev. 0 4-4 V Structural Integrity Associates, Inc.NEC066080 Table 4-2: Feedwater Nozzle Safe End Stress Summary 1 2 3 4 5 6 7 8 9 10 11 12 13 Total M+B Total M+B Total Total Number Total M+B Pressure Pressure Piping Piping Total M+B of Transient Time Stress Stress Temperature Pressure Stress Stress Stress Stress Stress Stress Cycles Number LsI (psi) (psi) F (psi (psi) (i (psi) (psi) s L (60 yearsl 0 0 0 0 70 0 0 0 0 0.00 0.00 12'0 0 0 70 0 0 0 0 0 0.00 0.00 12C 2 1680 0 0 100 1100 9780.1 9562.3 339.0875 339.0875 10119.19 9901.39 12C 69601 0 0 100 50 444.55 434.65 339.0875 339.0875 783.64 773.74 12C 0 -170 -165 100 50 444.55 434.65 -339.0875
-339.0875
-64.54 -69.44 30C 153.2 -235 -212 104.256 50 444.55 434.65 -387.1927
-387.1927
-177.64 -164.54 300 16328.2 2 3 549 1010 8979.91 8779.93 5414.097 5414.097 143901 14197.03 30 16664 -1 0 549 1010 8979.91 8779.93 -5414.097 5414.097 3564.81 14194.03 300 0 2 549 1010 8979.91 8779.93 -5414.097
-5414.097 3562.81 3363.83 300 3.6 44060 30988 100 1010 8979.91 8779.93 339.0875 339.0875 53379.00 40107.02 300 1804.6 -15889 -11224 260.286 1010 8979.91 8779.93 -2150.787
-2150.787
-9059.88 -4594.86 300 4102 21 23 392 1010 8979.91 8779.93 3639.539 3639.539 12640.45 12442.47 300 0 22 23 392 1010 8979.91 8779.93 3639.539 3639.539 12641.45 12442.47 10000 900.1 244 189 310 1010 8979,91 8779.93 2712.7 2712.7 11936.61 11681.63 10000 5 3600 -169 -110 392 1010 8979.91 8779.93 -3639.539
-3639.539 5171.37 5030.39 10000 3684.4 33 35 392 1010 8979.91 8779.93 3639.539 3639.539 12652.45 12454.47 10000 4100 22 23 392 1010 8979,91 8779.93 3639.539 3639.539 12641,45 12442.47 10000 0 22 23 392 1010 8979.91 8779.93 3639.539 3639.539 12641.45 12442.47 2000 1800.1 196 159 280 1010 8979.91 8779.93 2373.612 2373.612 11549,52 11312.54 2000 6 5400.2 -108 -68 392 1010 8979.91 8779.93 -3639.539
-3639.539 5232,37 5072.39 2000 5496.6 29 31 392 1010 8979.91 8779.93 3639.539 3639.539 12648.45 12450.47 2000 5900 22 23 392 1010 8979.91 8779.93 3639.539 3639.539 12641.45 12442.47 2000 0 22 23 392 1010 8979.91 8779.93 3639.539 3639.539 12641.45 12442.47 10 97.3 180 137 385.135 1010 8979.91 8779.93 3561.945 3561.945 12721.85 12478.87 10 1884.1 63 65 265 1010 8979.91 8779.93 2204.069 2204.069 11246.98 11049.00 10 2059.2 1161 859 226.597 1010 8979.91 8779.93 1770.003 1770.003 11910.91 11408.93 10 9 3420.1 -334 -211 265 1010 6979.91 8779.93 -2204.069
-2204.069 6441.84 6364.86 10 3490.2 97 98 265 1010 8979.91 8779.93 2204.069 2204.069 11280.98 11082.00 10 5400.1 -126 -80 392 1010 8979.91 8779.93 -3639.539
-3639.539 5214.37 5060.39 10 5470.6 31 32 392 1010 6979.91 8779.93 3639.539 3639.539 12650.45 12451.47 10 5000 22 23 392 1010 8979.91 8779.93 3639.539 3639.539 12641.45 12442.47 10 0 23 22 392 1010 8979.91 8779.93 3639.539 3639.539 12642.45 12441.47 70 77.1 2308 3188 285.461 1010 8979.91 8779.93 2435.338 2435.338 13723.25 14403.27 70 169.4 13 265 1010 8979.91 8779.93 -2204.069
-2204.069 6763.84 6562.86 70 10 1890 74 72 265 1010 897991 8779.93 2204.069 2204.069 11257.98 11056.00 70 1968.2 -1069 -1511 322.362 1010 8979.91 8779.93 -2852.427
-2852.427 5058.48 4416.50 70 2147.2 91 90 392 1010 8979.91 8779.93 3639.539 3639.539 12710.45 12509.47 70 2570 23 22 392 1010 8979.91 8779.93 3639.539 3639.539 12642.45 12441.47 70 I I I I I I I I I I I I U 0-29-27 392 1011 8979.M 8779.931 -3639.5391
-3639.539 5311.37 5113.391 10 2.9-20317-13859 565 11471 10197.1 9970.871 -5594.944-5594.944-15713.97-9483.071 10 6.8 42852 29563 11 1567.4 -15216 2168.4 60377 5409.4 -14924 6730.4 60377 7243.2 -1963 18215.4 52636 20015.5 -24511 -22314.5 22 0 23 100 23 5651 11 565 11 50 11 721 10420.-10188.21 5594.944 5594.1 45346.141 10 10 10 10 10 6.11-2149.6231
-2149.623-17680.71-9558.69 10 i.341 3635.;39 11992.41 11807.884 10 3639.5391 12642.451 12441.471 60 3639.539 13753.82 13528.091 12 30 23 22 392 94, 60 60 60 60 90_ 3174 4383 275 9z 4, 2793.5-161891 -24511 260.183 9411 8366.43 5091 23 22 392 10101 8979.9 0 23 22 392 10101 8979.9 8779.93 10 23 22 392 13751 12225.1: 1 13 30_ 231 221 3921 9401 8357.54 90 3174. 43831 2751 9401 8357.54 1952.88 8171.42 8171.42 180.113 3639.539 3639.!I I I I 2793.5-161891 -24511-260.183 9411 8366.43 8 5091 231 22 392 10101 8979.9 8779.93 3639.539 3639.24 For notes, see last page of table...SIR-07-130-NPS, Rev. 0 4-5 Structural Integrity Associates, Inc.I NEC066081 Table 4-2: Feedwater Nozzle Safe End Stress Summary (continued) 1 2 .3 4 5 6 7 a 9 10 11 12 13 Total M+B Total M+B Total Total Number Total M+B Pressure Pressure Piping Piping Total M+B of Transient Time Stress Stress Temperature Pressure Stress Stress Stress Stress Stress Stress Cycles Number s (psi) (psi) F (psiq) (psi) (psi) (psi) (psi) (psi) (psi) (60 years 0 22 23 392 1010 8979.91 8779.93 3639.539 3639.539 12641.45 12442.47 1 60 4383 3174 275 885 7868.535 7693.305 2317.098 2317.098 14568.63 13184.40 1 14 148 420 300 258.492 803 7139.473 6980.479 2130.509 2130.509 9689.98 9410.99 1 960 544 424 100 50 444.55 434.65 339.0875 339.0875 1327.64 1197.74 1 1460 137 139 100 50 444.55 434.65 339.0875 339.0875 920.64 912.74 1 0 23 22 392 1010 8979.91 8779.93 3639.539 3639.539 12642.45 12441.47 228 10 23 22 392 1135 10091.29 9866.555 3639.539 3639.539 13753.82 13528.09 228 30 23 22 392 940 8357.54 8171.42 3639.539 3639.539 12020.08 11832.96 228 90 3174 4383 275 940 8357.54 8171.42 2317.098 2317.098 13848.64 14871.52 228 2793.5 -16189 -24511 260.183 941 8366.431 8180.113 -2149.623
-2149.623
-9972.19 -18480.51 228 5091 23 22 392 1010 8979.91 8779.93 3639.539 3639.539 12642.45 12441.47 228 0 22 23 392 1010 8979.91 8779.93 3639.539 3639.539 12641.45 12442.47 300 19 1800 219 177 265 1010 8979.91 8779.93 2204.069 2204.069 11402.98 11161.00 300 2300 72 74 265 1010 8979.91 8779.93 2204.069 2204.069 11255.98 11058.00 300 0 -109 -105 265 1010 8979.91 8779.93 -2204.069
-2204.069 6666.84 6470.86 300 20 4 -17288 -12189 440.106 1010 8979.91 8779.93 -4183.277
-4183.277
-12491.37
-7592.35 300 4425 1 549 1010 8979.91 8779.93 -5414.097
-5414.097 3563.81 3364.83 300 0 2 549 1010 8979.91 8779.93 -5414.097
-5414.097 3562.81 3363.83 300 4 44060 30988 100 1010 8979.91 8779.93 339.0875 339.0875 53379.00 40107.02 300 20A 241 -7461 -5525 290.247 1010 8979.91 8779.93 -2489.433
-2489.433
-970.52 765.50 300 572 128 132 549 1010 8979.91 8779.93 5414.097 5414.097 14522.01 14326.03 300 951 2 549 1010 8979.91 8779.93 -5414.097
-5414.097 3562.81 3363.83 300 0 2 549 1010 8979.91 8779.93 -5414.097
-5414.097 3562.81 3363.83 300 138 62 45 545.167 989 8793.199 8597.377 5370.773 5370.773 14225.97 14013.15 300 21-23 6264 20 374.97 50 444.55 434.65 -3447.05 -3447.05 -3007.50 -3032.40 300 6390 104 59 366.172 50 444.55 434.65 3347.607 3347.607 3896.16 3841.26 3001 15644 -173 -167 100 50 444.55 434.65 -339.0875
-339.0875
-67.54 -71.44 300 0 0 0 100 50 444.55 434.65 339.0875 339.0875 783.64 773.74 1 24 600 0 0 100 1563 13896.63 13587.16 339.0875 339.0875 14235.72 13926.25 1 2400 0 0 100 50 444.55 434.65 339.0875 339.0875 783.64 773.74 1 0 0 0 100 0 0 0 339.0875 339.0875 339.09 339.09 123 1580 0 0 70 0 0 0 0 0 0.00 0.00 123 NOTES: Column 1: Transient number identification.
Colurmn 2: Time during transient where a maxima or minima stress intensity occurs from P-V.OUT output file.Column 3: Maxima or minima total stress intensity froom P-V.OUT output file.Column 4: Maxima or minima membrane plus bending stress intensity from P-V.OUT output file.Column 5: Temperature per total stress intensity.
Column 6: Pressure per Table 3-5.Column 7: Total pressure stress intensity from tite quantity (Column 6 x 8891)/1000
[Table 3, 10].Column 8: Membrane plus bending pressure stress intensity from the quantity (Column 6 x 8693)/1000
[Table3, 10].Column 9: Total external stress from calculation in Table 3-2, 5707.97 psi*(Column 5-70 0 F)/(575 0 F -70 0 F).Column 10: Same as Column 9, but for M+B stress.Column 11: Sum of total stresses (Columns 3, 7, and 9).Column 12: Surn of membrane plus bending stresses (Columns 4, 8, and 10).Column 13: Number of cycles for the transient (60 years).SIR-07-130-NPS, Rev. 0 4-6 U Structural Integrity Associates, Inc.NEC066082 Table 4-3: Fatigue Parameters Used in the Feedwater Nozzle Fatigue Analysis Blend Radius Safe End Parameters in and n for 2.0 & 0.2 (low alloy 3.0 & 0.2 (carbon steel)Computing K, steel) [15] [15]Design Stress Intensity Values, 26700 psi [9] @ 600'F 17800 psi [9] @ 600'F Sm Elastic Modulus from 30.0x 106 psi [15] 30.0x 106 psi [15]Applicable Fatigue Curve 1 Elastic Modulus Used in Finite 26.7x10 6 psi [10] 28.1x10 6 psi [10]Element Model The Geometric Stress CnenGeometration Ftore1.0 1.34 [2, page 35 of S4]Concentration Factor Kt II I I I I I I I I I I I I I I I I I SIR-07-130-NPS, Rev. 0 4-7 V Structural Integrity Associates, Inc.I I NEC066083 Table 4-4: Fatigue Results for Feedwater Nozzle Blend Radius LOCATION = LOCATION NO. 2 -- BLEND RADIUS FATIGUE CURVE = 1 (1 = CARBON/LOW ALLOY, 2 = STAINLESS STEEL)m =2.0 n= .2 Sm = 26700. psi Ecurve &#xfd; 3.OOOE+07 psi Eanalysis 2.670E+07 psi Kt 1.00 MAX MIN RANGE MEM+BEND Ke Salt Napplied Nallowed I]74568.70231.69395.67667.67667.67667.67282.67142.66791.66791.66791.66791.66298.66298.66298.66298.66298.64150.64150.59772.58992.55364.55364.55364.55364.55042.54965.54965.54965.53963.53963.53963.53963.53963.53963.53963.53963.53963.53963.51835.51835.0.0.0.0.0.0.0.0.0.0.16.1902.1902.1902 .1902.30389.31068.31068.31070.31070.31070.31070.31682.32964.34282.34282 .34282.34317.34327.34327.34328.34329.34329.34329.34329.41522.43358 .43358.43358.43358.46000.74568.70231.69395.67667.67667.67667.67282.67142.66791.66791.66775.64889.64396.64396.64396.35909.35230.33081.33079.28702.27922.24293.23681.22400.21082.20761.20683.20648.20638.19637.19636.19635.19635.19635.19635.12441.10605.10605.10605.8477.5835.62689.58499..59106.59377.59377.59377.60118.60462.62353.62353.62337.60505.47410.47410.47410.21760.23734.34263.34283.31815.31800.25433.17402.17300.17307.18195.18463.18464.18463.17393.17401.17413.17413.17413.17413.10688.9647.9647.9647.7712.5149.1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 I.000 1.000 1.000 I.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1 .000 1.000 1.000 1 .000 1.000 1.000 1 .000 1.000 1.000 1.000 41892.39456.38986.38015.38015.38015.37799.37720.37523.37523.37514 36454.36177.36177.36177.20173.19792.18585.18584 16125.15687.13648.13304.12584.11844.11663.11620.11600.11595.11032.11031.11031.11031.11031.11031.6989.5958.5958.5958.4762.3278.1. OOOE+01 1. OOOE+01 1. OOOE+01 9. 300E+01 1 200E+02 8 700E+01 1 OOOE+01 1 OOOE+01 1 OOOE+00 1. 500E+01 1 .230E+02 9. OOOE+01 3. OOOE+01 1. OOOE+00 1. OOOE+00 1. OOOE+00 2. 670E+02 3. 300E+01 2 .700E+01 1. OOOE+00 1 .OOOE+00 2 .710E-i+02
: 1. OOOE+01 1. OOOE+01 9. OOOE+00 7 .OOOE+01 2. 210E+02 1. OOOE+01 6. 900E+01 2. 310E+02 3 000E+02 3. OOOE+02 3. OOOE+02 3. OOOE+02 3. OOOE+02 1 .200E+02 6 OOOE+01 1. OOOE+00 8 800E+01 1. 400E+02 3. OOOE+02 7. 488E+03 8.944E+03 9.268E+03 9. 988E+03 9.988E+03 9. 988E+03 1.018E+04 1.025E+04 1. 044E+04 1. 044E+04 1. 045E+04 1. 152E+04 1. 182E+04 1. 182E+04 1. 182E+04 9. 581E+04 1. 038E+05 1. 303E+05 1. 303E+05 2 .222E+05 2. 519E+05 4 .757E+05 5. 703E+05 9 414E+05 1. 912E+06 2. 231E+06 2.310E+06 2. 348E+06 2.358E+06 3. 757E+06 3 .758E+06 3. 760E+06 3. 760E+06 3. 760E+06 3.760E+06 1. 000E+20 1. 000E+20 1. 000E+20 1. 000E+20 1. 000E+20 1 .000E+20.0013.0011.0011.0093.0120.0087.0010.0010 0001 0014.0118.0078.0025 0001 0001.0000.0026.0003.0002.0000.0000.0006.0000.0000.0000.0000.0001.0000.0000.0001.0001.0001.0001.0001.0001.0000.0000 0000 0000.0000.0000 SIR-07-130-NPS, Rev. 0 4-8 C Structural Integrity Associates, Inc.NEC066084 51835.51782.50914.50716.50716.46000.46000.46000.46000.46000.46000.46000.46000.46000.46000.46000.46000.46000.46000.46000.46000.46000.46000.46000.46000.46000.46000.46000.46000 46000.46000.46000.46000.46000.46000.46000.46000.46000.46000.46000.46000.46000.46000.46000.5835.5783.4915.4717.4717.0.0.0.0.0.0.0.0.0.0.0.0.0.0.0.0.0.5146.6568.6112.4582.4582.0.0.0.0.0.0.0.0.0.0.0.0.0.0.0.0.0.1.000 1.000 1.000 1.000 1.000 1 .000 1.000 1.000 1.000 1.000 1.000 1.1000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1 .000 3278.3249.2761.2650.2650.0.0.0.0.0.0.0.0.0.0.0.0.0.0.0.0.0.9. 560E+03 1. OOOE+01 1.OOOE+01 6. OOOE+01 2. 280E+02 1.320E+02 1. OOOE+04 2. OOOE+03 2. OOOE+03 1. OOOE+01 1. OOOE+01 7. OOOE+01 7. OOOE+01 1. OOOE+01 1. OOOE+01 6. OOOE+01 6. OOOE+01 1. 000E+00 1. OOOE+00 1. OOOE+00 2. 280E+02 2. 280E+02 1 OOOE+20 1 OOOE+20 1 OOOE+20 1 OOOE+20 1 OOOE+20 1 OOOE+20 1 OOOE+20 1 OOOE+20 1 000E+20 1 000E+20 1 000E+20 1 000E+20 1 000E+20 1 000E+20 1. 000E+20 1. 000E+20 1. 000E+20 1. OOOE+20 1. OOOE+20 1. 000E+20 1. 000E+20 1. 000E+20.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0636 TOTAL USAGE FACTOR I I I I I I I I U I I I I I I I I SIR-07-130-NPS, Rev. 0 4-9 V Structural Integrity Associates, Inc.I NEC066085 Table 4-5: Fatigue Results for the Feedwater Nozzle Safe End LOCATION = LOCATION NO. 1 -- SAFE END FATIGUE CURVE = 1 (1 = CARBON/LOW ALLOY, 2 = STAINLESS STEEL)m 3.0 n= .2 Sm = 17800. psi Ecurve = 3.OOOE+07 psi Eanalysis
= 2.810E+07 psi Kt = 1.34 MAX MIN RANGE MEM+BEND Ke Salt Napplied Nallowed U 70233. -17681. 87914. 60963. 1.283 74422. 1.000E+01 1.338E+03
.0075 70224. -15714. 85938. 60879. 1.280 72869. 1.000E+01 1.415E+03
.0071 61955. -12491. 74446. 53128 1.000 49383. 1.000E+01 4.568E+03
.0022 58867. -12491. 71359. 52938. 1.000 47700. 1.OOOE+01 5.094E+03
.0020 53379. -12491. 65870. 47699. 1.000 43819. 2.800E+02 6.552E+03
.0427 53379. -11148. 64527. 46869. 1.000 42951. 1.OOOE+01 6.953E+03
.0014 53379. -10720. 64099. 46361. 1.000 42631. 1.OOOE+01 7.109E+03
.0014 53379. -9972. 63351. 58588. 1.194 53087. 6.000E+01 3.628E+03
.0165 53379. -9972. 63351. 58588. 1.194 53087. 1.000E+00 3.628E+03
.0003 53379. -9972. 63351. 58588. 1.194 53087. 2.280E+02 3.628E+03
.0628 53379. -9060. 62439. 44702. 1.000 41444. 1.100E+01 7.731E+03
.0014 15888. -9060. 24948. 20209. 1.000 16985. 1.OOOE+00 1.802E+05
.0000 14569. -9060. 23629. 17779. 1.000 15840. 1.OOOE+00 2.410E+05
.0000 14522. -9060. 23582. 18921. 1.000 16022. 2.870E+02 2.287E+05
.0013 14522. -3008. 17530. 17358. 1.000 12508. 1.300E+01 9.944E+05
.0000 14396. -3008. 17404. 17229. 1.000 12417. 2.870E+02 1.083E+06
.0003 14396. -971. 15367. 13432. 1.000 10641. 1.300E+01 5.165E+06
.0000 14236. -971. 15206. 13161. 1.000 10506. 1.OOOE+00 5.563E+06
.0000 14226. -971. 15196. 13248. 1.000 10516. 2.860E+02 5.531E+06
.0001 14226. -178. 14404. 14178. 1.000 10262. 1.400E+01 6.379E+06
.0000 13849. -178. 14026. 15036. 1.000 10216. 6.OOOE+01 6.547E+06
.0000 13849. -178. 14026. 15036. 1.000 10216. 1.OOOE+00 6.547E+06
.0000 13849. -178. 14026. 15036. 1.000 10216. 2.250E+02 6.547E+06
.0000 13849. -68. 13916. 14943. 1.000 10141. 3.0OOE+00 6.837E+06
.0000 13754. -68. 13821. 13600. 1.000 9846. 6.OOOE+01 8.117E+06
.0000 13754. -68. 13821. 13600. 1.000 9846. 2.280E+02 8.117E+06
.0000 13723. -68. 13791. 14475. 1.000 9989. 9.OOOE+00 7.465E+06
.0000 13723. -65. 13788. 14473. 1.000 9987. 6.100E+01 7.474E+06
.0000 12722. -65. 12786. 12548. 1.000 9103. 1.000E+01 1.729E+07
.0000 12710. -65. 12775. 12579. 1.000 9102. 7.OOOE+01 1.730E+07
.0000 12652. -65. 12717. 12524. 1.000 9061. 1.590E+02 1.833E+07
.0000 12652. 0. 12652. 12454. 1.000 9014. 1.230E+02 1.959E+07
.0000 12652. 0. 12652. 12454. 1.000 9014. 1.200E+02 1.959E+07
.0000 12652. 0. 12652. 12454. 1.000 9014. 1.230E+02 1.959E+07
.0000 12652. 339. 12313. 12115. 1.000 8772. 1.230E+02 2.905E+07
.0000 12652. 784. 11869. 11681. 1.000 8456. 1.200E+02 4.952E+07
.0000 12652. 784. 11869. 11681. 1.000 8456. 1.OOOE+00 4.952E+07
.0000 12652. 784. 11869. 11681. 1.000 8456. 1.OOOE+00 4.952E+07
.0000 12652. 921. 11732. 11542. 1.000 8357. 1.OOOE+00 5.462E+07
.0000 12652. 1328. 11325. 11257. 1.000 8088. 1.OOOE+00 7.100E+07
.0000 12652. 3370. 9282. 8687. 1.000 6531. 1.OOOE+01 1.000E+20
.0000 12652. 3563. 9090. 9091. 1.000 6502. 3.OOOE+02 1.000E+20
.0000 SIR-07-130-NPS, Rev. 0 4-10 Structural Integrity Associates, Inc.NEC066086 n 12652. 3563. 9090. 9091. i.000 6502. 3.00E+02 1.000E+20
.0000 12652. 3563. 9090. 9091. 1.000 6502. 3.000E+02 1.000E+20
.0000 12652. 3563. 9090. 9091. 1.000 6502. 3.00E+02 10E+20 I0000 12652. 3564. 9089. 9090. 1.000 6501. 3.000E+02 1.OOOE+20
.0000 12652. 3565. 9088. -1740. 1.000 4535. 3.000E+02 1.OOOE+20
.0000 12652. 3896. 8756. 8613. 1.000 6237. 3.000E+02 1.000E+20
.0000 12652. 5058. 7594. 8038. 1.000 5513. 7.OOOE+01 1.OOOE+20
.0000 12652. 5171. 7481. 7424. 1.000 5341. 7.048E+03 1.000E+20
.0000 12650. 5171. 7479. 7421. 1.000 5339. 1.OOOE+01 1.OOOE+20
.0000 12648. 5171. 7477. 7420. 1.000 5338. 2.000E+03 1.OOOE+20
.0000 12642. 5171. 7471. 7411. 1.000 5333. 7.OOOE+01 1.OOOE+20
.0000 12642. 5171. 7471. 7411. 1.000 5333. 7.OOOE+01 1.000E+20
.0000 12642. 5171. 7471. 7411. 1.000 5333. 6.OOOE+01 1.000E+20
.0000 12642. 5171. 7471. 7411. 1.000 5333. 6.OOOE+01 1.OOOE+20
.0000 12642. 5171. 7471. 7411. 1.000 5333. 1.OOOE+00 1.OOOE+20
.0000 12642. 5171. 7471. 7411. 1.000 5333. 1.OOOE+00 1.000E+20
.0000 12642. 5171. 7471. 7411. 1.000 5333. 2.280E+02 1.OOOE+20
.0000 12642. 5171. 7471. 7411. 1.000 5333. 2.280E+02 1.OOOE+20
.0000 12641. 5171. 7470. 7412. 1.000 5333. 2.240E+02 1.OOOE+20
.0000 12641. 5214. 7427. 7382. 1.000 5304. 1.800E+01 1.OOOE+20
.0000 12641. 5232. 7409. 7370. 1.000 5293. 2.400E+03 1.OOOE+20
.0000 12641. 5311. 7330. 7329. 1.000 5243. 1.OOOE+01 1.000E+20
.0000 12641. 6442. 6200. 6078. 1.000 4412. 1.OOOE+01 1.000E+20
.0000 12641. 6667. 5975. 5972. 1.000 4273. 3.OOOE+02 1.OOOE+20
.0000 12641. 6764. 5878. 5880. 1.000 4205. 7.OOOE+01 1.OOOE+20
.0000 12641. 9690. 2951. 3031. 1.000 2126. 1.000E+00 1.OOOE+20
.0000 12641. 10119. 2522. 2541. 1.000 1808. 1.200E+02 1.OOOE+20
.0000 12641. 11247. 1394. 1393. 1.000 997. 1.000E+01 1.OOOE+20
.0000 I 12641. 11256. 1385. 1384. 1.000 991. 3.OOOE+02 1.OOOE+20
.0000 12641. 11258. 1383. 1386. 1.000 990. 7.OOOE+01 1.000E+20
.0000 12641. 11281. 1360. 1360. 1.000 973. 1.OOOE+01 1.000E+20
.0000 12641. 11403. 1238. 1281. 1.000 894. 3.OOOE+02 1.OOOE+20
.0000 12641. 11550. 1092. 1130. 1.000 7889 2.OOOE+03 1.OOOE+20
.0000 12641. 11911. 731. 1034. 1.000 578. 1.OOOE+01 1.OOOE+20
.0000 12641. 11937. 705. 761. 1.000 514. 4.555E+03 1.OOOE+20
.0000 12641. 11937. 705. 761. 1.000 514. 5.445E+03 1.OOOE+20
.0000 12641. 11992. 649. 635. 1.000 462. 1.OOOE+01 1.000E+20
.0000 12641. 12020. 621. 610. 1.000 442. 6.OOOE+01 1.OOOE+20
.0000 12641. 12020. 621. 610. 1.000 442. 1.OOOE+00 1.006E+20
.0000 12641. 12020. 621. 610. 1.000 442. 2.280E+02 1.OOOE+20
.0000 12641. 12640. 1. 0. 1.000 1. 3.OOOE+02 1.OOOE+20
.0000 12641. 12641. 0. 0. 1.000 0. 3.956E+03 1.OOOE+20
.0000 12641. 12641. 0. 0. 1.000 0. 2.OOOE+03 1.OOOE+20
.0000 12641. 12641. 0. 0. 1.000 0. 2.OOOE+03 1.OOOE+20
.0000 12641. 12641. 0. 0. 1.000 0. 1.OOOE+01 1.000E+20
.0000 12641. 12641. 0. 0. 1.000 0. 1.OOOE+01 1.000E+20
.0000 12641. 12641. 0. 0. 1.000 0. 1.OOOE+00 1.OOOE+20
.0000 I TOTAL USAGE FACTOR = .1471 I I SiR-07-1]30-NPS, Rev. 0 4-11 Structural Integrity Associates, Inc.NEC066087
 
===5.0 ENVIRONMENTAL===
 
FATIGUE ANALYSIS In the response to NRC request for additional information (RAI) 4.3-H-02 [19], VYNPS states that they have conservatively assumed that fatigue cracks may be present in the clad. VYNPS manages this cracking by performing periodic inspections that were implemented in response to Generic Letters 80-095 and 81-11, and NUREG-0619.
The inspection frequency is based on the calculated fatigue crack growth of a postulated flaw in the nozzle inner blend radius. The VYNPS fatigue crack growth calculation uses methods in compliance with GE BWR Owners Group Topical Report "Alternate BWR Feedwater Nozzle Inspection Requirements", GE-NE-523-A71-0594, Revision 1, August 1999 and the associated NRC Final Safety Evaluation (TAC No. MA6787) dated March 10, 2000. The NRC has reviewed and approved this approach to handling FW nozzle inner blend radius cracking (Letter D.H. Dorman (USNRC) to D.A. Reid (VYNPC),
 
==Subject:==
Evaluation of Request for Relief from NUREG-0619 for VYNPS dated 2/6/95, (TAC No. M88803)).The analysis performed for the feedwater nozzle calculated fatigue in the blend radius base metal, not the clad. This is consistent with the VYNPS position stated in the response to RAI 4.3-H-02, and is also consistent with ASME Code methodology since cladding is structurally neglected in fatigue analyses, per ASME Code, Section III, NB-3 122.3 [15].Environmental fatigue multipliers were computed for both normal water chemistry (NWC) and hydrogen water chemistry (HWC) conditions in Reference
[21] for various regions of the VY RPV and attached piping. Based on VY-specific dates for plant startup and HWC implementation, as well as past and future predicted HWC system availability, it was determined that overall HWC availability is 47% over the sixty year operating period for VY. Therefore, for the purposes of the EAF assessment of the FW nozzle, it was assumed that HWC conditions exist for 47% of the time, and NWC conditions exist for 53% of the time over the 60-year operating life of the plant. RPV upper region chemistry was assumed for the FW nozzle blend radius location, since this location experiences reactor conditions for all times. FW line chemistry was assumed for the FW nozzle safe end location, since this location experiences feedwater conditions for all times.SIR-07-130-NPS, Rev. 0 5-1 Structural Integrity Associates, Inc.NEC066088 I For the safe end location, the environmental fatigue factors for pre-HWC and post-HWC are both 1.74 from Table 3 of Reference
[21] for the RPV FW line. This results in an EAF adjusted CUF as follows: 60-Year CUF, U 6 0 = 0.1470 (from Table 4-5) U Overall EAF multiplier, Fn = 1.74 60-Year EAF CUF, Udo-,,,, = 0.14709 x 1.74 = 0.2560 The EAF CUF value of 0.2560 for 60 years for the safe end is acceptable (i.e., less than the I allowable value of 1.0).The fatigue calculation documented in Section 4.0 for the blend radius location was performed for the nozzle base material since cladding is structurally neglected in modern-day fatigue I analyses, per ASME Code, Section 111, NB-3122.3
[15]. This is also consistent with Sections 5.7.1 and 5.7.4 of NUREG/CR-6260
[16]. Therefore, the cladding was neglected and EAF I assessment of the nozzle base material was performed for the blend radius location.For the blend radius location, the environmental fatigue factors for pre-HWC and post-HWC ar-e 11.14 and 8.82, respectively, from Table 4 of Reference
[21] for the RPV upper region. This results in an EAF adjusted CUF as follows: I 60-Year CUF, U 6 0 = 0.0636 (from Table 4-4)Overall EAF multiplier, Fen = (11.14 x 53% + 8.82 x 47%) = 10.05 i 60-Year EAF CUF, U 6 (-env = 0.0636 x 10.05 = 0.6392 I The EAF CUF value of 0.6392 for 60 years for the blend radius is acceptable (i.e., less than the allowable value of 1.0).I SIR-07-130-NPS, Rev. 0 5-2 Structural Integrity Associates, Inc.NEC066089
 
==6.0 CONCLUSION==
S This report documents a refined fatigue evaluation for the VY FW nozzle. The intent of this evaluation is to use refined transient definitions and the revised cyclic transient counts for 60 years for a computation of CUF, including EAF effects, that is more refined than previously perforned fatigue analyses.
The fatigue-limiting locations in the FW nozzle and safe end are included in the evaluation, to be consistent with NUREG/CR-6260
[16] needs for EAF evaluation for license renewal. The final fatigue results are considered to be a replacement to the values previously reported in the VY LRA.The fatigue calculations for the VY FW nozzle were performed in accordance with ASME Code, Section III, Subsection NB-3200 methodology (1998 Edition, 2000 Addenda) [15]. The stress evaluation is summarized in Section 3.0, and the fatigue analysis is summarized in Section 4.0.The results in Section 4.0 reveal that the CUF for the limiting safe end location is 0.1470, and the CUF for the limiting blend radius location is 0.0636. Both of these values represent 60 years of plant operation, including all relevant EPU effects.EAF calculations for the VY FW nozzle were also performed, as summarized in Section 5.0.The results in Section 5.0 reveal that the EAF CUF for the limiting safe end location is 0.2560, and the EAF CUF for the limiting blend radius location is 0.6392. Both of these values represent 60 years of plant operation, including all relevant EPU effects.All fatigue allowables, both with and without EAF effects, are met, thus demonstrating acceptability for 60 years of operation.
SIR-07-130-NPS, Rev. 0 6-1 Structural Integrity Associates, inc.NEC066090
 
==7.0 REFERENCES==
 
I 1. REDACTED I 2. CB&I RPV Stress Report, Sections T4 and S4, "Feedwater Nozzle, Vermont Yankee Reactor Vessel, CB&I Contrac.t 9-6201," SI File No. VY-05Q-238.
: 3. GE Design Specification No. 21A4 115, Revision 4, "Vermont Yankee Reactor Pressure Vessel," October 21, 1969, SI File No. VY-05Q-210.
: 4. Kuo, A. Y., Tang, S. S., and Riccardella, P. C., "An On-Line Fatigue Monitoring System I for Power Plants, Part I -Direct Calculation of Transient Peak Stress Through Transfer Matrices and Green's Functions," ASME PVP Conference, Chicago, 1986.5. ANSYS, Release 8.1 (w/Service Pack 1), ANSYS, Inc., June 2004.6. Structural Integrity Associates Calculation No. VY-10Q-301, Revision 0, "Feedwater Nozzle Finite Element Model and Heat Transfer Coefficients." 7. Structural Integrity Associates'Calculation No. YAEC-13Q-303, Revision 0, "Thermal I Transient Analysis." 8. VY Drawing No. 5920-9057, Sheet 1, Revision 1, SI File No. VY-05Q-215.
: 9. American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section II, Part D, 1998 Edition, 2000 Addenda. I I STR-07-130-NPS, Rev. 0 7-1 Structural Integrity Associates, Inc.NEC066091
: 10. Structural Integrity Associates Calculation No. VY-16Q-301, Revision 0, "Feedwater Stress History Development for Nozzle Green's Function." 11. Vermont Yankee Drawing 5920-00024, Rev. IJ, GE Drawing No. 919D294, Revision 11, Sheet No. 7, "Reactor Vessel," SI File No. VY-05Q-241.
: 12. CB&I Addenda to RPV Stress Report, "Certification of Addenda to the Stress Report for Vermont Yankee Reactor Vessel," July 9, 1971, SI File No. VY-05Q-238.
: 13. VY CalculationChange Notice (CCN), CCN Number I for Calculation VYCIO05 Revision 2, "This CCN Provides a Basis for the Power Uprate Safety Analysis Report being submitted as part of the power uprate project. The 50.59 assessment will be handled by the EPU design change and NRC SER for this submittal." SI File Number VY-05Q-208.
: 14. Structural Integrity Associates Calculation No. SW-SPVF-OIQ-301, Revision 0,"STRESS.EXE, P-V.EXE, and FATIGUE.EXE Software Verification." 15. American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section III Subsection NB, 1998 Edition, 2000 Addenda.f6. NUREG/CR-6260 (INEL-95/0045), "Application of NUREG/CR-5999 Interim Fatigue Curves to Selected Nuclear Power Plant Components," March 1995.17. GE Certified Design Specification No. 26A6019, Revision 1, "Reactor Vessel -Extended Power Uprate," August 29, 2003, SI File No. VY-05Q-236.
: 18. General Electric Stress Report No. DC22A5583, Revision 0, Section T, "Thermal Analysis FitzPatrick Feedwater Nozzle Modification," SI File No. NYPA-53Q-212.
SIR-07-130-NPS, Rev. 0 7-2 V Structural Integrity Associates, Inc.NEC066092
: 19. Entergy Design Input Record (DIR) Revision 1, EC No. 1773, Revision 0"Environmental Fatigue Analysis for Vermont Yankee Nuclear Power Station," 7/26/2007, SI File No. VY- 16Q-209.20. Chicago Bridge & Iron Company Contractor 9-620 1, Revision 2, "Section S4, Stress Analysis Feedwater Nozzle Vermont Yankee Reactor Vessel," SI File No. VY-05Q-238.
: 21. Structural Integrity Associates Calculation No. VY-16Q-303, Revision 0,"Environmental Fatigue Evaluation of Reactor Recirculation Inlet Nozzle and Vessel Shell Bottom Head." 22. NUREG-1801, Revision 1, "Generic Aging Lessons Learned (GALL) Report," U. S.Nuclear Regulatory Commission, September 2005.23. Structural Integrity Associates Calculation No. VY-16Q-302, Revision 0, "Fatigue Analysis of Feedwater Nozzle." 24. J. P. Holman, "Heat Transfer," 4th Edition, McGraw-Hill, 1976.25. J. P. Holman, "Heat Transfer," 5th Edition, McGraw-Hill, 1981.26. N. P. Cheremisinoff, "Heat Transfer Pocket Handbook," Gulf Publishing Co, 1984.27. American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section 1II, Subsection A, Article 4, 1965 Edition with Winter 1966 Addenda.I I I I I I I I I I I I I I I I SIR-07-130-NPS, Rev. 0 7-3 Structural Integrity Associates, Inc.I NEC066093 NEC-JH_16 Report No.: SIR-07-141-NPS Revision No.: 0 Project No.: VY-16Q File No.: VY-16Q-402 July 2007 Environmental Fatigue Analysis for the Vermont Yankee Reactor Pressure Vessel Reactor Recirculation Outlet Nozzle Prepared for.Entergy Nuclear Operations, Inc.Contract Number: 10150394 Prepared by: Structural Integrity Associates, Inc.Centennial, CO Prepared by: Reviewed by: Approved by: Terry errmann, P.E.S Stevens, P.E.Terry JqIrrmann, P.E.Date: 7/26/2007 Date: 7/26/2007 Date: 7/26/2007 V Structural Integrity Associates, Inc.
REVISION CONTROL SHEET Document Number: SIR-07-141-NPS Title: Environmental Fatigue Analysis for the Vermont Yankee Reactor Pressure Vessel Reactor Recirculation Outlet Nozzle Client: Entergy Nuclear Operations, Inc.SI Project Number: VY- 16Q Section Pages Revision.
Date Comments 1.0 1-1 5 0 7/26/07 Initial Issue 2.0 2-1 3 3.0 3-1 34 4.0 4-1 11 5.0 5-1-552 6.0 6-1 7.0 7-1 2*&#xfd; Structural Integrity Associates, Inc.
Sectio 1.0 1.A 2.0 3.0 3.1 3.3.3.3.2 3.3 4.0 5.0 6.0 7.0 Table of Contents n Page INTRODUCTION
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1-1 Green's Function M ethodology
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1-2 FINITE ELEM ENT M ODEL .......................
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I ......................
2-1 LO A D D EFIN ITIO N S ...................................................................................................
3-1 T herm al L oading ..........................................................................................................
3-1 1.1 Heat Transfer Coefficients and Bounda'y Fluid Temperatures.......................
3-2 1.2 Green's Functions..
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3-4 1.3 Thermal Transients
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3-5 Pressure Loading ....... .............................................
3-5 P ip ing L oading ............................................................................................................
3-6 STRESS AND FATIGUE ANALYSIS RESULTS .........................
4-1 ENVIRONMENTAL FATIGUE ANALYSIS .............................
5-1 C O N C L U SIO N S............................................................................................................
6-1 REFERENCES
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7-1 SIR-07-141-NPS, Rev. 0 111 V Structural Integrity Associates, Inc.
List of Tables.Table I I I I I I I Table 2-1.Table 3-1: Table 3-2: Table 3-3: Table 3-4:.Table 4-1: Table 472: Table 4-3: Table 4-4: Table 4-5: M aterial Properties
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I .................
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2-2 Safe E nd T ransients
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3-7 B lend R adius T ransients
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I ..................................................................
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3-8 Stresses Due to Piping Loads for Safe End Location .....................
3-9 Stresses Due to Piping Loads for Blend Radius Location .................
3-10 Reactor Recirculation Outlet Nozzle Safe End Stress Summary ..............................
4-3 Reactor Recirculation Outlet Nozzle Blend Radius Stress Summary ..........
4-5 Fatigue Parameters Used in the Recirculation Outlet Nozzle Fatigue Analysis ....... 4-7 Fatigue Results for Reactor Recirculation Outlet Nozzle Safe End ..........................
4-8 Fatigue Results for the Reactor Recirculation Outlet Nozzle Blend Radius ............
4-10 I i I I I I I I I SStructural Integrity Associates, inc.I STR-07-141-NPS, Rev. 0 Iv List of Figures Fiazurc Pagte Figure 1-1.Figure 1-2.Figure 2-1.Figure 3-1 : Figure 3-2: Figure 3-3: Figure 3-4: Figure 3-5: Figure 3-6: Figure 3-7: Figure 3-8: Figure 3-9: Typical Green's Functions for Thermal Transient Stress ........................................
1-4 Typical Stress Response Using Green's Functions
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1-5 VY Reactor Recirculation Outlet Nozzle FEM .......................................................
2-3 Thermal Regions for Green's Functions
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3-.11 Therm al Regions for Transient 9 ............................................................................
3-12 Safe End Critical Thermal Stress Location ...........................
3-13 Blend Radius Critical Thermal Stress Location ...................................................
3-14 Safe End Total Stress Intensity Green's Function for 100% Flow ...........
3-15 Safe End Total Stress Intensity Green's Function for 50% Flow ............
3-16 Safe End Total Stress Intensity Green's Function for 0% Flow..........................
3-17 Blend Radius Total Stress Intensity Green's Function for 100% Flow .................
3-18 Blend Radius Total Stress Intensity Green's Function for 50% Flow ...................
3-19 Figure 3-10: Blend Radius Total Stress Intensity Green's Function for 0% Flow ...................
3-20 Figure 3-11: Figure 3:12: Figure 3-13: Figure 3-14: Figure 3-15: Figure 3-16: Figure 3-17: Figure 3-18: Figure 3-19: Figure 3-20: Figure 3-2 1: Figure 3-22" Figure 3-23: Figure 3-24: Transient 1: Norm al Startup at 100 0 F/hr ..............................................................
3-21 Transient 2: Turbine Roll and Increase to Rated POwer ...... o .............
3-22 Transient 3: Loss of Feedwater Heaters and Turbine Trip at 25% Power ...........
3-23 Transient 4: Loss of Feedwater Pumps .............................................................
3-24 Transient 5: Turbine Generator Trip ....... ...........................
3-25 Transient 6: Reactor Overpressure
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3-26 Transient 7: SRV Blow D ow n .............................................................................
3-27 Transient 8: Scram -O ther ......................................
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3-28, Transient 9: Im proper Startup ..............................................................................
3-29 T ransient 10: Shutdow n ......................................
I ...............................................
3-30 Reactor Recirculation Outlet Nozzle Internal Pressure Distribution
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3-31 Reactor Recirculation Outlet Nozzle Pressure Cap Load ...................................
3-32 Reactor Recirculation Outlet Nozzle Vessel Boundary Condition
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3-33 Pipe Reactions
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3-34 IPS, Rev. 0 v Structural Integrity Associates, Inc.SIR-07-141-IN
 
==1.0 INTRODUCTION==
 
In Table 4.3-3 of the Vermont Yankee License Renewal Application (LRA), the 60-year cumulative usage factor (CUF) value for the reactor pressure vessel (RPV) reactor recirculation outlet nozzle is reported as 0.810. Application of environmentally assisted fatigue (EAF) multipliers, as required for the license renewal period, resulted in an unacceptable EAF CUF value of 1.98. Therefore, further refined analysis is necessary to show acceptable EAF CUF results for this component.
This report documents a refined fatigue evaluation for the VY reactor recirculation outlet nozzle. The intent of this evaluation is to use refined transient definitions and the revised cyclic transient counts for 60 years for a computation of CUF, including EAF effects, that is more refined than previously performed fatigue analyses.
The fatigue-limiting locations in the reactor recirculation outlet nozzle are included in the evaluation, to be consistent with NUREG/CR-6260
[1] needs for EAF evaluation for license renewal. The resulting fatigue results will be used as a replacement to the value previously reported in the VY LRA.The refined evaluation summarized in this report included development of a detailed finite element model of the reactor recirculation outlet nozzle, including relevant portions of the safe end, the nozzle forging, a portion of the vessel shell, and cladding as shown in the applicable drawings [2, 3]. Thermal and pressure stress histories were developed for relevant transients affecting the reactor recirculation outlet nozzle, including any effects of Extended Power Uprate (EPU), as specified by the VY RPV I Design Specification
[4], the VY EPU Design Specification
[5] and other boiling water reactor (BWR)operating experience.
The thermal and pressure stress histories were used to determine total stress intensities and primary plus secondary stress intensities for use in a subsequent fatigue evaluation
[1.1].Stress intensities were also included due to loads from the attached piping for application in the stress/fatigue analysis based on the bounding reaction loads obtained from the relevant design document.II The revised fatigue calculation was performed using Section III methodology from the 1998 Edition, 2000 Addenda of the ASME Code [17], and was performed using actual cycles from past plant operation projected out to 60 years of operation.
SIR-07-141-NPS, Rev. 0 1-1 Structural Integrity Associates, Inc.I I 1.1 Green's Function Methodology I For the reactor recirculation outlet nozzle evaluated as a part of this work, stress intensity histories were computed by a time integration of the product of a pre-determined Green's Function and the transient data. This Green's Function integration scheme is similar in concept to the Duhamel theory used in I structural dynamics.
A detailed derivation of this approach and examples of its application to specific plant locations is contained in Reference (6]. A general outline is provided in this section.A Green's Function is derived by using finite element methods to determine the transient stress response I of the component to a step change in loading (usually a thermal shock). The critical location in the component is identified based on the maximum stress intensity, and the thermal stress intensity response* over time is extracted for this location.
This response to the input thermal step is the "Green's Function." Figure 1-1 shows a typical set of two Green's Functions, each fora different set of heat I transfer'coefficients (representing different flow rate conditions).
I To compute the thermal stress response for an arbitrary transient, the loading parameter (usually local fluid temperature) is deconstructed into a series of step-loadings.
By using the Green's Function, the response to each step can be quickly determined.
By the principle of superposition, these can be added (algebraically) to determine the response to the original load history. The result is demonstrated in I Figure 1-2. The input transient temperature history contains five step-changes of varying size, as shown in the upper plot in Figure 1-2. These five step changes produce the five successive stress responses in I the second plot shown in Figure 1-2. By adding all five response curves, the real-time stress response for the input thermal transient is computed&The Green's Function methodology produces identical results compared to running the input transient through the finite element model. The advantage of using Green's Functions is that many individual transients can be run with a significant reduction of effort compared to running all transients through the finite element model. The trade-off in this process is that the Green's Functions are based 0n-constant material properties and heat transfer coefficients.
Therefore, these parameters are chosen to bound all transients that constitute the majority of fatigue usage, i.e., the heat transfer coefficients at 300'F bound SIR-07-14 1-NPS, Rev. 0 1-2 Structural Integrity Associates, Inc.
the cold water injection transient.
In addition, the instantaneous value for the coefficient of thermal expansion is used instead of the mean value for the coefficient of thermal expansion.
This conservatism is more than offset by the benefit of not having to analyze every transient, which was' done in the VY reactor recirculation outlet nozzle evaluation.
Once the stress history is obtained for all transients using the Green's Function approach, the remainder of the fatigue analysis is carried out using traditional methodologies in accordance with ASME Code, Section III requirements
[17].I I I I 3 I I I I I I I I I I i I I i SIR-07-141-NPS, Rev. 0 1-3 C Structural Integrity Associates, Inc.
Q)0)C/)CY)400 Time (sec)92825r0 Note: A typical set of two Green's Functions is shown, each for a different set of heat transfer coefficients (representing different flow rate conditions).
Figure 1-1. Typical Green's Functions for Thermal Transient Stress SIR-07-141 -NPS, Rev. 0 1-4 Structural Integrity Associates, Inc.
700'450 -, 1 5C SIko-50 sf*p 0-75 Sfk,-IS SteP 116&#xfd;iI -* 0r 204 400 400 806 WOO0 1200 1400 1600 1800 ZOO.I J to, 1A-t-4 I I I I I I I I I I I I I I I I I I 20m 400 600 t00 10001200 1400 1600 100 rum.In 20m Figure 1-2. Typical Stress Response Using Green's Functions SIR-07-141-NPS, Rev. -0 1-5 C Structural Integrity Associates, Inc.
 
===2.0 FINITE===
ELEMENT MODEL An ANSYS [7] finite element model (FEM) of the VY reactor recirculation outlet nozzle configuration was developed and used to perform the updated stress and fatigue analyses.
The details of the model development are documented in the Reference
[8] calculation.
The materials of the Various components of the model are listed below: Safe End -SA182 F316 (16Cr-12Ni-2Mo)
* Piping -SA376 TP316 (16Cr-12Ni-2Mo)
*
* Nozzle Forging -SA508 Class 2 (3/4Ni-1/2Mo-1/3Cr-V)
* Vessel -SA533 Grade B (Mn-1/2Mo-1/2Ni)
* Cladding -SA240 Type 304 (18Cr-8Ni)
The radius of the RPV was increased by a factor of two to account for the fact that the vessel portion of the two dimensional axisymmetric finite element model is a sphere and the actual geometry is a cylinder..
Material properties were based upon the 1998 ASME Code, Section I1, Part D, with 2000 Addenda [9], andare shown in Table 2-. The properties for the Green's Functions were evaluated at an average temperature of 300'F. This average temperature is based on a thermal shock of 500'F to 100lF which was applied to the FEM model for Green's Function development.
Due to the thermal shocks having a differenttemperature range at the nozzle blend radius and safe end for the Improper Start transient (Transient 9), this transient was run separately.
Material properties were evaluated at 400'F for all locations except for the safe end and piping, which were evaluated using material properties at 300'F since the temperature is lower at this location and the properties at 300'F are closest to the average temperature of 330'F.The finite element model is shown in Figure 2-1.SIR-07-141 -NPS, Rev. 0 2-1 Structural Integrity Associates, Inc.
I I I I Table 2-1. Material Properties For the Glree~n's Funcrtions (evaluated1 at 3O0cF)SA533 Gr. B SA508 C1. 2 SA18 Material IVIOMn-ll2Mo-314Ni-1/2Mo-SA240 TP 304 l8-* " ~18Cr-8Ni S3 112Ni 1/3Cr-V 16Cr-I Modulus of Elasticity, e+6 psi 28.0 26.7 27.0 2 Coefficient of Thermal Expansion, e-6, 73 9.8 in/in/0 F Thermal Conductivity, Btu/hr-ft-&deg;F 23.4 23.4 9.8 Thermal Diffusivity, ft 2/hr 0.401 0.401 0.160 0.Specific Heat, Btu/Ib-&deg;F 0.119 0.119 0.125 0.Density, lb/in 3  0.283 0.283 0.283 0.Poisson's Ratio 0.3 0.3 0,3 For Transient 9 (evaluated at 400'F -except for the saf-end and piping, which are evaluated at 300'F): I Property SA533 Gr. B Mn-I/2Mo-1/2Ni SA508 Cl. 2 3/4Ni-I/2Mo-1/3Cr-V SA240 TP 304 18Cr-8Ni SA18 SA37*l 6 Cr-U Modulus of Elasticity, e+6 psi " 27.4 ' 26.1 .j 26.5 1 :6 Coefficient of Thermal Expansion, e-6, in/in/OF *8.0 7.7 10.2 I Thermal Conductivity, Btuthr-ft-0 F 23.1 .23.1 10.4 Thermal Diffusivity, ft 2/hr 0.378 ;0.378* 0.165 Specific Heat, Btu/Ib-0 F 0.125 0.125 0.129 Density, lb/in 3  0.283 0.283 0.283 0.Poisson's Ratio 0.3 0.3 03 1 Note: 1. Material properties are taken from the 1998 ASME Code, Section II, Part D, with 2000 Addenda [9], except for den!which-are assumed typical values and specific heat calculated as [k/pd] /12 .3 SIR-07-141-NPS, Rev. 0 2-2.$trJl I I I Figure 2-1. VY Reactor Recirculation Outlet Nozzle FEM SIR-07-141-NPS, Rev. 0 2-3 Structural Integrity Associates, Inc.
3.0 LOAD DEFINITIONS The pressure and thermal stresses for the reactor recirculation outlet nozzle for the revised fatigue evaluation were developed using the axisymmetric FEM model described in Section 2.0 of this report. The details of the Green's Function development and associated stress and fatigue evaluations are documented in the Reference
[10] and [11] calculations.
I 3.1 Thermal Loading I Thermal loads were applied to the recirculation outlet nozzle model to generate the Green's Functions.
As a first step in the Green's Function process, heat transfer coefficients were determined for various regions of the reactor recirculation outlet nozzle FEM for three different flow cases: (1) 100% reactor recirculation outlet nozzle flow, (2) 50% rea~ctor recirculation 3 outlet nozzle flow and (3) 0% reactor recirculation outlet nozzle flow.Y I The 100% flow case simulates the operational condition of the reactor recirculation outlet nozzle (i.e., normal recirculation system flow). The -heat transfer coefficients for the high flow case are for forced convection.
The applied boundary fluid temperatureis changed to simulate a thermal shock from 500F to 100YF to develop the stress response on the reactor recirculation outlet nozzle due to normal operating conditions.
U The 50% flow case simulates a reduced flow condition of the reactor recirculation outlet nozzle (i.e., during power ascension).
The heat transfer coefficients for the reduced flow case are also i for forced convection.
The applied boundary fluid temperature is changed to simulate a thermal shock from 500'F to 100&deg;F to develop the stress response on the reactor recirculation outlet nozzle under reduced flow conditions.
The 0% flow case simulates a stagnant ,ondition of the-reactor recirculation outlet nozzle when recirculation flow is stopped and the entire reactor recirculation outlet nozzle is at the same I temperature as the RPV fluid. The heat transfer coefficients for the 0% flow case are for free *i SIR-07-141-NPS, Rev. 0 3-1 Structural Integrity Associates, Inc.
convection (stagnant) conditions.
The applied boundary fluid temperature is changed to simulate a thermal shock from 500'F to I 00&deg;F to develop the stress response on the reactor recirculation outlet nozzle in the stagnant condition.
The temperature on the exterior of the reactor, nozzle, safe end and pipe was assumed to be 120'F (ambient).
Figure 3-1 shows the heat transfer coefficient regions assumed for the reactor recirculation outlet nozzle FEM. The applied heat transfer coefficients and the fluid temperatures are summarized in the sections that follow.3.1.1. Heat Transfer Coefficients and Boundaiy Fluid Temperatures Referring to Figure 3-1, heat transfer coefficients for the Green's Functions were applied as follows: For Green's Functions:.
Region I The heat transfer coefficient, h, for 100% flow is.3,577.8 BTU/hr-ft 2 -F at 300 0 F.The heat transfer coefficient, h, for 50% flow is 2,054.9 BTU/hr-ft 2-OF at 300 0 F.The heat transfer coefficient, h, for 0% flow is 112.34 BTU/hr-ft 2 -F at 300'F.Region 2 The heat transfer coefficient for Region 2 was, linearly transitioned from the value of the heat transfer coefficient used in Region 1 to the value used in Region 3.Region 3 The heat transfer coefficient, h, for 100% flow is 3,361 BTU/hr-ft 2-&deg;F at 300&deg;F.The heat transfer coefficient, h, for 50% flow is 1,930.9 BTU/hr-ft 2-&deg;F at 300 0 F.The heat transfer coefficient, h, for 0% flow is 112.34 BTU/hr7ft 2-&deg;F at 300&deg;F.Region 4 The heat transfer coefficient for Region 4 (nozzle blend radius) was linearly transitioned from the value of the heat transfer coefficient used in Region 3 to the value used in Region 5.SIR-07-141.-NPS, Rev. 0 3-2 .Structural Integrity Associates, Inc.
Region 5 The heat transfer coefficient, h, for 100% flow is 1,788.9 BTU/hr-ft 2-OF at 300 0 F.The heat transfer coefficient, h, for 50% flow is 1,027.4 BTU/hr-ft 2-&deg;F at 300&deg;F. I The heat transfer coefficient, h, for 0% flow is 101 BTU/hr-ft 2-OF at 300 0 F.Region_ 6 I The heat transfer coefficient, h, is 0.4 BTU/hr-ft 2-OF.For all three Green's functions, a 50OOF to 100'F thermal shock was evaluated in Regions I through 5 to determine the stress response.
For Region 6, a constant temperature of 120'F was I used.Referring to Figure 3-2, heat transfer coefficients for Transient 9 were applied as follows: For Transient 9: Region I The heat transfer coefficient, h, for 12% flow is 672.8 BTU/hr-ft 2-&deg;F at 500 0 F. 3 The heat transfer coefficient, h, for 12% flow is 308.2 BTU/hr-ft 2-&deg;F at 100&deg;F.The fluid temperature shock is: T = 526&deg;F -130'F -526&deg;F.Region 2 The heat transfer coefficient, h, for 12% flow is 632.2 BTU/hr-ft 2-OF at 500F.The heat transfer coefficient, h, for 12% flow is 616.6 BTU/hr-ft 2-OF at 300&deg;F.The fluid temperature shock is: T = 526&deg;F -268&deg;F -526&deg;F.Region 3 The heat transfer coefficient, h, for 12% flow is 336.4 BTU/hr-ft 2-OF at 500&deg;F.The heat transfer coefficient, h, for 12% flow is 328.0 BTU/hr-ft 2-OF at 300 0 F.The fluid temperature shock is: I Case 1: T = 526&deg;F -268&deg;F -526&deg;F Case 2: T = 526 0 F I I SIR 141-NPS, Rev. 0 3-3 Structural Integrity Associates, Inc.
Region 4 The heat transfer coefficient, h, is 0.4 BTU/hr-ft 2-OF.The temperature, T, is 120'F.Transition Regions The heat transfer coefficient was linearly transitioned from the value of the heat transfer coefficient used in adjacent regions.3.1.2 Green 's Functions The three flow-dependent thermal load cases outlined in the previous section were run on the reactor recirculation outlet nozzle FEM with the heat transfer coefficients and the fluid temperature conditions listed in Section 3.1.1. Two locations were selected for analysis (see Figures 3-3 and 3-4): 1. The critical safe end location was chosen as the node with the highest stress intensity due to thermal loading under high flow conditions.
The highest stress intensity due to thermal loading occurred at Node 6395 (see Figure 3-3), on the inside diameter of the nozzle safe end. Therefore, this node was selected for analysis.2. The critical blend radius location was chosen based upon the highest pressure stress intensity, neglecting the cladding.
The critical location is selected as Node 3829, as shown in Figure 3-4.Twelve stress intensity Green's Functions were developed (i.e., total stress intensity and membrane plus bending stress intensity for each location and each flow case). The total stress intensity Green's Functions for the safe end location at 100%, 50% and 0% flow are shown in Figures 3-5, 3-6 and 3-7, respectively.
The total stress intensity Green's Function for the blend radius location at 100%, 50% and 0% flow are shown in Figures 3-8, 3-9 and 3-10, respectively.
SIR-07-141-NPS, Rev. 0 3-4 Structural Integrity Associates, Inc.
 
====3.1.3 Thermal====
Transients The transients analyzed for the reactor recirculation outlet nozzle were developed based on the definitions in the original RPV Design Specification
[4], as modified for EPU [5], as well as more recent definitions based on BWR operating experience.
For BWR operating experience, the transients described in the thermal cycle diagrams for a BWR-4 plant similar in design and vintage to VY were obtained, and plant-specific data from VY was applied to each transient.
The resulting thermal cycle diagrams are shown in References
[12 and 13]. The final transients evaluated in the stress and fatigue analyses are shown in Figures 3-11 through 3-20.Thenumber of cycles projected for the 60-year operating life was used for each transient
[14].Tables 3-1 and 3-2 summarize the thermal transients for the safe end and blend radius locations, respectively.
 
===3.2 Pressure===
Loading 3 A uniform pressure of 1,000 psi was applied along the inside surface of the reactor recirculation outlet nozzle and the RPV wall. A pressure load of 1,000 psi was used because it is easily scaled up or down to account for different pressures that occur during transients.
In addition, a cap load 3 was applied to the piping at the end of the FEM. This cap load Was calculated as follows: I (R.2)where: Pcap -end cap pressure load (psi) U P unit pressure load = 1,000 psi 3 Ri 1  Inner Radius = 12.969 in R, Outer Radius= 14.188 in I SIR-07-141-NPS, Rev. 0 3-5 Structural lnlegrity Associates, Inc.3 The calculated pressure cap load of 5,081.7 psi was applied asa negative value so that it would exert tension on the end of the model. The nodes on the end of the FEM were coupled in the axial direction to ensure mutual displacement of the end of the FEM due to the attached piping.Figures 3-21, 3-22, and 3-23 show the internal pressure distribution, cap load, and symmetry condition applied to the RPV end of the model, respectively.
The internal pressure load case for the blend radius resulted in a total stress intensity of 31,300 psi, and for the safe-end resulted in a total stress intensity of 11,490 psi. The membrane plus bending stress intensity at the blend radius is .33,640 psi and at the safe end is 11,350 psi, respectively.
 
===3.3 Piping===
Loading The piping stress- intensities (stress caused by the attached piping) were determined for the two evaluated reactor recirculation outlet nozzle locations.
The design piping reactions that were used in the stress and fatigue evaluation are defined on the Reference
[15] drawing. These loads represent shear and moment loadings on the nozzle resulting from thermal .expansion of the attached piping and seismic loads. The loads are as shown in Figure 3-24. The stresses resulting from these loads were calculated by hand using classical structural mechanics formulas, as documented in Reference
[ 11 ], and are shown in Tables 3-3 and 3-4 for the safe end and blend radius locations, respectively.
SIR-07-141-NPS, Rev. 0 3-6 Structural Integrity Associates, Inc.
I I I I Table 3-1: Safe End Transients Transient Time Temp Time Step Pressure Flow Rate Transient Time Temp .Time Step Pressure Flow Rate Number W .(!F J U WM iGPM_ Number M iLss (mm (GPMI 1. Normal Startup with 0 100 0 14147.0 6. Reactor Overpressure 0 526. 1010 28294 Heatup at 100lFhr 16164 549 16164 1010 (50%), 1 Cycle 2 526 2 1375 (100%).300 Cycles 16864 549 700 '1010 32 526 30 940 2. Turbine Roll and 0 549 1010 28294 1832 526 1800 940 Increase to Rated Power 1 542 1 1010 (1(o0%) 2252 549 420 1010 300 Cycles 601 542 600 1010 2312. 549 60 1010 602 526 1 1010 2313 542 1 1010 1302 526 700 1010 .I 2913 542 600 1010 3. Loss of Feedwater 0 526 1010 28294 2914' 526 1 1010 I Heaters 1800 542 1800 1010 (100%)' 3614 526 700 1010 Turbine Trip 25% Power 2100 542 300 1010 7. SRV Blowdown .0 526 1010 28294 10 Cycles -2460 526 .360 1010 1 Cycle 600 375 600 170 (100%)'3060 526 600 1010 11580 70 10990 50 3960 542 900 1010 12280 70 700 50 4260 542 300 1010 8. SCRAM Other 0 526 1010 28294 6060 526 .1800, 1010 228 Cycles T5 526 15 940 (100%)6760 526 700 1010 1815 526 1800 940 4. Loss of Feedwater 0 526 1010 0 2235 549 420 1010 Pumps 3 526 3 1190 (0%)' 2295 549 60 1010 10 Cycles 13 526 10 1135 2296 542 1 1010 233 300 220 1135 2356 542 60 1010 2213 500 1980 1135 2357 526 1 1010 2393 300 180 885 3057 526 700 1010 6773 500 4380 1135 9. Improper Startup 0 526 1010 3395 7193 300 420 675 14147 1 Cycte 1 130(' 1 1010 (12%)7493 300 300 675 (50%), 27 130 ' 26 1010 11093 400 3600 240 28 526 1 1010 16457 549 5364 1010 728 526 700 1010 16517 549 60 1010 1I. Shutdown 0 549 1010 14147 16518 542 1 1010 28294 300 Cycles 6264 375 6264 170 (50%)'17118 542 600 1010 (100%). 6864 330 600 88 17119 526 1 1010 16224 70 9360 50 17819 526 700 1010 16924 70 700 50 I U I I I I 5. Turbine Generator Trip 60 Cycles 0 10 15 30 1830 2250 2310 2311 2911 2912 3612 526 526 ,-526 526 526 549 549 542 542 526 526 10 15 1800 420 60 1 600 1 700 1010.1135 1135 940 940 1010 1010 1010 1010 1010 1010 28294 11. Design Hydrostatic
-(100%:' rest 120 Cycles 100 0 1100 50 19811 (7%)'I 12. Hydrostatic Test -100 -50 1961 1 Cycle 1563 (7%)'50 Notes: 1. The instant temperature change is assumed as I second time step.2. The number of cycles is for 60 years (14).3. 130'F is (he safe end temperature for this transient The blend radius has a different temperature for Transient
: 9. (13]Note: These transients are the same as in Table 3-2 with the exception of the 700 second steady state time increment that is used. The transients in Table 2 are plotted using a 6000 second steady state increment.
The difference is due to the length of the Green's Function for the safe end which is shorter compared to the blend radius.I I I I U I I SIR-07-141-NPS, Rev. 0 3-7 Structural integrity Associates, Inc I1 Table 3-2: Blend Radius Transients Transient Time Temp Time Step Pressure Flow Rate Transient Time Temp Time Step Pressure Flow Rate Number Ws) CFJ L(S) s(pg) (GPMI Number (s) (7FI W s P 1. Normal Startup with 0 100 0 14147.0 6. Reactor Overpressure 0 526 1010 28294 Heatup at 100*F/hr 16164 549 16164 1010 (50%), 1 Cycle 2 526 2 1375 (100%)'300 Cycles 22164 549 6000 1010 32 526 30 940 2- Turbine Roll and 0 549 1010 28294 1832 526 1800 940 Increase to Rated Power 1
* 542 1 1010 (100%)' 2252 549 420 1010 300 Cycles 601 542 600 1010 2312 549 60 1010 602 526 1 1010 2313 542 1 1010-6602 526 6000 1010 2913 542 600 1010 3. Loss of Feedwater 0 526 1010 28294 2914 526 1 1010 Heaters 1800 542 1800 1010 (100%). 8914 526 6000 1010 Turbine Trip 25% Power 2100 542 300 1010 7. SRV Blowdown 0 526 1010 26294 10 Cycles 2460 526 360 1010 1 Cycle 600 375 600" 170 (100%)'3060 526 600 1010 11580 70 10980 50 3960 542 900 1010 17580 70 6000 50 4260 542 300 1010 8. SCRAM Other 0 526 1010 28294 6060 526 1800 1010 228 Cycles 15 526 15 940 (100%)y 12060 526 6000 1010 1815 526 1800 940 4. Loss of Feedwater 0 526 1010 0 2235 549 420 1010 Pumps. 3 526 3 1190 (0%)- 2295 549 60 1010 10 Cycles 13 526 10 1135 2296 542 1 1010 233 300 220 1135 2356 542 60 1010 2213 500 1980 1136 2357 526 1 1010 2393. 300 180 885 8357 526 6000 1010 6773 500 4380 1135 9. Improper Startup 0 526 1010 3395 7193 300 420 675 1 Cycle 1 268 1 1010 (12%)&#xfd;7493 300 300 675 27 2685" 26 1010 10793 400 3600 240 28 526 1 1010 12862 549 5369 1010 6028 526 6000 ..1010 12922 549 60 1010 10. Shutdown 0 549 1010 14147 12923 542 1 1010 300 Cycles 6264 375 6264 170 (50%).13523 542 600 1010 6864 330 600 .88 13524 526 1 1010 16224 70 9360 50 19524 526 6000 1010 1 22224 70 6000 50 5. Turbine Generator Trip 60 Cycles 0 10 15 30 1830 2250 2310 2311 2911 2912 8912 526 526 526 526 526 549 549 542 542 526 526 10 15 1800 420 60 1 600 1 1010 1135 1135 940 940 1010 1010 1010 1010 1010 1010 28294 11. Design Hydrostatic (100%). Test 120 cycles 100 1981 1563 (7%)12. Hydrostatic Test -. 100 -I 0 1981 1 Cycle 1100 .(7%)___________________1
_____ 1______ _____
* 50 [____Notes: 1. The instant temperature change is assumed as I second time step.2. The number of cycles is for 60 years [14).3. 268&deg;F is the blend radius temperature for this transient.
The safe end has a different temperature for Transient
: 9. [13)I SIR-07-141-NPS, Rev. 0 3-8 U Structural Integrity Associates, Inc.
II i Table 3-3: Stresses Due to Piping Loads for Safe End Location Safe End External Piping Loads__ _ Parameters F. 20.00 kips i e .20.00 kips Fz= 30.00 kips M 2004.00 in-kips__M_ = 3000.00 in-kips Mz 2004.00 in-kips OD= 26.38 in ID=. 25.938 in RN= 13.58 in.L 4.25 in tN= 1-.22 in V0_)2 1919.00 in-kips (My)2= 3085.00 in-kips Mx_ 3633.15 in-kips Fxy 28.28 kips Nz=_ 6.62 kips/in qN_=_. -1.07 kips/in Primary Membl)rane Stress Intensity SPMz 5.43 ksi T_ _ -0.88 ksi SlIMx = 5.71 ksi SImax = 5708.89 psi I!I I I I I I U I I I I I SfR-07-141-NPS, Rev. 0 3-9 SRStructural Integrity Associates, Inc.
Table 3-4: Stresses Due to Piping Loads for Blend Radius Location Blend Radius External Piping Loads Parameters Fx= 20.00 kips Fy = 20.00 kips Fz = 30.00 kips Mx= 2004.00 in-kips my= 3000.00 in-kips Mz = 2004.00 in-kips OD= 55.88 in ID= 37.368 in RN 23.31 in L= 42.77 in tN 9.25 in (M.)2 = 1148.54 in-kips (My)2 = 3855.46 in-kips Uxy= 4022.90 in-kips FXY 28.28 kips Nz= 2.56 kips/in qN= -0.20 kips/in Primary Membrane Stress Intensity PMz 0.28 ksi C = -0.02 ksi Slmax= 0.28 ksi Simax = 280.16 psi SIR-07-141-NPS, Rev. 0 3-10 V Structural Integrity Associates, Inc.
AREA8 Region 5 Region 6 Region4 1 Region 2 Region 3 Recirc Outlet Nozzle Finite Element Model AN !:$::i APR 19 2007 13:35:14 Region 1 I I I I I I I I I I I I I I I i I I x 1z_; ,V Figure 3-1: Thermal Regions for Green's Functions SIR-07-141-NPS, Rev. 0 3-11 Structural Integrity Associates, Inc.
I I I I I I I I I I I-I I Figure 3-2: Thermal Regions for Transient 9 SIR-O7-141-NPS, Rev. 0 3-12 Structural lntegrity Associates, Inc.
I I I I I I I I I Figure 3-3: Safe End Critical Thermal Stress Location SIR-07-141-NPS, Rev. 0 3-13 V Structural Integrity Associates, Inc.
Figure 3-4: Blend Radius Critical Thermal Stress Location SIR-07-141-NPS, Rev. 0 3-14 V Structural Integrity Associates, Inc.
140000 C.0 200 400 600 800 1000 Time (sec)Figure 3-5: Safe End Total Stress Intensity Green's Function for 100% Flow SIR-07-141-NPS, Rev. 0 3-15 Structural Integrity Associates,.
Inc.
.U)0.U)U)C,'0 100 200 300 400 500 600 700 800 900 1000 Time (sec)Figure 3-6: Safe End Total Stress Intensity Green's Function for 50% Flow SIR-07-1417NPS,-
Rev. 0 3-16 SRvStructural Integrity Associates, Inc.
0.I I I I I I I I I I I I U I I I U I I 0 100 200 300 400 500 600 700 800 900 1000 Time (sec)Figure 3-7: Safe End Total Stress Intensity Green's Function for 0% Flow SIR-07-141-NPS, Rev. 0 3-17 Structural Integrity Associates, Inc.
60000 0 0.0 U'40000 20000 0 0 1000 2000 3000 4000 5000 6000 7000 Time (sec)8000 Figure 3-8: Blend Radius Total Stress Intensity Green's Function for 100% Flow SIR-07-141-NPS, Rev. 0 3-18 Structural Integrity Associates, Inc.
CLi 0 1000 2000 3000 4000 5000 6000 7000 .8000 Time (sec)Figure 3-9: Blend Radius Total Stress Intensity Green's Function for 50% Flow 7-141-NPS Rev. 0 3-19 W itr.ptrr!f Infnarvif A SIR-O0 nniltac inr I%~4W 6*IflM* 1*5 *Rf*I.yl fIj IWI.fl.fltLtJiJ~
U'fl.~.
I I I I I I I I I I I I 0 0 0 cn 35000 30000 25000 20000 15000.100001 5000 0-0 1000 2000 3000, 4000 5000 6000 7000 8000 Time (sec)Figure 3-10: Blend Radius Total Stress Intensity Green's Function for 0% Flow 07-141-NPS.
Rev. 0 3-20 ffr.pfgrM Infparifu A', SIR-(nri~t~ Inc J~~~~.v~dae Inc~ t ..ysV,~
-Temp (VF) --- Pressure (psig) I 600 500 400 7 300 I--200 100 -.1100-1050 1000 950 900 850 800 750 700 650 600-550 500 450 400 350 300 250 a, a 4'(4 4, 3000 6000 9000 12000 15000 Time (seconds)Figure 3-11: Transient 1: Normal Startup at 100 0 F/hr i I I I I Structural Integrity Associates, inc 1 SIR-07-141-NPS, Rev. 0 3-21 1-- Temp (&deg;F) --Pressure (psig)j 555 550 545 540 C 535 530 525 1120 1040 960 880 800 720 640 560 &deg;480 a.400 320 240 160 80 0 500 0 50 100 .150 200 250 Time (seconds)300 350 400 450 Figure 3-12: Transient 2: .Turbine Roll and Increase to Rated Power SIR-07-141-NPS, Rev. 0 3-22 V Structural Integrity Associates,.
Inc.
I--Temp (CF) ---Pressure (psig) I 600 550-500-450 400350-_300 E 0 250 I--200 150 100 50 0--------------------------1080 1040 1000 960 920 880 840 800"760 720 680 640 600 560 520 480 440 400 360 320 280 240 200 160 120.80 40Q-0 10000 0, a, a 0.(a 0~I I 0 2000 4000 6000 8000 Time (seconds)Figure 3-13: Transient 3: Loss of Feedwater Heaters and Turbine Trip at 25% Power I I I I I I I SIR-07-141I-NPS, Rev. 0 3-23 V Structural Integrity Associates, Inc.
I-Temp (TF) --Pressure (psig) I 600 U-0~ 300 0.E I-1280 1240 1200 1160 1120 1080 1040--------1000 960 920 880 840 800 760 720 680 640 600 560 520 480 440 400 360 320 280 240 200 160 120 80 40 0 18000 20000 22000 0C 0 2000 4000 .6000 8000 10000 12000 14000 16000 Time (seconds)Figure 3-14: Transient 4: Loss of Feedwater Pumps SIR-07-141-NPS, Rev. 0 3-24 Structural lntegrity Associates, Inc.
I- Temp (-F) --Pressure (psig) I 555 550 II I--- ---------------LL 540 535 I--530 525 1200 1150 1100 1050 1000 950 900 850 800 750 700 _650 600 550 500 o-450 400 350 300 250 200 150 100 50 0 ,3000 0 500 1000 1500 2000 2500 Time (seconds)Figure 3-15: Transient 5: Turbine Genera~tor Trip I SIR-07-141-NPS, Rev. 0 3-25 Structural Integrity Associates, Inc..3I I- Temp (&deg;F) --Pressure (psig)600 I.500-I--400 300 L -1500 1400 1300 1200 1100 1000 900 800 ..700 300 200-100 0 3000 0 500 1000 1500 Time (seconds)2000 2500 Figure.3-16:
Transient 6: Reactor Overpressure SIR-07-141-NPS, Rev. 0 3-26 U Structural Integrity Associates, Inc.
I Temp (F-) --Pressure (psig)600 400 300 CL E I-I 1100 1000 900 800 700 01 600 a 500 CL-400 300 200 100 0.200 I I 1001 I --------0 2000 4000 6000 8000 10000 12000 Time (seconds)Figure 3-17: Transient 7: SRV Blowdown I I I Structural Integrity Associates, Inc.<I SIR-07-141-NPS, Rev. 0 3-27
[- Temp (&deg;F) -Pressure (psig)600--------------500 -400 300 E.200 100 1100 1000 900 800 700-600 500 400 300 200 100 0 0 1000 2000 3000 4000 5000 Time (seconds)Figure 3-18: Transient 8: Scram -Other SIR-07-141-NPS, Rev. 0 3-28 Structural IntegrityAssociates, Inc.
-Temp (F) --- Pressure (psig) I 600 1100 1000 500 400 300 E 200-100 0 900 800.700 600 .-500 C (L Blend Radius I_1 Safe End 400 300 200.A-100 0 0 10 20 30 40 50 Time (seconds)60 70 80 90 100 Figure 3-19: Transient 9: Improper Startup I I I I I SIR-07-141-NPS, Rev. 0 3-29 I SStructural Integrity Associates, Inc.I I I I I I I I I I I I-Temp (&deg;F) --Pressure (psig)600 500 400 300 E 200-1100 1000 900 800 700 600 C.500 a-100 300 200 100 0 16000 0 0 2000 4000 6000 6000 10000 12000 Time (seconds)14000 I Figure 3-20: Transient 10: Shutdown I I I I I I I SIR-07-141-NPS, Rev. 0 3-30 V Structural Integrity Associates, Inc.
I I I I I I Figure 3-21: Reactor Recirculation Outlet Nozzle Internal Pressure Distribution I I I SStructural Integrity Associates, Inc.I SIR-07-141-NPS, Rev. 0 3-31 E~LEMENTS PRE S-NOPM APR 19 2007 13:32:34-5082-4406-3730-3054-2379-1703-1027-351. 496 324. 252 10001 Rec-irc- OutlePt. Wozzi t-- i nifte F.1 Pment Model Figure 3-22: Reactor Recirculation Outlet Nozzle Pressure Cap Load SIIR-0 7-141-NPS, Rev. 0 3-32 Structural Integrity Associates, Inc.
AN.APR 19 2007*13-34:01 I IBoundary Condition I I I Figure 3-23: Reactor Recirculation Outlet Nozzle Vessel SIR-07-141-NPS, Rev. 0 ,3-33 F.Figure 3-24: Pipe Reactions SIR-07-141-NPS, Rev. 0 3-34 V Structural Integrity Associates, Inc.
 
===4.0 STRESS===
AND FATIGUE ANALYSIS RESULTS Fatigue calculations for the VY reactor recirculation outlet nozzle were performed in accordance with ASME Code, Section 1II, Subsection NB-3200 methodology (1998 Edition, 2000 Addenda)[17]. Fatigue analysis was performed in the Reference
[1.1] calculation for the two locations identified in Section 3.1.2 using the Green's Functions developed for these two locations and the 60-year projected cycle counts from Reference
[14].Three computer programs were used to facilitate the fatigue analysis process: STRESS.EXE, I P-V.EXE, and FATIGUE.EXE.
The first program, STRESS.EXE, calculates a stress history in response to a thermal transient using a Green's Function.
The second program, P-V.EXE, reduces the stress history to peaks and valleys. The third program, FATIGUE.EXE, calculates fatigue from the reduced peak and valley history using ASME Code, Section III methodology.
All three programs are explained in detail and were independently verified for use in the Reference
[16] calculation.
i In order to perform the fatigue analysis, input files with the necessary data were prepared and the i three analysis programs were run. The program STRESS.EXE required the following three input files: n o Green.dat:
This file contains the Green's Function.
As discussed above, the reactor recirculation outlet nozzle analyses utilize twelve Green's Functions:
a I membrane plus bending stress intensity Green's Function and a total stress intensity Green's Function for both the safe end and blend radius locations for each of three flow conditions.
II" Green.cfg:
A configuration file containing parameters that describe the Green's Function.
3* Transnt.inp:
This file contains the input transient history defined in Tables 3-1 and 3-2.SIR-07-141-NPS, Rev. 0 4-1
* Structural Integrity Associates, Inc.i Tables 4-1 and 4-2 show the stresses for each location that were used in the fatigue analysis'Columns 2 through 5 of Table 4-1 (for the safe end) and Table 4-2 (for the blend radius) show the final peak and valley outputafter stress history reduction.
The pressure values for Columns 6 through 8 in each table were determined from the transient pressures specified in Tables 3-1 and*3-2. The pressure stress intensities from Section 3.2 were scaled appropriately for each transient case. The scaled piping stress values are shown in Columns 9 and 10 of Tables 4-1 and 4-2. The piping stress intensities from Section 3.3 were scaled based on the transient case RPV fluid temperature and assuming no stress occurs at an ambient temperature of 70'F. Both of these stress intensities were then added to the thermal stress intensity peak and valley points to calculate the final stress values used for the fatigue analysis.
In the case of the piping load stress intensities, the sign of the stress intensity was conservatively set to the same sign as the thermal stress intensity to ensure bounding fatigue usage results.:
Columns 11 and 12 of Tables 4-1 and 4-2 show the summation of all stresses for each thermal peak and valley stress point. The last column shows the number of cycles associated with each peak or valley based on the cycle counts shown in Tables 3-1 and 3-2.The program FATIGUE.EXE perfonns the ASME Code peak event-pairing required to calculate a fatigue usage value. The input data for the configuration input file for FATIGUE.EXE, which is named FATIGUE.CFG, is shown in Table 4-3.The results of the fatigue analysis are presented in Tables 4-4 and 4-5 for the safe end and the blend radius for&deg;60 years, respectively.
SIR-07-141-NPS, Rev. 0 4-2 Structural Integrity Associates, Inc.
I I I Table 4-1: Reactor Recirculation Outlet Nozzle Safe End Stress Summary 1 2 3 4 5 6 7 8 9 10 11 12 13 Total M-B Total M+B Total Total Number Total M+B Pressure Pressure Piping Piping Total M+B of Transient Time Stress Stress Temperature Pressure Stress Stress Stress Stress Stress Stress Cycles Number (s) (psi) si F .(ps1<j (psi) pi) (psi (psi) (psi) (psi) (60 years)1 0 -925 -949 100.00 -0 0 0 -339.1419
-339.1419
-1264.14 -1288.14 300 16164 .-4814 -4433 549.00 1010 11604.9 11463.5 -5414.966
-5414.966 1375.93 1615.53 300 16864 -3749 -3705 549.00 1010 11604.9 11463.5 -5414.966
-5414.966 2440.93 2343.53 300 2 0 -3838 -3665 549 1010 11604.9 11463.5 -5414.966
-5414.966 2351.93 2383.53 300 6 -1664 -2263 542 1010 11604.9 11463.5 -5335.833
-5335.833 4605.07 3864.67 300 601 -3773 -3607 542 1010 11604.9 11463.5 -5335.833
-5335.833 2496.07 2520.67 300 606.6 1196 -403 526 1010 11604.9 11463.5 5154.958 -5154.958 17955.86 5905.54 300 1302 -3670 -3509 526 1010 11604.9 11463.5 -5154.958
-5154.958 2779.94 "2799.54 300 3 0 -3688 -3522 526 1010 11604.9 11463.5 -5154.958
-5154.958 2761.94 2786.54 10 1800.1 -4165 -3904 542 1010 11604.9 11463.5 -5335.B33
-5335.833 2104.07 2223.67 10 2460.2 -1932 -2200 526 1010 11604.9 11463.5 -5154.958
-5154.958
.4517.94 4108.54 10 3960.2 -4537 -4185 542 1010 11604.9 11463.5 -5335.833
-5335.833 1732.07 1942.67 10 6060.2 -3315 -3241 526 1010 11604.9 11463.5 -5154.958
-5154.958 3134.94 3067.54 10 6760 -3687 -3522 526 1010 11604.9 11463.5 -5154.958
-5154.958 2762.94 2786.54 10 4 0.00 -3756 -3716 526 1020 11719.8 11577 -5154.958
-5154.958 2808.84 2706.04 10 3.00 -3756 -3716 526 1190 13673.1 13506.5 -5154.958
-5154.958 4762.14 4635.54 .10 13.00 -3756 -3716 526 1135 13041.15 12882.25 -5154.958
-5154.958 4130.19 4011.29 10 242.30 15878 10049 302.374 1135 13041.15 12882.25 2626.926 2626.926 31546.08 25558.18 10 2213.10 -6388 -5428 499.889 1135 13041.15 12882.25 -4859.78 -4859.78 1793.37 2594.47 10" 2408.601 13203 8265 301.443 .885 10168.65 10044.75 2616.401 2616.401 25988.05 20926.15 10 6773A0 -4763 -4312 499.809 1135 13041.15 12882.25 -4858.875
-858.875 3419.27 3711.37 10 7193.10 15374 9801 .300 675 7755.75 7661.25 2600.088 2600.088 25729.84 20062.34 10 16457.50 -4812 -5032 549 240 2757.6 2724 -5414.966
-5414.966
-7469.37 -7722.97 10 16524170 -2358 -2725 542 1010 11604.9 11463.5 -5335.833
-5335.833
*3911,07 3402.67 10 17118.00 -3778 ,-3610 541.996 1010 11604.9 11463.5 -5335.788
-5335.788 2491.11 2517.71 10 17123.60 1192 -406 526 1010 .11604.9 11463.5 5154.958 -5154.958 17951.86 5902.54 10 17819.00 -3670 -35091 526 1016 1166a. 11463.5 -5154.958
-5154.958!
2779,94 2799.54, 10 5 0.00 -3688, -3522 526 10101 11604.9 11463.5, -5154-958
-5154.958, 2761.94 2786.54 60.10,0 -3688 -3522 526 1135 13041.15 12882.25 -5154.958
-5154.958 4195.79 4205.29 60 30,00 -3688 -3522 526 940 10800.6 10669 -5154.958
-5154.958 1957.64 1992.04 60 2250,10 -6054 -5337 549 1010 11604.9 11463.5 -5414.966
-5414.966 135.93 711.53 60 2319.90 -2977 -3123 542 1010 11604.9 11463.5 -5335.833
-5335.833 3292.07 3004.67 60 2911.00 -3782 -3613 541.999 1010 11604.9 11463.5 -5335.822
-5335.822 2487.08 2514.68 60 2916870 1188 -408 526 1010 11604.9 11463.5 5154.958 -5154.958 17947.86 5900.54 60 3612,00 -3670 -3509S 526 1010 11604.9 11463.5 -5154.958
-5154.958 2779.94 "2799.54 60 6 0.00 -3688 -3522 5.26E+02 1010 11604.9 11463.5 -5154.958
-5154.958 2761.94 2786.54 1 2.0 7 -3688 -3522 5 326E+02 1375 15798.75 15606.25 -5154.954
-5154.958 6955.79 6929.24 1 32.00 -3688 -3522 5.26E+02 940 10800.6 10669 -5154.958
-5154,958 1957.64 1992.0. 1 2252.10 -6054 -5336 5.49E+02 1010 11604.9 11463.5 -5414.960
-5414.966
.135.93 711.53 1 2322.20 -2977 -3123 5.42E+02 1010 11604.9 11463.5 -5335.833
-5335.833 3292.07, 3004.67 1 2913.00 -3782 -3613 5-42E+02 1010 11604.9 11463.5 -5335.822
-5335.822 2487.09 2514.68 12 2918.70 1188 -408 5.26E+02 1010 11604.9 11463.5 5154.958 -5154.958 17947.86 5900.54 1 3614.00 -3670 -3509 5.26E+02 1010 11604.9 11463.5 -5154.958
-5154.958 2779.94 2799.54 1 7 0 -3688 -3528 5265 1010 11604.9 11463.5 -5154.958
-5154.958 2761.94 2746.54 ' 1 600 77737 5336 375 170 1953.3 1929.5 3447.943 3447.943 13174.24 10713.44 1 1367.9 -1390 -1567, 354.172 162 1861.38 1838-7 &#xfd;3212.488
-3212.488
-27T4 1l -2940.79 1 11580.1 454 1901 70 50 574.5 567.5 0 0 1028.50 :A .5 12280 -707 -689 70 50 574.5 567.5 0 0 -132.50 -121.50 1 8 0.00 -3688 -3522 526 1010 11604.9 11463.5 -5154.958"-5154.958 2761.94 2786.541 228 15.00 -3688 -3522 526 940 10800.6 10669 -5154.958
-5154.958 1957.64 .1992.04 228 2235.10 -6054 -5337 549 1010 1 1604.8 11463.5 -5414.966
-5414.966 135.93 8711.53 228 2305.20 -2977 -3123 542 1010 11604.5 11463.5 -5335.839 3395.833 3292.07 3004.67 228 2356.0F -3183 -3151 541.999 1010 11604r. .11463.5 -5335.822
-5335.822 3086.08 2976.68 228 2361.50 1761 -28 526 1010 11604.9 11463-5 5154.958 -5154.958 18520.86 _6280-54 228 3057.00 *-3667 -3506 526 1010' 11604-9 11463-5 -5154.958
-5154.958 2782.94 2802.54 228 9 0 -2968 -2837 525.7 1010 11604.9 11463.5 -5151.566
-5151.566 3485.22. 3474.82 1 27 68473 45303 291.3 1010 11604.9 11463.5 2501.737 2501.737 82579.74 59268.34.
1 80.7 -11546 -8877 518.4 1010 11604.9, 11463.5 -5069.042
-5069.042
-5010.04 -2482-14 1 5200 -2967 -2832 525.7. 1010 11604.9 11463.5 -5151.566
-5151.566 3486.21 1 10 0 -3745 -3709 549 1010 11604.9 11463.5 -5414.966
-5414.966 2444.93 2339.53 300' 68614.2 501, -A05 329,994 170 1953.3 1929.5 2939.162 -2939.162 5393,46 -1414.66 300 7455.5 -1183 -1528 314.325 88 1011.12 998-8 -2762.029
-2762.029
-2933.91 -3291-23 300 16224.1 334 -35 70 50 574.5 0 0 908.50! 532.50 300 16924 -731 -763 70 50, 574.5 567.5, 0 0 -156.50, -195.50 3001 11 0 O0 100 0 0 0 339.1419 339.1419 339.14 339.14 120 0 0 100 1100 12639 12485 339.'1419 339.1419 12978.14 12824.14 120 0 o 1 10 .o *50 574.5 567.5 339.1419, 339.1419 913.64 906-64 120 12O 0 0 100 50 574.5 567.5 339.141 339.1419 913.64 906.64 10 00 1531988 74.539141 33911 18298.01 18079.19 1'&#xfd;2 0 1No 50 574.5 567-5]39.
339 3314 41 913.64 906.64 11 For notes, see next page.I I I I I I I I 1 U I I I I I SIR-07-141-NPS, Rev. 0 4-3 V Structural Intaerity Associates, Inc.1 Table 4-1: Reactor Recirculation Outlet Nozzle Safe End Stress Summary (concluded)
NOTES: Column 1: Transient number identification.
Column 2: Time during transient where maximum or minimum stress intensity occurs from P-V.OUT output file.Column 3: Maximum or minimum total stress intensity from P-V.OUT output file.Column 4: Maximum or minimum membrane plus bending stress intensity from P-V.OUT output file.Column 5: Temperature per total stress intensity.
Column 6: Pressure per Table 3-1.Column 7: Total pressure stress intensity from the quantity (Column 6 x 11490)/1000.
Column 8: Membrane plus bending pressure stress intensity from the quantity (Column 6 x 11350)/1000.
Column 9: Total external stress, 5707.89 psi*(Column 5-70&deg;F)/(549&deg;F
-70'F).Column 10: Same as Column 9, but for M+B stress.Column l1: Sum of total stresses (Columns 3, 7, and 9).Column 12: Sum of membrane plus bending stresses (Columns 4, 8, and 10).Column 13: Number of cycles for the transient (60 years).SIR-07-141-NPS, Rev. 0 4-4 SRvStructural Integrity Associates, Inc.
Table 4-2: Reactor Recirculation Outlet Nozzle Blend Radius Stress Summary 1 2 3 4 5 6 7 8 9 10 11 12 13 Total M+1B Total M+B Total Total Number Total M+B Pressure Pressure Piping Piping .Total M+4 of Transient Time Stress Stress Temperature Pressure Stress Stress Stress Stress Stress Stress Cycles Number Jl f (psi) (Psi F .(psiS) (psi. (psil 10i3 ps pi (60 years)1 0 459 388 100.00 0 0 0 16.64312 16.64312 475.64 404.64 300 4303 -3417 -1594 219.53 1010 31613 33976.4 -82.95209
;82.95209 28113.05 32299.45 300 22164 2713 2306 549.00 1010 31613 33976.4 265.7352 265.7352 34591.74 36548.14 300 2 0.00 3094 1934 549 1010 31613 33976.4 265.7352 265.7352 34972.74 36176.14 300 94.30 4079 2481 542 1010 31613 33976.4 261.8518 261.8518 35953.85 36719.25 300 601.70 3683 2435 538.8 1010 31613 33976.4 260.0765 260.0765 35556.08 36671.48 300 680.10 .5891 3489 526 1010 31613 33976.4 252.9754 252.9754 37756.98 37718.38 300 6602.00 2977 1859 526 1010 31613 33976.4 252.9754 252.9754 34842.98 36088.38 300 3 0.00 2959 1849 526 1010 316131 33976.4 252.9754 252.9754 34824M98 36078.38 10 1807.20 1834 1043 542 1010 31613 33976.4 261.8518 261,8518 33708.85 35281.25 10 2491.50 4425 2667 526 1010 31613 33976.4 .252.9754 252.9754 36290.98 36896.38 10 3974.40 1706 1060 542 1010 31613 33976.4 261.8518 261.8518 33580.85 35298.25 10 6070.80 3971 2551 526 1010 31613 33976.4 252.9754 252.9754 35836.98 36780.38 10 12060.00 2965 1852 526 1010 31613 33976.4 252.9754 252.9754 34830.98 36081.38 10 4 0 2465 -703 526.00 1010 31613 33976.4 252.9754 -252.9754 34330.98 33020.42 10 3 2465 -703 526.00 1190 37247 40031.6 252.9754 -252.9754 39964.98 39075.62 10 13 2465 -703 526.00 1135 35525.5 38181.4 252.9754 -252.9754 38243.48 37225.42 10 435.6 18138 9690 356.38 1135 35525.5 38181.4 158.8774 158.8774 53822.38 48030.28 10 2222.5 -1169 -2598 489.44 1135 35525.5 38181.4 -232.6952
-232.6952 34123.80 35350.70 10 2665.5 12763 6695 328.40 885 27700.5 29771.4 143.3539 143.3539 40606.85 36609.75 10 6779.2 -4008 -2829 497.05 1010 31613 33976.4 -236.9137
-236.9137 27368.09 30910.49 10 7243.8 19275 9965 302.91 1010 31613 33976.4 129.2122 129.2122 51017.21 44070.61 10 13996 -2135 34 542.00 1010 .31613 33976.4 -261.8518 261.8518 29216.15 34272.25 10 17247 3413 2074 526.00 1010 31613 33976.4 252.9754 252.9754 35278.98 36303.38 10 23119 2971 18551 526.00 1010 31613 33976.4 252.9754 252.9754 34836.98 36084.38 10 5 0.00 2959 1849 526 1010 316131 33976.4 252.9754 252.9754 .34824.98 36078.38 60 10.00 2959 1849 526 1135 '35525.5 '38181.4 252.9754 .252.9754 38737.48 40283.38 60 15.00 2959 1849 526 940 29422 31621.6 252.9754 252.9754 32633.98 33723.58 60 2269.50 111 295 549 1010 31613 33976.4 265.7352 265.7352 31989.74 34537.14 60 3010.10 4407 2579 .526 1010 ,31613 33976.4 252.9754 252.9754 36272.98 36808.38 60 8912.00 2968 1854 526 1010 .31613 33976.4 252,9754 252.9754 34833.98 36083.38 60 6 0.00 2959 1849 525.00 1010 31613 33976.4 252.9754 252.9754 34824.98 36078.38 1 2.00 2959 1849 526.00 1375 43037.5 46255 252.9754 252.9754 46249.48 48356.98 1 32.00 29591 1849 526.00 940 29422 31621.6 252.9754 252.9754 32633.98 33723.58 1 2271.50 111 295 549.00 1010 31613 33976.4 265.7352 265.7352 31989.74 34537.14 1 3022.00 4407 2579 526.00 1010 31613 33976.4 252.9754 252.9754 36272.98 36808.38 1 8914.00 2968 1854 526.00 1010 31613 33976.4 252.9754 252.9754 34833.98 36083.38 1 7 0,00 2959 1849 526 1010 31613 33976.4 252.9754 252.9754 34824.98 36078.38 1 615.10 20260 12980 374.581 170 5321 5718.8 168.9726 168.9726 25749.97 18867.77 1 17580.00.
279 179 70 50 1565 1682 0 0 1844.00 1861.00 1 8 0.00 2959 1849 -526 1010 .31613 33976.4 252.9754 252,9754 34824.98 36078.38 228 15.00 2959 1849 -526 940 29422 .31621.6 252.9754 252,9754 32633.98 33723.58 228 2254.50 111 295 549 1010 31613 33976.4 265.7352 265.7352 31989.74 34537.14 228 2491.20 3792 2234 526 1010 31613 33976.4 252.9754 252.9754 35657.98 36463.38 228 8357.00 2963 1851 526 1010 31613 33976.4 252.9754 252.9754 34828.98 36080.38 228 9 .0 2058 961 525.8 1010 31613 33976.4 252.8645 252.8645 33923,86 35190,26 1 0.52 1956 734 525.6 1010 31613 33976.4 252.7535 252.7535 33821.75 34963.15 1 28 23747 3188 504.5 1010 31613 33976.4 241.0479 241.0479 55601,05 37405.45 1 425 1520 611 .. 525.5 1010 31613 33976.4 252.698 252.698 33385.70 34840.10 l1 12400 2058 .679 525.8 1010 31613 33976.4 252.8645 252.8645 33923.86 35108.26 '1 10 1 0 2767 2176 549 1010 31613 33976.4 265.7352 265.7352 34645.74 36418.14 300 4240.8 6643 4158 445.775 441 13803.3 14835.24 208.469 208.469 20654.77 19201.71 300 6268 6498 3675 374.7 170 5321 5718.8 169.0386 169.0386 11988.04 9562.84 300 6891.8 9282 5241 329.228 88 2754.4 2960.32 143.8121 143.8121 12180.21 8345.13 300 22224 361 120 70 50 1565 1682 0 0 1926.00 1802.00 300 11 0 0 100 0 0 0 16.64312 16.64312 .16.84 16.64 120 0 0 100 1100 34430 37004 16.64312 16.64312 34446.64 37020.64 120 1 0 0 100 50 1565 1682 16.64312 16.64312 1581.64 1698.64 120 12 0 _ 0 .100 50 1565 1682 16.64312 16.64312 1581.64 1698.64 0 ____ 0 100 1563 489219 52579.32 16.84312 16.64312 48938.54 .52595.96 1 1 0 0 100 50 1565 1682 16.64312 16.64312 1581.4 1698.64 1 For notes, see next page.I I I I U I I I I I I I I I I I SIR-07-141-NPS, Rev. 0 4-5 I SStructural Integrity Associates, Inc.1 Table 4-2: Reactor Recirculation Outlet Nozzle Blend Radius Stress Summary (concluded)
NOTES: Column 1: Transient number identification.
Column 2: Time during transient where maximum or minimum stress intensity occurs from P-V.OUT output file.Column 3: Maximum or minimum total stress intensity from P-V.OUT output file.Column 4: Maximum or minimum membrane plus bending stress intensity from P-V.OUT output file.Column 5: Temperature per total stress intensity.'
Column 6: -Pressure per Table 3-2.Column 7: Total pressure stress intensity from the quantity (Column 6 x 31300)/1000.
Column 8: Membrane plus bending pressure stress intensity from the quantity (Column 6 x 33640)/1000.
Column 9: Total external stress, 280.16 psi*(Column 5-70&deg;F)/(549&deg;F
-70&deg;F).Column 10: Same as Column 9, but for M+B stress.Column 11: Sum of total stresses (Columns 3, 7, and 9).-Column 12: Sum of membrane plus bending stresses (Columns 4, 8, and 10).Column 13: Number of cycles for the transient (60 years).J SIR-07-141-NPS, Rev. 0 4-6 e Structural Integrity Associates, Inc.
I I Table 4-3: Fatigue Parameters Used in the Recirculation Outlet Nozzle Fatigue Analysis Parameter Blend Radius J Safe End Parameters m and n for 2.0 & 0.2 (low alloy 1.7 & 0,3 (stainless Computing K, steel) [17] steel) [17]Design Stress Intensity Values, 26700 psi [9] 17000 psi [9]Sm @ 600&deg;F @(600&deg;F Elastic Modulus from66 Alastica Modulusfrom 30.0xl 0 psi [17] 28.3x106 psi [17]Applicable Fatigue'Curve Elastic Modulus Used in Finite 26.7x10 6 psi [10] 27.0x10 6 psi [10]Element Model The Geometric Stress Concentration Factor Kt 1 I I I I I I I I I I I I I I I SStructural Integrity Associates, Inc.m SIR-07-141-NPS, Rev. 0 4-7 Table 4-4: Fatigue Results for Reactor Recirculation Outlet Nozzle Safe End LOCATION = LOCATION NO. 1 -- SAFE END FATIGUE CURVE = 2 (1 = CARBON/LOW ALLOY, 2 STAINLESS STEEL)m 1.7 n= .3 Sm 17000. psi Ecurve 2.830E+07 psi Eanalysis 2.700E+07 psi Kt =1.53 MAX 82580.31546.31546.25988.257.30.18521.18298.17956.17956.17956.17952.17948.17948.17948.13174.* 12978.6956.5393.5393.5393.5393.539'3.4762.4605.4605.4605.4518.4198.4130.3911.3486.3485.3419.3292.3292.3292.3292.3292.3292.MIN RANGE MEM+BEND Ke Salt Napplied Nallowed-7469.-7469.-5010.-2934.-2934.-2934.-2934.-2934.-2741.-1264.-1264.-1264.-157.-157.-157.-157.-157.-157.-133.136.136.136.136.136.339.909.909.909.909.909.909.909.909.909.909.909.914.914.914.90049.39015.36556.28922.28664.21455.21232.20890.20697.19220.19216.19212.18104.18104.13331.13135.7112.5550.5526.5258.5258.5258.4626.4469.4266.3697.3609.3290.3222.3003.2578.2577.2511.2384.2384.2384.2378.2378.2378.66991.332.81.28040.24217.23354.9572.21370.9197.8846.7194.7191.7189.6096.6096.10909.13020.7125.-1219.-1293.-2126.-2126.-2126.3924.3153.3526.3332.3576.3673.3479.2870.2947.2942.3179.2472.2472.2472.2098.2098.2098.2.045 1.000 1.000 1.000 i.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 134573.29691.26947.21884.21509.13903.17063.13502.13304.12071.12068.12065.11181.11181.10016.10500.5706.2570.2537.2165.2165.2165.3514.3218.3215.2&#xfd;63.2885.2744.2655.2371.2170.2168.2199.1936.1936.1936.1829.1829.1829.1. OOOE+00 9 .OOOE+00 1. OOOE+00 1. OOOE+01 1. OOOE+01 2. 280E+02 1. 000E+00 5.100E+01 1. OOOE+00 2.480E+02 1. 000E+01 4. 200E+01 1.800E!01 1. OOOE+00 1. OOOE+00 1.200E+02 1.00 OE+00 1. 590E+02 1. OOOE+00 6. OOOE+01 1 .OOOE+00 7. 900E&#xf7;01 1 .OOOE+01 1. 390E+02 1. 200E+02 4. 100E+01 1. OOOE+01 6. OOOE+01 1. OOOE+01 1. OOOE+01 1. OOOE+00 1 OOOE+00 1.0 O0E+01 6. OOOE+01 1. OOOE+00 9. 600E+01 1. 200E+02 1. 000E+00 1. OOOE+00 6.7 65E+02 6.857E+05 1. 160E+06 2.383E+06 2.566E+06 9. 710E+08 7.876E+06 1. OOOE+20 1 .0OOOE+20 1.OOOE+20 1. OOOE+20 1.OOOE+20 1. OOOE+20 1.000E+20 1. OOOE+20 1 .OOOE+20 1 .OOOE+20 1. OOOE+20 1. OOOE+20 1. OOOE+20 1. OOOE+20 1. OOOE+20 1.000E+20 1.000E+20 1.000E+20 1. OOOE+20 1. OOOE+20 1. OOOE+20 1. 000E+20 1.OOOE+20 i. OOOE+20 1.OOOE+20 1. OOOE+20 1. 000E+20 1. 000E+20 1. OOOE+20 1. OOOE+20 1. OOOE+20 1. 000E+20 U.0015.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000~.0000.0000...0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000 SIR-07-141-NPS, Rev, 0.4-8 RvStructural Integrity Associates, Inc.
I I I Table 4-4: Fatigue Results for Reactor Recirculation Outlet Nozzle Safe End (concluded)
AX MIN RANGE MEM+BEND Ke Salt Napplied Nallowed U I H 3292.3292.3135.3086.2809.2783.2783.2783.2783.2783.2783.2780.2780.2780.2780.2780.2780.2763.2762.2762.2762.2762.2762.2762.2496.2496.2491.2487.2487.1029.1376.1376.1376.1376.1376.1732.1793.1958.1958.1958.1958.2104.2352.2352.2352.2352.2352.2352.2352.2441.2441.2441.2441.2441.2445.2445.2445.2487.2264.1916.1759.1710.1433.1407.1051.990.825.825.825.822 676.428 428 428 428.411.410.410.321.321.321.321.55.51.46.42.0.2247.1389.1452.1361.1091.1187.860.208.811.811.811.808.576.416.416.416.416.403.403.403.443.443.443.443.177.181.178: 175.0.1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.oo0 1.000 1.000 1.000 1.000 1.000 1.000 1.0.00 1.000 1810.1390.1325.1274.1054.1067..790.576.658.658.658.655.514.340.340.340.340.327.327.327.291.291.291.291.78.77.74.71.0.1. OOOE+00 9. OOOE+00 1. OOOE+01 2. 280E+02 1.000E+01 4. 300E+01 1. OOOE+01 1.OOOE+01 6.OOOE+01 1. OOOE+00 1.040E+02 1.240E+02 1. OOOE+01 1. 660E+02 1. OOOE+01 6.OOOE+01 1. OOOE+00 1.000E+01 1.OOOE+01 4. 300E+01 1. 700E+01 1. OOOE+00 1. OOOE+00 2. 280E+02 5. 300E+01 2. 470E+02 1. OOOE+01 4.300E+01 1.700E+01 1.000E+20 1.OOOE+20 1. OOOE+20 1. OOOE+20 1. OOOE+20 1. OOOE+2D 1. OOOE+20 1. OOOE+20 1. OOOE+20 1.OOOE+20 1. OOOE+20 1. OOOE+20 1. OOOE+20 1. OOOE+20 1. OOOE+20 1. 000E+20 1. 00OE+20 1. OOOE+20 1.OOOE+20 1. OOOE+20 1.000E+20 1.. OOOE+20 1.OOOE+20 1. OOOE+20 1.OOOE+20 1. 000E+20 1. OOOE+20 1. OOOE+20 1. OOOE+20.0000.0000.0000.0000.0000.0000.0000.-0000.0000.0000.0000..0000.0000.0000.0000.0000.0000.0000.0000 o0000.0000.0000 ,0000.0000.0000.0000.0000.0000.0000.0015 I U I I I I I TOTAL USAGE FACTOR I I I I S tructural Integrity Associates, Inc.I SIR-07-141-NPS, Rev. 0 4-9 Table 4-5: Fatigue Results for the Reactor Recirculation Outlet Nozzle Blend Radius LOCATION = LOCATION NO. 2 -- BLEND RADIUS FATIGUE CURVE = 1 (1 = CARBON/LOW ALLOY, 2 = STAINLESS STEEL)m = 2.0 n= .2 Sm 26700. psi Ecurve = 3.000E+07 psi Eanalysis
= 2.670E+07 psi Kt = 1.00 MAX&deg;55601.53822.51017.48939.46249.40607.39965.38737.38243.37757.37757.36291.36291.36273.36273.35954.35954.35954.35954.35954.35837.35658.35658.35556.35556.35279.34973.34973.34843.34843.34843.34843.34837.34834.34834.34831.34829.34829.34829.MIN 17.17.17.17.17.17.17.17.17.17.476.476.1582.1582.1582.1582.1582.1582.1844.1926.1926.1926.11988.11988.12180.12180.12180.20655.20655.25750.27368.28113.28113.28113.28113.28113.28113.29216.31990.RANGE 55584.53806.51001.48922.46233.40590.39948.38721.38227.37740.37281.3581.5.34709.34691.34691.34372.34372.34372.34110.34028.33911.33732.23670.23568.23376.23099.22793.14318.14188.9093.7475.6730.6724.6721.6721.6718.6716.5613.2839.MEM+BEND Ke Salt Napplied.
Nallowed U 37389.48014.44054.52579.48340.36593.39059.40267.37209: 37702.37314.36492.35198.3511.0.35110.35021.35021.35021.34858.34917.34978.34661.26901.27109.28326.27958.27831.16974.16887.17221.5178.3789.3785.3784.3784.3782.3781.1808.1543.1.000 1.000 1.000 1.ooo 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.b000 1.000 1.000 1.000 1.000 i.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1..000 1.000 1.000 1.000 1.000 1. 00 0 1.000 1.000 31227.30228.28652.27484 25974.22803.22443.21753.21476.21202.20945.20121.1-9500.19490.19490..19310.19310.19310.19163.19117.19051.18951.13298.13240.13133.12977.12805.8044.7971.5108.4199.3781.3777.3776.3776.3774.3773.3153.1595.1. OOOE+00 1.OOOE+01 1. OOOE+01 1. OOOE+00 1. OOOE+00 1. OOOE+01 I. OOOE+01 6. OOOE+01 1 ..oooE+01 7 .OOOE+00 2. 930E+02 7. OOOE+00 3. OOOE+00 6.OOOE+01 1. OOOE+00 5. 600E+01 1. OOOE+00 1. OOOE+00 1..oooE+00
: 2. 410E+02 1. O0E+01 4 .900E+01 1.790E+02 1.210E+02 1.790E+02 1. OOOE+01 1. 11OE+02 1. 890E+02 1. 11OE+02 1. OOOE+00 1. OOOE+01 1. 780E+02 1. OOOE+01 6. OOOE+01 1. OOOE+00 1. OOOE+01 4. 100E+01 1. OOOE+01 6.000E+01 1. 951E+04 2.161E+04 2.547E+04 2.894E+04 3. 443E+04 5. 217E+04 5. 647E+04 6.592E+04 7.025E+04 7.486E+04 7.954E+04 9. 705E+04 1.096E+05 1.098E+05 1.098E+05 1. 135E+05 1.135E+05 1. 135E+05 1. 167E+05 1. 177E+05 1. 191E+05 1.214E+05 5.728E+05 5. 955E+05 6. 411E+05 7.138E+05 8. 050E+05 7.421E+07 7. 983E+07 1. OOOE+20 1. OOOE+20 1.000E+20 1. OOOE+20 1. 000E+20 1. OOOEt20 1. OOOE+20 1. 0.OOE+20 1 .000E+20 1. OOOE+20.0001.0005.0004.0000.0000.0002.0002.0009.0001..0001 0037 0001 0000 0005.0000 0005 0000.0000.000.0 0020.0001 0004 0003 0002.0003.0000.0001.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000 SIR-07-141-NPS, Rev. 0 4-10 V Structural Integrity Associates, Inc.
I I I Table 4-5: Fatigue Results for Reactor Recirculation Outlet Nozzle Blend Radius (concluded)
I MAX MIN RANGE MEM+BEND Ke Salt Napplied Nallowed U 34829.34829.34825.34825.34825.34825..34825.34825.34825.34825.34646.34646.34646.34646.34646.34646.34646.34646.34646.34646.34646.31990.31990.31990.31990.31990.31990.31990.32634.32634.32634.32634.33386.33581.33709.33822.33924.33924.34124.34331.34447.34592.2839.2839.2835.2835.2835.2835.2835.2191.2191.2191.2012.1260.1065.937.824.722.722.522.315.199.54.1543.1543.1541.1541.1541.1541.1541.2355.2355.2355.2695.1578.1120.1137.1455.1228.1310.1067..3398.-603.-130.1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000*1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1595.1595..1593.1593.1593.1593.1593.1231.1231.1231.1130.708.598.526.463.406.406.293.177.112.30.1.000E+00 1.i60E+02 1. 000E+01 6.000E+01 1. 000E+00 1. OOOE+00 4. 000E+01 6.000E+01 1.000E+00 1.270E+02 1.010E+02 1. OOOE+00 1.000E+01 1.000E+01 1.000E+00 1. O00E+00 1.000E+00 1.000E+01 1. 000E+01 1.200E+02 3. 500E+01 1.0008E20 1.000E+20 1.008E+20 1.000E+20 1.000E+20 1.000E+20 1.000E+20 1.000E+20 1. OOOE+20 1 .000E+20 1 .000E+20 1.000E+20 1.000E+20 1.000E+20 1.000E+20 1. 000E+20 1 .000+/-+20 1.000E+20 1.000E+20 1.000E+20 1.000E+20 0000.0000.0000.0000.0000.0000.0.000.0000.0000.0000.0000.0000.0000.o000.0000.0000.0000.0000.0000.0000.0000..0108 I I I U U TOTAL USAGE FACTOR =I I I I I SIR-07-141-NPS, Rev. 0 4-11 I SStructural Integrity Associates, Inc.I
 
===5.0 ENVIRONMENTAL===
 
FATIGUEANALYSIS Environmental fatigue multipliers were computed for both normal water chemistry (NWC) and hydrogen water chemistry (HWC) conditions in Reference
[18] for various regions of the VY RPV and attached piping.The Recirculation Outlet nozzle has three materials:
a Ni-Cr-Fe dissimilar metal weld (DMW), a low alloy steel forging, and a stainless steel safe end. To ensure the maximum CUF considering environmental effects was identified; locations in the safe end and nozzle forging were selected.This selection produces bounding environmental fatigue results for the entire nozzle assembly for the following reasons: The highest thermal stresses from the FEM analysis occur in the stainless steel safe end.Stainless steel Fen multipliers are significantly higher than Ni-Cr-Fe multipliers (Fen values are 2.55 or higher for stainless steel [18] vs. a constant value of 1.49 for Ni-Cr-Fe[19]). Therefore, evaluation of the safe end bounds the Ni-Cr-Fe weld material.* The highest pressure stresses from the FEM analysis occur in the low alloy steel nozzle forging. Low alloy steel Fe, multipliers are higher than Ni-Cr-Fe multipliers (Fen values are 2.45 or higher for low alloy steel [ 18] vs. a constant value of 1.49 for Ni-Cr-Fe [19]).Therefore, evaluation of the nozzle forging bounds the Ni-Cr-Fe weld material.Based on VY-specific dates for plant startup and HWC implementation, as well as past and future predicted HWC system availability, it was determined that overall HWC availability is 47% over the sixty year operating period for VY. Therefore, for the purposes of the EAF assessment of the reactorrecirculation outlet nozzle, it was assumed that HWC conditions exist for 47% of the time, and NWC conditions exist for 53% of the time over the .60-year operating life of the plant. RPV beltline region chemistry was assumed for both the reactor recirculation outlet nozzle safe end and blend radius locations, since both locations experience reactor conditions at all times.SIR-07-141 -NPS, Rev. 0 5-1 Structural ntegrity Associates, Inc.
For the safe end location, the environmental fatigue factors for NWC and HWC are 8.36 and 15.35, respectively, from Table 5 of Reference
[18] for the RPV beltline region. This results in an EAF adjusted CUF as follows: 60-Year CUF, U 6 0 ='0.00 15 Overall EAF multiplier, Fe,, (8.36 x 53% + 15.35 x 47%) 11.65 60-Year EAF CUF, U 6 0-env 0.0015 x 11.65 0.0175 The EAF CUF value of 0.0175 for 60 years for the safe end is acceptable (i.e., less than the I allowable value of 1.0).The fatigue calculation documented in Section 4.0 for the blend radius location was performed for the nozzle base material since cladding is structurally neglected in modern-day fatigue I analyses, per ASME Code, Section III, NB-3122.3
[17]. This is also consistent with Sections II 5.7.1 and 5.7.4 of NUREG/CR-6260
[1]. Therefore, the cladding was neglected and EAF assessment of the nozzle base material was performed for the blend radius location.
g For the blend radius location, the environmental fatigue factors for NWC and HWC are 12.43 and 2.45, respectively, from Table 5 of Reference
[18] for the RPV beltline region. This results in an EAF adjusted CUF as follows: i 60-Year CUF, U 6 0  0.0108 Overall EAF multiplier, Fn (12.43 x 53% + 2.45 x 47%) 7.74 60-Year EAF CUF, U 6 0-env 0.0108 x 7.74 0.0836 The EAF CUF value of 0.0836 for 60 years for the blend radius is acceptable (i.e., less than the 3 allowable value of 1.0).In SIR-07-14 1-NPS, Rev. 0 5-2 Structural Integrity Associates, inc.I
 
==6.0 CONCLUSION==
S This report documents a refined fatigue evaluation for the VY reactor recirculation outlet nozzle.The intent of this evaluation is to use refined transient definitions and the revised cyclic transient counts for 60 years for a computation of CUF, including EAF effects, that is more refined than previously performed, fatigue analyses.
The fatigue-limiting locations in the reactor recirculation outlet nozzle and safe end are- included in the evaluation, to be consistent with NUREG/CR-6260
[1] needs for EAF evaluation for license renewal. The final fatigue results are considered to be a replacement to the values previously reported in the VY LRA.The fatigue calculations for the VY reactor recirculation outlet nozzle were performed in accordance with ASME Code, Section III, Subsection NB-3200 methodology (1998 Edition, 2000 Addenda) [17]. The stress evaluation is summarized in Section 3.0, and the fatigue analysis is summarized in Section 4.0. The results in Section 4.0 reveal that the CUF for the limiting safe end location is 0.0015, and the CUF for the limiting blend radius location is 0.0108.Both of these values represent 60 years of plant operation, including all relevant EPU effects.EAF calculations for the VY reactor recirculation outlet nozzle were also performed, as summarized in Section 5.0. The results in Section 5.0 reveal that the EAF CUF for the limiting safe end location is 0.0 175, and the EAF CUF for the limiting blend radius location is 0.0836.Both of these values represent 60 years of plant operation, including all relevant EPU effects.All fatigue allowables, both with and without EAF effects, are met, thus demonstrating acceptability for 60 years of operation.
SIR-07-141 -NPS, Rev. 0 6-1 Structural Iltegrity Associates, Inc.
 
==7.0 REFERENCES==
 
I 1. NUREG/CR-6260 (INEL-95/0045), "Application of NUREG/CR-5999 Interim Fatigue I Curves to Selected Nuclear Power Plant Components," March 1995.2. Vermont Yankee Drawing 5920-06623, Rev. 0, (Hitachi, Ltd. Drawing No IOR290-127), 1"Recirc. Outlet Safe End,' SI File No. VY-16Q-204.
3.- Vermont Yankee Drawing 5920-00238, Rev. 4, (Chicago Bridge & Iron Company, I Contract No. 9-6201, Drawing No. 21) "36"x28" Nozzles Mk NIAIB," SI File No. VY-16QQ-204.
I 4. GE Design Specification No. 21AA 1115, Revision 4, "Vermont Yankee Reactor Pressure Vessel," October 21, 1969, SI File No. VY-05Q-210.
I 5. GE Design Specification No. 26A6019, Revision 1, "Reactor Vessel- Extended Power Uprate," June 2, 2003, SI File No. VY-05Q-236.
: 6. Kuo, A. Y., Tang, S. S., and Riccardella, P. C., "An On-Line Fatigue Monitoring System for Power Plants, Part I -Direct Calculation of Transient Peak Stress Through Transfer Matrices and Green's Functions," ASME PVP Conference, Chicago, 1986.7. ANSYS, Release 8.1 (w/Service Pack 1), ANSYS, Inc., June 2004.8. Structural Integrity Associates Calculation No. VY-16Q-304, Revision 0, "Recirculation Outlet Nozzle Finite Element Model." 9. American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section II, Materials, Part D, "Properties (Customary)," 1998 Edition, 2000 Addenda.10. Structural Integrity Associates Calculation No. VY-16Q-305, Revision 0, "Recirculation Outlet Stress History Development for Nozzle Green Function." 11. Structural Integrity Associates Calculation No. VY-16Q-306, Revision 0, "Fatigue Analysis of Recirculation Outlet Nozzle." 12. Reactor Thermal Cycles, Attachment 1, page 2 of Entergy Design Input Record (DIR)Revision 1, EC No. 1773, Rev. 0, "Environmental Fatigue Analysis for Vermont Yankee Nuclear Power Station," 7/26/07, SI File No. VY-16Q-209.
I SIR-07-141-NPS, Rev. 0 7-1 Structural Integrity Associates, Inc.
: 13. Nozzle Thermal Cycles (Recirculation Outlet), Attachment 1, page 4 of Entergy Design Input Record (DIR) EC No. 1773, Rev. 1, "Environmental Fatigue Analysis for Vermont Yankee Nuclear Power Station," 7/26/07, SI File No. VY-16Q-209.
: 14. Reactor Thermal Cycles for 60 Years of Operation, Attachment 1, page 1 of Entergy Design Input Record (DIR) EC No. 1773, Rev. 1, "Environmental Fatigue Analysis for Vermont Yankee Nuclear Power Station," 7/26/07, SI File No. VY- 16Q-209.15. Vermont Yankee Drawing 5920-0024, Rev. 11, (GE Drawing No. 919D294, Sheet No.7), "Reactor Vessel," SI File No. VY-05Q-241.
: 16. Structural Integrity Associates Calculation No. SW-SPVFO1Q-301, Revision 0,"STRESS.EXE, P-V.EXE, and FATIGUE.EXE Software Verification." 17. American Society of Mechanical Engineers Boiler & Pressure Vessel Code, Section III, Rules for Construction of Nuclear Facility Components, 1998 Edition, 2000 Addenda.18. Structural Integrity Associates Calculation No. VY- I6Q-3 03, Revision 0,"Environmental Fatigue Evaluation of Reactor Recirculation Inlet Nozzle and Vessel Shell/Bottom Head." 19. EPRI Report No. TR-t105759, "An Environmental Factor Approach to. Account for Reactor Water Effects in Light Water Reactor Pressure Vessel and Piping Fatigue Evaluations," December 1995.20. CB&I, RPV Stress Report Section: S9 "Stress Analysis Recirculation Outlet Nozzle Vermont Yankee Reactor Vessel." 9-6201, SI document, VY-16Q-204.
SIR-07-141-NPS, Rev. 0 7-2 Structural Integrity Associates.
Inc.
NEC-JH_17 Report No.: SIR-07-138-NPS Revision No.: 0 Project No.: VY-16Q File No.: VY-16Q-403 July 2007 Environmental Fatigue Analysis for the Vermont Yankee Reactor Pressure Vessel Core Spray Nozzle Prepared for: Entergy Nuclear Operations, Inc.(Contract No. 10150394)Prepared by: Structural Integrity Associates, Inc.Centennial, CO Prepared by: Reviewed by: Approved by: Stevens, P.E.T. J. Nt6rrmann, P.E.T.
P.E.Date: 7/26/2007 Date: 7/26/2007 Date: 7/26/2007 V Structural Integrity Associates, Inc.
REVISION CONTROL SHEET Document Number: SIR-07-138-NPS.
Title: Environmental Fatigue Analysis for the Vermont Yankee Reactor Pressure Vessel Core Spray Nozzles Client: Entergy Nuclear Operations, Inic.SI Project Number: VY-16Q Section Pages Revision Date Comments 1.0 1-1-1-.5 0 07/26/07 Initial issue.2.0 2-1-2-3 3.0 3-1-3-26 4.0 4-1-4-8 5.0 5-1 2 6.0 6-1 7.0 7-1-.7-3 I I I I I I I I I I I I I I I I I inc.9 strwctural Integrity Associates, Table of Contents Section Page
 
==1.0 INTRODUCTION==
 
..........................................................................................................
1-1 1.1 Green's Function Methodology
......................................
1-2 2.0 FINITE ELEMENT MODEL ....................................................................................
... 2-1 3.0 LOAD DEFINITIONS
.....................................
..........................................................
31 3.1 T herm al L oading .............
I ....................
-.-.....................................................................
3-1 3.1.1 Heat Transfer Coefficients and Boundary Fluid Temperatures
..........................
3-2 3.1.2 G reen 's F unctions ................................................................................................
3-2 3.1.3 Therm al Transients
............................................................................................
3-3 3.2 Pressure Lodn "--" 3. r s u e L oadin g ............
.... o.............................
:........
.......................................
:............ _3.3 P iping L oading ............................................................................................................
3-4.4.0 STRESS AND FATIGUE ANALYSIS RESULTS .........................
4-1 5.0 ENVIRONMENTAL FATIGUE ANALYSIS .......................
........................................
5-1
 
==6.0 CONCLUSION==
S....................................................................................................
61 1
 
==7.0 REFERENCES==
 
....................................
..............
7-1 SIR-07-138-NPS.
Rev. 0 121 R Structural Integrity Associates, Inc.
List of Tables Table page Table 2-1:.Table 3-1.: Table 3-2: Table 3-3: Table 3-4: Table 3-5: Table 4- 1: Table 4-2: Table 4-3" Table 474: Table 4-5: Table 4-6: Material Properties
@ 300 0 F (1) ...................................
...................
2-2 Summary of Heat Transfer Coeffi cients .............
.......................................................
3-5 Safe End Transients
................
I ............................
3-6 Blend Radius Transients
..............................................
3-7 Stresses Due to Piping Loads for Safe End Location ...............................................
3-8 Stresses Due to Piping Loads for Blend Radius Location .........................................
3-9 Core Spray Nozzle Safe End Stress Summary ..........................................................
4-4 Core Spray Nozzle Blend Radius Stress Summary .......................
4-5 Fatigue Parameters Used in the Core Spray Nozzle Fatigue Analysis .....................
4-6 Fatigue Results for Core Spray Nozzle Safe End ........................
4-7 Fatigue Results for the Core Spray Nozzle Blend Radius ..........................
4-8 Fatigue Results for the Core Spray Stainless Steel Piping ........................................
4-9 List of Figures Figure Page I I I I I I I I I U I I I I I I I I I Figure 1- 1: Typical Green's Functions for Thermal Transient Stress ........................................
1-4 Figure 1-2: Typical Stress Response Using Green's Functions
................................................
1-5 Figure 2-1: VY Core Spray N ozzle FEM .................................................................................
2-3 Figure 3-1: Core Spray Nozzle Internal Pressure Distribution
........................
... 3-10 Figure 3-2: Core Spray Nozzle Pressure Cap Load .................................................................
3-11 Figure 3-3: Core Spray Nozzle Vessel Boundary Condition
....................................................
3-12 Figure 3-4: Therm al R egions ..................
................................................................................
3-13 Figure 3-5: Safe End Critical Thermal Stress Location ............................................................
3-14 Figure 3-6: Blend Radius Critical Thermal Stress Location ...................................................
3-15 Figure 3-7: Safe End Green's Function for 100% Flow.........................................................3-16 Figure 3-8: Safe End Green's Function for 0% Flow ..........................
I ................................
3-17 Figure 3-9: Blend Radius Green's Function for 100% Flow. ..................................................
.3-18 Figure 3-10: Blend RadiusGreen's Function for. 0% Flow ..................................................
3-19 Figure 3- l1: Transient 03: Startup .........................................................................................
3-20 Figure 3-12: Transient 11: Loss of Feedwater Pumps, Isolation Valves Close ...........
3-21 Figure 3-13: Transient 14: Single Relief of Safety Valve Blow Down .....................................
3-22 Figure 3-14: Transient 21-23: Shutdown Vessel Flooding .......................................................
3-23 Figure. 3-15: Transient 30: Emergency Shutdown 100% Flow (Safe End) ..............
3-24 Figure 3-16: Transient 30: Emergency Shut Down 100% Flow (Blend Radius) .....................
3-25 Figure 3-17: Pipe Reactions
.. ...............................................
3-26 SIR-07-138-NPS, Rev 0 iv r Structural Integrity Associates, Inc.
 
==1.0 INTRODUCTION==
 
In Table 4.3-3 of the Vermont Yankee License Renewal Application (LRA), the 60-year cumulative usage factor (CUF) values for the reactor pressure vessel (RPV) core spray nozzle are reported as 0.625 (nozzle) and 0. 182 (safe end). The safe end value was reported as a generic value, since no plant-specific value was determined.
Application of environmentally assisted fatigue (EAF) multipliers, as required for the license renewal period, resulted in unacceptable EAF CUF-values of 1.53 and 2.79 for the nozzle and safe end, respectively.
Therefore, further refined analysis was necessitated to show acceptable EAF CUF results for this component.
This report documents a refined fatigue evaluation for the VY core spray nozzle. The intent of this evaluation is to use refined transient definitions and the revised cyclic transient counts for 60 years for a computation of CUF, including EAF effects, that is more refined than previously performed fatigue analyses.
The fatigue-limiting locations in the core spray nozzle and safe end are included in the evaluation, to be consistent with NUREG/CR-6260
[1] needs for EAF evaluation for license renewal.The EAF effects forthe core spray piping, which is also a NUREG/CR-6260 location, are considered to be covered by the nozzle and safeend calculations because the nozzle region bounds the piping'. The.resulting fatigue results will be used as a replacement to the values previously reported in the VY LRA.The refined evaluation summarized in this report included the development of a detailed finite element model of the core spray nozzle, including relevant portions of the safe end, thermal sleeve, the RPV wall, and the weld overlay repair documented in Reference
[2]. Thermal and pressure stress histories were developed for relevant transients affecting the core spray nozzle, including any effects of Extended Power Uprate (EPU), as specified by the VY RPV Design Specification
[3], the VY EPU Design Specification
[4] and other boiling water reactor (BWR) operating experience.
The thermal and pressure stress histories were used to determine total stress and primary plus secondary stress for use in a.subsequent fatigue evaluation, Stresses were also included due to loads from the attached piping for application in the stress/fatigue analysis, based on the bounding reaction loads obtained from the.' The nozzle stresses are more severe due to the nozzle discontinuity, and the nozzle thermal transients are more severe due to interaction with the hot RPV.SIR-07-138-NPS, Rev. 0 1-1 Structural Integrity Associates, Inc.
I relevant design documents.
The revised fatigue calculation was performed using Section III methodology from the 1998 Edition, 2000 Addenda of the ASME Code, and were performed using actual cycles from past plant operation projected out to 60 years of operation.
 
===1.1 Green's===
Function Methodology For the core spray-nozzle evaluated as a part of this work, stress histories were computed by a time integration of the product of a pre-determined Green's Function and the transient data. This Green's Function integration scheme is similar in concept to the well-known Duhamel theory used in structural dynamics.
A detailed derivation of this approach and examples of its application to specific plant locations is contained in Reference
[5]. A general outline is provided in this section.A Green's Function is derived by using finite-element methods to determine the transient stress response of the component to a step change in loading (usually a thermal shock). The critical location in the component is identified based on the maximum stress, and the thermal stress response over time is. I extracted for this location.
This response to the input thermal step is the "Green's Function." Figure 1-1 shows a typical set of two. Green's Functions, each for a different set of heat transfer coefficients (representing different flow rate conditions).
1I To compute the thermal stress response for an arbitrary transient, the loading parameter (usually local fluid temperature) is deconstructed into a series of step-loadings.
By using the Green's Function, the response to each step can be quickly determined.
By the principle of superposition, these can be added (algebraically) to determine the response.
to.theoriginal load history. The result is demonstrated in Figure 1-2. The input transient temperature history contains five step-changes of varying size, as shown in the upper plot in Figure 1-2. These five step .changes produce the five successive stress responses in .the second plot shown in Figure 1-2. By adding all five response curves, the real-time stress response for the input thermal transient is computed.
*The Green's Function methodology produces identical results compared to running the input transient 3 through the finite element model. The advantage of using Green's Functions is that many individual I SIR-07-138-NPS, Rev. 0 1-2 Structural Integrity Associates, Inc.I transients can be run with a significant reduction of effort compared to running all transients through the finite element model. The trade-off in this process is that the Green's Functions are based on constant material properties and heat, transfer coefficients.
Therefore, these. parameters are chosen to bound all transients that constitute the majority of fatigue usage, i.e., the heat transfer coefficients at 300'F bound the cold water injection transient.
In addition, the instantaneous value for the coefficient of thermal expansion is used instead of the mean value for the coefficient of thermal expansion.
This conservatism is more than offset by the benefit of not having to analyze every transient, which was done in the VY core spray nozzle evaluation.
Once the stress history is obtained for all transients using the Green's Function approach, the remainder of the fatigue analysis is carried out using traditional methodologies in accordance with ASME Code, Section III requirements.
SIR-07-138-NPS, Rev. 0 1-3 V SR tructural Integrity Associates, Inc.
.L-0)0)ci)-0 a_-4--Cl)Time (sec)9282510*Note: A typical set of two Green's Functions is shown, each for a different set of heat transfer coefficients (representing different flow rate conditions).
Figure 1-1: Typical Green's Functions for Thermal Transient Stress SIR-07-138-NPS, Rev. 0 1-4 SRvStructural Integrity Associates, Inc.
I ILn 500*I'*L*200~7 50 50 Skqo-25&#xfd; SUP r-I 5 SNiP em o 200 40, ..06 :&#xfd;w* ..00+o W 40: IS-02o158002000, T. m i6 d Skewnow-10.0 200 400 500 80 1000 1200 1400 t100 1800 tool TW* w Figure 1-2: Typical Stress Response Using Green;s Functions SIR-07-138-NPS, Rev. 0 1-5 Structural Integrity Associates, Inc.
 
===2.0 FINITE===
ELEMENT MODEL An ANSYS [6] finite element model (FEM) of the VY core spray nozzle and safe end was developed and used to perform the updated stress and fatigue analyses.
The details of the model development are documented in the Reference
[7] calculation.
The materials of the Various components of the model are listed below:.Safe End -SB 166 (72Ni-I5Cr-8Fe, N06600)* 80 x 100 Conc. Reduction
-SA312 TP304 (18Cr-8Ni)
* Nozzle Forging -SA508 Class II (3/4Ni-1/2Mo-I/3Cr-V)
* Vessel -SA533 Grade B (Mn-1/2Mo-l/2Ni)'
* Cladding -SA240 TP 304 (18Cr-8Ni)
In the FEM model, the radius of RPV was increased by a factor of two to account for the fact that the vessel portion of the finite element model is a sphere and the actual geometry is a cylinder.Material properties were based upon the 1998 ASME Code, Section II, Part D, with 2000 Addenda [8], and are shown in Table 2-1. The properties were evaluated at an average temperature of 300'F. This average temperature is based on a thermal shock of 500&deg;F to 100T, which was applied to the FEM model for Green's Function development.
The finite element model, which includes the weld overlay, is shown in Figure 2-1.I I I I I I I I I I I I I SIR-07-138-NPS, Rev. 0 2-1 iz Structural Integrity Associates, Inc.
Table 2-1: Material Properties
@ 300 0 VF (Coefficient Modulus of of Thermal Thermal Thermal Specific Heat, Material Part Elasticity, e+6 Expansion,, Conductivity, Diffusivity, Btu/lb-0 F ID Description psi e-6, Btulhr-ft-&deg;F fte/hr 3 )IEXI in/in/&deg;F IKlXXI[ALPXJ 72Ni-2 Safe End SB 166 l5Cr-8Fe 29.8 7.9 9.6 0.160 0.1157*N06600 Weld INCONEL 72Ni-2 L15Cr-8Fe 29.8 7.9 9.6 0.160 -0.1157 Overlay 82 N06600 SA508 %Ni-Nozzle 1/2Mo-1./3 26.7 7.3 23.4 0.40.1 0.1193 Class I C Cr-V Mn-3 Vessel SA533 1/2Mo- 28.0 7.7 23.4 0.401 0.1193 Grade B /N___________
* l/2Ni _ _ _ _4 3/16 Clad SA240 18Cr-8Ni 27.0. 9.8 0.160 0.1252 TP 304 80 x 100 SA312(2)4 .Conc. 18Cr-SNi 27.0 9.8 9.8 0.160 0.1.252 Reduction(2)
TP304 Note: 1. Material properties are evaluated at 300'F from the 1998 ASME Code, Section 11, Part D; with 2000 Addenda [8], Poisson's ratio, which are assumed typical values and specific heat is calculated as [k/pd]/12 3.2. The 80 x 100 concentric reduction was modeled as a straight pipe with the material properties of the original desil was replaced by a new material (SA403 T3 16L). These two stainless steels have the same modulus of elasticity an properties.
SIR-07-138-NPS, Rev. 0 2-2 strt Figure 2-1: VY Core Spray Nozzle FEM I I I SIR-07-138-NPS, Rev. 0 2-3 Structural Integrity Associates, Inc.I 3.0 LOAD DEFINITIONS The pressure and thermal, stresses for the core spray nozzle for the revised fatigue evaluation were developed using the axisymmetric FEM model, described in Section 2.0 of this report. The details of the Green's function development and associated stress evaluation are documented in the Reference
[9] and [10] calculations.
 
===3.1 Thermal===
Loading* Thermal loads were applied to the core spray nozzle model to generate the Green's Function.
As a first step in the Green's Function process, heat transfer coefficients were determined for various regions of the core spray FEM for two different flow cases: (1) 0% core spray flow, and (2) 100% core spray flow through the nozzle.The 0% flow case simulates a stagnant condition of the core spray nozzle when not in operation and the entire core spray nozzle is at the same temperature as the RPV fluid. The heat transfer coefficients for the 0% flow case are for free convection (stagnant) conditions.
The applied* boundary fluid temperature is changed to simulate a thermal shock from 500OF to I 00&deg;F to develop the stress response on the core spray nozzle in the stagnant condition.
The 100% flow case simulates the operational condition of the core spray nozzle (i.e., the entire*core spray nozzle experiences 100&deg;F water due to injection).
The heat transfer coefficients for the high flow case are for forced and free convection depending on the region of the. FEM. The applied boundary fluid temperature is changed to simulate, a thermal shock from 500'F to 100'F.to develop the stress response on the core spray nozzle due to injection.
The temperature on the exterior of the reactor, nozzle, safe end and pipe was assumed to be 120'F (ambient).
Figure 3-4 shows the heat transfer coefficient regions assumed for the core spray nozzle FEM. The applied heat transfer coefficients and the fluid temperatures are summarized in the sections that follow.SIR-07-138-NPS, Rev. 0 3-1 Structural Integrity Associates, Inc.
I I 3.1.1 Heat Transfer Coefficients and Boundary Fluid Temperatures Referring to Figure 3-4, heat transfer coefficients were applied as follows:* The heat transfer coefficient for the outside surfaces of the FEM (Region 12) was a constant value of 0.2 BTU/hr-ft 2 -F (3.858x1 0 7 BTU/sec-in 2-'F).Table 3-1 shows the results of the heat transfer coefficient calculations for all of the thermal regions identified in Figure 3-4. The detailed heat transfer calculations for 3 Regions 1, 3, 5, 7, 9, and 11 are contained in the Reference
[9] calculation.
* In Regions 2, 4, 6,8 and 10, the heat transfer coefficients are interpolated.
I For both Green's Functions, a 500'F -100&deg;F thermal shock was run to determine the stress response.
For the 0% flow case, the entire inside surface of the FEM was shocked. For the 100% flow case, only the nozzle flow path was shocked.3.1.2 Green's Functions I The two flow-dependent thermal load cases outlined in previous section were run on the core spray nozzle FEM with the heat transfer coefficients and the fluid temperature conditions listed in Table 3-1. Two locations were selected for analysis (see Figures 3-5 and 3-6): i I 1. The critical safe end location was chosen as the node with the highest stress intensity due to thermal loading under nozzle flow conditions.
The highest stress intensity due to thermal loading occurred at Node 3719 (see Figure 3-5), on the inside diameter of the I nozzle safe end. Therefore, this node was selected for analysis.2. The critical blend radius location was chosen based upon the highest pressure stress I intensity.
The critical location was selected as Node 2166, as shown in Figure 3-6.Two stress intensity Green's Functions were developed for each location and each flow case: (1)total stress intensity, and (2) membrane plus bending stress intensity.
The total stress intensity RI S IR 138-NPS, Rev. 0 3-2 Structural Integrity Associates, Inc.I Green's Functions for the safe end location are shown in Figures 3-7 and 3-8. The total stress intensity Green's Functions for the blend radius location are shown in Figures 3-9 and 3-10.3.1.3 Thermal Transients The transients analyzed for the core spray nozzle were developed based on the definitions in the original RPV Design Specification
[3], as modified for EPU [4], as well as more recent definitions based on BWR operating experience.
For BWR operating experience, the transients described in the thermal cycle diagrams for a BWR-4 plant similar in design and vintage to VY were obtained, and plant data from VY applied to each transient.
The resulting thermal cycle diagrams are shown in References
[11 and 12]. The final transients evaluated in the stress and fatigue analyses are shown in Figures 3 -1 1 through 3-16.The number of cycles projected for the 60-year operating life is used for each transient
[13].Tables 3-2. and 3-3 summarize the thermal transients for the safe end and blend radius locations, respectively.
 
===3.2 Pressure===
Loading A uniform pressure of 1,000 psi was applied along the inside surface of the core spray nozzle and the RPV wall. A pressure load of 1,000 psi was used because it is easily scaled up or down to account for different pressures that occur during transients.
In addition, a cap load of 4,774 psi was applied to the piping at the end of the nozzle. This cap load was calculated as follows: PDi 2 Pcap 2 2 where: Pcap = end cap pressure load (psi)P = unit pressure load = 1,000 psi Di inside diameter of end of FEM = 9.834" SIR-07-138-NPS, Rev. 0- 3-3 Structural Integrity Associates, Inc.
Do outside diameter of end of FEM = 10.815" The calculated pressure was applied as a negative value so that it would exert tension on the end of the model. The nodes on the end of the FEM were coupled in the axial direction to ensure mutual displacement of the end of the nozzle due to attached piping. Figures 3-1, 3-2, and 3-3 show the internal pressure distribution, cap load, and. symmetry condition applied to the vessel end of the model, respectively.
The internal pressure load case for Node 2166 (blend radius) resulted in a total stress intensity of 35,860 psi, and for Node 3719 (safe end) resulted in a total stress intensity of 12,030 psi. The membrane plus bending stress intensity at Node 2166 and Node 3719 are 34,970 psi and i2,020 psi, respectively.
I 3.3 Piping Loading 3.The piping stress intensities (stress caused by the attached piping) were determined for the two evaluated core spray nozzle locations.
The design piping reactions that were used in the stress and fatigue evaluation are defined on the Reference
[14] drawing. These loads represent shear and moment loadings on the nozzle resulting from thermal expansion of the attached piping and seismic loads. The loads are applicable at the piping end of the safe end, as shown in Figure 3-17. The stresses resulting from these loads were calculated by hand using classical structural mechanics formulas, as documented in Reference
[10], and are shown in Tables 3-4 and 3-5 for the safe end and blend radius locations, respectively.
I I I I SIR 138-NPS, Rev. 0 3 -4 Smructural Integrity Associates, Inc.I Table 3-1: Summary of Heat Transfer Coefficients SIR-07-138-NPS, Rev. 0 3-5 V Structural lntegrity Associates, Inc.
Table 3-2: Safe End Transients Transient Time Temp Time Step Pressure Flow Rate Number _s _ __F __Us_ _ s(sgq) (GPM)2. Design HYD Test -- 100 0 120 Cycles 1100 50 3. Startup 0 100 .0 0 300 Cycles 16164. 549 16164 1010 (0%)17164 549 1000 1010 11. Loss of Feedwater 0 526 1010 .0: Pumps 3 526 3 1190 (0%)10 Cycles 13 526 10 1135 233 300 220 1135 2213 500 1980 1135 2393 300 180 885 6893 500 4500 1135 7313 300 420 675 7613 300 300 675 11213 400 3600 240 16577 549 5364 1010 16637 549 60 1.010 16638 542 1 1010 16698 542 60 1010 16699 526 1 1010.17699 526 1000 1010 14. SRV Blowdown 0 526. 1010 0 I Cycle 600 375 600 400 (0%)11580 70 10980 50 12580 70 1000 50 21-23. Shutdown 0 549 1010 0 300 Cycles 6264 375 6264 50 (0%)6864 330 600 50 16224 100 9360 50 17224 100 1000 50 12. Hydrostatic Test .10 100 50 I cycle 1563 50 30. Emergency Shut Down 0 549 1010 3200 1 Cycle 10 406 10 250 (100%)11 70 1 250 i__1011 70 1000 0 I I I I I I I I I I I I I I I I I I I SIR-07-138-NPS, Rev. 0 3-6 V Structural Integrity Associates, Inc.
Table 3-3: Blend Radius Transients Transient Time Temp Time Step Pressure Flow Rate Number f s (F) Ls1 (psiq). (GPM)2. Design HYD Test 100 --- 0 1100 120 Cycles 50 3..Startup 0 100 0 0.300 Cycles 16164 549 16164 1010 (0%)24164 549 .8000 1010 11. Loss of Feedwater 0 526 1010 0 Pumps .3 526 3 1190 (0%)10 Cycles 13 526 10 1135 233 300 220 1135 2213 500 1980 1135 2393 300 180 885 6893 500 4500 1 135 7313 300 420 675 7613 300 300 675 11213 400 3600 240 16577 549 5364 1010 16637 549 60 1010 16638 542 1 1010 16698 542 60 1010 16699 526 1 10.10 24699 526 8000 1010 14. SRV Blowdown 0 526 .1010 0 1. Cycle 600 375 600 -400 (0%)11580 70 10980 50 19580 70 8000 50 21-23. Shutdown 0 549 1010 0 300 Cycles 6264 375 6264 50 (0%)6864 330 600 50 16224 100 9360 50 24224 .100 8000 50 24. Hydrostatic Test --- .100 50 1 Cycle 1563 50 30. Emergency Shut Down 0 549 1010 3200 1 Cycle 10 406 10 250 (100%)11 70 1 250 8011 70 8000 0 SIR-07-138-NPS.
Rev. 0 3-7 V Structural Integrity Associates, Inc.
Table 3-4: Stresses Due to Piping Loads for Safe End Location Safe End External PiDina Loadsl t,#FX Fy =Fz=Mx =my=Mz=OD=ID=RN =kips kips kips in-kips in-kips in-kips in in in I I I I I I I I 5.16 L _ in tN 0.49 in (M-01 = 262.60 in-kips (My), = 85.96 in-kips My.=. 276.31 in-kips FX. 5.24 kips Nz= 3.35 kips/in qN = -0.31 kips/in Primary Membrane Stress Intensity PMz = 6.84 ksi T -0.63 ksi Slmax = 6.95 ksi SImax = 6949.94 psi I I I I I I I I I SIR-07-138-NPS, Rev. 0 3-8 V Structural Integrity Associates, Inc.I I Table 3-5: Stresses Due to Piping Loads for Blend Radius Location* Blend Radius External Pipinq Loads Fx=F=Fz =My=MY OD=ID=RN =kips kips kips in-kips in-kips in-kips in in in 7.65 L3= 92 in tN= 356 in (M 0= 122.24 in-kips (MY)2 162.24 in-kips Mxy= 203.14 in-kips Fx= 5.24 kips Nz- 1.14 kips/in qN = -0.07 kips/in Primary Membrane Stress Intensity PMz = 0.32 ksi= -0.02 ksi= 0.32 ksi Slmax = 322.52 psi SIR-07-138-NPS, Rev. 0 3-9 SRStructural Integrity Associates, Inc.
Figure 3-1: Core Spray Nozzle Internal Pressure Distribution SIR-07-138-NPS, Rev. 0 3-10 V Structural Integrity Associates, Inc.
1 11 11 11 1 Core Spray Nozzle Finite Element Model Figure 3-2: Core Spray Nozzle Pressure Cap Load SIR-07-138-NPS, Rev. 0 3-11 Structural Integrity Associates, Inc.
Figure 3-3: Core Spray Nozzle Vessel Boundary Condition SIR-07-138-NPS, Rev. 0 3-12 V Structural Integrity Associates, Inc.
R nRegion 11 Region 10 Region Region Region Region 12 Region I Figure 3-4: Thermal Regions SIR-07-138-NPS, Rev. 0 3-13 V Structural lntegrity.Associates, Inc.
I I I NODAL SOLUTION STEP=26 SUB =1 TIME=2.5 SINT (AVG)DMX =-.816948 SMN =97.958 SMX =758744 Node 3719 -APR 27 2007 16:10:09 A1N Node3737~xf 97.958 16937 33776 50615 67454 97. 958 : 16937 " 33776 50615 67454 8517 -25357 42196 59035 75874 Core Spray Nozzle Finite Element Model Figure 3-5: Safe End Critical Thermal Stress Location I I I I I I SIR-07-138-NPS, Rev. 0 3-14 I Strctural integrity Associates, Inc.I Figure 3-6: Blend Radius Critical .Thermal Stress Location SIR-07-138-NPS, Rev. 0 3-15 Structural integrity Associates, Inc.
I 0.4, 0)0 200 400 600 Time (sec)Figure 3-7: Safe End Green's Function for 1 II_ _ I 800 10003 t00% FlowI I I I Itrclra Iteriy ssciteInc I SIR-07-138-NPS, Rev. 0 3-16 30000 25000 20000 15000 10000 5000 200 400 600 800 Time (sec)Figure 3-8: Safe End Green's Function for 0% Flow 1000 SIR-07-138-NPS, Rev. 0 3-17 V Structural Integrity Associates, Inc.
30000 25000 20000 15000 10000.5000 1000 2000 3000 4000 5000 6000 7000 8000 Time (sec)Figure 3-9: Blend Radius Green's Function for 100% Flow Rev. 0 3-18 Structural Integrity Associates, Inc.SIR-07-138-NPS, 25000 20000 1500010000 5000 0 1000 2000 3000 4000 5000 6000 7000 Time (sec)Figure 3-10: Blend Radius Green's Function for 0% Flow 8000 SIR-07-138-NPS, Rev. 0 3-19 V Structural Integrity Associates, Inc.
-Temp (F) -Pressure (psig)600 500 1100 1050 1000 U-4, (U 4, 0~*E 4, I-400 300 200*
* f,900* }850 800 750+ 650" 600 I-550 A-500 I-450+ 400 350'300-I- 250-1-200+ 150/ / t ' , -ioo 1 50/___ --- ------,--- -5050 3000 4000 5000 6000 7000 8000 9000 10000 11000 12000 13000 14000 15000 16000 17000 Time (seconds)(4 4, 100 0 -0 1000 2000 I I I I I I I I I I I I I I I I I Figure 3-11: Transient 03: Startup SIR-07-138-NPS, Rev. 0 3-20 I Structural Integrity Associates, Inc.I
-- Temp (F) --Pressure (psig)600-13--d 400 300 E w 200 -100//////T 1280 4 1240 I 1200 1160 1120 1080 1040 1000: L 9 6 0/ 920 880/ -840/ t-800 760-720  4680 4-640 4 600-560 520 O.480-440-400 360-320 240" 200-160 T 120-80 40 000 16000 17000///", 0 1000 2000 .3000 4000 5000 6000 7000 8000 9000 10000 11000 12000 13000 14000 15'Time (seconds)Figure 3-12: TransientIlt:
Loss of Feedwater Pumps, Isolation Valves Close SIR-07-138-NPS, Rev. 0 3-21 Structural Itgrity Associates, Inc.
I- Temp (F) --Pressure (psig): 600 500 400 i~3004 CL E 4, I-T 1100 11050 i L 1000 1 950-900 850 800 750+ 700-650+ 600 i 4 550 500 450+ 400 350 300 250 200 150 100---------50 01 0 4, 0 4, a-I I I I I I I I I I I 200 100 0 " " 0 0 1000 2000 3000 4000 5000 6000 7000 8000 9000 10000 11000 12000 13000 14000 15000 16000 17000 Time (seconds)Figure 3-13: Transient 14: Single Relief of Safety Valve Blow Down I I I I I I SIR-07-138-NPS, Rev. 0 3-22 I SStracturaf Integrity Associates, Inc.I V- Temp (&deg;F) --Pressure (psig) I 600I 1100 1000 5 \900 4800*- 700 4, 600 Z.300 1, 0 .4 "-500 '4 E-4 4, "0 .. i o I- -400 200O 100 100 0 -- ---.- --. -- -0 0 1000. 2000 3000 4000 5000 6000. 7000 8000 9000 10000 11000 12000 13000 1'4000 15000 16000 17000 Time (seconds)Figure 3-14: Transient 21-23: Shutdown Vessel Flooding R-07-138-NPS, Rev. 0 3-23 Structural Integrity Associates, Inc.SI' I-- Temp (F) --Pressure (psig) I 600 1 500 400 300 E T 1100 1-1000 T 900 i 800-700+-6o0-500 =.a.400! 300.200". 100 300 400 500 200 100 j 0 0 100 200 Time (seconds)Figure 3-15: Transient 30: Emergency Shutdown 100% Flow (Safe End)I I I I SIR-07-138-NPS, Rev. 0 3-24 RS vStructural Integrity Associates, Inc.
1777Temp ('F) --Pressure (psig)600. -500 400 4)300 E I.-200 100 V.0'1100 1000 900 1-800 700 500+/- 400 300 200 100 50oo--3000 4000 1000 2000 Time (seconds)Figure 3-16: Transient 30: Emergency Shut Down 100% Flow (Blend Radius)SIR-07-138-NPS, Rev. 0 3-25 Structural Integrity Associates, Inc.
Fj 1 Figure 3-17: Pipe Reactions I SI~I Si, I 77 I I I I I I I I I I I I SStructural Integrity Associates, Inc.I SIR-07-138-NPS, Rev. 0 3-26
 
===4.0 STRESS===
AND FATIGUE ANALYSIS RESULTS* Fatigue calculations for the VY core spray nozzle were performed in accordance with ASME Code, Section III, Subsection NB-3200 methodology (1998 Edition, 2000 Addenda) [ 16].Fatigue analysis was performed in the Reference
[10] calculation for the two loca-tions identified in Section 3.1.2, using the Green's Functions developed for these two locations and the 60-year projected cycle counts from Reference
[13].Three computer programs were used to. facilitate the fatigue analysis process: STRESS.EXE, P-V.EXE, and FATIGUE.EXE.
The first program, STRESS.EXE, calculates a stress history in response to a thermal transient using a Green's Function.
The second program, P-V.EXE, reduces the stress history to peaks and valleys. The third program, FATIGUE.EXE, calculates fatigue from the reduced peak and valley history using ASME Code, Section III methodology.
All three programs, are explained in detail and were independently verified for use in the Reference
[15] calculation.
In order to perform the fatigue analysis, input files with the necessary data were prepared and the three analysis programs were run. The program STRESS.EXE required the following three input files:* Green.dat:
This file contains the Green's Function.
As discussed above, the core spray nozzle analyses utilize four Green's Functions:
a membrane plus bending stress intensity Green's Function and a total stress intensity Green's Function for both the safe end and blend radius locations.
* Green.efg:
A configuration file containing parameters that describe the Green's Function.* Transnt.inp:
This file contains the input transient history defined in Tables 3-2 and 3-3.Tables. 4-1 and 4-2 show the stresses for each location that were used in the fatigue analysis.Columns 2 through 5 of Table 4-1 (for the safe end) and Table 4-2 (for the blend radius) show SIR-07-138-NPS, Rev. 0 4-1 Structural Integrity Associates, Inc.
the final peak and valley output. The pressure values for Column 6 in each table were determined from the transient pressures, specified in Tables 3-2 and 3-3. The pressure stress intensities from Section 3.2 were scaled appropriately for each transient case. The scaled piping stress values are shown in columns 9 and 10 of Tables 4-1 and 4-2. The piping stress intensities from Section 3.3 were scaled based on the transient case RPV fluid temperature and assuming no stress occurs at an ambient temperature of 70'F.. Both of these stress intensities were then added to the thermal stress intensity peak and valley points to calculate the final stress values used for the fatigue analysis.
In the case of the piping load stress intensities, the sign of the stress intensity was conservatively set to the same sign as the thermal stress intensity to ensure bounding fatigue usage results. Columns 11 and 12 of Tables 4-1 and 4-2 show the summation of all stresses for each thermal peak and valley stress point. The last column shows the number of cycles associated with each peak or valley based on the cycle counts shown in Tables 3-2 and 3-3. I The program FATIGUE.EXE performs the ASME Code peak event-pairing required to calculate I a fatigue usage value. The input data for the configuration input file for FATIGUE.EXE, which is named FATIGUE.CFG, is shown in Table 4-3.The core spray piping adjacent to the safe end was also analyzed because of its proximity to the 3 maximum safe end thermal stress location.
For this fatigue analysis, the stress results of the safe end were used with stainless steel material properties and a value of 1.8 was selected for Kt at the I weld location, based on the maximum value given in ASME Code, Section 1II, Table NB-3681(a)-l
[16]. I The results of the fatigue analysis are presented in Tables 4-4, 4-5 and 4-6 for the safe end, blend I radius, and piping for 60 years, respectively.
I I SIR-07-138-NPS, Rev..0 4-2 Structural Integrity Associates, Inc.Ii SIR-07-138-NPS, Rev. 0 4-3 V Structural Integrity Associates, Inc.
I I Table 4-1: Core Spray Nozzle Safe End Stress Summary 1 2 3 4 5 6 7 8 9 10 11 12 13 Total M+B Total M+B Total Total Number Total M+B Pressure Pressure Piping Piping Total M+B of Transient Time Stress Stress Temperature Pressure Stress Stress Stress Stress Stress Stress Cycles Number (s) (psi) (psi) F (psig) (psi)) (psi (psi) (ps) (psi) (psi) (60 years)'i2 7 &sect;~l 100 (1 '>0 0>~. &.J _ 413 ___41381~
413 A1 120 2.1001,1 10o -- 13323 ~13i22 413 >4131K 13646 13635 , ~20~K~'>"'~ 1> 100 &#xfd;5 2 50 2.1>02&#xfd; '2 "601 413 '~413> >104 '1014 1U' 20 3 0 661 759 " _ 100 0. 0 0 413. 413 1074 1172 300 17164 9240 10700 549 1010 12150 12140 6592 6592 27982 29432 300 0 ' 0 " 8802 16138 526 >12166 1240 6276 ....62.6 :'27j22 .2 2 S.' ~ ~ 3 802 >123 >26 >721,190 ,143,16 ' 143041 6276 ,6276 >29393&#xfd;J 3&#xfd;0815 <Ki.13 38802 10236 526 113 13654 136430 6276 , 6276 ,2328 30154 1.164 19499 11,598 408 ..85 13265 13643 4578 '4578 )21566 29898 10* 8080 .1 &#xfd;595 725362200 0 " 0 9961....2 .... 5791 .3..1.3'654 j .3643 223775. , 3775 24,237 ,:;62030 '> 'S237.4 1114"io "36 ,,<12' K109,71 >10962 4005 '5"'4005 &#xfd;216 25808 0" A"21955 "4-722 "5577 2. -2325, '916A..11019
,110O <3509' > 359'192510
<20096 '> IQ 9518 10162 6 441 :1959 153710 26155' 26784 10 7930 4491 5276 30 63 3 7657 3287 3287 15441 1621920 10--'-~-'1 709 -90 116 526, > 1010 ''12150 2121'40 , 6276 6276 <28386- _29532' >10--'A'799' $8N2 "10236 1-,>56"'i00<"210 2.. 1Z40 6276 '6276 '27224 -28652 "10.14 0 8802 10236 56 1010 12150 1140 6276 6276 27228 28652 1 152 9499 10570 497 855 10286 10277 5880 .5880 25664 26727 1 12580 91, 95 70 50 602 --601 01 0 693 696L I 21'2.0 5,'242; 0- 549 -i'1010 12-150 1272146 6592 6592 >27&#xfd;984< 18732 300 I """ i7'224' '664 0 ' 100> !7 50"'-602'
,601 ,413 '413 " 1678' 1014 30 24 100 50 602 601 413 413 1014 1014 1 100 1563 18803 18787 413 413 19216 19200 1 1 100 501 .6021 601 413 413 1014 1014 1 30 -22. '9:2680,1080 0 "','549' 10610 ,1 2,1'50'>12140 6592 69 ' 29022,. 29)532, ' '1'.'',13 8560>4464
' 162< 25 '302 .300 12601 1260' '89862' 48195.3 ' "1 i10111 '-12~ -101 ' ,7 '', L'~ 70700, 0'-p 0 ," "41-2 AI -1' 1 NOTES: Column I: Transient number identification.
Column 2: Time during transient where a maximum or minimum stress intensity occurs from P-V.OUT output file.Column 3: Maxima or minima total stress intensity from P-V.OUT output file.Column 4: Maxima or minima membrane plus bending stress intensity from P-V.OUT output file.Colunm 5: Temperature per total stress intensity.
Column 6: Pressure per Table 3-4.I II I I I I I I I Column 7: Column 8: Column 9: Column 10: Column 11: Column 12: Column 13: Total pressure stress intensity from the quantity (Column 6 x 12,030)/1000.
Membrane plus bending pressure stress intensity from the quantity (Column 6 x 12,020)/1000.
Calculated using the total external stress from Table 3-4 as 6949.94 psi*(Column 5-70 0 F)/(575&deg;F
-70&deg;F).Same as Column 9, but for M+B stress.Sum of total stresses (Columns 3, 7, and 9).Sum of membrane plus bending stresses (Columns 4, 8, and 10).Number of cycles for the transient (60 years).I I I I I I SIR-07-138.-NPS, Rev. 0 4-4 I SStructural Integrity Associates, Inc.I Table 4-2: Core Spray Nozzle Blend Radius Stress Summary UI I I Transient I *Number-- -2 2 3. 4 6 7 8 9 10 11 Total M+B Total M+B Total Total M+B Pressure Pressure Piping Piping Total Time Stress Stress Temperature Pressure Stress *Stress Stress Stress Stress 12 Total M+B Stress-13 Number.of Cycles NOTES: Column 1: Transient number identification.
Column 2: Time during transient where a maximum or minimum stress intensity occurs from P-V.OUT output file.Column 3: Maxima or minima total stress intensity from P-V.OUT output file.Column 4: Maxima or minima membrane plus bending stress intensity from P-V.OUT output file.Column 5: Temperature per total stress intensity.
Column 6: Pressure per Table 3-5.Column 7: Total pressure stress intensity from the quantity (Column 6 x 35,860)/1000.
Column 8: Membrane plus bending pressure stress intensity from the quantity (Column 6 x 34,970)/1000.
Column 9: Calculated using the total external stress from Table 3-5 as 322.52 psi*(Column 5-70 0 F)/(575-F  F).Column 10: Same as Column 9, but for M+B stress.Column i1: Sum of total stresses (Columns 3, 7, and 9).Column 12: Sum of membrane plus, bending stresses (Colunms 4, 8, and 10).Column 13: Number of cycles for the transient (60 years).SIR-07-138-NPS, Rev. 0 4-5 Structural Integrity Associates, Inc.
Table 4-3: Fatigue Parameters Used in the Core Spray Nozzle Fatigue Analysis I Blend Radius Safe End Piping (SA508 Class II) (N06600) (Stainless Steel)Parameters m and n for Computing Ke 2.0 & 0.2 1.7 & 0.3 1.7 & 0.3 ParametersmandnforComputin K(low alloy steel)Design Stress Intensity Values, S. 26,700 psi @ 600TF 23,300 psi @ 600&deg;F 17,000 psi @ 600TF Elastic Modulus from Applicable 10 6 Fatigue Curve 30.0x106 psi 28*.3x10psi 28.3x psi Elastic Modulus Used in Finite 26.7x106 psi 29.8x106 psi 27.0xi06 psi Element Model (300 0 F)The Geometric Stress Concentration See Note 1 Factor Kt 1.0_4.0 SeNote_ _"_ _1.8 Note: 1. Conservative bounding value per ASME:Code, Subsection NB-3600 to conservatively cover adjacent thread and weld regions.I I I I I I I I I U U I I I I I I SIR-07-138-NPS, Rev. 0 4-6 Structural Integrity Associates, Inc.
Table 4-4: Fatigue Results for Core Spray Nozzle Safe End LOCATION.=
LOCATION NO. 1 -- SAFE END FATIGUE CURVE = 2 (1 = CARBON/LOW ALLOY, 2 STAINLESS STEEL)m=1.7 n= .3 Sm = 23300. psi Ecurve = 2,830E+07 psi Eanalysis
= 2.980E+07 psi Kt = 4.00 MAX 89862.29956.29393.28732.28386.28022.27984.27984.27984.27984.27984.27984.27982.27&sect;82.27228.27228.27228.26155.26116.25664.22237.19250.19216.15441.13646.MIN RANGE MEM+BEND Ke Salt Napplied Nallowed-12. .89874.413. 29543.413.. 28980.413. 28319.413. 27973.413. 27609.413. 27571.6.93. 27291..1014. 26970.1014. 26970.1014. 26970.1074. 26910.1074. 26908.1678. 26304.1678. 25550.1678. 25550.1678. .25550.1678. 24477.1678. 24438.1678. 23986.1678. 2055.9.1678. 17572.1678. 17538.1678. 13763.1678. 11968..48 29 30 29 29 29 18 18 17 17 17 17 28 28 27 27 27 25 24 25 22: 19(181 152 12 963. 1.000 485. 1.000 402. 1.000 741.. 1.000 119. 1.000 119. 1.000 319. 1.000 036. 1.000 718. 1.000 718. 1.000 718. 1.000 560. 1.000 260. 1.000 418. 1.000 638. 1.000 638. 1.000 638. 1.000 775. 1.000 794. 1.000 713. 1.000 195. 1.000 082. 1.000 186. 1.000 205. 1.000 621. 1.000 112423. 1.000E+00 56029. 1.OOOE+01 57068. 1.OOOE+01 55813. 1.OOOE+01 54762. 1.000E+/-01 54590. 1..O00E+00 39187. 7.900E+01 38651. 1*0OOE+00 38045. 1.200E+02 38045. 1.O00E+00 38045. 1.000E+00 37792. 9.800E+01 53033. 2.020E+02 52971. 9.800E+01 51502. 1.OOOE+01 51502. 1.OOOE+01 51502. 1.000E+00 48339. 1.OOOE+01 46923. 1.000E+01 48017. 1.000E+00 41379. 1.OOOE+01 35526. 1.000E+01 34234. 1.000E+00 28195. 1.OOOE+01 23661. 1.200E+02 1.'213E+03
: 1. 910E+04 1. 746E+04 1. 946E+04 2. 140E+04 2.174E+04 1.244E+05 1. 34 1E+05 1. 460E+05 1. 4 60E+05 1. 460E+05 1. 514E+05 2. 517E+04 2. 532E+04 2. 919E+04 2. 919E+04 2. 919E+04 4. 021E+04 4. 673E+04 4. 159E+04 9. 257E+04 2. 135E+05 2. 691E+05 1. 00IE+06 1. 772E+06 U.0008.0005.0006..0005.0005.0000.0006.0000.0008.0000.0000.0006.0080.0039 0003.0003.0000.0002.0002.0000.0001.0000.0000 0000.0001 TOTAL USAGE FACTOR = .0184 Structural Integrity Associates, Inc.SIR-07-138-NPS, Rev. 0 4-7 Table 4-5: Fatigue Results for the Core Spray Nozzle Blend Radius LOCATION LOCATION NO. 2 BLEND RADIUS FATIGUE CURVE = 1 (1 = CARBON/LOW ALLOY, 2 STAINLESS STEEL)m= 2.0 n= .2 Sm = 26700. psi Ecurve = 3.000E+07 psi Eanalysis
= 2.670E+07 psi.Kt= 1.00 I I I I I I I I I I I MAX 56068.51325.46174.46013.45991.44605.39899.39719.39719.39719.39465.-39465.39292.38628.38628.38628.38628.38625.38625.38565.35265.26915.25700.MIN RANGE 19. 56049.19. 51306.19. 46155.19. 45994.19. 45972.19. 44586.19. 39880.19. 39700..19. 39700.19. 39700.19. 39446..1812. 37653.1812. 37480.1812. 36816.1812. 36816.1812. 36816.23719. 14909.23719. 14906.25492. 13133.25492. 13073.25492. 9773.25492. 1423.25492. 208.MEM+BEND Ke*54658. 1.000 45212. 1.000 45531. 1.000 43180. 1.000 41149. 1.000 39443. 1.000 39707. 1.000 39236. 1.000 39236. 1i000 39236. 1.000 38467. 1.000 36718. 1.000 38223. 1.000 37019. 1.000 37019. 1.000:37019. 1.000 26168. 1.000 26187. 1.000 24470. 1.000 24240. 1.000 14585. 1.000 610. 1.000 564. 1.000 Salt 31488.28824.25930.25839.25827.25048.22404.22303.22303.22303.22161.21153.21056.20683.20683.20683.8376.8374.7378.7344.5490.799.117.Napplied 1. 000E+00 1.000E+01 1.000E+01 1.000E+01 1. 000E+01 1. OOOE+01 1.000E+01 1. 000E+01 1.000E+01 1.000E+00 3.800E+01 8.200E+01 1.000E+01 2.800E+01 1.000E+00 1. 000E+00 2. 700E+02 3.000E+01 2. 700E+02 1. OOOE+00 1.000E+01 1.000E+00 1. 000E+00 Nallowed 1. 896E+04 2. 501E+04 3.460E+04 3. 498E+04 3.503E+04 3.848E+04 5. 695E+04 5. 824E+04 5. 824E+04 5.824E+04 6. 012E+04 7. 572E+04 7.747E+04 8. 466E+04 8.466E+04 8. 466E+04 5.366E+07 5.375E+07 3.042E+08 3. 374E+08 1.000E+20 1. OOOE+20 1.000+E20 U.0001.0004.0003.0003.0003.0003.0002.0002.0002.0000.0006 0011.0001.0003.0000.0000.0000 0000.0000.0000.0000.0000 0000 TOTAL USAGE FACTOR =.0043 I I I I SIR-07-138-NPS, Rev. 0 4-8 V Structural Integrity Associates, Inc.
Table 4-6: Fatigue Results for the Core Spray Stainless Steel Piping LOCATION = LOCATION NO. 1 -- SS Piping FATIGUE CURVE = 2 (1 = CARBON/LOW ALLOY, 2,=m = 1.7 n = ..3 Sm =17000. psi Ecurve = 2.830E+07 psi Eanalysis
= 2.700E+07 psi Kt = 1.80 STAINLESS STEEL)MAX 89862.29956.29393.28732.28386.28022 27984 27984 27984.27984.27984.27984.27982.27982.27228.27228.27228.26155.26116.25664.222237.19250.19216.15441.MIN-12.413.413.413.413.413.413.693.1014.1014.1014.1074.1074.1678.1678.1678.1678.1678.1678.1678.1678.1678.1678.1678.RANGE MEM+BEND 89874. 48963.29543. 29485.28980. 30402.28319. 29741.27973. 29119.27609. 29119.27571. 18319'27291. 18036.26970. 17718.26970. 17718.26970. 17718.26910. 17560.26908. 28260.26304. 28418.25550. .27638.25550. 27638.25550. 27638.24477. 25775.24438. 24794.23986. 25713.20559. 22195.17572. 19082.17538. 18186.13763. 15205.1.1.I.1 i.1 1.i1.1.1.1.1.1.1.I.1.(i..1.1.7*1.Ke Salt 000 67629.000 27845.000 27934..000 27310.000 26868.000 26678.000 :22130.000 21864.000 21563.000 21563.000 21563.000 21465.000 25950.000 25700.000 24978.000 24978.000 24978.000 23634.000 23202.000 23351.000 20080.000 17209.000 16816.000 13588.)00 11564.Napplied 1.OOOE+00 1.600E+01 1.000E+01 1.OOOE+01 1.OOOE+01 1.000E+00 7.900E+01 1.000 E+00 1.200E+02 1.000E+00 1.OOOE+00 9.800E+01 2.020E+02 9.800E+01 1.000E+01 1.OOOE+01 1.000E+00 1.000E+01 1.O00E+01 1.000E+00 1.OOOE+01 1.000E+01 1.000E+00 1.000E+01 1.200E+02 Nallowed 8. 006E+03 1. 042E+06 1. 031E+06 1. 11OE+06 1. 171E+06 1. 198E+06 2. 272E+06 2. 392E+06 2. 539E+06 2. 539E+06 2. 539E+06 2. 588E+06 1.311E+06 1. 354E+06 1. 485E+06 1.485E+06 1.485E+06 1.779E+06 1.889E+06 1. 8505+06 3. 442E+06 7.481E+06 8. 600E+06 1. 000E+20 1. 000E+20 U.0001.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0002.0001.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000.0000 13646. 1678. 11968. 12621. 1.0 TOTAL USAGE FACTOR .0005 Structural Integrity Associates, Inc.SIR-07-138-NPS, Rev. 0 4-9 I 5.0 ENVIRONMENTAL FATIGUE ANALYSIS I Environmental fatigue multipliers were computed for both normal water chemistry (NWC) and hydrogen water chemistry (4WC) conditions in Reference
[17] for various regions of the VY RPV and attached piping. Based on VY-specific dates for plant startup and HWC implementation, as well as past and future predicted HWC system availability, it was determined that ,overall HWC availability is 47% over the sixty year operating period for VY. Therefore, for the purposes of the EAF assessment of the core spray. nozzle, it was assumed that HWC conditions exist for 47% of the time, and NWC conditions exist for 53% of the time over the 60-year operating life of the plant. RPV upper region chemistry was assumed for both the core spray nozzle safe end and blend radius locations, since both locations experience reactor conditions for all times except during core spray injections, (which are rare occurrences).
I For the safe end location, the environmental fatigue factors for pre-HWC and post-HWC are both 1.49 from Reference
[181. This results in an EAF adjusted CUF as follows: Year CUF, U 6 0 = 0.0184 (from Table 4-4)Overall EAF multiplier, Fe, = 1.49 60-Year EAF CUF, U 6 0-,v, = 0.0 184 x 1.49 0.0274 The EAF CUF value of 0.0274 for 60 years for the safe end is acceptable (i.e., less than the allowable value of 1.0).For the stainless steel piping, the environmental fatigue factors for pre-HWC and post-HWC are both 8.36 from Table 4 of Reference
[17] for the RPV upper region. This results in an EAF adjusted CUF as follows: 60-Year CUF, U 6 0 = 0.0005 (from Table 4-6)Overall EAF multiplier, F 1 , = 8.36 I 60-Year EAF CUF, U 6 0-vn = 0.0005 x 8.36 = 0.0042 I SIR 138-NPS, Rev. 0 5-1 Structural Integrity Associates, Inc.I The EAF CUF value of 0.0042 for 60 years for the blend radius is acceptable (i.e., less than the allowable value of 1.0).*The fatigue calculation documented in Section 4.0 for the blend radius location was performed for the nozzle base material, since cladding is structurally neglected in. modem-day fatigue analyses, per ASME Code, Section 111, NB-3122.3
[16]. This is also consistent with Sections 5.7.J.1 and 5.7.4 of NUREG/CR-6260
[I]. Therefore, the cladding was neglected and EAF assessment of the nozzle base material was performed for the blend radius location.For the blend radius location, the environmental fatigue factors for pre-I-IWC and post-HWC are 11.14 and 8.82, respectively; from Table 4 of Reference
[17] for the RPV upper region. This results in an EAF adjusted CUF as follows: 60-Year CUF, U 6 0 = 0.0043 (from Table 4-5)Overall EAF multiplier, Fe, = (11.14 x 53% + 8.82 x 47%) = 10.05 60-Year EAT CUF, U 6 0..evn 0.0043 x 10.05 = 0.0432 TheEAF CUF value of 0.0432 for 60 years for the blend radius is acceptable. (i.e., less than the allowable value of 1.0).'SIR-07-138-N.PS, Rev. 0 5-2 RRvStructural Integrity Associates, Inc.
 
==6.0 CONCLUSION==
S This report documents a refined fatigue evaluation for the VY core spray nozzle. The intent of this evaluation is to use refined transient definitions and the revised cyclic transient counts for 60 years for a computation of CUF, including EAF effects, that is more refined than previously performed fatigue analyses.
The fatigue-limiting locations in the core spray nozzle, safe end, and piping are included in the evaluation, to be consistent with NUREG/CR-6260
[1] needs for EAF evaluation for license renewal. The final fatigue results are considered to be a replacement to the values previously reported in the VY LRA..The fatigue calculations for the VY core spray nozzle were performed in accordance with ASME Code, Section 111, Subsection NB-3200 methodology (1998 Edition, 2000 Addenda) [16]. The stress evaluation is summarized in Section 3.0, and the fatigue analysis is summarized in Section 4.0. The results in Section 4.0 reveal that the CUF for the limiting safe end location is 0.0184, the CUF for the limiting blend radius location is 0.0043, and the CUF for the stainless steel piping is 0.0005. All of these values represent60 years of plant operation, including all relevant EPU effects.EAF calculations for the VY core spray nozzle were also performed, as summarized in Section 5.0. The results in Section 5.0 reveal that the EAF CUF for the limiting safe end location is 0.0274, the EAF CUF for the limiting blend radius location is 0.0432, and the EAF CUF for the stainless steel piping is 0.0042. All of these values represent 60 years of plant operation, including all relevant EPU effects.All fatigue allowables, both with and without EAF effects, are met, thus demonstrating acceptability for 60 years of operation.
I I SI[R 138-NP S, Rev. 0 6 -1 Structural Integrity Associates, Inc.I
 
==7.0 REFERENCES==
: 1. NUREG/CR-6260 (1NEL-95/0045), "Application of NUREG/CR-5999 Interim Fatigue Curves to Selected Nuclear Power Plant Components," March 1995.2. Structural Integrity Associates Report No. SIR-86-037, Revision 0, "Evaluation of Modifications to Vermont Yankee Core Spray Nozzle and Safe End," January 1987, SI Project No. YAEC-08.3. GE Design Specification No. 21AI 115, Revision 4, "Vermont Yankee Reactor Pressure Vessel," October 21, 1969, S1 File No. VY-05Q-210;
: 4. GE Design Specification No. 26A6019, Revision 1, "Reactor Vessel -Extended Power Uprate," August 29, 2003, SI File No. VY-05Q-236.
: 5. Kuo, A. Y., Tang, S. S., and Riccardella, P. C., "An On-Line Fatigue Monitoring System for Power Plants, Part I -Direct Calculation of Transient Peak Stress Through Transfer Matrices and Green's Functions," ASME PVP Conference,, Chicago, 1986.6. ANSYS, Release 8. 1A1 (w/Service Pack 1), ANSYS, Inc., June 2.004.7. StructuralIntegrity Associates Calculation No. VY-16Q-308, Revision 0, "Core Spray Nozzle Finite Element Model." 8. American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section II, Materials, Part D, "Properties (Customary)," 1998 Edition, 2000 Addenda.9. Structural Integrity Associates Calculation No. VY-16Q-309, Revision 0, "Core Spray Nozzle Green's Functions." SIR-07-138-NPS, Rev. 0 7-1 Structural lntegrity Associates, Inc.
: 10. Structural Integrity Associates Calculation No. VY- 16Q-310, Revision 0, "Fatigue Analysis of Core Spray Nozzle.".11. Reactor Thermal Cycles, Attachment I of Entergy Design Input Record (DIR) Revision 1, EC No. 1773, Rev. 0, "Environmental Fatigue Analysis for Vermont Yankee Nuclear Power Station," 7/26/07, SI File No. VY-16Q-209.
: 12. Nozzle Thermal Cycles (Drain, Core Spray & Head Spray), Attachment 1 of Entergy Design Input Record (DIR) Revision 1, EC No. 1773, Rev. 0, "Environmental Fatigue Analysis for Vermont Yankee Nuclear Power Station," 7/26/07, SI File No. VY-16Q-209.13. Reactor Thermal Cycles for 60 Years of Operation, Attachment 1 of Entergy Design Input Record (DIR) Revision 1, EC No. 1773, Rev. 0, "Environmental Fatigue Analysis for Vermont Yankee Nuclear Power Station," 7/26/07, SI File No. VY-16Q-209.
3 14. Vermont Yankee Drawing 5920-00024, Rev. 11, (GE Drawing No. 919D294, Sheet No. 3 7), "Reactor Vessel," SI File No. VY-05Q-241.
l 15. Structural Integrity Associates Calculation No. SW-SPVF-O1 Q-301, Revision 0,"STRESS.EXE, P-V.EXE, and FATIGUE.EXE Software Verification."I
: 16. American Society of Mechanical Engineers Boiler & Pressure Vessel Code, Section III, Rules for Construction of Nuclear Facility Components, 1998 Edition, 2000 Addenda..17. Structural Integrity Associates Calculation No. VY- 16Q-303, Revision 0,"Environmental Fatigue Evaluation of Reactor Recirculation Inlet Nozzle and Vessel i Shell/Bottom Head." I SIR-07-1I38-NPS, Rev. 0 7-2 Structural Integrity Associates, Inc.I
: 18. EPRI Report No. TR- 105759, "An Environmental Factor Approach to Account for Reactor Water Effects in Light Water Reactor Pressure Vessel and Piping Fatigue Evaluations," December 1995.IR-07-138-NPS.
Rev. 0 7-3 tnlnih, SI Ac-ent-iDtac In,-I NEC-JH_18 Report No.: SIR-07-132-NPS Revision No.: I Project No.: VY-16Q File No.: VY-16Q-404 December 2007 Summary Report of Plant-Specific Environmental Fatigue Analyses for the Vermont Yankee Nuclear Power Station Prepared for: Entergy Nuclear Operations.
Inc.(Contract Order No. 10150394)Prepared by: Structural Integrity Associates, Inc.Centennial, CO Prepared by: Reviewed by: Approved by: T. J. 4 ann P.E.L. Stevens, P.E.T. J.
P.E.Date: 12/15/2007 Date: 12/15/2007 Date: 12/15/2007 REVISION CONTROL SHEET Document Number: SIR-07-132-NPS Title: Summary Report of Plant-Specific Environmental Fatigue Analyses for the Vermont Yankee Nuclear Power Station Client: Entergy Nuclear Operations, Inc.SI Project Number: VY-16Q SectionT Pages ] Revision Date Comments 1.0 1-1 0 7/27/07 Initial issue.2.0 2-1-2-2 3.0 3-1 18 4.0 4-1 5.0 5-1 2 1.0 1-1 1 12/15/07 Revised based on revision to VY-16Q-2.0 2-1-2-2 309 and VY-16Q-310 associated with 3.0 3-1 18 CAR 07-25 and NCR 07-11. Editorial 4.0 4-1 correction on page 3-5.,5.0 5-1 2 Table of Contents Section Page
 
==1.0 INTRODUCTION==
 
..............................................................................................................
1-1 2.0 BACKGROUND
.................................................................................................................
2-1 3.0 ENVIRONM ENTAL FATIGUE CALCULATIONS
.....................................................
3-1 3.1 Reactor Vessel Shell and Lower Head .........................................................................
3-3 3.2 Reactor Vessel Feedwater Nozzle ................................................................................
3-4 3.3 Reactor Recirculation Piping (Including the Reactor Inlet and Outlet Nozzles) .........
3-5 3.3.1 Reactor Recirculation Piping ................................................................................
3-5 3.3.2 Reactor Recirculation Inlet Nozzle ......................................................................
3-6 3.3.3 Reactor Recirculation Outlet Nozzle ....................................................................
3-7 3.4 Core Spray Line Reactor Vessel Nozzle and Associated Class 1 Piping .....................
3-7 3.5 RHR Return Line Class 1 Piping .................................................................................
3-8 3.6 Feedwater Line Class 1 Piping .....................................................................................
3-8 3.7 Summary of Results .....................................................................................................
3-8 4.0 SUM M ARY AND CONCLUSIONS
.................................................................................
4-1
 
==5.0 REFERENCES==
 
...................................................................................................................
5-1 SIR-07-132-NPS, Rev. I&deg;.&deg;V Structural Integrity Associates, Inc.
LIST OF TABLES Table Title Page Table 3-1. Environmental Fatigue Evaluation for the Reactor Vessel Shell ...............................
3-9 Table 3-2. Environmental Fatigue Evaluation for the Reactor Vessel Shell at ................................
Shroud Support ...........................................................................................................................
3-10 Table 3-3. Environmental Fatigue Evaluation for the Reactor Vessel Feedwater Nozzle ...............
Forging B lend R adius .................................................................................................................
3-11 Table 3-4. Environmental Fatigue Evaluation for the Recirculation/RHR Piping Tee .............
3-12 Table 3-5. Environmental Fatigue Evaluation for the Reactor Recirculation Inlet ..........................
N ozzle F orging ...........................................................................................................................
3-13 Table 3-6. Environmental Fatigue Evaluation for Reactor Recirculation Inlet Nozzle ...................
Safe End ................................................................
.............................
3-14 Table 3-7. Environmental Fatigue Evaluation for Recirculation Outlet Nozzle Forging .........
3-15 Table 3-8. Environmental Fatigue Evaluation for Core Spray Reactor Vessel ................................
Nozzle Forging Blend Radius, Safe End, and Piping .................................................................
3-16 Table 3-9. Environmental Fatigue Evaluation for the Feedwater Line Class 1 Piping .............
3-17 Table 3-10. Summary of Environmental Fatigue Calculations for VYNPS .............................
3-18 I I I 1 U I I I I I I I U I I I I I SIR-07-132-NPS, Rev. I iv U Structural Integrity Associates, Inc.I
 
==1.0 INTRODUCTION==
 
This report provides the results of plant-specific environmental fatigue calculations for the Vermont Yankee Nuclear Power Station (VYNPS). These calculations are performed to satisfy Nuclear Regulatory Commission (NRC) requirements for Entergy Nuclear Vermont Yankee's (ENVY's) License Renewal Application for VYNPS, submitted to the NRC in 2006.Generic Safety Issue (GSI) 166 [1], later renumbered as GSI-190 [2], was identified by the NRC staff because of concerns about the effects of reactor water environments on fatigue life during the period of extended operation
[3]. GSI-190 was closed in December 1999, based on a memorandum from NRC-RES to NRC-NRR [4]. Timing of issue closure required the first two license renewal applicants
-Baltimore Gas & Electric Company for the Calvert Cliffs Nuclear Power Plant and Duke Energy for the Oconee Nuclear Station -to address GSI-190 in their applications prior to issue closure. Each of the applicants developed responses to the NRC staff without the benefit of information from GSI-190 closure. Subsequent license renewal applicants have had the benefit of this information that could be used to guide the resolution of the fatigue design basis and time limited aging analyses (TLAA) issues.This report addresses VYNPS reactor water environmental effects on the fatigue life of selected fatigue-sensitive reactor coolant system (RCS) components, in accordance with the resolution of GSI-190, as required by Chapter X, "Time Limited Aging Analyses Evaluation of Aging Management Programs Under IOCFR54.21 (c)(1)(iii), Section X.M I "Metal Fatigue of Reactor Coolant Pressure Boundary", of the Generic Aging Lessons Learned (GALL) Report [5].Consistent with the requirements of the GALL report, the method chosen for this environmentally-assisted fatigue (EAF) evaluation is based on evaluation of the locations identified in NUREG/CR-6260
[6] and the NRC-accepted EAF relationships generated from laboratory data, as documented in References
[7] and [8].SIR-07-132-NPS, Rev. 1 1-1 Structural Integrity Associates, Inc-
 
==2.0 BACKGROUND==
As a part of the NRC's Fatigue Action Plan [3], incorporation of environmental fatigue effects originally involved a reduced set of fatigue design curves, such as those proposed by Argonne National Laboratory (ANL) in NUREG/CR-5999
[9]. As a part of the effort to close GSI-166 (later GSI-190) for operating nuclear power plants during the current 40-year licensing term, Idaho National Engineering Laboratory (INEL) evaluated fatigue-sensitive component locations at plants designed by all four U. S. nuclear steam supply system (NSSS) vendors. The ANL I fatigue curves were used by INEL to recalculate the cumulative usage factors (CUFs) for fatigue-sensitive component locations in early and late vintage Combustion Engineering (CE)pressurized water reactors (PWRs), early and late vintage Westinghouse PWRs, early and late vintage General Electric (GE) boiling water reactors (BWRs), and Babcock & Wilcox Company (B&W) PWRs. The results of the INEL calculations were published in NUREG/CR-6260
[6].The INEL calculations took advantage of conservatisms present in governing ASME Code fatigue calculations, including the numbers of actual plant transients relative to the numbers of design-basis transients, but did not recalculate stress ranges based on actual plant transient profiles.
The BWR calculations, especially the early-vintage GE BWR calculations, are directly relevant to VYNPS.The fatigue-sensitive component locations chosen for the older-vintage GE BWR plant were: (1) I the reactor vessel shell and lower head, (2) the reactor vessel feedwater nozzle, (3) the reactor recirculation piping (including the reactor inlet and outlet-nozzles), (4) the core spray line reactor U vessel nozzle and associated Class 1 piping, (5) the residual heat removal (RHR) return line Class 1 piping, and (6) the feedwater line Class 1 piping. For the recirculation, RHR, and feedwater piping locations, INEL performed representative design-basis fatigue calculations.
This is because no CUF calculations had originally been performed since the piping systems for the selected BWR plant were initially designed and analyzed in accordance with the criteria of USAS B31.1-1967
[10].I SIR-07-132-NPS, Rev. 1 2-1 Structural Integrity Associates, inc.H I The six RCS component locations described above are evaluated for EAF effects for VYNPS in this report through separate plant-specific analyses of nine VY component locations (with report section numbers indicated):
the reactor pressure vessel (RPV) shell and lower head (3.1); the RPV shell at the shroud support junction (3.1); the feedwater nozzle (3.2); the recirculation
/residual heat removal Class I piping (3.3.1 and 3.5); the recirculation inlet nozzle forging (3.3.2); the recirculation inlet nozzle safe end (3.3.2); the recirculation outlet nozzle forging (3.3.3); the core spray nozzle, safe end, and Class 1 piping (3.4); and the feedwater Class 1 piping (3.6).The calculations reported in NUREG/CR-6260 were based on the interim reduced fatigue design curves given in NUREG/CR-5999
[9]. Such an approach penalizes the component location fatigue analysis unnecessarily, because research has shown that a combination of environmental conditions is required before reactor water environmental effects become pronounced.
The strain rate must be sufficiently low and the strain range must be sufficiently high to cause continuing rupture of the passivation layer that protects the exposed surface area. Temperature, dissolved oxygen content, metal sulfur content, and water flow rate are additional variables to be considered.
In order to take these parameters into consideration, EPRI and GE jointly developed a method, called the Fen approach [11], which permits reactor water environmental effects to be applied selectively, as justified by parameter combinations.
In 1999, the NRC staff raised a number of issues relative to the use of the EPRI/GE methodology in various industry applications.
Those issues, coupled with more recent laboratory fatigue data in simulated LWR reactor water environments generated by ANL for carbon and low-alloy steels and stainless steels, resulted in a revised Fen methodology, as published in NUREG/CR-6583
[7]for carbon and low alloy steels, and NUREG/CR-5704
[8] for stainless steels. The methodology documented in these reports was used to evaluate environmental effects for VYNPS components, as described in Section 3.0 of this report.SIR-07-132-NPS, Rev. 1 2-2 ... ..atruc runi inwegrury
/isVouldle, Mc1.
 
===3.0 ENVIRONMENTAL===
 
FATIGUE CALCULATIONS Section 2.0 identifies the locations evaluated in NUREG/CR-6260 for the older vintage GE plant, which corresponds to VYNPS. NUREG/CR-6260 provided an assessment of these six selected component locations with respect to environmental fatigue using the older reduced environmental fatigue curves. Potential reactor water environmental effects are evaluated using the updated Fen methodology on a plant-specific basis in this subsection, in order to address the associated effects on fatigue as required by the GALL Report [5].For each of the components identified in Section 2.0, environmental fatigue calculations were I performed.
The details of these calculations are documented in the Reference
[12, 17, 18, 21, 22 and 24] calculations.
The calculations were carried out using the appropriate methodology I contained in NUREG/CR-6583 for carbon/low alloy steel material, and in NUREG/CR-5704 for stainless steel material.
This methodology is as follows: For Carbon Steel [7]: Fen = exp (0.585 -0.00124T'
-0.101 S* T* 0* I= exp (0.554- 0.101 S* T* O*S*)For Low Alloy Steel [7]: Fen = exp (0.929 -0.00124T'
-0.101 S* T* 0* I=exp(0.898-0.l0l S* T* O**)Note that the above expressions have been corrected as summarized in Reference
[23].where: Fen = fatigue life correction factor H T' 25&deg;C (NUREG/CR-6583, Section 6, Fen relative to air)S* -- S for 0 <sulfur content, S < 0.015 wt. %-0.015 for S > 0.015 wt. %T* 0 for T < 150'C 3= (T- 150) for 150 <T_< 350'C T = fluid service temperature
(&deg;C) 3 0* = 0 for dissolved oxygen, DO < 0.05 parts per million (ppm)-ln(DO/0.04) for 0.05 ppm < DO < 0.5 ppm= ln(12.5) for DO > 0.5 ppm I SIR-07-1I32-NPS, Rev. 1 3-1 Structural Integrity Associates, Inc. 3 I
= 0 for strain rate, > 1%/sec= In( ) for 0.001 1 1%/sec= In(0.001) for &#xfd; < 0.001%/sec For Types 304 and 316 Stainless Steel [8]: Fen = exp (0.935 -T* *O*)where: Fen = fatigue life correction factor T = fluid service temperature
('C)= 0 forT <200 0 C= I forT > 200 0 C= 0 for strain rate, &#xfd; > 0.4%/sec= ln(/0.4) for 0.0004 :5 0.4%/sec= ln(0.0004/0.4) for s < 0.0004%/sec 0* = 0.260 for dissolved oxygen, DO < 0.05 parts per million (ppm)-0.172 for DO >_ 0.05 ppm Bounding Fen values are determined or, where necessary, computed for each load pair in a detailed fatigue calculation.
The environmental fatigue is then determined as Uenv = (U) (Fen), where U is the original fatigue usage, and Uenv is the EAF usage factor.INFORMATION REDACTED Since implementation of HWC in 2003, VYNPS's availability has exceeded 98.5% and the objective for future HWC system availability is a minimum of 99% [12]. With these considerations, the overall availability for HWC since implementation at VYNPS until the end of the 60-year operating period was estimated at 98.5%.SIR-07-132-NPS, Rev. 1 3-2 Structural Integrity Associates, Inc.T-~( Pagi Ccnfortation Rifsarkw ito Vea"dor Ihadmrgin)r(such information is marke'd with a "'bar" in the right-hand margin)
I Some nozzles, (e.g., recirculation outlet nozzle) have three materials:
a Ni-Cr-Fe dissimilar metal weld (DMW), a low alloy steel forging, and a stainless steel safe end. To ensure the maximum CUF considering environmental effects was identified, locations in both the safe end and nozzle forging were selected.
This selection produces bounding environmental fatigue results for the 3 entire nozzle assembly for the following reasons: " The highest thermal stresses from the finite-element model (FEM) analysis occur in the I stainless steel safe end. Stainless steel Fen multipliers at VYNPS are significantly higher than Ni-Cr-Fe multipliers (F,, values are 2.55 or higher for stainless steel [12] vs. a constant value of 1.49 for Ni-Cr-Fe [11]). Therefore, evaluation of the safe end bounds the Ni-Cr-Fe weld material.* The highest pressure stresses from the FEM analysis occur in the low alloy steel nozzle forging. Low alloy steel Fen multipliers at VYNPS are higher than Ni-Cr-Fe multipliers (Fen values are 2.45 or higher for low alloy steel [12] vs. a constant value of 1.49 for Ni-Cr-Fe [11]). Therefore, evaluation of the nozzle forging bounds the Ni-Cr-Fe weld material.The number of cycles for forty years was adjusted based on the number of cycles actually I experienced by the plant, projected out to 60 years of operation
[14]. In addition, VYNPS has implemented extended power uprate (EPU). These effects have been incorporated into the I evaluations documented in this report. With the use of this information, the CUF values documented in this report are applicable for 60 years of operation.
I The environmental fatigue calculations are shown in Tables 3-1 through 3-9 and summarized in I Table 3-10. Component-specific details are provided in the subsections that follow.I 3.1 Reactor Vessel Shell and Lower Head I The environmental fatigue calculations for the reactor vessel shell and lower head location are shown in Table 3-1. The limiting CUF value reported in the VY LRA for the RPV shell/bottom I SIR-07-132-NPS, Rev. 1 3-3 Structural Integrity Associates, Inc.I il head location corresponds to a point located on the outside surface of the RPV bottom head at the junction with the support skirt. Therefore, this location is not exposed to the reactor coolant, and EAF effects do not apply. Based on this, evaluation of the limiting location along the inside surface of the RPV bottom head was performed.
The calculations shown in Table 3-1 are for the RPV lower head at the area with the highest alternating stress, which represents the limiting RPV bottom head location [12]. Reference
[15]is the governing stress report for this low alloy steel location.
The design fatigue calculation for the limiting RPV lower head location is reproduced in Table 3-1. The effects of EPU as well as conservative cycle counts for 60 years of plant operation are incorporated in this table. The final results in Table 3-1 show an EAF adjusted CUF of 0.0809 for 60 years, which is acceptable (i.e., less than the allowable value of 1.0).The calculations shown in Table 3-2 are for the RPV shell at the RPV shell junction to the shroud support plate, which represents the limiting RPV shell location exposed to the reactor coolant [12]. Reference
[16] is the governing stress report for this low alloy steel location.
The design fatigue calculation for the limiting RPV shell location is reproduced in Table 3-2, which considers the effects of EPU and conservative cycle counts were used for 60 years of plant operation.
The final results in Table 3-2 show an EAF adjusted CUF of 0.7364 for 60 years, which is acceptable (i.e., less than the allowable value of 1.0).3.2 Reactor Vessel Feedwater Nozzle The environmental fatigue calculations for the reactor vessel feedwater nozzle location are summarized in Table 3-3. The calculations summarized in Table 3-3 show both the blend radius, which represents the limiting feedwater nozzle location, and the safe end. Reference
[17]contains the governing fatigue calculation for this location.
Upper RPV region chemistry was assumed for the feedwater nozzle blend radius location, since this location is exposed to the reactor water chemistry in this region, whereas feedwater line chemistry was assumed for the safe end location.SIR-07-1w32-NPS, Rev. 1 3-4 Structural Integrity Associates, Inc.
The governing fatigue calculation for the limiting feedwater nozzle locations includes the effects of EPU and cycle counts for 60 years of operation obtained from Attachment 1 of Reference[14]. The blend radius cumulative usage factor (CUF) from system cycling is 0.0636 for 60 years. The safe end CUF is 0.1471 for 60 years. Although the carbon steel safe end has a higher CUF prior to considering environmental effects, the environmental multiplier from Table 3-3 results in a higher CUF at the low alloy steel blend radius. For the safe end location, the EAF adjusted CUF is 0.2560 for 60 years. For the blend radius location, EAF adjusted CUF is 0.6392 for 60 years, which is acceptable (i.e., less than the allowable value of 1.0).3.3 Reactor Recirculation Piping (Including the Reactor Inlet and Outlet Nozzles)Three locations were identified for the reactor recirculation piping in NUREG/CR-6260:
the reactor vessel nozzle (includes both the inlet and outlet nozzles), and the recirculation piping.The evaluations for each of these components are described in the following subsections.
 
====3.3.1 Reactor====
Recirculation Piping Two locations (both stainless steel) were identified for VY for the reactor recirculation/R!-IR piping that correspond to the equivalent locations to those identified in NUREG/CR-6260:
the RI-JR return tee connection to the recirculation piping, and the valve to pipe weld at the RHR isolation valve. Reference
[ 18] contains the governing fatigue calculations for these locations.
These analyses determined the limiting location to be at the RHR return tee.The environmental fatigue calculations for the limiting recirculation/RHR piping-location is summarized in Table 3-4, which includes the effects of EPU and cycle counts for 60 years of plant operation.
A review of the shutdown cooling mode of operation since the time of recirculation piping replacement in 1986 was performed by VYNPS, and the number of cycles per loop was conservatively estimated to be 150 through Year 60 [14]. Based on this, the cycle counts for the SIR-07-132-NPS, Rev. 1 3-5 Structural Integrity Associates, Inc.I Recirculation piping were reduced by a factor of 150/300 (50%) for all transients with the exception of transients that have fewer than 10 transient cycles. To ensure this cycle reduction adequately considered the potential impact on the RHR piping, the full number of transient cycles listed in Attachment 1 of Reference
[14] was initially applied to the PIPESTRESS model and the highest CUF for the RHR piping was lower than the value obtained for the recirculation piping with reduced cycles.Due to replacement of the recirculation piping, HWC conditions exist for 39% of the time, and NWC conditions exist for 61% of the time. This is based on 17.5 years of operation with NWC between March 1986 when the piping was replaced and November 2003 when HWC was implemented, and 46 years of operation from March 1986 to the end of the period of extended operation in March 2032. Using the bounding EAF multipliers (8.36 for HWC and 15.35 for NWC) [12], the overall multiplier is 12.62. Applying this to the 60-Year CUF of 0.0590 results in a total environmentally assisted CUF of 0.7446.3.3.2 Reactor Recirculation Inlet Nozzle References
[15, 19 and 20] are the applicable stress reports for this location.
An evaluation was performed for both the inlet nozzle forging (low alloy steel) and the safe end (stainless steel).The environmental fatigue calculations for the recirculation inlet nozzle forging location are shown in Table 3-5. The governing fatigue calculation for the recirculation inlet nozzle location is reproduced in Table 3-5 [12], which includes the effects of EPU and cycle counts for 60 years of plant operation from Attachment 1 of Reference
[14]. The final results show an EAF adjusted CUF of 0.5034 for 60 years, which is acceptable (i.e., less than the allowable value of 1.0).The environmental fatigue calculations for the recirculation inlet nozzle safe end location are shown in Table 3-6. The governing fatigue calculation for the recirculation inlet nozzle location is reproduced in Table 3-6 [12], which includes the effects of EPU and cycle counts for 60 years SIR-07-132-NPS, Rev. 1 3-6 ...-V 5ruC rau ,ntegry /-SSVUIdUl.s, inc of plant operation from Attachment 1 of Reference
[14]. The final.results show an EAF adjusted CUF of 0.0199 for 60 years, which is acceptable (i.e., less than the allowable value of 1.0).3.3.3 Reactor Recirculation Outlet Nozzle 1 The recirculation outlet nozzle was evaluated for environmental fatigue effects. Reference
[24] I is the fatigue calculation for this location.
An evaluation was performed for both the outlet nozzle safe end (stainless steel) and the nozzle inner comer blend radius (low alloy steel). The results for the limiting nozzle forging location are reported here.The environmental fatigue calculations for the limiting recirculation outlet nozzle forging blend radius location are shown in Table 3-7 [24], which includes the effects of EPU and cycle counts I for 60 years of plant operation from Attachment 1 of Reference
[14]. The final results in Table 3-7 show an EAF adjusted CUF of 0.0836 for 60 years, which is acceptable (i.e., less than the 3 allowable value of 1.0).I 3.4 Core Spray Line Reactor Vessel Nozzle and Associated Class 1 Piping Locations that were evaluated in NUREG/CR-6260 included the reactor vessel nozzle blend radius (low alloy steel), the reactor vessel nozzle safe end (Alloy 600) and the core spray piping (stainless steel).Reference
[21] is the applicable fatigue calculation for these locations, which shows the nozzle i limiting location to be the blend radius. The design fatigue calculations for the limiting location at the core spray nozzle, safe end, and piping are summarized in Table 3-8 [21], which include the effects of EPU and cycle counts for 60 years of plant operation from Attachment 1 of U Reference
[14]. The cumulative fatigue usage, prior to considering environmental effects for the blend radius, is 0.0166. Factoring in the environmental multiplier from Table 3-8 [12], the EAF adjusted CUF is 0.1668 for 60 years, which is acceptable (i.e., less than the allowable value of 1.0).SIR 1 32-NPS, Rev. 1 3-7 Structural Integrity Associates, Inc.I I 3.5 RHR Return Line Class 1 Piping The environmental fatigue calculations for the RHR return line Class I piping are covered by the calculations in Subsection 3.3.1 above.3.6 Feedwater Line Class 1 Piping The environmental fatigue calculation for the limiting feedwater Class I piping location (carbon steel) is summarized in Table 3-9. The calculations shown in Table 3-9 are for the limiting feedwater Class 1 piping location.
Per Reference
[22], the limiting total fatigue usage for the analyzed feedwater/high pressure coolant injection (HPCI) piping system occurs on the riser to the RPV feedwater nozzle N4B. The limiting fatigue usage value for the feedwater Class I piping location is 0.1661, which includes the effects of EPU and cycle counts for 60 years of plant operation from Attachment I of Reference
[14]. The final results in Table 3-9 show the EAF adjusted CUF of 0.2890 for 60 years, which is acceptable (i.e., less than the allowable value of 1.0).3.7 Summary of Results The results of the calculations contained in Tables 3-1 through 3-9 are summarized in Table 3-10.It is noteworthy that the CUF results presented in this section include uniformly applied environmental effects without consideration of threshold criteria that might indicate an absence of conditions that would lead to environmental fatigue effects. Furthermore, conservative values were applied for temperature, strain rate and metal sulfur content in calculating environmental multipliers.
Therefore, the environmental adjustments to the CUF results are considered to be conservative.
SIR-07-132-NPS, Rev. 1 3-8 Structural Integrity Associates, Inc.
Table 3-1. Environmental Fatigue Evaluation for the Reactor Vessel Shell Component:
RPV Shell/Bottom Head NUREG/CR-6260 CUF: 0.032 (Wor reference only)
 
==Reference:==
 
NUREG/CR-6260, p. 5-102 Stress Report CUF: 0.0057 (for Point 14. see below)Material:
Low Alloy Steet (Matea = A-533 Gr. B)Design Basis CUF Calculation for 40 years: Ejaisgnncl/Eni, = 1.149 Power Uprate = 1.0067 K, 1.000 m = 2.0 n 0.2 S= 26,700 Conservatively used minimum E of 25.1 sImn Section 52 Appendix of RPV Stress Report.=(549 -100)/(546
-t00) per 4.4..b of 26A6019, R.e. I stress concentration factor NB1-3228.5 of ASME Code. Section III NB-3228.5 OfASME Code. Section III psi (ASME Code, Section II, Part 0)PL-PO.aQ (seeNe)44,526 K. seeVote 2) Sa, (see Ntue 3) n (see Note 4) N (see Note 5) U 1.00 25,762 200 35,300 0.0057 1 Total, U, 0 0.0057 Notes: I. PL +P8 Qis obtained for Point14 from p. A52 of VYC-378, Re. 0.2. K. cosputedin acordrance with N8-32285 ufASME Code. Section Ill.3. S, =n0.5 "K. 'It, E , 5 ,s,&deg; PowerUprate
"(PrL+Pa+).
: 4. n for 40 years is the number of Hedtup-Cooldown cycles, per p. 58 of VY'C-378, Rec. 0.5. N obtained from Figure 1-9. 1 ofAppendix I of ASME Code. Section Ill.6. n for 60 years is the projected number of Heatup-Cooldown cycles.Revised CUF Calculation for 60 Years: PL+PB+Q (see Note t) K, (see Note 2) Salt (see Note 3) n (see Note 6) N (see Note 4) U 44.526 1.00 25,762 300 35.300 0.0085 Total, Uso = 0.0085 Environmental CUF Calculation for 60 Years: Maximum F.n-.Wc Multiplier for HWC Conditions
= 5.39 Maximum F-,.rdc Multiplier for NWC Conditions
= 13.17= U 6 o x F x-Nc x 0.63 + Usn X Fo..wWC x 0.47 = 0.0809 Overall Multiplier
= Ue,.solU 6 o = 9.51 I I I I I I I I I I I I I I I SIR-07-132-NPS, Rev. I 3-9 6 Structural Integrity Associates, Inc.U I Table 3-2. Environmental Fatigue Evaluation for the Reactor Vessel Shell at Shroud Support Component:
RPV Shell at Shroud Support NUREG/CR-6260 CUF: 0.032 (forreference only)
 
==Reference:==
 
NUREG/CR-6260, p. 5-102 Stress Report CUF: 0.0549 (for Point 9, see below)Material:
Low Alloy Steel (Material A-533 Gt eI Design Basis CUF Calculation for 40 years: Hydrotest Ia =Hydrotest Ki =Stress Concentration Factor, K=Hydrotest Kq 0 =Improper Startup l-1 =Improper Startup -I =Improper Startup Skin Stress Improper Startup K",I + Skin Stress Warmup Ill, Warmup IA=Warmup KJAI, =Etoal~e c,,e)Ennaysls
=Power Uprate =In=n =26,240-1.250 2.40 62.976 28,060-1,025 156,099 223,443-5,707-102-13,696 1.0417 1.0067 2.0 0.2 26,700 psi (p. S3-97 of RPV Stress Report)psi (p. S3-97 of RPV Stress Report)(p. S3-ggd of RPV Stress Report)psi (p. S3-97 of RPV Stress Report)psi (p. S3-96 of RPV Stress Report)psi (p. S3-98 at RPV Stress Report)psi (p. S3-98 of RPV Stress Report)psi (p S3-98 of RPV Stress Report)psi (p. S3-99a of RPPV Stress Report)psi (p. $3-99a of RPV Stress Report)psi (p. S3-t9a of RPV Stress Report)30,0/28 per S3-99f of RPV Stress Report and ASME Code fatigue rome (549a- 100) /(546 -100) per 4.41 b of26A6019.
Rev. I NR-3228,5 of ASME Code, Section H/NB-3228 5 of ASME Code, Section Il psi (ASME Code. Section tt, Part 0)n (see Note 4) N (see Note 5) U 5 332 0.0151 322 8,095 0.0398 Total, U 4 0= 0.0549 S,, =PL+PB+O (see Note 5) Events K, (see Note 2) Sa&#xfd; (see Note 3)34,690 Improper Startup -Warmup 1.00 124,825 33,095 Hydrotest
-Warmup 1.00 40,804 Notes t. PL ePe .0 is computed for Point P based on the [(11, -11)e_, -(1 1, c I stress intensity 2 K. computed in accordance wth NB-32285 of ASME Code, Section IH.3. S,, = 0.5 l, *KE. -n *er ,, Power Uprate &deg;[(KH f -Iff) -(Kj,- -If) 1.4 n for 40 years is the number of cycles as follows per p S3-99e and S3P99f of the RPV Stress Report: Improper Startup = 5 cycles Hydrotest=
2 cycles Isothermal at 70'F and t,000 psi = 120 cycles (same as number of Startup events)Warmtp-Cooldown P 199 cycles Warwup-8lowdown
= I cycle TOTAL = 327 cycles 5 N obtained from Figure I-, t of Appendix I ofASME Code, Section gIl 6 n for 60 years is the projected number of cycles as follows Improper Startup = I cycles Hydrotest I cycles Isothermal at 70'F and .0e00 psi = 300 cycles (same as number of Startup events)Warmunp-Cooldown
= 300 cycles Warmup-Ptowdown
= I cycle TOTAL = 603 cycles Revised CUF Calculation for 60 Years: PL Pn+Q (see Note I) K, (see Note 2) Sail (see Note 3) n (see Note 6) N (see Note 4) U 34,690 Improper Startup -Warmup 1.00 124,825 1 332 0.0030 33,095 Hydrotest
-Warmup 1.00 40,804 602 8,095 0.0744 Total, U 0 o = 0.0774 Environmental CUF Calculation for 60 Years: Maximum Fsn.,Wc Multiplier for HWC Conditions
= 5.39 Maximum FK-nwc Multiplier for NWC Conditions
= 13.17 U_4 0 = U 6 o X F.n.,c x 0.53 + Uv o x FKeswc x 0.47 = 0.7364 Overall Multiplier
= U...o 0 0 U 0 0 o = 9.51 SIR-07-132-NPS, Rev. I 3-10 Structural Integrity Associates, Inc.
Table 3-3. Environmental Fatigue Evaluation for the Reactor Vessel Feedwater Nozzle Forging Blend Radius Low Alloy Steel. F., = exp(0.898
-0.101S*T*O*Er)
Assume S* = 0.015 (maximum)
I Assume 0N= fn(0.001)
= -6.908 (minimum)For a BWR with HWC environment (post-HWC implementation):
For a BWR with NWC environment (pre-HWC implementation):
00 = 97 ppb = 0.097 ppm. so 0= (n(0.09710.04)
= 0.886 00 = 114 ppb = 0.114 ppm, so 0* = ln(0.11410.04)
= 1.047 Thus: Thus: T (-C) T (&deg;F) F_ T ('C) T (&deg;F) F,, 0 32 2.45 0 32 2.45 50 122 2.45 50 122 2.45 100 212 2.45 100 212 2.45 I 150 302 2.45 150 302 2.45 200 392 3. 90 200 392 4.25 250 482 6.20 250 482 7.35 288 550 8.82 288 550 11.14 Thus. maximum F., 8.82 [T-= (T-150) for T l150'Cl Thus, maximum F_,= 11.14 Carbon Steel F,_ = exp(0.554
-0.101S*T*O*a)
Assume S* = 0.015 (maximum)Assume [= In(0.001)
= -6.908 (minimum)II For a BWR with HWC environment (post-HWC implementation):
For a BWR with NWC environment (pre-HWC implementation):
DO = 40 ppb = 0.040 ppm n0.050 ppm so 0* = 0 DO 40 ppb 0.040 ppm < 0.050 ppm so 0* =0 Thus: Thus: T ('C) T ('F) F,. T (-C) T ('F) F,.0 32 1.74 0 32 1.74 I 50 122 1.74 50 122 1.74 100 212 1.74 100 212 1.74 150 302 1.74 150 302 1.74 200 392 1.74 200 392 1.74 250 482 1.74 250 482 1.74 288 550 1.74 288 550 1.74 I Thus, maximum F,,= 1.74 [T'= (T-150) for T 150"Cl Thus, maximum F,. i.74 Overall 60-Year No. Component Material CUF Environmental Environmental Multiplier CUF (1,2)1 Feedwater Nozzle Forging Blend Radius Low Alloy Steel 0.0636 10.05 0.6392 2 Feedwater Nozzle Forging Safe End Carbon Steel 0.1471 1.74 0.2560 Notes: 1. An Fen Multiplier was used for each respective component with the following conditions:
+ 47% HWC conditions and 53% NWC conditions
: 2. Results using updated ASME Code fatigue calculations and actual cycles accumulated to-date and projected to 60 years.I I I I SIR-07-132-NPS, Rev. 1 3- Structural Integrity Associates, Inc.I Table 3-4. Environmental Fatigue Evaluation for the Recirculation/RHR Piping Tee Stainless Steel: F,, = exp(0.935
-T'P*O*)For a BWR with HWC environment (post-HWC implementation):
For a BWR with NWC environment (pre-HWC implementation):
DO = 46 ppb = 0.046 ppm e 0.050 ppm. so 0 = 0.260 DO = 123 ppb = 0.123 ppm -0.05 ppm, so 0* = 0.172 Conservatively use T' = 1 for T > 200oC Conservatively use T = 1 for T > 200&deg;C Thus: Thus:-E = 0 for c > O.4%/sec so F,,= 2.55 so F,, 2.55=ln(l.4) for0.0004
<= =0.4%/sec so F., ranges from 2.55 so F., ranges from 2.55 15.35 to 8.36-" = ln(0.0004/0,4) forE < 0.0004%/sec so F.. = 15.35 so P., = 8.36 Thus, maximum F., = 15.35 Thus, maximum F., = 8.36 60-Year Overall 60-Year No. Component Material CUF Environmental Environmental Multiplier CUF (1,2)1 Recirculation
/RHR Piping Return Tee Stainless Steel 0.0590 12.62 0.7446 Notes: 1. An Fe, multiplier was used for each respective component with the following conditions:
+ 39% HWC conditions and 61% NWC conditions
: 2. Results using updated ASME Code fatigue calculations and actual cycles accumulated to-date and projected to 60 years.SIR-07-132-NPS, Rev. 1 3-12 ....MF&#xfd;StucuWaiI iegrJFIy /-Vs UIdiW$, inc.
Table 3-5. Environmental Fatigue Evaluation for the Reactor Recirculation Inlet Nozzle Forging Component:
Recirculation Inlet Nozzle Forging NUREG/CR-6260 CUF: 0.310 (for reference only)
 
==Reference:==
 
NUREG/CR-6260.
: p. 5-105 Stress Report CUF: 0.0433 (updated for Point 12, see below)Material:
Low Alloy Steel. (Material
= A-508 CI. I/ perp. I-S8-4 of CBIN Stress Report Section S8)Design Basis CUF Calculation for 40 years: Efatgue _/E.n.lysis
= 1.1278 Power Uprate = 1.0067 K,= 1.660 m= 2.0 n= 0.2 S 0= 26,700= 30.0/26,6 (per p. I-$8-24 Of CBIN Stress Report Section S8 and ASSME Code fatigue curve)=(549 -100) 1(546 -100) per 4.4.1.b of 26A5019, Rev. I stress concentration factor (p. A270 of VYC-378, Rev. 0)NB-3228.5 ofASME Code, Section III NB-3228.5 of ASME Code, Section I//psi (ASME Code, Section II. Part D)PL+PS+Q (see Note 1) Skin Stress (see Note 2) Ke (see Note 3) Sb, (see Note 4) n (see Note 5) N (see Note 6) U 43,110 15,145 1.00 49,224 200 4,614 0.0433 Total, U 0  0.0433 Notess 1. PL +P8 +0 is obtained for Point 12 from p A270 of VYC-378, Rev. 0.2. Skin Stress is obtained for Point 12 from p A270 of VYC-378, Rev. 0.3. K. computed in accordance with NB-3228,5 of ASME Code. Section tIt.4. S , = 0.5 *K.
* E tat0_+_1E_
-Power Uprate -[ (P, +P +O) K, + Skin Stress .5. n for 40 years is the number of Heatup-Cootdown cycles, per p. 828 of VYC-3?8. Rev. 0.6. N obtained from Figure 1-9. of Appendix I Of ASME Code, Section Ill.7. n for 60 years is the projected number of Heatup-Cooldown cycles, Revised CUF Calculation for 60 Years: PL+PO+Q (see Note 1) Skin Stress (see Note 2) K 0 (see NOte 3) Salt (see Note 4) n (see Note 5) N (see Note 7) U 43,110 15,145 1.00 49,224 300 4,614 0.0650 Total, U, 0 = 0.0650 Environmental CUF Calculation for 60 Years: Maximum Feo-.wc Multiplier for HWVC Conditions
= 2.45 Maximum Fe.-c Multiplier for NWVC Conditions
= 12.43 U-.-o = U6e x F-&#xfd;Vwc x 0.53 + Uoo x Fe.-,wc X 0.47 = 0.5034 Overall Multiplier=
U,,.6-0/U 0 o = 7.74 I U I I I I I I I I I I I I I I I SIR-07-132-NPS, Rev. I 3-13 V StructurallIntegrity Associates, Inc.I I Table 3-6. Environmental Fatigue Evaluation for Reactor Recirculation Inlet Nozzle Safe End Component:
Recirculation Inlet Nozzle Safe End NUREG/CR-6260 CUF: 0.310 (forreference orty)
 
==Reference:==
 
NUREG/CR-6260, p. 5-105 Stress Report CUF: 00017 (updated for Location 6-i. see below)Material:
Stainless Steel (316L per p. 8 of23A4292, Re, 4)lieslutr eaSln &#xfd;ur uarcutaoton or tou years: Etigre nue/Eo, Power Upr'Iy'm = 11076 ate 1.0067 K,= 1.280 m= 1.7 no 0.3 S, = 16.600= 28,3/25.55 (per p. 62 of Reference
[18] and ASME Code fatigue curve)=(549 -100)/(546
-100) per 4.4.1.bof 26A6019, Rev. I stress concentration factor (p. 27 of VYC-378, Rev. 0)NB-3228.5 of ASME Code, Section III NB-3228.5 of ASME Code, Section III psi (ASME Code, Section 1t, Part D)n (see Note 5) N (see Note 6) U 2,076 1,242,266 0.0017 1 Total, U 4 0= 0.0017 PL+PB+Q (see Note 1) P+Q+F (see Note 2), K, (see Note 3) Sa, (see Note 4)47,183 36,972 1.00 26,385 Ntes. t+ P, +Pa +O is obtained for Surface I (after weld overlay) from p. t 170o'Reterence (18].2. P+Q+F is obtained for Point 6-1 from p. 118 of Reference
[18] (BEFORE weld overlay), 3. K computed in accordance with NB-3228.5 of ASME Code. Section Ill.4. S 5' Kz 0  E5r,- n ,Y,,,
* Power Uprate
* I (P +Q +F) K, ].5. n for 40 years is the number of cycles as follows per p. 826 of VYC-378, Rev, 0:--sign Hydrotest
= 130 Lens of Feedoompn Comoitie: Startup/Shutdown
= 290 SRV Slowdown = 8 i Loss of Feedwater Pumps 30 1I10 events a 3 up/down cycles per event SCRAM 270........ .... ........ .. ..........................
...... ..... .... s. -....... ....... ... .o..... ... .......Normal +/. Seismic = I1 10 cycles of upset seismic. plus I Level C seismic event Normal = 739 = Sum of al of above events Zeroload = 598 = Startup/Shutdown
+ SRV 0lowdown + Scram + LOFP Total number of cycles = 2,076 6. N obtained from Figure /-9.2 of Appendix I of ASME Code, Section Itl.7. n for 60 years is the projected number of cycles as follows: Oensign Hyd. tenl 1 20 Loss of Feedopmon Composite:
Startup/Shutdown
= 300 SRBV 81odow~ t 1 Loss of Feedwaler Pumps 30 o10 events x 3 up/down cycles per event sCRAM= 288 tiAl remaining scrams Normal +/- Seismic = f I Assume the same Normal = 751 = Sum of all of above events Zeroload = 620 = Startup/Slhutdown
+ SRV Blowdown + Scram + LOFP Total number of cycles = 2.122 Revised CUF Calculation for 60 Years:.PL0-P Q (see Note 1) P+Q+F (see Note 2) K, (see Note 3) S,&#xfd; (see Note 4) n (see Note 5) N (see Note 7) U 47,183 36,972 1.00 26,385 2,122 1,242,266 0.0017 I Total, U 6 0 = 0.0017 Environmental CUF Calculation for 60 Years: Maximum Feen.WC Multiplier for HWC Conditions
= 15.35 Maximum F.-nWC Multiplier for NWC Conditions
= 8.36 Ue.6 o = U. x F-AVOC x 0.53 + U,, x F..... x 0.47 = 0.0199 Overall Multiplier=
Un vso/U 6 o = 11.64 SIR-07-132-NPS, Rev. I 3-14 Structural Integrity Associates, Inc.
Table 3-7. Environmental Fatigue Evaluation for Recirculation Outlet Nozzle Forging Low Alloy Steel: F_ = exp(0.898
-O.1O1S*T*O'&#xfd;*)
Assume S' = 0.015 (maximum)Assume E- = In(O.001)
= -6.908 (minimum)For a BWR with HWC environment (post-HWC implementation):
For a BWR with NWC environment (pre-HWC implementation):
0O = 46 ppb = 0.046 ppm DO = 123 ppb = 0.123 ppm, soO = In(0.12310.04)
= 1.123 DO 0.050 ppm, so 0* 0 Thus: Thus: T (&deg;C) T (F) F_, T ('C) T (-F) F,, 0 32 2.45 0 32 2.45 50 122 2.45 50 122 2.45 100 212 2.45 100 212 2.45 150 302 2.45 150 302 2.45 200 392 2.45 200 392 4.42 269.45 517.01 2.45 269.45 517.01 10.00.288 550 2.45 288 550 12.43 Thus, maximum F., 2.45 lT= (T-150) for T s150C] Thus, maximum F., 12.43 60-Year Overall 60-Year No. Component Material CUF Environmental Environmental Multiplier CUF (1,2)1 Recirculation Outlet Nozzle Forging Blend Radius Low Alloy Steel 0.0108 7.74 0.0836 Notes: 1. An F-. multiplier was used for each respective component with the following conditions:
+ 47% HWC conditions and 53% NWC conditions
: 2. Results using updated ASME Code fatigue calculations and actual cycles accumulated to-date and projected to 60 years.SIR-07-132-NPS, Rev. 1 3-15 V Structural Integrity Associates, Inc.
Table 3-8. Environmental Fatigue Evaluation for Core Spray Reactor Vessel Nozzle Forging Blend Radius, Safe End, and Piping Low Alloy Steel: F_. = eep(O.898
-0.101S*T'O*')
Assume S = 0.015 (maximum)Assume -= ln(O.001)
= -6.908 (minimum)For a BWR with HWC environment (post-HWC implementation):
For a BWR with NWC environment (pre-HWC implementation):
DO = 97 ppb = 0.097 ppm. so O* =ln(0.097/0.04)
= 0.886 00 = 114 ppb = 0.114 ppm, sOO = In(0.11410.04)
= 1.047 Thus: Thus: T (-C) T ('F) F,, T (-C) T (F) F,_0 32 2.45 0 32 2.45 50 122 2.45 50 122 2.45 100 212 2.45 100 212 2.45 150 302 2.45 150 302 2.45 200 392 3.90 200 392 4.25 250 482 6.20 250 482 7.35 288 550 8.82 288 550 11.14 Thus. maximum F-, = 8.82 lT'&#xfd; (T-150) fo T' 150'CI Thus, maximum F.,= 11,14 Stainless Steel: F,_ exp(0.935
-T*&deg;*0*)For a BWR with HWC environment (post-HWC implementation):
For a BWR with NWC environment (pre-HWC implementation):
DO = 97 ppb = 0.097 ppm ' 0.050 ppm, so O* = 0172 00 = 114 ppb = 0.114 ppm -0.05 ppm. so O0 = 0172 Conservatively use T* = 1 for T -200'C Conservatively use T* = 1 for T > 200&deg;C Thus: Thus: 0Olor' S0.4%/sec so F_, 2.55 so F_= 2.55-ln(&deg;/0.4) for 0.0004 -= I= 0.4%/sec so F., ranges from 2.55 so F.n ranges from 2.55 to 8.36 to 8.38__ " -n _- -_ ----- --------- --- -----se ..... .... ........ ....... .. .........s --- -- -- =i ... ...................
... ...... ..........
................
........ ..........................
.... ...8 3 .........
..............
_ .... ..... ... ................
... -to -- 8.36 ----ln(0.0004/0.4) for u0.0004%/sec so F,, = 8.36 .so F_, = 8.36 Thus. maximum F_, = 8,36 Thus, maximum F., = 8.36 Overall 60-Year No. Component Material CUF Environmental Environmental Multiplier CUF (1,2)1 Core Spray Nozzle Forging Blend Radius Low Alloy Steel 0.0166 10.05 .0.1668 2 Core Spray Nozzle Safe End Ni-Cr-Fe 0.0398 1.49 0.0593 3 Core Spray Piping Stainless Steel 0.0011 8.36 0.0092 Notes: 1. An Fen Multiplier was used for each respective component with the following conditions:
+ 47% HWC conditions and 53% NWC conditions
: 2. Results using updated ASME Code fatigue calculations and actual cycles accumulated to-date and projected to 60 years.SIR-07-132-NPS, Rev. 1 3-1,16 r Structural Integrity Associates, Inc.
Table 3-9. Environmental Fatigue Evaluation for the Feedwater Line Class I Piping Carbon Steel: F., = exp(0.554
-0.101S*T*O%')
Assume S* = 0.015 (maximum)Assume E' = ln(0.001)
= -6.908 (minimum)For a BWR with HWC environment (post-HWC implementation):
For a BWR with NWC environment (pre-HWC implementation):
DO = 40 ppb = 0.040 ppm G 0.050 ppm so O = 0 DO = 40 ppb = 0.040 ppm < 0.050 ppm so O* =0 Thus: Thus: T ('C) T (&deg;F) F.. T (-C) T ('F) F,, 0 32 1.74 0 32 1.74 50 122 1.74 50 122 1.74 100 212 1.74 100 212 1.74 150 302 1.74 150 302 1.74 200 392 1.74 200 392 1.74 250 482 1.74 250 482 1.74 288 550 1.74 288 550 1.74 Thus. maximum F,, = 1.74 (T'= (T-150) for T 150-C) Thus. maximum F., = 1.74 60-Year Overall 60-Year No. Component Material CUF Environmental Environmental Multiplier CUF (1,2)1 Feedwater Piping Riser to RPV N~oze N4AB Carbon Steel 0.1661 1.74 0.2890 Notes: 1. An Fenmultiplier was used for each respective component with the following conditions:
+ 47% HWC conditions and 53% NWC conditions
: 2. Results using updated ASME Code fatigue calculations and actual cycles accumulated to-date and projected to 60 years.SIR-07-132-NPS, Rev. I 3-17 Structural Integrity Associates, Inc.
Table 3-10. Summary of Environmental Fatigue Calculations for VYNPS Overall 60-Year 40-Year Design 60-Year Ovrl 0Ya 40-Yar Dsig 60-earEnvironmental Environmental No. Component Material CUF (13 CUF (2 ronmental CUF_______________
______ Multiplierl'I CUIF 1 RPV Shell/Bottom Head Low Alloy Steel 0.0057 0.0085 9,51 0.0809 2 RPV Shell at Shroud Support Low Alloy Steel 0.0549 0.0774 9.51 0.7364 3 Feedwater Nozzle Blend Radius Low Alloy Steel (4) 0.0636 10.05 0.6392 4 Recirculation/RHR Class I Piping (Return Tee) Stainless Steel (4) 0.0590 12.62 0.7446 5 Recirculation Inlet Nozzle Forging Low Alloy Steel 0.0433 0.0650 7.74 0.5034 6 Recirculation Inlet Nozzle Safe End Stainless Steel 0.0017 0.0017 11.64 0.0199 7 Recirculation Outlet Nozzle Forging Low Alloy Steel (4) 0.0108 7.74 0.0836 8 Core Spray Nozzle Forging Blend Radius (5) Low Alloy Steel (4) 0.0166 10.05 0.1668 9 Feedwater Class 1 Piping Carbon Steel (4) 0.1661 1.74 0.2890 Notes: 1. Updated 40-year CUF calculation based on recent ASME Code methodology and design basis cycles.2. CUF results using updated ASME Code methodology and actual cycles accumulated to-date and projected to 60 years, 3. An Fe_ multiplier was used for each respective component with the following conditions:
+ 47% HWC conditions and 53% NWC conditions
: 4. 40 year values were not calculated for these locations 5. Only the highest CUE from Table 3-8 is shown SIR-07-132-NPS, Rev. 1 3-18 Structural Integrity Associates, Inc.
4.0
 
==SUMMARY==
AND CONCLUSIONS The results of Tables 3-1 through 3-9, as summarized in Table 3-10, demonstrate that the fatigue usage factor, including environmental effects, remains within the allowable value of 1.0 for 60 years of operation for the following component locations:
/Reactor vessel shell, bottom head and shroud support Reactor vessel feedwater nozzle Reactor recirculation piping (including the reactor inlet and outlet nozzles)Core spray line reactor vessel nozzle and associated Class I piping Feedwater line Class 1 piping Therefore, the environmental fatigue assessment results for all of the NUREG/CR-6260 locations associated with the older vintage BWR plant are acceptable for 60 years of operation for VYNPS.I I I I I I I I U U I I I I I I I I I SIR-07-132-NPS, Rev. I 4-1 V Structural Integrity Associates, Inc.
 
==5.0 REFERENCES==
: 1. U. S. Nuclear Regulatory Commission, Generic Safety Issue 166, "Adequacy of Fatigue Life of Metal Components." 2. U. S. Nuclear Regulatory Commission, Generic Safety Issue 190, "Fatigue Evaluation of Metal Components for 60-Year Plant Life." 3. SECY-95-245, "Completion of the Fatigue Action Plan," James M. Taylor, Executive Director for Operations, U. S. Nuclear Regulatory Commission, Washington, DC, September 25, 1995.4. Memorandum, Ashok C. Thadani, Director, Office of Nuclear Regulatory Research, to William D. Travers, Executive Director for Operations, Closeout of Generic Safety Issue 190, "Fatigue Evaluation of Metal Components for 60 Year Plant Life," U. S. Nuclear Regulatory Commission, Washington, DC, December 26, 1999.5. NUREG-1801, Revision 1, "Generic Aging Lessons Learned (GALL) Report," U.S.Nuclear Regulatory Commission, September 2005.6. NUREG/CR-6260 (INEL-95/0045), "Application of NUREG/CR-5999 Interim Fatigue Curves to Selected Nuclear Power Plant Components," March 1995.7. NUREG/CR-6583 (ANL-97/18), "Effects of LWR Coolant Environments on Fatigue Design Curves of Carbon and Low-Alloy Steels," March 1998.8. NUREG/CR-5704 (ANL-98/3 1), "Effects of LWR Coolant Environments on Fatigue Design Curves of Austenitic Stainless Steels," April 1999.9. NUREG/CR-5999 (ANL-93/3), "Interim Fatigue Design Curves for Carbon, Low-Alloy, and Austenitic Stainless Steels in LWR Environments," April 1993.10. USAS B31.1 -1967, USA Standard Code for Pressure Piping, "Power Piping," American Society of Mechanical Engineers, New York.11. EPRI Report No. TR-105759, "An Environmental Factor Approach to Account for Reactor Water Effects in Light Water Reactor Pressure Vessel and Piping Fatigue Evaluations," December 1995.12. Structural Integrity Associates Calculation No. VY-16Q-303, Revision 0, " Environmental Fatigue Evaluation of Reactor Recirculation Inlet Nozzle and Vessel Shell/Bottom Head." SIR-07-132-NPS, Rev. 1 5-1 Structural Integrity Associates, Inc.
: 13. INFORMATION REDACTED 14. Entergy Design Input Record (DIR) Rev. 1, EC No. 1773, Rev. 0, "Environmental Fatigue Analysis for Vermont Yankee Nuclear Power Station," 7/26/07, SI File No. VY-16Q-209.
: 15. VY Calculation No. VYC-378, Revision 0, "Vermont Yankee Reactor Cyclic Limits for Transient Events," 10/16/85, SI File No. VY-05Q-21 1.16. Chicago Bridge & Iron RPV Stress Report, Section S3, Revision 4, "Stress Analysis,Shroud Support, Vermont Yankee Reactor Vessel, CB&I Contract 9-6201," 2/3/70, SI File No. VY-16Q-203.
: 17. Structural Integrity Associates Calculation No. VY-16Q-302, Revision 0, "Fatigue Analysis of Feedwater Nozzle." 18. Structural Integrity Associates Calculation No. VY-16Q-307, Revision 0, "Recirculation Class I Piping Fatigue and EAF Analysis." 19. CB&I RPV Stress Report, Section S8, Revision 4, "Stress Analysis, Recirculation Inlet Nozzle, Vermont Yankee Reactor Vessel, CB&I Contract 9-620i1," 2/3/70, SI File No.VY- 16Q-203.20. GE Nuclear Energy Certified Stress Report No. 23A4292, Revision 0, "Reactor Vessel -Recirculation Inlet Safe End Nozzle," January 21, 1985, SI File No. VY-16Q-203.
: 21. Structural Integrity Associates Calculation No. VY-I 6Q-3 10, Revision 1, "Fatigue Analysis of Core Spray Nozzle." 22. Structural Integrity Associates Calculation No. VY-I 6Q-31 1, Revision 0, "Feedwater Class I Piping Fatigue Analysis." 23. EPRI/BWRVIP Memo. No. 2005-271, "Potential Error in Existing Fatigue Reactor WaterEnvironmental Effects Analyses," July 1, 2005 24. Structural Integrity Associates Calculation No. VY-16Q-306, Revision 0, "Fatigue Analysis of Recirculation Outlet Nozzle." SIR-07-132-NPS, Rev. 1 5-2 Structural Integrity Associates, Inc(such information is marked with a "bar" in the right-hand margin) 3 I NEC-JH_19 Structural IntegrityAssociates, Inc. File No.: VY-19Q-301 CALCULATION PACKAGE Project No.: VY-19Q PROJECT NAME: Provide VY Support for Questions Related to Environmental Fatigue Analyses CONTRACT NO.: 10163217 CLIENT: PLANT: Entergy Nuclear Operations, Inc. Vermont Yankee CALCULATION TITLE: Design Inputs and Methodology for ASME Code Confirmatory Fatigue Usage Analysis of Reactor Feedwater Nozzle Doc:ment Affected Project Manager Preparer(s)
&D ein Revision Description Approval Checker(s)
Revision Pages Signature
& Date Signatures
& Date 0 1-18 Original Issue Computer Files J Ierrmann WF Weitze TJ.1IHI1P/,2008 WFW 01/29/2008 A. Chintapalli AC 0 1/2n/2008 Page 1 of 18 F0306-01 RO Structural Integrity Associates, Inc.Table of Contents 1.0 O B JE C T IV E .................................................................................................................................
3 2.0 METHODOLOGY
............................................................................................................
3 3.0 ASSUMPTIONS/DESIGN INPUTS .................................................................................
4 4.0 C A L C U L A T IO N S ......................................................................................................................
13 5.0 RESULTS OF ANALYSIS ..................................................................................................
17
 
==6.0 REFERENCES==
 
..........
...............................................
18 List of Tables T ab le 1 : T ran sien ts ...............................................................................................................................
5 Table 2: Properties of Liquid W ater ...............................................................................................
8 Table 3: Properties of Saturated Steam .................................
I ......................................................
8 Table 4: Forced Flow and Natural Circulation Heat Transfer Coefficients, Btu/hr-ft 2-&deg;F ...................
8 Table 5: Temperature-Dependent Material Properties
.................................................................
10 Table 6: Condensation Heat Transfer Coefficients, Btu/hr-ft 2_-F ................................................
13 Table 7: Membrane Plus Bending Stresses Due to Piping Loads ................................................
14 List of Figures U Figure 1: Nozzle and Vessel Wall Thermal and Heat Transfer Boundaries
.........................
9 Figure 2: Safe End L inearization Path ................................................................................................
11 Figure 3: Nozzle Comner Linearization Path .................................................................................
I1 Figure 4: Coordinate System for Forces and Moments .................................................................
14 Figure 5: Reducer Geometry Parameters
.......................................................................................
15 Figure 6: FW Nozzle Safe End Geometry .....................................................................................
16 3 FileNo.: VY-19Q-301 Page 2 of 18 Revision:
0 F0306-01 RO Structural Integrity Associates, Inc.1.0 OBJECTIVE The objective of this calculation package is to establish the design inputs and methodology to be used for an ASME Code, Section III fatigue usage calculation of the reactor pressure vessel (RPV)feedwater (FW) nozzle at VennontYankee Nuclear Power Station (VYNPS).2.0 METHODOLOGY A detailed fatigue usage analysis of the FW nozzle will be performed using the methodology of Subarticle NB-3200 of Section III of the ASME Code [1]. The analysis will be used as a confirmatory analysis for comparison with&#xfd; a previous fatigue usage analysis that was done using simplified methods. Therefore, only the fatigue portion of the ASME Code methodology will be used, and the analysis will be a fatigue assessment only, and not a complete ASME Code analysis.Finite element analysis will be perfomried using a previously-developed axisymmetric finite element model (FEM) of the FW nozzle. Thermal transient analysis will be performed using the FEM for each defined transient.
ConcurTent with the thermal transients are pressure and piping interface loads; for these loads, unit load analyses (finite element analysis for pressure, and manual calculations for piping loads) will be performed.
The stresses from these analyses will be scaled appropriately based on the magnitude of the pressure and piping loads during each thermal transient, and combined with stresses fromthe thermal transients.
Additional scaling of pressure stresses will be performed to account for nozzle comer contour effects (i.e., the effects of approximating the nozzle-to-RPV intersection of two cylinders with an axisyrnmetric model). Other stress concentration factors (SCFs) will be applied as appropriate.
All six components of the stress tensor will be used for stress calculations.
The stress components for the non-axisymmetric loads (shear and moment piping loads) can have opposite signs depending upon which side of the nozzle is being examined.
Therefore, when combining stress components from these loads with stress components from thermal transients and other loads, the signs of the stress components will be adjusted to maximize the magnitude of the stress component ranges.The fatigue analysis will be performed at previously-examined locations for direct comparison of results. Stresses will be linearized at these locations.
The linearized primary plus secondary membrane plus bending stress will be used to determine the value of K, to be used in the simplified elastic-plastic analysis in accordance with ASME Code NB-3200 methodology.
Enviromnental fatigue multipliers will be applied in accordance with NUREG/CR-6583
[15].File No.: VY-19Q-301 Page 3 of 18 Revision:
0 F0306-O1 RO Structural Integrity Associates, Inc.3.0 ASSUMPTIONS/DESIGN INPUTS 3.1 Assumptions
: 3.1.1 Power uprate effects are con'sidered as being applied to the entire period of operation.
The higher pressures, flows, and temperatures at uprate conditions are used in determining and applying heat transfer coefficients
[3, Section 3.2] [2, Section 3.1].3.1.2 The Boltup transient
[2, Tables I and 2] analysis does not affect the FWnozzle and is therefore excluded from the transients analyzed.3.1.3 Where the flow rates in the thermnal cycle diagram are at a value not calculated in Table 2, the next highest flow rate heat transfer coefficient will be used. This results in a higher heat transfer coefficient and is therefore conservative.
3.1.4 The effect of non-uniform geometries isjudged to be insignificant forflow inside the safe end, because of the smooth transition and small geolnetiy changes as shown in Figure 6. The smaller inner diameter (9.669') at the safe end was used to calculate heat transfer coefficients, resulting in a higher flow velocity and therefore conservative values.3.1.5 The annulus leakage.flow rate used is 31 GPMfor EPU conditions
[3, Section 3.2].3.1.6 Density and Poisson's ratio'used in the FEM are assumed typical values of p = 0. 283 lb/in 3 and 0.3, respectively.
3.1.7 For purposes of linearizing stress at the nozzle corner, the effect of the cladding is.conservatively neglected.
 
====3.1.8 Stress====
components due to piping loads are scaled assuming no stress occurs at an ambient temperature of 70&deg;F and the full values are reached at react Ir design temperature, 575TF, as was done in the previous analysis [2, Section 3.4]-3.2 ASME Code Edition The analysis will be performed in a manner consistent with the fatigue usage rules in NB-3200 of Section III of the ASME Code; the 1998 Edition with Addenda through 2000 [1] will be used, for consistency with the previous analysis'
[2].3.3 Transients Previously developed thermal and pressure transients
[2, Section 3.1 and Tables 1 and 2] are used for this analysis.
The transients to be evaluated are shown in Table 1. For each transient, the time, nozzle fluid temperature (Tnz), RPV'pressure, percent FW flow rate, and number of cycles are included.
In some cases, flow rates and Tn 0 6 values from the nozzle thermal cycle diagram [10, Attachment 1, p. 3] are used to reduce excess conservatism.
Note that the only difference between the nozzle comer and the safe end transients.in the referenced document is the length of the steady state time increment used at the end of the transients.
These steady state periods are not included in Table I; the analyst will use a value greater than or equal to the largest steady time increment from the referenced document.At the inside surface of the RPV, the Region A temperature from the reactor thermal cycle diagram[10, Attachlnent 1, p. 2] shall be applied. Table 1 also includes these values as Tppv.File No.: VY-19Q-301 Page 4 of 18 Revision:
0 F0306-O1RO Structural Integrity Associates, Inc.Table 1: Transients Time, FW Transient see Tn.., OF TRPv, 'F P, psig Flow, % Cycles 1. Boltup 0 70 70 0 0% 123 2. Design Hydrotest 0 70 70 0 0% 120 1080 100 100 0 0%1680 100 100 1100 0%5280 100 100 1100 0%5880 100 100 50 0%3. Startup 0 100 100 50 0% 300 16164 549 549 1010 0%4. Turbine Roll and 0 549 549 1010 0% 300 Increased to Rated 1 100 549 1010 25%*Power 1801 100 549 1010 25%*1802 260 549 1010 25%*3602 392 549 1010 100%5. Daily Reduction 0 392 549 1010 100% 10,000 75% Power 900 310 549 1010 100%*2700 310 549 1010 100%*3600 392 549 1010 100%6. Weekly Reduction 0 392 549 1010 100% 2,000 50% Power 1800 280 549 1010 100%*3600 280 549 1010 100%*5400 392 549 1010 100%9. Turbine Trip at 0 392 549 1010 100% 10 25% Power 1800 265 549 1010 100%1980 265 549 1010 25%*2340 90 549 1010 25%*2520 90 549 1010 25%*3420 265 549 1010 25%*3600 265 549 1010 100%5400 392 549 1010 100%10. FW Heater 0 392 549 1010 100% 70 Bypass 90 265 549 1010 100%1890 265 549 1010 100%2070 392 549 1010 100%File No.: VY-19Q-301 Revision:
0 Page 5 of 18 F0306-01RO Structural Integrity Associates, Inc.Transient 11. Loss of FW Pumps Time, sec 0 1 3.5 4.5 13.5 184.5 1564.5 1565.5 2165.5 2166.5 2346.5 5406.5 5407.5 6727.5 6728.5 7148.5 7448.5 11048.5 16411.5 16412.5 18212.5 18213.5 20013.5 20014.5: 21814.5.Tloz, OF 392 565 565 50 50-50 440 565 565 50 50 440 549 565 50.50 300 400 549 549 549 100 100 260 392 TRp\,, OF 549 565 565 565 565 565 565 565 565 565 532 549 549 565 565 502 502 400 549 549 549 549 549 549 549 P, psig 1010 1010 1190 1184.5 1135 1135 1135 1135 1135 1135 885 1055.1055 1135 1135 675 675 232 885 1010 1010 1010 1010 1010 1010 FW Flow, %100%0%0%40%40%40%0%0%0%40%*&#xfd;40%*0%0%0%25%*25%*0%0%0%0%0%25%*25%*25%*100%Cycles 10 12/13/15.
Turbine 0 392 549 1010 100% 289 Generator Trip, 10 392 565/600**
1135/1375**
100%Reactor Overpressure, 15 392 565/600**
1135/1375**
100%Other SCRAMs 30, 392 539 940 100%90 275 539 940 25%*990 100 539 940 25%*2790 100 539 940 25%*2791 260 539 940 100%3210 291 549 1010 100%4591 392 549 1010 100%14. SRV Blowdown 0&#xfd; 392 549 1010 100% 1 60 275 531.6 885 100%960 100 365 50 25%*19. Reduction to 0% 0t 392 549, 1010 100% 300 Power 1800 265 549 1010 25%*20. Hot Standby 0 265 549 1010 25%* 300 (Heatup Portion) *1" 440 549 1010 0%3925 549 549 1010 0%20A. Hot Standby 0. 549 549 1010 0% 300 (FW Injection Portion) 1 100 549 1010 25%181 100 549 1010 25%241' 290 549 1010 0%451 549 549 1010 25%21-23. Shutdown 0' 549 549 1010 25%* 300 6264 375 375 50 25%*6864, 330 330 50 25%*15144 1 00 100 50 .0%I I I I I I I I I I I I I U I I I I I File No.: VY-19Q-301 Revision:
0 Page 6 of 18 F0306-01 R0 Structural Integrity Associates, Inc.Time, FW Transient sec ToZ, OF T OF P, psig Flow, % Cycles 24. Hydrostatic Test 0 100 100 50 0% 1 600 100 100 1563 0%1200 100 100 1563 0%1800 100 100 50 0%25. Unbolt 0 100 100. 0 0% 123.1080 70 70 0 0%* Flow rate is conservatively rounded up to one of the three flow rates considered (25%, 40%, 100%).** The second value applies for one cycle; the first value applies for the rest of the cycles.3.4 Heat Transfer Coefficients, Condensation When steam floods a relatively cold component, the steam condenses on the component surface.Holnan [5, p. 413] gives the following equation for average heat transfer coefficient:
h = 0.555 {p(p -pv)gk 3 h' g/[VLD(Tg
-T,)]} ') , where p = mass density of liquid, PV = mass density of vapor, g = acceleration of gravity, k = conductivity of liquid at average temperaturle, h'fg hfg + 0.68c(Tg -Yw), hfg = heat of condensation at vapor temperature, c = specific heat of liquid at average temperature, Tg = saturated vapor temperature
= Tfmai, T= pipe inner wall temperature
= Tinitial, l.t = viscosity of liquid at average temperature D = inner diameter of pipe The portion of the equation inside the brackets, p(p -pv)gk 3 h'fg/[l-tD(Tg
-T,)], has the following units: (ft 3)2 (sec 2)(Btu)3 (hr-ft-OF) 3 (Btu)(OF)(ft-hr)(Ibm) (ft)(OF)(BtU 4)(36002 se)(hr)12960000 Btu 4 hr4_ft _OF 4 After taking the fourth root, this becomes 60 Btu/hr-ft 2-0 F. Steam properties are interpolated at Tg, and water properties are interpolated at Tf, which is taken as the average of Tg and T,. Then, h'f, and heat transfer coefficient h are calculated for each set of steam properties, water properties, Tg and T,.Tables 2 and 3 list selected properties of liquid water [12, Table 1-8] and saturated steam [13], respectively.
File No.: VY-19Q-301 Revision:
0 Page 7 of 18 F0306-01RO V Structural Integrity Associates, Inc.Table 2: Properties of Liquid Water c T, 'F 300 400 500 600 Ibm/ft 3 57.3 53.6 49.0 42.4 Btu/Ibm-OF 1.03 1.08 1.19 1.51 III Ibm/ft-hr 0.468 0.335 0.252 0.208 V, ft 2/sec 2.27E-06 1.74E-06 1.43E-06 1.37E-06 k, Btu/hr-ft-OF 0.395 0.382 0.349 0.293 Table 3: Properties of Saturated Steam T,, &deg;F v,, ft 3 flbm hr, Btu/Ibm 545 0.4449 649.6 550 0.4249 641.6 565 0.3703 616.4 3.5 Heat Transfer Coefficients, Forced Flow and Natural Circulation Table 4 summarizes the force flow and natural circulation heat transfer coefficients to be used in the analysis [3, Section 3.2.1]. For each. flow rate, values are taken at 300'F as in the previous analysis.These values are within 11% of the maximum values for a given flow rate, and are more than 30%greater than the minimum values for a given flow rate [3, Table 4] [4, Tables 4 and 5]. Therefore, the use of heat transfer coefficients at 300'F is bounding for the most severe transients, which occur at a wide range of temperatures.
Figure 1 illustrates the heat transfer coefficient regions [4, Figure 6].Table 4: Forced Flow and Natural Circulation Heat Transfer Coefficients, Btu/hr-ft 2-IF I I I I I I I I I Region 1 2 3 4 5 6 100% flow 3705 1489 177 40% flow 25% flow 1780 1222 0% flow, water 144 109 12 743 89 504 60 7 864 864 "864 864 8 0.2 0.2 0.2 0.2* Linearly transition between the values for the adjacent regions.File No.: VY-19Q-301 Revision:
0 Page 8 of 18 F0306-0 I RO I I
: Structural Integrity Associates, Inc.Region 7 Region 8-F RegioRgio 4.~ ItI A B c Reg [n 5 Region 6 E Notes: Point A: Point B: Point C: Point D: Point E: Point F: End of thermal sleeve = Node 204 = 0.25" from feedwater inlet side of thermal sleeve flat.Beginning of annulus = Node 252.Beginning of thermal sleeve transition
= approximately 4.0" from Point A = Node 294.End of thermal sleeve transition
= approximately 9.5" from Point A = Node 387.End of inner nozzle corner (nozzle side) = Node 553.End of inner nozzle corner (vessel wall side) = Node 779.Figure 1: Nozzle and Vessel Wall Thermal and Heat Transfer Boundaries
 
===3.6 Finite===
Element Model The ANSYS program [6] will be used to perform the finite element analysis.
A previously-developed axisyrmnetric model will be used [4, file FW.INP], except that temperature-dependent material properties will be used. Table 5 shows the applicable material properties
[14].File No.: VY-19Q-301 Revision:
0 Page 9 of 18 F0306-OIRO Structural Integrity Associates, Inc.Table 5: Temperature-Dependent Material Properties Mean Young's Coefficient of Conductivity, Diffusivity, Specific Heat, Material Description Tempera- Modulus, Thermal k d .m No. ture, 'F E x 106 Expansion, (BTU/hr-ft-&deg;F) (ft 2/hr) (BTU/ibm-*F)(psi) Ct x 10.6 (see Note 1) (see Note 5)(in/in-0 F)SA533 Grade B, 70 27.8 6.4 23.5 0.458 0.105 A508 Class 11 200 27.1 *6.7 23.6 0.425 0.114 (see Note 2) 300 26.7 6.9 23.4 0.401 0.119 400 26.1 7.1 23.1 0.378 0.125 500 25.7 7.3 22.7 0.356 0.130 600 25.2 7.4 22.2 0.336 0.135 2 SS Clad 70 28.3 8.5 8.6 0.151 0.116 (see Note 3) 200 27.6 8.9 9.3 0.156 0.122 300 27.0 9.2 9.8 0.160 0.125 400 26.5 9.5 10.4 0.165 0.129 500 25.8 9.7 10.9 0.170 0.131 600 25.3 9.8 11.3 0.174 0.133 3 A508 Class 1 70 29.3 6.4 35.1 0.695 0.103 (see Note 4) 200 28.6 6,7 33.6 0.613 0.112 300 28.1 6.9 32.3 0.561 0.118 400 27.5 7.1 30.9 0.512 0.123 500 27.1 7.3 29.5 0.472 0.128 600 26.5 7.4 28.0 0.433 0.132 4 A106 Grade B 70 29.3 6.4 35.1 0.695 0.103 (see Note 4) 200 28.6 6.7 33.6 0.613 0.112 300 28.1 6.9 32.3 0.561 0.118 400 27.5 7.1 30.9 0.512 0,123 500 27.1 7.3 29.5 0,472 0.128 600 26.5 7.4 28.0 0.433 0.132 Notes: L. Convert to BTU/sec-in-&deg;F for input to ANSYS.I I I I I I I I I I I I I I I I I I I 2.3.4.5.Properties of A508 Class I1 are used (3/4Ni-1/2Mo-lI/3Cr-V).
Properties of 18Cr -8Ni austenitic stainless steel are used.Composition
= C-Si; k and d for plain carbon steel are used [II].Calculated as [k/(pd)]/12 3.Stresses will be extracted and linearized at two locations, both on the inside surface. The critical safe end location is Node 192, which has the highest stress intensity due to thermal loading under high flow conditions
[3, Section 4.0 and Figures 6 and 7]. The corresponding linearization path is from Node 192 to Node 187 (Figure 2 [3, Figure 7]).The critical nozzle corner location is Node 657 at the base metal of the nozzle, chosen based upon the highest pressure stress [3, Section 4.0 and Figures 8 and 9]. The corresponding linearization path is from Node 657 to Node 645 (Figure 3 [3, Figure 9]).File No.: VY-19Q-301 Revision:
0 Page 10 of 18 F0306-01 RO Structural Integrity Associates, Inc.Feedwater Nozzle Finite Element Model Figure 2: Safe End Linearization Path MAR 19 2007 13:36:47 Feedwater Nozzle Finite Element Model Figure 3: Nozzle Corner Linearization Path File No.: VY-19Q-301 Page 11 of 18 Revision:
0 F0306-OIRO I Structural Integrity Associates, Inc.3.7 Nozzle Corner Effects The axisymrnetric model has the effect of modeling the cylindrical RPV as spherical.
To partially counter the resulting reduction in stress in the RPV wall, the radius in the model was increased by a factor of 1.5 [3, p. 8]. This yields a general membrane stress that equals the average of the hoop and axial stress for the cylinder.
I Stresses from the axisymmetric analysis will need to be increased to account for the three-dimensional (3-D) geometry.
A factor of 1.333 has been established in a previous calculation I package that modeled the nozzle [3, p. 9], to achieve an overall pressure multiplication of 2.0. This is consistent with the maximum value used in prior VYNPS analyses [7, Appendix A, p. 4-10].No other SCF is required at the nozzle corner inside surface, since this location has no stress riser.3.8 Piping Interface Loads I The previous analysis of the FW nozzle calculated membrane axial and shear stresses due to the piping interface loads by closed fonrin solution, then combined them into stress intensities for the two locations of interest [2, Section 3.4]. All shear stresses were treated as existing in the same plane.In this analysis, the stress components are recalculated in Section 4.3 taking into account through-wall distribution.
Forces and moments are taken from the same reference as before [8, Table 3].3.9 SCFs, Safe End In the previous analysis, an SCF of 1.34 was used for the safe end location for all load conditions
[2]. That value was obtained from the original design basis evaluation for the FW nozzle. For the current analysis, the SCF is updated to reflect modem-day ASMiE Code fatigue usage analysis I methodology for consistency with the rest of the evaluation.
At the safe end inside surface, guidance is taken from the piping analysis rules in Subarticle NB-3600 of Section III of the ASME Code [1]. These rules specify stress indices C 1 , C 2 , and C 3 , which are applied to nominal stress to yield primary plus secondary membrane plus bending stress (P+Q);and KI, K 2 , and K 3 , which are applied to nominal stress along with the C factors to yield total stress I (P+Q+F). The subscripts indicate the type of loading: I for pressure, 2 for moments, and 3 for thennal transients.
Stress indices for a reducer are used.Section 4.3 contains calculations of the safe end SCFs. For stresses due to piping loads, the moment stress indices C 2 and K 2 are applied to the nominal stress components at the safe end. For pressure stresses, the ANSYS model is sufficient to account for the effects of gross structural discontinuity I such that C 1 is not needed. To account for the effects of local structural discontinuity, K, is applied to the linearized P+Q stress to yield P+Q+F. These factors are conservatively applied to all six components of the stress tensor.For thermal stresses, C 3 and K 3 are given as 1.0 [1, Table NB-3681(a)-I];
therefore, no SCF is required.FileNo.: VY-19Q-301 Page 12 of 18 Revision:
0 F0306-01 RO W Structural Integrity Associates, Inc.3.10 Environmental Fatigue Multipliers The enviromnental fatigue multipliers for the safe end and nozzle comer will be calculated in accordance with NUJREG/CR-6583 methodology
[ 15].4.0 CALCULATIONS 4.1 Heat Transfer Coefficients, Condensation Condensation heat transfer coefficients are calculated with the formula shown in Section 3.4 for times during which the nozzle is filled with steam at Region A temperature
[10, Attachnment 1, p. 3].This is done in the sheet labeled "Condensation" in Excel workbook VY-19Q-301.xls in the project computer files. The highest heat transfer coefficient values for the transient temperature range are used. These are provided in Table 6.Table 6: Condensation Heat Transfer Coefficients, Btu/hr-ft 2 -F O%. flow, Region steam 1 598 2 *3 1515 4 *5 874 6 *7 **8 *** Linearly transition between the values for the adjacent regions.** Use values from Table 4, since these are bounding and there is no change in temperature.
 
===4.2 Piping===
Interface Loads From general structural mechanics, the membrane plus bending stresses at the inside surface of a thick-walled cylinder are: Uzi = axial stress due to axial force = Fz/A az2 = axial stress due to bending moment = Mxy(ID/2)/I Uz = Uzi + Uz2 ,o = shear stress due to torsion = M,(ID/2)/J ,c = shear stress due to shear force = 2Fy/A, where F,S, F z) F,, M., MY, and M, are forces and moments at the pipe-to-safe end weld MxL = moment about x axis translated by length z = -L = M, -Fy L MyL = moment about y axis translated by length z --L = My + F, L Mxy = resultant bending moment = (MXL2 + Myc2)0.5 Fxy = resultant shear force = (F 2 + Fy2)0.5 ID, OD = inside and outside diameters A = area of cross section = (n/4)(0D 2 -ID 2)FileNo.: VY-19Q-301 Page 13 of 18 Revision:
0 F0306-01 RO Structural Integrity Associates, Inc.I = moment of inertia = (n/64)(OD 4 -ID 4)J = polar moment of inertia = (70/32)(OD 4 -IDa) I Figure 4 shows the coordinate system for the forces and moments [8, Figure 1]. The shear stresses are expressed in a local coordinate system with r radial (X in ANSYS coordinates), 0 circumferential I (Z in ANSYS coordinates), and Z axial (Y in ANSYS coordinates).
Table 7 shows the calculation of stresses; ID, OD, and L are taken fioin the previous piping load stress calculations
[2, Section 3.4].Forces and moments are taken from the same reference as before, except that signs are chosen to I maximize stress [8, Table 3].I"49- 1 tfmy Fi -nle 4 []'Figure 4: Coordinate System for Forces and Moments Table 7: Membrane Plus Bending Stresses Due to Piping Loads I Safe Nozzle End Corner Fx, kip 3.00 3.00 FY, kip -15.00 -15.00 Fz, kip 3.20 3.20 M., kip-in 336.00 336.00 MY, kip-in 156.00 156.00 M,, kip-in 480.00 480.00* L, in 12.09 27.57 ML, kip-in 517.31 749.58 MYL, kip-in 192.26 238.72 M,, kip-in 551.88 786.67 FY, kip-in 15.30 15.30 OD, in 11.86 22.67 I ID, in 10.409 10.750 A, in 2  25.28 312.73 I, in 4  393.28 12300.41 J, in 786.55 24600.82 (7,1, ksi 0.127 0.010 a, ksi 7.304 0.344 cy, ksi 7.430 0.354-t,o, ksi 3.176 0.105-c,, ksi 1.210 0.098 I FileNo.: VY-19Q-301 Page 14 of 18 Revision:
0 F0306-01RO Structural Integrity Associates, Inc.4.3 SCFs, Safe End Figure 5 shows the geometry parameters used in calculating stress indices for reducers [1, Figure NB-3683.6-1], and Figure 6 shows the feedwater nozzle safe end geometry [9]. Comparing the two figures gives the following values: L, = 0", r, = 0.75", D, = 12.000", t 1 = (12 -10.515)/2 0.7425" L2 = 0", r 2 = 0.75", D 2 = 10.840", t 2 = (10.840 -9.669)/2 = 0.5855" ax= 100 (LI and L 2 are taken as zero because the location of interest is on the radius of curvature.)
Figure 5: Reducer Geometry Parameters File No.: VY-19Q-301 Revision:
0 Page 15 of 18 F0306-O1RO Structural Integrity Associates, Inc.D 1j~-J rJ I I Figure 6: FW Nozzle Safe End Geometry File No.: VY-19Q-301 Revision:
0 Page 16 of 18 F0306-01 RO Structural Integrity Associates, inc.Equations for stress indices are taken from the ASME Code [1, NB-3683.6].
For K, and K 2 , since the location of interest is not on a weld, the equation for flush welds is used: K, = K 2 = 1.1 -0.1 L 1 i/(D 1 m t,,)&deg;5 , where Lin/(Din tin)0'5 = the lesser of LA/(D 1 t1)0 5 and L 2/(D 2 t 2)0 5 Since L 1 = L2 = 0, one finds: KI =K2= 1.1 -0.1 (0)= 1.1 Since r, and r2 are less than 0.1D 1 , C 2 is given as: C 2  1.0 + 0.0 185 cx (Dn/tn) 5 , where D/t, -- the larger of DI/tl and D 2/t 2 The bounding D/t value is D 2/t 2 = 10.840/0.5855
= 18.514, so that: C 2 = 1.0 + 0.0185 (10) (18.514).5
= 1.796 C 2 K2 = 1.796 (1.1) = 1.976 5.0 RESULTS OF ANALYSIS This calculation package specifies the ASMIE Code edition, finite element model, thermal and pressure transients (Table 1), and heat transfer coefficients (Tables 4 and 6) to be used in a fatigue usage analysis of the FW nozzle at VYNPS. Thenrnal transient and pressure stress components will be calculated using ANSYS, and piping load stress components are calculated herein using closed form solutions (Table 7).Linearized stress components at Nodes 192 (safe end inside surface) and 657 (nozzle comer inside surface) will be used for the fatigue usage analysis.
At the nozzle comer, P+Q and P+Q+F pressure stress components will be increased by a factor of 1.333. For the nozzle corner location, the stresses used in the evaluation shall be for the base metal only; that is, the cladding material should be unselected prior to stress extraction.
At the safe end, linearized P+Q pressure stress components will be multiplied by 1.1 to yield P+Q+F pressure stress components, and nominal stress components due to piping loads are multiplied by 1.796 to yield P+Q stress components and 1.976 to yield P+Q+F stress components.
The fatigue usage analysis will consider all six stress components, and will be performed using the NB-3200 rules of Section III of the ASME Code [1]. Calculated fatigue usage factors will be multiplied by the overall Fen of 1.74 for the safe end [2, Section 5.0] and values to be developed in a subsequent calculation package, to be assigned file number VY-19Q-303, for the nozzle corner.File No.: VY-19Q-301 Page 17 of 18 Revision:
0 F0306-O1RO Structural Integrity Associates, Inc.
 
==6.0 REFERENCES==
: 1. American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section III, Subsection NB, 1998 Edition with Addenda through year 2000.2. SI Calculation Package, Fatigue Analysis of Feedwater Nozzle, Revision 0, SI File No. VY- 16Q-302.3. SI Calculation Package, Feedwater Nozzle Stress History Development for Greens Functions, Revision 0, SI File No. VY-16Q-301.
: 4. SI Calculation Package, Feedwater Nozzle Finite Element Model and Heat Transfer Coefficients, Revision 0, SI File No. VY-10Q-301.
: 5. Holman, J.P., Heat Transfer, Fifth Edition, McGraw-Hill, 1981.6. ANSYS, Release 8.1 (w/Service Pack 1), ANSYS, Inc., June 2004. (Listed for reference only;this program is not used in this calculation package.)7. Entergy Document VYC-378, Revision 0, Vermont Yankee Reactor Cyclic Limnits for Transient Events, SI File No. VY-05Q-21 1.8. GE Drawing No. 919D294, Revision 11, Sheet 7, Reactor Vessel, Spec. Control, SI File No. VY-05Q-241.9. Ebasco Drawing 5920-234R1, 08/03/67, Safe End Detailfor Nozzles MK. N4A THRUN4D, (CB&I Contract 9-620 1, Drawing #M14, Revision 0, 05/02/67), S1 File No. VY-05Q-215.
: 10. 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-209.11. Letter MLH-08-001 from M.L. Herrera (SI) to N. Lobo (ASME), ASME Code, Section II, Part D, 1998 Edition and Later, Subpart 2, Table TCD, January 10, 2008.12. Cherernisinoff, N., Heat Transfer Pocket Handbook, Gulf Publishing Co., Houston, 1984.13. Keenan, J.H., Keyes, F.G., Hill, P.G., Moore, J.G, Steam Tables, Thermodynamic Properties of Water Including Vapor, Liquid, and Solid Phases (English Units), John Wiley & Sons, 1969.14. American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section II, Part D, 1998 Edition with Addenda through year 2000.15. NUREG/CR-6583 (ANL-97/18), Effects ofL WR Coolant Environments on Fatigue Design Curves of Carbon and Low-Alloy Steels, March 1998.File No.: VY-19Q-301 Page 18 of 18 Revision:
0 F0306-O1RO NEC-JH 20 Structural intearity Associates, Inc. File No.: VY-19Q-302 CALCULATION PACKAGE Project No.: VY-19Q PROJECT NAME: Provide VY Support for Questions Related to Environmental Fatigue Analyses CONTRACT NO.: 10163217 CLIENT: PLANT: EtryNuclear Operations, Inc. ]Vermont Yankee Nuclear Power Station CALCULATION TITLE: ASME Code Confirmatory Fatigue Evaluation of Reactor Feedwater Nozzle Document Affected Project Manager Preparer(s)
&D o n afe Revision Description Approval Checker(s)
Revision Pages Signature
& Date Signatures
& Date 0 1-12 Original Issue Computer Files -- ' \'1A/tv--,' TJ\Herrmann WF Weitze',-..TJHOIPDO/2008 WFW 01/30/2008 P. "Lohse CSL 01/30/2008 Page 1 of 12 F0306-O IRO Structural Integrity Associates, Inc.1.0 2.0 3.0 4.0 5.0 6.0 7.0 Table of Contents OBJECTIVE
................................................................................................................................
3 M ETHOD O LO GY .......................................................................................................................
3 D ESIGN IN PUTS .........................................................................................................................
3 CA LCULATION S ........................................................................................................................
9 RESULTS O F AN ALY SIS ........................................................................................................
10 CON CLU SION S AN D D ISCU SSION S ....................................................................................
11 REFERENCES
.................................................................
12 List of Tables 1: Transients as Input to VESLFA T .....................................................................................
7 2: Tem perature-D ependent M aterial Properties, VESLFAT ......................................................
8 3: Carbon/Low Alloy Steel Fatigue Curve ...........................................................................
8.4: Stress Com ponents Before SCF, psi .........
.........................................................................
9 5: Stress Com ponents W ith SCF, psi ...........
...........................................................................
9 6: Fatigue U sage Results for Safe End .................................................................................
10 7: Fatigue U sage Results for N ozzle Corner ......................
I .................................................
.11 I ,I I I I I I I I Table Tablc Table Table Table Table Table List of Figures Figure 1: AN SY S Finite Elem ent M odel ........................................................................................
4 Figure 2: Linearization Paths ................................................................................................................
5 I I I I I I I 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]. Thennal 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]. Environimental 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 thennal transient and stress analyses are perforned.
Figure 1 shows the FEM [4, Figure 4].For the thermal transient ANSYS analysis, previously defined thennal 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-OIRO Structural Integrity Associates, Inc.I I I 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, FWS VY 40.INP, and FWS VY _O0.INP].
Figure 1 shows the locations of these boundary conditions.
ELEMENTS Y coupled Mn SEP 6 2002 16:23:51 Y=O I I I I I I I I U I 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-GEOM.INP:
Geometry and material properties FW-HTBC.INP:
Set heat transfer boundary conditions TRAN02-T.INP, TRANO3-T.INP, TRAN04- T.INP, TRANO5-T.INP, TRAN06-.T.INP, TRANO9-TINP, TRAN1O-T.INP, TRANJ1-T.INP, TRAN13-T.INP, TRANO2-S.INP:
TRANO3-S.INP:
TRANO4-S.INP:
TRANO5-S.INP:
TRANO6-S.INP:
TRANO9-S.JNP:
TRANI O-S.INP: TRANl J-S.INP: TRAN13-S.INP:
Transient 2, thermal and stress analysis Transient 3, thennal and stress analysis Transient 4, thermal and stress analysis Transient 5, thermal and stress analysis Transient 6, thenrnal 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 I I I I I I File No.: VY-19Q-302 Revision:
0 Page 4 of 12 F0306-01RO Structural Integrity Associates, Inc.TRAN]4-T.INP, TRAN]4-S.INP:
Transient 14, thermal and stress analysis TRAN19-T.INP, TRAN19-S.INP:
Transient 19, thennal and stress analysis TRAN20-TINP, TRAN20-S.INP:
Transient 20, thennal and stress analysis TRAN2OAT.INP, TRANI2OAS.NP:
Transient 20A, thermal and stress analysis TRAN21-T.INP, 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 forim solutions
[1, Table 7].Node 187 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-O IRO I Structural Integrity Associates, Inc.3.3 Fatigue Usage Analysis, General The VESLFAT program [7] is used to perforn the fatigue usage analysis in accordance with the1 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 3 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 3S,,, then the total stress range is increased by the factor Ke, as described in NB-3228.5
[3]. The value of S 1 , is specified as a function of temperature.
The input maximum temnperature for both states of a load set pair is used to determine the temperature upon which S,, 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 detenrmined for all of the potential loadings, saving the maximum for the event pair, based on the pair producing the largest alternating total stress intensity (Sail), including the effects of Ke. The principal stresses for the stress ranges are determined by solving for the roots of the cubic equation: S3 (x-----)S 2 _+ (CF"x (7y + -y aa- + a-a -uY 2  Txz2 _ Tyz 2)S U-7, (YY ( + 2 Txy -E, YZy -UYz %y2 _ CFy %Z2 -( Tyz2 0 The stress intensities for the event pairs are reordered in decreasing order of Sat, including a con-ection 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 Sait.For the VYNPS FW nozzle analysis, transients that consist of both upward and downward n 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 I are entered in VESLFAT input files VFAT-1.LCYC (safe end) and VFAT-2I.CYC (nozzle comer).I I I File No.: VY-19Q-302 Page 6 of12 1 Revision:
0 F0306-O1RO n
Structural Integrity Associates, Inc.Table 1: Transients as Input to VESLFAT VESLFAT Start Time, Temp. Pressure Load Set Transient sec** Change Change Cycles I 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 DailyRed1 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_FWIfBypI 0 Downward None 70 14 10_FWI-Byp2 1890 Upward None 70 15 11 LoFPL 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 LoFP1O 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 I 32 19_RedTo0pct 0 Downward None 300 33 20 HSHeatup 0 Upward None 300 34 20AHSFWlnj 1 0 Downward None 300 35 20A HSFWInj2 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 VFAT-]LFDT (safe end) and VFAT-21.FDT (nozzle corner). 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 V Structural Integrity Associates, Inc.I I I Other material properties are input as follows: in = 3.0, n = 0.2, parameters used to calculate factor Ke, safe end [9]m = 2.0, n = 0.2, parameters used to calculate factor Ke, 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 T, -F E, psi Sn, ksi Sv, ksi A508 Class I (safe end)70 200 300 400 500 600 70 200 300 400 500 600 29.3(10)6 28.6(10)6 28.1(1 0)6 27.5(10)6 27.1(10)6 26.5(l 0)6 27.8(10)6 27. 1(10)6 26.7(10)6 26.1(10)6 25.7(10)6 25.2(l 0)6 23.3 21.9 21.3 20.6 19.4 17.8 26.7 26.7 26.7 26.7 26.7 26.7 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 11 (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 Sa, ksi 580 410 275 205 155 105 83 I I I I I U I I I I I I I I I I 64 48 38 31 23 20 16.5 13.5 12.5 File No.: VY-19Q-302 Revision:
0 Page 8 of 12 F0306-OIRO VStructural 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&deg;F [1, Section 3.1.8].Table 4: Stress Components Before SCF, psi Loading Type Node S, S, S, S,. S, Sv,.Unii Membrane 192, -810.7 6116 7853 -450.1 0 0 Pressure, plus Bending 657 -705.2 1198 24020 -3590 0 0 1,000psi Total *657 -705.2 985.5 27590 -121.1 0 0 Piping Loads Nominal 192 0 7430 0 1210 3176 0 at 575 0 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 S, S, S, SXV SXZ S,.Z S" S, S 2 SXV Sxz SIZ 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-1I.XLS (safe end) and VFAT-21.XLS (nozzle).
These files are organized with sheets labeled as follows:* Overview:
Contains general information.
FileNo.: VY-19Q-302 Page 9 of 12 Revision:
0 F0306-01 RO 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 StressResilts.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 Sx, and Sy, 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 thenrinal 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-]LSTR (safe end) and VFAT-21.STR (nozzle corner). To avoid double counting of stress states, the initial time steps of each load set before the first stress 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 VFA T-1J.FA T (safe end) and VFA T-21.FA T (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 S,,, psi K, S.1, psi N Usage 15 11 LoEPi 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 30 13_Overpr3 34 20AHSFWhijl 1 42194 1 37182 10769 0.0001 33 20_HSHeatup 34 20AHSFWInj 1 21 42563 1 35966 12060 0.0017 5 4_TurbRolll 33 20_HSHeatup 279 43986 1 35597 12491 0.0223 64 TurbRoIl2 2311 LoFP9 10 39882 1 32197 17579 0.0006 54 TurbRoIll 64 TurbRoll2 21 39842 1 32178 17615 0.0012 16 11 _LoFP2 35 20AHSFWInj2 10 40708 1 31762 18413 0.0005 35 20AHSFWInj2 37 24_HydroTestl 1 20956 1 13081 664055 0.0000 1711_LoFP3 35 20AHSFWInj2 10 20399 1 12667 887275 0.0000 19 11 ,LoFP5 35 20A HSFWInj2 10 19602 1 12135 infinite 0.0000 TOTAL = 0.0571 I I I I I I I I I I I I I I I I I I I File No.: VY-19Q-302 Revision:
0 Page 10 of 12 F0306-01RO Structural Integrity Associates, Inc.Table 7: Fatigue Usage Results for Nozzle Corner Load Set A 2 2_DesHydrol 2 2_DesHydrol 2 2DesHydrol
.22 2DesHydrol 2 2_DesHydro 1 54 TurbRolll 3 2_DesHydro2 3 2_DesHydro2 3 2_DesHydro2 34 20AHSFWInj 1 34 20A HSFW~nj 1 26 12 TGTrip2 21 11 LoFP7 26 12_TGTrip2 22 11 LoFP8 4 3 Startup 4 3 Startup 4 3 Startup 4 3 Startup 32 19_RedTo0pct 13 10_FWHByp 1 13 10 FWJHBypl 35 20AHSFWInj2 9 6 WklyRedl Load Set B 1611 LoFP2 20 11 LoFP6 18 11 LoFP4 11 9_TurbTripl 5 4 TurbRolll 39 25 Unbolt 54 TurbRolll 23 11 LoFP9 34 20AHSFWlnj 1 38 24_HydroTest2 36 21 Shutdown 36 21 Shutdown 26 12_TGTrip2 31 14 SRVBIwdn 26 12_TGTrip2 26 12_TGTrip2 29 13_Overpr2 28 13Overprl 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 Ke 1 1 1 1 1 Sato, 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
 
==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 corner location was detennined to be 0.0889. Both values are less than the ASME Code allowable value of 1.0.Enviromnental fatigue usage analysis will be performed in A separate calculation package.File No.: VY-19Q-302 Revision:
0 Page 11 of 12 F0306-0IRO Structural Integrity Associates, Inc.
 
==7.0 REFERENCES==
: 1. SI Calculation Package, Design h2puts and Methodology for ASME Code Confirmatoiy 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-1OQ-301.
: 5. Entergy Document EC No. 1773, Revision 0 (Design Input Revision 1), Environmental Fatigue Analysisfoir Vermont Yankee Nuclear Power Station, SI File No. VY- 16Q-209.6. SI Calculation Package, Feedwater Nozzle Stress Histoiy 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 klr% IULi '14 Structural Integrity Associates, Inc. File No.: VY-19Q-303 CALCULATION PACKAGE Project No.: VY-19Q 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: Feedwater Nozzle Environmental Fatigue Evaluation Document Affected Project Manager Preparer(s)
&Revision Pages Revision Description Approval Checker(s)
Signature
& Date Signatures
& Date 01 -7 Initial issue. Ten-y J. Herrmann Gary L. Stevens 01/30/2008 01/30/2008 Terry J. Hernrann 01/30/2008 A% \1 Page I of 7 F0306-OIRO Structural Integrity Associates, Inc.Table of Contents 1.0 INTROD UCTION ..........................................................................................................................
3 2.0 APPROACH .....................................................................................................................................
3 3.0 M ETHODOLO GY ........................................................................................................
4 4.0 CA LCULATION S ...........................................................................................................................
5 5.0 CON CLUSION S .............................................................................................................................
5 6.0 REFEREN CES..................................................................................................................................
6 List of Tables Table 1: EAF Calculations for the Feedwater Nozzle Comer .........................................................
7 I I I I I I I I I I I I I I I I I File No.: VY-19Q-303 Revision:
0 Page 2 of 7 F0306-OI RO I I Structural Integrity Associates, Inc.
 
==1.0 INTRODUCTION==
 
The purpose of this calculation is to perform a plant-specific evaluation of reactor water environmental effects for the reactor pressure vessel (RPV) feedwater nozzle identified in NUREG/CR-6260
[1] for the older vintage General Electric (GE) plant for the Vermont Yankee Nuclear Power Station (VY).2.0 APPROACH Per Chapter X, "Time-Limited Aging Analyses Evaluation of Aging Management Programs Under 10 CFR 54.21 (c)(l)(iii)," Section X.M1, "Metal Fatigue of Reactor Coolant Pressure Boundary," of the Generic Aging Lessons Learned (GALL) Report [2], detailed, vintage-specific, fatigue calculations are required for plants applying for license renewal for the locations identified for the appropriate vintage plant in NUREG/CR-6260.
In this calculation, detailed enviromnentally assisted fatigue (EAF) calculations are performed for VY for one of the locations associated with the older vintage GE plant in NLTREG/CR-6260.
The older-vintage GE plant is the appropriate comparison to VY since the original piping design at VY was in accordance with USAS B31.1 [3], as well as the fact thaft the older-vintage boiling water reactor (BWR) in NUREG/CR-6260 was a BWR-4 plant, which is the same as VY.Entergy perforned an initial assessment of EAF effects for VY in their License Renewal Application (LRA) that was submitted to the NRC in January 2006. Table 4.3-3 of the VY LRA provides the results of those evaluations.
All but two of the VY locations evaluated for EAF in the LRA did not yield acceptable results for 60 years of operation, as they were based on generic analysis results from NUREG/CR-6260 that were not VY-specific.
Plant-specific analyses have been recently completed to address those components for VY. Relevant chemistry input for this calculation is contained in Reference
[5]. This calculation documents the EAF evaluation for the feedwater nozzle locations.
File No.: VY-19Q-303 Revision:
0 Page 3 of 7 F0306-01 RO I Structural Integrity Associates, Inc.I I 3.0 METHODOLOGY Per Section X.MI of the GALL Report [2], the EAF evaluation must use the appropriate Fen relationships from NUREG/CR-6583
[4] (for carbon/low alloy steels), which are the materials under consideration for the feedwater nozzle. Per Figure 2 and Table 2 of Reference
[6], the two locations being evaluated are the feedwater nozzle safe end (carbon steel) and the feedwater nozzle forging comer (low alloy steel). Based on the materials of these locations, the appropriate expressions are: For Carbon Steel [4, p. 69]: Fen = exp (0.585 -0.00124T'
-0.101S*T*O*E*)
(1)Substituting T' = 25&deg;C in the above expression, as required by NUREG/CR-6583 to relate room temperature air data to service temperature data in water [7], the following is obtained: Fen= exp (0.585 -0.00124(25&deg;C)
-0.101 S* T* O*&*) (2)= exp (0.554 -0.101 S* T* O* F*)(3)(4)For Low Alloy Steel [4, p. 69]: Fen = exp (0.929 -0.00124T'
-0.101S*T*O*
6*)Substituting T'= 25'C in the above expression, as required by NUR-EG/CR-6583 to relate room temperature air data to service temperature data in water [7], the following is obtained: Fen = exp (0.929- 0.00124(25&deg;C)
-0.101 S* T* O*E*) (5)I I I I I I I I I I I I I I I I= exp (0.898 -0.101 S* T*0* F* )(6)where [4, pp. 60 and 65]: Fen S*T 0*fatigue life correction factor= S for 0 < sulfur content, S  0.015 wt.. %0.015 for S > 0.015 wt..%= 0forT< 150 0 C= (T-.150) for i50_<T< 350-C= fluid service temperature
('C)0 for dissolved oxygen, DO < 0.05 parts per million (ppm)= ln(DO/0.04) for 0.05 ppm  DO 0.5 ppm= 1n(12.5) for DO > 0.5 ppm 0 for strain rate, g* > 1%/sec ln(E*) for 0.001 _ * -< 1%/sec= ln(0.001) for E* < 0.001%/sec Bounding Fen values were determined in Reference
[5]. The values determined in Table 3 of Reference
[5] will be used for the carbon steel feedwater nozzle safe end location, where feedwater.DO levels are low and the Fen value is a constant valueof 1.74 for all temperatures for both hydrogen water chemistry (HWC) and nonrial water chemistry (NWC) conditions.
For the low alloy steel File No.: VY-19Q-303 Revision:
0 Page 4 of 7 F0306-01RO I
Structural Integrity Associates, Inc.nozzle corner location, the applicable Fe, values are shown in Table 4 of Reference
[5]. Since there is a significant variation in values with temperature, Fen values will be computed for each load pair in the detailed fatigue calculation for this location.The environmental fatigue is determined as Uen, v= (U) (F17), where U is the original fatigue usage and U,,, is the environmentally assisted fatigue (EAF) usage factor. All calculations can be found in Excel spreadsheet "VY-19Q-303 (Env. Fat. Calcs).xls" associated with this calculation.
From Table 1 of Reference
[5], the following water chemistry input applies for the low alloy steel nozzle corner location:* Over the 60-year operating life of the plant, HWC conditions exist for 47% of the time, and NWC conditions exist for 53% of the time.* For the RPV Upper Region, which is applicable to the nozzle corner location, DO is 114 ppb pre-HWC and 97 ppb post-HWC.With these assumptions, the cumulative usage factor (CUF) values documented in this calculation are considered applicable for sixty years of operation including all relevant EAF and EPU effects.4.0 CALCULATIONS From Table 6 of Reference
[6], the CUF for the safe end for 60 years of operation is 0.0571. Thus, the EAF CUF for 60 years is 0.0571 x 1.74 = 0.0994, which is less than the allowable value of 1.0 and is therefore acceptable.
The CUF for the nozzle comer for 60 years of operation is shown in Table 7 of Reference
[6], and has a value of 0.0889. This calculation is reproduced in Table 1, along with EAT calculations on a load pair basis using the F,, expression in Equation (6) above for low alloy steel. The final EAF CUF for 60 years is 0.3531, which is less than the allowable value of 1.0 and is therefore acceptable.
The overall Fen multiplier for this location is 3.97.
 
==5.0 CONCLUSION==
S In this calculation, EAF calculations were perforned in accordance with the GALL Report [2] for the feedwater nozzle safe end (carbon steel) and nozzle corner (low alloy steel) locations.
These locations were selected based on the locations identified in NUREG/CR-6260 for the older vintage GE plant and plant-specific fatigue calculations that detennined the limiting locations for VY.Calculations for the remaining NUREG/CR-6260 locations are documented in other calculations.
The EAF results for the locations identified above indicate that the fatigue usage factors, including environmental effects, are within the allowable value for 60 years of operation.
The calculations for both locations make use of the 60-year projected cycles for VY and incorporate EPU effects File No.: VY-19Q-303 Page 5 of 7 Revision:
0 F0306-0 1 RO Structural Integrity Associates, Inc.(conservatively assumed to apply for all 60 years of operation).
Therefore, no additional evaluation is required for these components, and the GALL requirements are satisfied.
 
==6.0 REFERENCES==
: 1. NUREG/CR-6260 (INEL-95/0045), "Application of NUREG/CR-5999 Interim Fatigue Curves to Selected Nuclear Power Plant Components," March 1995.2. NUREG-1801, Revision 1, "Generic Aging Lessons Learned (GALL) Report," U. S. Nuclear Regulatory Conmmission, September 2005.3. USAS B31.1.0 -1967, USA Standard Code for Pressure Piping, "Power Piping," American Society of Mechanical Engineers, New York.4. NUtREG/CR-6583 (ANL-97/18), "Effects of LWR Coolant Environments on Fatigue Design Curves of Carbon and Low-Alloy Steels," March 1998.5. St Calculation Package, Environmental Fatigue Evaluation of Reactor Recirculation Inlet Nozzle and Vessel Shell/Bottom Head, Revision 0, SI File No. VY-16Q-303.
: 6. S1 Calculation Package, ASME Code Confirmatory Fatigue Evaluation of Reactor Feedwater Nozzle, Revision 0, SI File No. VY-19Q-302.
: 7. EPRL/BWRVIP Memo No. 2005-271, "Potential Error in Existing Fatigue Reactor Water Envirorunental Effects Analyses," July 1, 2005.I I I I I I I I I I I I I I I I File No.: VY-19Q-303 Revision:
0 Page 6 of 7 I F0306-OIRO I
-m --m -m- ---- -m --m m -m Structural Integrity Associates, Inc.Table 1: EAF Calculations for the Feedwater Nozzle Corner$1.C17 Fafccaion ront Table 0 of Referenc.
61: EAF Calculations L NWC DO 67 114 ppb% Hi 4750 7 3,4 = 50% 0NWC Index Load# 1 Description n#int (cycles) Load #2(Description
#2o 1n1(cyles) n (cyclesl 0 ,A2Is tI<, 5,,, Oe(0 .,,tt, U 1 2 _O naeydroI 120 16 1 liLoFP 10 10 H5.109 ,000 46.047 6.65578 000177 22Desdr O tol 110 t 11LoFF6 244 1.000 43.9L0 6.471.19 0.001W4 0esHydr : 1040 1 11 -LoFPJ 10 10 50100 1 000 43,202 6,32083 000145 4 2 2-DesHydrol 90 II 9_TtirbTnpl 10 10 ;51712 1.000 43,011 6.926 58 0.00144 S 2. 2esHydrol -T, bRoll 200 60 4 0296 1000 43,008 6,92 97 0.01165 6 4"TusbRofll 220 40 O6Ulrbolt
;23 123 13.306 1.000 41.430 17730a36 0 01509 7 3 2 OeslHyd2 9120 6 Tutb .1 7 01437 1000 40.391 60343.98 0.01102 8 3 2 DesHydron2 23 23 { 1 LoFP9 1 r 0 93.178 1.000 40101 8.524 36 0 00117 q 3 2 Deoblyr Qt I0,A HSFWfrtl 300 12 40606 1.000 36.17 66.10.73 000146 10 34 204A HSFA,hl B?1 87 38 24_HydroT3e 2 1 1 49.097 1000 39,22 0.03306 0 00011 11 34 20A HSFInjl 286ef 21 ShwOdtl I 2,00 260 498111 1.000 39,616 8637.800 0.03206 12 20 12.TGTrip2 238 ?6 , 21- n 14 004379 1000 38.,5,3 9.57340 0.00136 13 21 i11 LoF7 10 26 127G7T,9p2 274 10 403966 1.000 "3.091 16,015.00 0.00002 14 2s 6 12 GTrdp2 204 31 14 SP.VBKdn { 1 1 42902 1.000 27,518 23.03100 0.00003 10 22 11_LoFP8 .0 26 12_Tl7Tp2 2 03 1 ? 2.212 1,000 24 567 40 237.00 0 06025 15 4 i30t1rtup 143 t2 1TGTri 7  200 263 30.212 1.000 232:13 4G.72.00 0.00641 17 4 3 StSnvp J7 29 123_O~pr2 1 1 30.212 1.000 23.513 46728.00 0 00002 13 4 I StarUp 4!l, N 1Cvoetpr 1 1 1 2I.0s00 1.000 19.423 111,113.00 0.00001 10 4 3 Starup 1 92 19 RndTotpct 300 45 24.083 1.000 17,66 156.402.00 0.00029 30 32 lRedTo0pct 55 i 31 20HSHeatop 300 2065 t.765 1.00 12.603 761.835.00 0.00033 21 13 10 FWH~ypI 70 33 20 HSHeatup 45 45 19,030 10N0 12.679 B79.615.00 0.00600 22 13 1 10FWHBptI 2 36 120A HSFWOlnj2 300 26 20288 1.000 12.024 614634.00 000003 23 35 220A_H!SFhVnj2 275 37 24_HydreTestl 1 1 19,050 1.M00 12.369 infinite 0.00060 24 1 9 G Wklt ed 1 2000 r n 1 20A HSFWlni2 , 274 274 19.241 1.000 11.962 infloile 000000 Total. U 0 s = 0.96692 Tran.riel Marirnum Ternoraofrees Index Load 31. Oescrptlon#t 1n icycles Load #2 Oesctlptlon
#2 Index TI s2 T2I1 1' fa Sn (psI) T ('F)f 1 2 2 DesHfdrol 120 16 F 11 LcFP2 1 2 30 16 14 66.100 356 2 2 2 DesHydrol 110 20 11 LoFP6 2 2 30 20 3 50.344 391 3 2 2- DesHYdrol 100 66 11 LoFPJ 3 2 30 10 7 S60160 389 4 2 2_DesHydrel 90 16 9STuFoTdpl 4 2 30 11 6 65.712 351 0 2 2 2esHvdrcl 50 6 4 TuobRolll 6 2 30 61 12 64.296 360 6 n i 4" TotOlloli 0 220 39 O-SUnbolt 6 5 12 39 23 63.301 200 7 3 2 3Dsa00 dr02 14 ' 4_TrbhRoIll 7 3 1 5 12 61,437 260 6 3 2 DesHydto2 2 3  23 11 _L[F9 6 2 .1 23 7 63.132 353 9 3 2_DesHydrn2 13 34 20A_HSFWlnjl 9 3 1 34 21 49.06S 288 10 34 20A HOFWfnj 1 l 267 38 26 HydtoTesl2 10 34 21 28 1 49,097 388 11 34 120A HSF77 nj11 286 36 21lShutdnow 11 34 21 36 160 49.111 389 12 20 i 12 TGTdp2 .2 I 3 1 Shutdcwn 12 26 6 36 166 60.37 3249 12 41 1 LrFPFS 10 26 12fTTrip2 13 21 69 23 7 49,365 424 1t 26 12-GTtp2?
264 31 l4_SRVhh.rdn 14 2E 31 41 42,902 349 16 22 _L0FF9a 10 2G 12_TGThp2 16 22 6 26 7 12,21Z 536 13 3 Startup '00 20 12_TGTsip2 16 4 I 20 7 30.212 603 17 4 1 Startup 47 29 l30Ovetpr2 17 4 I 29 7 30.212 503 10 3 Startup. 46 26 13Overplp 10 4 I 26 1 28.9650 03 19 4 3Startup 4J 32 19RedToOpct 19 4 6 32 45 24,083 003 20 32 196RedToOpct O 255 33 20 HSHeatup 20 32 46 33 20 10.765 543 21 13 10FWHByp1 i 70 33 20HSHeatup 21 13 23 32 26 16,627' 645 22 i3 i10 WVHBypl t 25 35 20HSFWrnj2 22 13 23 35 14 20.389 546 23 35 20A- HSFW'inj2i 273 37 24_Hyoroest1 23 36 14 327 1 19.850 645 24 q 6 .1 ,$Redl : 000 36 20A H1FWit2t 24 0 S 10 25 14 19.341 040 ,TIc ('F) !I j V'$ 5 W4 F~,rr F1O"C Fr r'l 306.0 10.0 12.2 3.410 361 0 103.9 3.681 2.971 309.0 198.3 .2.002 4.169 351 0 1772 3.159 3 308 350.0 162.2 3.309 2.494 3200.0 162.2 2.309 3 494 300.0 1332 309 3 494 363.0 1783 3.192 3 349 26s0 1979 3923 0.114 300.0 1972 2.023 4 144 2000 1097.8 3.823 4.144 349.0 176.1 3.127 3 2.9 424.0 217.8 4,001 0 .160 349.0 1761 3.127 3.268 63860 281.1 6.277 10330 003.0 261 7 6.912 0.147 503.0 201.7 6.912 S 347 003.0 261.2 6.912 8.347 503.0 261.7 6.912 0347 542 0 203.9 6.493 10.649 048.0 286 7 0.714 10.078 649.0 287.2 9.759 11046 546.0 266.7 9.714 10.918 548.0 286.7 a.714 10 975 0.005.9 0 00692 0 .005009 0 00468 0.03916 0.00415 0 (13961 0.00304 0.00506 0.00045 0 12921 0 00,410 0.00305 0 00011 0.00233 0.74104 0.000 16 0.02007 0.00221 7 00323 G.00027 0 00000 0.00000 0.35306 3.970 Overall F2I Notes: 1. T-w is !he m-inmum tetmpe'aiure of the nwo paired load stlates, and represenrs tIe motal (rodlaf t.lnponalute at the location being analnaed.
This is determined from the VESLFAT oulpotl Itom Reference
[6).which is included as T in theiTmnnsient Maximum Temperatures table aboe,.Frsaloes comnuted usi0g Eqoation (61 with 0S cosenar.tiely, set to a taoinurn oalue of 0.016 aol the transftored son cafo consortolralo set to a minimum value of 14,(0.0011 -S.900 for alt loa4 pairs., 32 LU., = [U x HV'C F,? o % HWC) a (U x N7WC F., x n9 NWVC].4, T1 and T2 represent the load number ton Load O1 and Lead 62. osepectinly.
end el and 32 represent the state nuitber for each of those loads.FileNo.: VY-19Q-303 Revision:
0 Page 7 of 7 F0306-01 RO NEC-JH_22 LICENSEE:
Entergy Nuclear Operations, Inc.FACILITY:
Vermont Yankee Nuclear Power Station
 
==SUBJECT:==
 
==SUMMARY==
OF MEETING HELD ON JANUARY 8, 2008, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION STAFF AND ENTERGY NUCLEAR OPERATIONS, INC. REPRESENTATIVES TO DISCUSS THE RESPONSE TO A REQUEST FOR ADDITIONAL INFORMATION PERTAINING TO THE VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION On January 8, 2008, the Nuclear Regulatory Commission staff (the staff) met with members of Entergy Nuclear Operations, Inc. (the applicant) in a public meeting to discuss the response to a request for additional information (RAI) made by the staff pertaining to the Vermont Yankee Nuclear Power Station (VYNPS) license renewal application.
The applicant had an opportunity to comment on this summary.A list of attendees is provided in Enclosure
: 1. The meeting agenda is provided in Enclosure 2.Comments made by the public during the meeting are provided in Enclosure
: 3. A copy of the slides presented by the applicant is provided as Enclosure
: 4. A summary of the discussion follows: Background In a letter dated November 27, 2007, the staff issued RAI 4.3.3-2 to the applicant.
The purpose of the request was to gather additional information on the calculations used at VYNPS to reanalyze their time-limited aging analysis (TLAA) that addresses environmentally-assisted fatigue. In a letter dated December 11, 2007, the applicant provided its response to RAI 4.3.3-2 to the staff. The staff reviewed the response and further questioned the methodology described in the submittal and statements made that shear stresses are negligible during a conference call with the applicant on December 18, 2007. During the call, the applicant requested a face-to-face meeting to ensure that its position pertaining to this highly technical issue was properly and effectively communicated.
Discussion During the meeting, the applicant made a slide presentation of the reactor vessel nozzle environmental fatigue analyses for license renewal at VYNPS. The applicant reviewed the terminology used in the response to RAI 4.3.3-2. The applicant reviewed the analyzed vessel nozzle configurations to identify where the shear stresses in the nozzles were negligible, where they were not, and the effects on the fatigue analysis at the locations where shear stresses were not negligible.
NEC072277 I The applicant explained that nozzle corner, blend radius, and inner radius are interchangeable terms for locations with geometrical discontinuities; that is, locations where stresses are maximum. The applicant explained that the methodology employed incorporates the use of axisymmetric modeling rather than an exact configuration 3- i Dimensional (3-D) or 2-Dimensional (2-D) modeling.
They explained that axisymmetric modeling is a 3-D model except that it models the nozzle/vessel interface as a sphere with a multiplier to account for pressure stress effects, rather than a pipe joined to a I cylinder.
With the aid of colored graphs, the applicant demonstrated specific nozzles where shear stresses are negligible.
The applicant also discussed the various conservatisms used in their analysis.
3 Conclusion
: 1. Based on the analyses performed, the applicant presented its conclusion that the i effects of shear stresses were negligible or were separately addressed for all nozzles analyzed.2. Based on its interaction with the NRR staff during the meeting, the applicant agreed to perform additional confirmatory work and submit results to the staff for review and acceptance.
This work effort will include: 1) Performing benchmarking calculations on the feedwater nozzle, which is the most limiting component, using the axisymmetric finite element model, taking fully into account all stress components on the nozzle and using the ANSYS FEM computer code to model all defined transients;
: 2) Demonstrating that the Vermont Yankee specific benchmarking calculations I bound the results for the Core Spray and Recirculation outlet nozzles.3) Calculating fatigue usage factors (CUFs) using NRC approved ASME Section III NB-3200 methods; and 4) Comparing the resulting CUFs to the previous environmental assisted fatigue calculations to establish whether the previous calculations are adequate.I Jonathan G. Rowley, Project Manager Projects Branch 2 Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-271 I NEC072278
 
==Enclosures:==
: 1. Attendance List 2. Agenda 3. Public Comments 4. Presentation slides cc w/encls: See next page NEC072279 Jonathan G. Rowley, Project Manager Projects Branch 2 Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-271' 3
 
==Enclosures:==
: 1. Attendance List 2. Agenda m 3. Public Comments 4. Presentation slides cc w/encls: See next page DISTRIBUTION:
See next page ADAMS Accession No.: DOCUMENT NAME: G:\ADRO\DLR\RLRB\ROWLEY\Meeting with VY-Entergy Summary -January 8, 2008.doc OFFICE LA:DLR PM:RPB2:DLR BC:RPB2:DLR BC:RERI:DLR NAME J Rowley RFranovich KChang DATE / I I / / I I OFFICIAL RECORD COPY NEC072280 MEETING BETWEEN THE NRC STAFF AND ENTERGY NUCLEAR OPERATIONS, INC.VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION 6003 EXECUTIVE BOULEVARD ROOM EBB1B15 ROCKVILLE, MARYLAND MEETING ATTENDANCE LIST JANUARY 8, 2008 PARTICIPANTS Jonathan Rowley Samson Lee John Fair Kenneth Chang PT Kuo Rani Franovich Robert Sun Qi Gan Kaihwa Hsu Ricardo Rodriguez Mary Baty Perry Buckberg Evelyn Gettys Yeon-Ki Chung Peter Wen On Yee Gary Hammer David Mannai John McCann Jay Thayer Matias Travieso-Diaz Michael Metell Garry Young Norm Rademacher AFFILIATIONS U.S. Nuclear Regulatory Commission (NRC)NRC NRC NRC NRC NRC NRC NRC NRC NRC NRC NRC NRC NRC NRC NRC NRC Entergy Nuclear Operations, Inc. (Entergy)Entergy Entergy Entergy Entergy Entergy Entergy Enclosure 1 NEC072281 Alan Cox Entergy PARTICIPANTS James Fitzpatrick Scott Goodwin John Dreyfuss Gary L. Stevens Terry. J. Herrmann Joe Hopenfeld David Lochbaum THE FOLLOWING PARTICAPATED Sarah Hoffman John Sipos Paul Eddy Joan Leary Matthews Blaise Constantakes Rudolf Hausler Raymond Shadis Claire Chang Ulrich Witte Ed Anthes Rich Schaller Chalmer Myer Bob Audette Susan Smallheer Sally Shaw Fred Mogolesko AFFILIATIONS Entergy Entergy Entergy Structural Integrity Associates Structural Integrity Associates New England Coalition (NEC)Union of concerned Scientist VIA TELEPHONE BRIDGELINE I I I I I I I I I I I I Vermont Department of Public Service New York Office of the Attorney General New York Office of the Attorney General New York Office of the Attorney General New York Office of the Attorney General New York Office of the Attorney General NEC NEC NEC Nuclear Free Vermont Strategic Teaming and Resource Sharing Southern Nuclear Operating Company The Brattleboro Reformer The Rutland Herald Entergy MEETING BETWEEN THE NRC STAFF AND ENTERGY NUCLEAR OPERATIONS, INC.VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION 6003 EXECUTIVE BOULEVARD ROOM EBB1B15 ROCKVILLE, MARYLAND I I I I I I AGENDA NEC072282 JANUARY 8, 2008 IV.Introduction and opening remarks Discussion of Response to Request for Additional Information (Response to RAI 4.3.3-2)Public Comments Adjourn 10 minutes 80 minutes 30 minutes Enclosure 2 NEC072283 I I MEETING BETWEEN THE NRC STAFF AND ENTERGY NUCLEAR OPERATIONS, INC.VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION ROCKVILLE, MARYLAND ROOM EBB1B15 5 MEETING MINUTES JANUARY 8, 2008 In a letter dated November 27, 2007, the staff issued RAI 4.3.3-2 to the applicant.
The purpose of the request was to gather additional information on the calculations used at VYNPS to reanalyze their time-limited aging analysis (TLAA) that addresses environmentally-assisted fatigue. In a letter dated December 11, 2007, the applicant provided its response to RAI 4.3.3-2 to the staff. The staff reviewed the response and further questioned the methodology described in the submittal and statements made i that shear stresses are negligible during a conference call with the applicant on December 18, 2007. During the call, the applicant requested a face-to-face meeting to ensure that its position pertaining to this highly technical issue was properly and I effectively communicated.
Discussion 3 During the meeting, the applicant made a slide presentation of the reactor vessel nozzle environmental fatigue analyses for license renewal at VYNPS. The applicant reviewed the terminology used in the response to RAI 4.3.3-2. The applicant reviewed i the analyzed vessel nozzle configurations to identify where the shear stresses in the nozzles were negligible, where they were not, and the effects on the fatigue analysis at the locations where shear stresses were not negligible.
The applicant explained that nozzle corner, blend radius, and inner radius are interchangeable terms for locations with geometrical discontinuities; that is, locations where stresses are a maximum. The applicant explained that their methodology incorporates the use of axisymmetric modeling rather than an exact configuration 3-Dimensional (3-D) or 2-Dimensional (2-D) modeling.
They explained that axisymmetric modeling is a 3-D model except that it models the nozzle/vessel interface as a sphere with a multiplier to account for pressure stress effects, rather than a pipe joined to a cylinder.
With the aid of colored graphs, the applicant demonstrated specific nozzles where shear stresses are negligible.
The applicant also discussed the various l conservatisms used in their analysis.Conclusion i 1. Based on the analyses performed, the applicant presented its conclusion that the effects of shear stresses were negligible or were separately addressed for all nozzles analyzed.Enclosure3 3 NEC072284
: 2. Based on its interaction with the NRR staff during the meeting, the applicant agreed to perform additional confirmatory work and submit results to the staff for review and acceptance.
This work effort will include: 1) Performing benchmarking calculations on the feedwater nozzle, which is the most limiting component, using the axisymmetric finite element model, taking fully into account all stress components on the nozzle and using the ANSYS FEM computer code to model all defined transients;
: 2) Demonstrating that the Vermont Yankee specific benchmarking calculations bound the results for the core spray and recirculation outlet nozzles.3) Calculating fatigue usage factors (CUFs) using NRC approved ASME Section III NB-3200 methods; and 4) Comparing the resulting CUFs to the previous environmental assisted fatigue calculations to establish whether the previous calculations are adequate Enclosure 3 NEC072285 NEC-JH_23 UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION WASHINGTON, DC 20555-0001 April 11,2008 NRC REGULATORY ISSUE
 
==SUMMARY==
2008-10 FATIGUE ANALYSIS OF NUCLEAR POWER PLANT COMPONENTS ADDRESSEES' All holders of operating licenses for nuclear power reactors, except those who have permanently ceased operations and have certified that fuel has been permanently removed from the reactor vessel.INTENT The U.S. Nuclear Regulatory Commission (NRC) is issuing this regulatory issue summary (RIS)to inform licensees of an analysis methodology used to demonstrate compliance with the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code)fatigue acceptance criteria that could be nonconservative if not correctly applied.BACKGROUND INFORMATION Title 10 of the Code of Federal Regulations (10 CFR) Part 54, "Requirements for Renewal of Operating Licenses for Nuclear Power Plants," requires that applicants for license renewal perform an evaluation of time-limited aging analyses relevant to structures, systems, and components within the scope of license renewal. The fatigue analysis of the reactor coolant pressure boundary components is an issue that involves time-limited assumptions.
In addition, the staff has provided guidance in NUREG-1800, Rev. 1, "Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants," issued September 2005.NUREG-1 800, Rev. 1, specifies that the effects of the reactor water environment on fatigue life be evaluated for a sample of components to provide assurance that cracking because of fatigue will not occur during the period of extended operation.
Since the reactor water environment has a significant impact on the fatigue life of components, many license renewal applicants have performed supplemental detailed analyses to demonstrate acceptable fatigue life for these components.
10 CFR 50.55a, "Codes and Standards," specifies the ASME Code requirements for operating reactors.
Some operating facilities may have performed supplemental detailed analysis of components because of new loading conditions identified after the plant began operation.
ML080950235 I I RIS 2008-10 Page 2 of 4
 
==SUMMARY==
OF ISSUE The staff identified a concern regarding the methodology used by some license renewal applicants to demonstrate the ability of nuclear power plant components to withstand the cyclic loads associated with plant transient operations for the period of extended operation.
This particular analysis methodology involves the use of the Green's function to calculate the fatigue usage during plant transient operations such as startups and shutdowns.
The Green's function approach involves performing a detailed stress analysis of a component to calculate its response to a step change in temperature.
This detailed analysis is used to establish an influence function, which is subsequently used to calculate the stresses caused by the actual plant temperature transients.
This methodology has been used to perform fatigue calculations and as input for on-line fatigue monitoring programs.
The Green's function methodology is not in question.
The concern involves a simplified input for applying the Green's function in which only one value of stress is used for the evaluation of the actual plant transients.
The detailed stress analysis requires consideration of six stress components, as discussed in ASME Code, Section III, Subsection NB, Subarticle NB-3200. Simplification of the analysis to consider only one value of the stress may provide acceptable results for some applications; however, it also requires a great deal of judgment by the analyst to ensure that the simplification still provides a conservative result. 3 The staff has requested that recent license renewal applicants that have used this simplified Green's function methodology perform confirmatory analyses to demonstrate that the simplified Green's function analyses provide acceptable results. The confirmatory analyses retain all six i stress components.
To date, the confirmatory analysis of one component, a boiling-water reactor feedwater nozzle, indicated that the simplified input for the Green's function did not produce conservative results in the nozzle bore area when compared to the detailed analysis.However, the confirmatory analysis still demonstrated that the nozzle had acceptable fatigue I usage.Licensees may have also used the simplified Green's function methodology in operating plant fatigue evaluations for the current license term. For plants with renewed licenses, the staff is considering additional regulatory actions if the simplified Green's function methodology was used. 3 RIS 2008-10 Page 3 of 4 BACKFIT DISCUSSION This RIS informs addressees of a potential nonconservative calculation methodology and reminds them that the ASME Code fatigue analysis should be performed properly.
For license renewal, metal fatigue is evaluated as a time-limited aging analysis in accordance with 10 CFR 54.21(c).
The associated staff review guidance appears in Section 4.3, "Metal Fatigue Analysis," of NUREG-1 800, Rev. 1. For operating reactors, the ASME Code requirements appear in 10 CFR 50.55a. This RIS does not impose a new or different regulatory staff position.It requires no action or written response and, therefore, is not a backfit under 10 CFR 50.109,"Backfitting." Consequently, the NRC staff did not perform a backfit analysis.FEDERAL REGISTER NOTIFICATION A notice of opportunity for public comment on this RIS was not published in the Federal Register because the RIS is informational.
CONGRESSIONAL REVIEW ACT The NRC has determined that this RIS is not a rule as designated by the Congressional Review Act (5 U.S.C. &sect;&sect;801-808) and; therefore, is not subject to the Act.PAPERWORK REDUCTION ACT STATEMENT This RIS does not contain information collection requirements that are subject to the requirements of the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.).Public Protection Notification The NRC may not conduct or sponsor, and a person is not required to respond to, a request for information or an information collection requirement unless the requesting document displays a currently valid Office of Management and Budget control number.
RIS 2008-10 Page 4 of 4 I I I I I I CONTACT Please direct any questions about this matter to the technical contacts listed below.IRA/Michael J. Case, Director Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Technical Contacts: Kenneth C. Chang, NRR 301-415-1913 E-mail: kxc2@Nrc..qov John R. Fair, NRR 301-415-2759 E-mail: irf(anrc.goV Note: The NRC's generic communications may be found on the NRC public Web site, http://www.nrc.gov, under Electronic Reading Room/Document Collections.
m I I I I I I I I I I I NEC-JH_24 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 OFFICE OF THE GENERAL COUNSEL April 3, 2008 E. Roy Hawkens, Chair Administrative Judge Atomic Safety and Licensing Board U.S. Nuclear Regulatory Commission Mail Stop: T-3F23 Washington, DC 20555-0001 Anthony J. Baratta Administrative Judge Atomic Safety and Licensing Board U.S. Nuclear Regulatory Commission Mail Stop: T-3F23 Washington, DC 20555-0001 Paul B. Abramson Administrative Judge Atomic Safety and Licensing Board U.S. Nuclear Regulatory Commission Mail Stop: T-3F23 Washington, DC 20555-0001 In the Matter of AMERGEN ENERGY COMPANY, LLC (License Renewal for Oyster Creek Nuclear Generating Station)Docket No. 50-219-LR Dear Administrative Judges: Enclosed for your information is a copy of the April 3, 2008 Notification of Information in the Matter of Oyster Creek Nuclear Generating Station License Renewal Application, which the Staff has provided to the Commission.
Sincerely, CounsJames E. Adler Counsel for the NRC Staff
 
==Enclosure:==
 
As Stated cc w/enclosure:
Service List
** *~UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 April 3, 2008 Board Notification 2008-01 MEMORANDUM TO: Chairman Klein Commissioner Jaczko Commissioner Lyons Commissioner Svinicki Atomic Safety and Licensing Board All Parties FROM: Samson S. Lee, Acting Director -<' -Division of License Renewal Office of Nuclear Reactor Regulation
 
==SUBJECT:==
NOTIFICATION OF INFORMATION IN THE MATTER OF OYSTER CREEK NUCLEAR GENERATING STATION LICENSE RENEWAL APPLICATION In conformance with the Commission's policy on notification to the Commission and the Atomic Safety Licensing Board (ASLB) regarding significant new information, this memorandum provides the following information.
The staff is reviewing the use of a simplified method to calculate cumulative usage factors (CUF) that may not be conservative.
Oyster Creek Nuclear Generating Station (Oyster Creek)used this simplified fatigue calculation method for one type of nozzle, the recirculation nozzle at the plant. This type of calculation was not applicable to the. drywell shell analysis, which is the subject of the appealed contention pending before the Commission.
Although, this simplified calculation is not relevant to the contention in the proceeding that was before the ASLB, we are providing this information, because this may be an issue of public interest.The staff plans to ask Oyster Creek to perform a confirmatory analysis consistent with the methodology in Section III of the ASME Code. However, the staff believes that the safety significance of using the simplified analysis method is low based on the risk assessments performed by the staff in resolving generic safety issues (GSI)-1 66 and GSI-1 90.Docket No. 50-219 cc: See next page CONTACT: Donnie J. Ashley, NRR 301-415-3191 Accession Number: ML080930335 I I I I I I I I I I I I I I I I I I I Oyster Creek Nuclear Generating Station cc: Site Vice President
-Oyster Creek Nuclear Generating Station AmerGen Energy Company, LLC P.O. Box 388 Forked River, NJ 08731 Senior Vice President
-Operations Support AmerGen Energy Company, LLC 4300 Winfield Road Warrenville, IL 60555 Kathryn M. Sutton, Esq.Morgan, Lewis, & Bockius LLP 1111 Pennsylvania Avenue, NW Washington, DC 20004 Patrick Mulligan, Chief Bureau of Nuclear Engineering New Jersey Department of Environmental Protection 25 Arctic Parkway Ewing, NJ 08638 Vice President
-Licensing and Regulatory Affairs AmerGen Energy Company, LLC 4300 Winfield Road Warrenville, IL 60555 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406-1415 Mayor of Lacey Township 818 West Lacey Road Forked River, NJ 08731 Senior Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 445 Forked River, NJ 08731 Director -Licensing and Regulatory Affairs AmerGen Energy Company, LLC Correspondence Control P.O. Box 160 Kennett Square, PA 19348 Manager Licensing
-Oyster Creek Exelon Generation Company, LLC Correspondence Control P.O. Box 160 Kennett Square, PA 19348 Regulatory Assurance Manager Oyster Creek AmerGen Energy Company, LLC P.O. Box 388 Forked River, NJ 08731 Assistant General Counsel AmerGen Energy Company, LLC 200 Exelon Way Kennett Square, PA 19348 Ron Bellamy, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406-1415 Correspondence Control Desk AmerGen Energy Company, LLC 200 Exelon Way, KSA 1-1 Kennett Square, PA 19348 Oyster Creek Nuclear Generating Station Plant Manager AmerGen Energy Company, LLC P.O. Box 388 Forked River, NJ 08731 License Renewal Manager Exelon Generation Company, LLC 200 Exelon Way, Suite 230 Kennett Square, PA 19348 Oyster Creek Nuclear Generating Station cc: Mr. Michael P. Gallagher Vice President License Renewal Exelon Generation Company, LLC 200 Exelon Way, Suite 230 Kennett Square, PA 19348 Mr. Christopher M. Crane President and Chief Nuclear Officer AmerGen Energy Company, LLC 4300 Winfield Road Warrenville, IL 60555 E. Roy Hawkens, Chair Administrative Judge Atomic Safety and Licensing Board Mail Stop: T-3F23 U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Anthony J. Baratta Administrative Judge Atomic Safety and Licensing Board Mail Stop: T-3F23 U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Paul B. Abramson Administrative Judge Atomic Safety and Licensing Board Mail Stop:' T-3F23 U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Office of the Secretary ATTN: Docketing and Service Mail Stop: O-16G4 U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Office of Commission Appellate Adjudication Mail Stop: O-16G4 U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Emily Krause Law Clerk Atomic Safety and Licensing Board Mail Stop: T-3F23 U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Suzanne Leta Liou New Jersey Public Interest Research Group 11 N. Willow Street Trenton, NJ 08608 Donald Silverman, Esq.Morgan, Lewis & Bockius LLP 1111 Pennsylvania Ave., N.W.Washington, DC 20004 Alex S. Polonsky, Esq.Morgan, Lewis & Bockius LLP 1111 Pennsylvania Ave., N.W.Washington, DC 20004 Raphael P. Kuyler, Esq.Morgan, Lewis & Bockius LLP 1111 Pennsylvania Ave., N.W.Washington, DC 20004 Paul Gunter, Director Reactor Watchdog Project Nuclear Information and Resource Service 6930 Carroll Avenue, Suite 340 Takoma Park, MD 20912 Kevin Kamps Reactor Watchdog Project Nuclear Information and Resource Service 6930 Carroll Avenue, Suite 340 Takoma Park, MD 20912 J. Bradley Fewell, Esq.Exelon Corporation 4300 Warrenville Road Warrenville, IL 60555 I I I I I I I I I I I I I I I I I I I Oyster Creek Nuclear Generating Station cc: Richard Webster, Esq.Eastern Environmental Law Center 744 Broad Street, Suite 1525 Newark, NJ 07102 Julia LeMense, Esq.Eastern Environmental Law Center 744 Broad Street, Suite 1525 Newark, NJ 07102 Manager Regulatory Assurance Oyster Creek Generating Station AmerGen Energy Company, LLC P.O. Box 388 Forked River, NJ 08731 Associate General Counsel Exelon Gernation Company, LLC 4300 Winfield Road Warrenville, IL 60555 Chief Operating Officer (COO)AmerGen Energy Company, LLC 4300 Winfield Road Warrenville, IL 60555 Senior Vice President
-Mid-Atlantic Operations AmerGen Energy Company, LLC 200 Exelon Way, KSA 3-N Kennett Square, PA 19348}}

Latest revision as of 16:28, 14 January 2025

New England Coalition, Inc., Contentions 2A and 2B Prefiled Exhibits, NEC-JH_03 - NEC-JH_24, Volume 1
ML081570606
Person / Time
Site: Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date: 04/28/2008
From: Hopenfeld J
New England Coalition
To: Karlin A, Wendy Reed, Richard Wardwell
Atomic Safety and Licensing Board Panel
SECY RAS
References
50-271-LR, ASLBP 06-849-03-LR, RAS M-39
Download: ML081570606 (737)
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